Text

Annual Radioactive Effluent Release Report
	ML061210398
Person / Time
Site:	Oconee
Issue date:	04/28/2006
From:	Brandi Hamilton; Duke Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML061210398 (127)
	v • d • e

MkDuke

[OPouwer.

BRUCE H HAMILTON Vice President Oconee Nuclear Station i

I I

Duke Power ON0I VP / 7800 Roctherster Highway Seneca, SC 29672 April 28, 2006 864 885 3487 864 885 4208 fax U.S). Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Subject:

Oconee Nuclear Site Docket Nos. 50-269, 50-270 and 50-287 2005 Annual Radioactive Effluent Release Report Gentlemen:

Pursuant to Oconee Nuclear Site Selected Licensee Commitment Manual, SLC 16.11-9, and 10 CFR 50.36a(a)(2), please find attached the Oconee Annual Radioactive Effluent Release Report for the period of January 1, 2005 through December 31, 2005.

Attechment I Radioactive Effluent Releases Attachment II Supplemental Information Attachment III Solid Waste Disposal Report Attachment IV Inoperable Monitoring Equipment Attachment V Unplanned Offsite Releases Attachment VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Attachment VII SLC 16.11 Radiological Effluent Controls Enclosure Enclosure Radioactive Waste Process Control Program Manual 2005 Update CD-ROM Offsite Dose Calculation Manual CD-ROM Should there be questions concerning this report please contact Judy E. Smith at (864) 885-4309.

www. dukepower. corn

U. S. Nuclear Regulatory Commission April 28, 2006 Page 2 Very truly yours, B. H. Hamilton Site Vice President Oconee Nuclear Site Attachments Enclosures

b-U. S. Nuclear Regulatory Commission April 28, 2006 Page 3 xc:

Mr. W. D. Travers Regional Administrator, Region II Mr. L. N. Olshan Project Manager, ONRR 1Mr. Mel Shannon Senior Resident Inspector, ONS Mr. Henry Porter Division of Radioactive Waste Management American Nuclear Insurers 95 Glastonbury Blvd, Suite 300 Glastonbury, CT 06033'!4443 Mr. William Nestel INFO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957

U. S. Nuclear Regulatory Commission April 28, 2005 Page 4 bce: C. D. Ingram EC07F J. A. Twiggs ONOIRP B. G. Davenport ON03RC D. J. Berkshire ONO1RP M. I. Sanders ONOIRW ELL ECO50 NSRB EC05P R. L. Gill EC05P Document Management

b Attachment I Oconee Nuclear Site Effluent Release Data l \\

OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2005 through December 31, 2005)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 1.12E-01

2. Avg. Release Rate pCi/sec 1.44E-02 B. Iodine-131

1. Total Release Ci 3.94E-08

2. Avg. Release Rate ACi/sec 5.06E-09 C. Particulates Half Life >= 8 days

1. Total Release Ci 0.OOE+00

2. Avg. Release Rate yCi/sec 0.OOE+00 D. Tritium

1. Total Release Ci 1.12E+01

2. Avg. Release Rate ACi/sec 1.43E+00 2.06E+00 2.88E+00 4.27E+01 4.78E+01 2.62E-01 3.62E-01 5.37E+00 1.51E+00 1.80E-05 0.OOE+00 3.71E-04 3.89E-04.

2.29E-06 0.00E+00 4.67E-05 1.23E-0' 0.OOE+00 0.OOE+00 8.88E-06 8.88E-Ot 0.OOE+00 0.OOE+00 1.12E-06 2.82E-07 1.78E+01 1.37E+01 3.84E+01 2.26E+00 1.73E+00 4.83E+00 8.l0E+01 2.57E+00 E. GrosS Alpha Radioactivity

1. Total Release Ci 0.00E+00

2. Avg. Release Rate ACi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS -

ELEVATED RELEASES -

CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases XE-133 Ci Totals for Period...

Ci

2. lodines 1-131 Ci 1-133 Ci Totals for Period...

Ci 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00

0. 00E+00 0.00E+00

0. OOE+00

3. Particulates Half Life CO-58 Totals for Period...

4. Tritium H-3 Totals for Period...

>= 8 days Ci 0.OOE+00 Ci 0.OOE+00 Ci 7.90E+00 Ci 7.90E+00 1.73E-05 1.44E-05 3.17E-05

0. 00E+00

1. 62E+01 1.62E+01 2.51E+00 2.51E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0 0E+00 1.06E+01 1.06E+01 4.06E+01 4.06E+01 3.70E-04 1.65E-05 3.87E-04 8.88E-06 8.88E-06 3.41E+01 3.41E+01 4.31E+03.

4.31E+01.

3. 87E-04 3.09E-0!

4.18E-04 8.88E-06 8.88E-06

6. 87E+02 6.87E+01

5. Gro3s Alpha Radioactivity

- No Nuclide Activities **

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS -

ELEVATED RELEASES -

BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4

1. Fission and Activation Gases AR-41 KR-85 KR-85M XR-88 XE-131M XE-133 XE-133M XE-135 Ci 8.39E-03 Ci 5.59E-02 Ci 2.43E-05 Ci 0.OOE+00 Ci 0.OOE+00 Ci 4.40E-02 Ci 1.06E-03 Ci 2.68E-03 Ci 1.12E-01 Ci 3.94E-08 Ci 1.96B-07

____35-0 Ci 2.35E-07 1.40E-02 1.07E+00 0.00E+00 2.64E-04 1.68E-02 9.55E-01 0.OOE+00 4.59E-03 2.06E+00 6.76E-07 4.33E-08 7_1____7 7.19E-07 1.63E-02 2.85E-01 0.OOE+00 0.OOE+00 2.39E-03 6.92E-02 0.OOE+00 6.13E-04 3.73E-01 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 1.19E+00 0.00E+00 O.OOE+00 0.00E+00 1.02E-02 8.95E-01 4.28E-03 3.00E-03 2.10E+00 7.71E-07 9.44E-09 7_80__07 7.80E-07 YEAR 3.88E-0:

2.61E+00 2.43E-0!i 2.64E-041 2.93E-02 1.96E+00 5.35E-03 1.09E-02

4. 65E+00 1.49E-0G; 2.49E-0.

___3___..

1.73E-0G; Totals for Period...

2. lodines 1-131 1-133 Totals for Period...

3. Particulates Half Life >= 8 days

- No Nuclide Activities **

4. Tritium H-3 Totals for Period...

Ci 4.86E-03

______- 0 Ci 4.86E-03 4.23E-02 4.23E-02 9.29E-03 9_2_____

9.29E-03 5.68E-02 5.68E-02 1.13E-01.

1.13E-01.

5. Gross Alpha Radioactivity No Nuclide Activities **

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS -

GROUND RELEASES -

CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

2. lodines 1-131 Totals for Period...

Ci

0. OOE+00 Ci 0.OOE+00 0.00E+00

0. OOE+00 0.OOE+00 o.OOE+00 2.42E-07 2.42E-07 2.42E-07 2.42E-07

3. Particulates Half Life >= 8 days

- No Nuclide Activities **

4. Tritium H-3 Totals for Period...

Ci 3.25E+00 Ci 3.25E+00 1.54E+00 1.54E+00 3.16E+00 3.______

3.16E+00 4.28E+00 4.28E+00 1.22E+01 1.22E+01

5. Gro;s Alpha Radioactivity

- No Nuclide Activities **

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS -

GROUND RELEASES -

BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1

1. Fission and Activation Gases

- No Nuclide Activities **........

2.

Iod:Lnes

- No Nuclide Activities **........

3. Part:iculates Half Life >= 8 days

- No Nuclide Activities **........

4. Tril:ium

- No Nuclide Activities **........

5. Grosls Alpha Radioactivity

- No Nuclide Activities **........

QTR 2 QTR 3 QTR 4 YEAR

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 1.21E-02

2. Average Diluted Concentration

a. Continuous Releases yCi/ml 0.OOE+00

b. Batch Releases pCi/ml 7.26E-10 B. Tril:ium

1. Total Release Ci 1.53E+02

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 4.56E-08

b. Batch Releases pCi/ml 9.11E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.00E+00

b. Batch Releases pCi/ml 0.OOE+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00

b. Batch Releases ACi/ml 0.OOE+00 4.59E-02 2.33E-02 2.12E-02 l.03E-01 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.71E-09 1.36E-09 1.24E-09 1.51E-09 2.21E+02 3.19E+02 2.OOE+02 8.93E.02 1.95E-08 2.81E-08 3.25E-08 3.14E-08 1.30E-05 1.86E-05 1.17E-05 1.31E-05 0.OOE+00 1.93E-03 2.53E-05 1.95E-03 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.13E-10 1.48E-12 2.88E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste

1. Continuous Releases

2. Batch Releases liters 5.62E+08 liters 1.57E+06 4.14E+08 4.08E+08 4.94E+08 1.88E+09 3.07E+06 1.68E+06 3.71E+06 1.OOE+07 F. Volume of Dilution Water

1. Continuous Releases liters 1.67E+10

2. Batch Releases liters 1.67E+10 1.69E+10 l.71E+10 l.71E+10 6.78E+10 1.69E+10 1.71E+10 1.71E+10 6.78E+10

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID EFFLUENTS -

CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2005 Unit QTR I QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities **

2. Tril:ium H-3 Totals for Period...

Ci 7.87E-01 3.38E-01 4.92E-01 Ci 7.87E-01 3.38E-01 4.92E-01 5.72E-01. 2.19E+00 5.72E-01. 2.19E+00

3. Dissolved and Entrained Gases

- No Nuclide Activities **

4. Grosts Alpha Radioactivity

- No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID EFFLUENTS -

BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPOF.T FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission AG-l110M CE-14';

CO-57 CO-58 CO-60 CR-51 CS-134 CS-131 1-131 1-132 MN-54 MO-99 NB-95 RU-103 SB-124 SB-125 TC-99M:

TE-132 ZR-95 and Activation Products Ci Ci Ci Ci ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3.11E-03 0.OOE+00 1.22E-05 3.88E-03 1.29E-03 0.0OE+00 9.23E-05 6.11E-04 0.0OE+00 0.OOE+00 6.51E-06 0.OOE+00 4.02E-05 0.OOE+00 0.0OE+00 3.06E-03 0.OOE+00 0.OOE+00 3.11E-05 1.37E-02

0. OOE+00 6.44E-05 1.11E-02 3.07E-03 0.OOE+00 9.47E-05 1.76E-03 0.OOE+00 0.OOE+00 1.74E-04 0.0 OE+00 8.79E-06 0. OOE+00 2.02E-05 1.59E-02 0.OOE+00 0.OOE+00 9.45E-06 2.54E-03 0.0OE+00 1.29E-05 1.12E-02 1.16E-03 1.90E-04 7.31E-05 7.85E-04 0.OOE+00 0.OOE+00 5.86E-05 0.OOE+00 2.60E-04 7.08E-06 0.OOE+00 6.83E-03 0.OOE+00 0.OOE+00 1.82E-04 4.32E-04 1.50E-05 9.06E-06 1.2OE-02 8.15E-04 0.OOE+00 2.88E-04 1.74E-03 2.49E-04 1.56E-04 0.OOE+00 9.39E-06 1.54E-05 0.OOE+00 0.OOE+00 5.30E-03 9.13E-06 1.14E-04 0.OOE+00 1.97E-02 1.50E-05 9.86E-05 3.83E-02 6.33E-03 1.90E-04 5.48E-04 4.89E-03 2.49E-04 1.56E-04 2.39E-04 9.39E-06 3.24E-04 7.08E-06 2.02E-05 3.11E-02 9.13E-06 1.14E-04 2.23E-04 Ci 1.21E-02 4.59E-02 2.33E-02 2.12E-02 1.03E-01 Totals for Period...

2. Tritium H-3 Ci Totals for Period...

Ci

3. Dissolved and Entrained Gases XE-133 Ci XE-135 Ci 1.52E+02 2.20E+02 3.19E+02 2.OOE+02 8.91E+02 1.52E+02 2.20E+02 3.19E+02 2.OOE+02 8.91E+02 0.00E+00 0.OOE+00 l.91E-03 2.53E-05 0.OOE+00 0.OOE+00 2.22E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.93E-03 2.53E-05 1.93E-03 2.22E-05 1.95E-03 Totals for Period...

Ci

4. Gross Alpha Radioactivity

- No Nuclide Activities **

Attachment II Oconee Nuclear Site Supplemental Information

OCONEE NUCLEAR STATION 2005 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS -

STATION A.

NOBLE GASES -

AIR DOS]

1.

CALENDAR QUARTER -

2.

CALENDAR QUARTER -

3. CALENDAR YEAR

4. CALENDAR YEAR GAMMA DOSE = 15 MRAD BETA DOSE

30 MRAD GAMMA DOSE

30 MRAD BETA DOSE 60 MRAD B. LIQUID EFFLUENTS -

DOSE

1.

CALENDAR QUARTER -

TOTAL BODY DOSE -

4.5 MREM

2.

CALENDAR QUARTER -

ORGAN DOSE

15 MREM

3.

CALENDAR YEAR TOTAL BODY DOSE -

9 MREM

4.

CALENDAR YEAR ORGAN DOSE

30 MREM C. IODINE -

131 AND 133,

1. CALENDAR QUARTER =

2. CALENDAR YEAR

TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS -

ORGAN DOSE 22.5 MREM 45 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A.

GASEOUS EFFLUENTS -

INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE: ENERGY -

NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF' SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT.

SUPPLEMENTAL REPORT, PAGE 2,

PROVIDES A

SUMMARY

DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVIrY MEASUREMENTS.

V. BATCH RELEASES A. LIQUID EFFLUENT

1. 1.85E+02

TOTAL NUMBER OF BATCH RELEASES

2. 2.49E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 2.46E+02 ' MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 1.34E+02

AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 1.40E+01 -

MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

6. 3.41E+04

AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 4.30E+01.

TOTAL NUMBER OF BATCH RELEASES.

2. 8.55E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 2.16E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 1.99E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 2.20E+01 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES

0

2. TOTAL ACTIVITY RELEASED (CURIES)

=

0 B.

GASEOUS

1. NUMBER OF RELEASES

=

0

2.

TOTAL ACTIVITY RELEASED (CURIES)

0

SUPPLEMENTAL REPORT PAGE 2 OCONEE NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at Oconee Nuclea: Station has been determined to be +/- 25.2%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

(1) Flow rate determining devices

=

+2096 (2) Counting error

=

+15%

(3) Sample preparation error

=

+ 3%

OCONEE NUCLEAR STATION 2005 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC.

STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

OCONEE NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A WIND SPEED CLASS I

I I

I 1 0.75-1 1.00-I 1.25-I 1.50-I 2.00-I 3.00-1 4.00-1 5.00-I 6.00-I 8.00-1>9.99 1 I

l 0.99 l 1.24 j 1.49 I 1.99 l 2.99 l 3.99 l 4.99 I 5.99 I 7.99 I 9.99 l M/S lTOTAL I I- -+-+-+-+-+-+-+-+-+-+-+-

I NO.

I lSECTOR I

I I

I-------------------------------1 I

-N-I I 1 I 31 51 21 1

1 1

I

lI *I I

l-NNE-I

l

l 11

-71 81 1I

l1

l

l

l

l 171 I-NE-I 1I

.1 31 171 321 171 61 1l

.1

.1 771 l-ENE-l 41 91 251 16l 91

.l

.1

1 631 I-E_

I

'I

l

I 21 III 1

l1.1

l

.1

.1 151 l-ESE-I 11

1

1 21 1!

..1 l1

.1

.1 41 l-SE-I 1I 1I 1I 21 11

l

l

l

l

l

l 61 I-SSE-I

.1

1

.1 1I 21 1I

.1

l

1

.1

l 41 l-S-I I.

1I 1I 41 1I 1I

1

1

1

1

1 el I-SSW-I

.1

1 21 161 401 151 41

.1

.1 l

.1 771 I-+-+-

+-+-+-+-+-+-+-+-+-+-

I-SW-I

.1

.1 31 311 801 101 51

.1

1 1291 I-WSW-I

1 1I 21 121 19!

21 1I 21 21 31

.1 441 I-W-I

.1

1 31 41 51 41 -1 21 31

1 221 I-WNW-I

I

.1

.1 31 11 31 41 41 91 21

1 261 I-NW-I 11

1 11 21

1 11 41 41 21 21 1I 181 l-NNW-I 1I 31

1 1l 31 11 1i

1

l

.1

1 101 ITOTAL I

61 71 211 1171 2301 741 381 121 151 10!

1I 5311

OCONEE NUCLEAR STN. METEOROLOGY (2005)

PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASS I

I 1 0.75-f 1.00-f 1.25-f 1.50-f 2.00-f 3.00-f 4.00-f 5.00-f 6.00-f 8.00-1>9.99 1

I f 0.99 f 1.24 f 1.49 f 1.99 i 2.99 l 3.99 l 4.99 l 5.99 I 7.99 I 9.99 l MIS lTOTAL I I------+

+

+-+-+-+-+-+-+-------

I I NO. I NO.

I NO. I NO.

I NO.

I NO. I NO. f NO. I NO.

I NO.

I I---------

lSECTOR I

I I

III I

I I

I -I I

I I

I f-N-I

.1 21 41 91

l 11

.1

1 1s6 I-

+ -

I f-NNE-I

.1 1I 21 61 71 1I

'I

l1 *

l

.1 18l f-NE-I 1I 1f 21 ill 241 13f 51 l1

.1

.1 571 l-ENE-I

.1 1I 41 91 31I 15I 21

1

.1

.1 621 f-E-I

.f

.f 21 51 241

l

l

l

f

l 311 l-ESE-I 1I

.1

1 51 21

1

.1

1

.1

.1 81 l-SE-I

1

1

.1 31 21 1I

.1

1

.1 61 f-SSE-I lf

f 1I 41 l1 1

.1

1

1 61 l-S-I

.1 11

.1 41 91

1

.1

f

.1

f

1 141 l-SSW-I

.1

.1 41 14f 601 281 41

.1

.1 1101 f-SW-I 1I 1I 61 231 531 1of 51 1I

.1

1

1 1001 f-WSW-I

1

1 41 251 17f 21 1I 21 21

1

1 531 l-W-I

1

1 21 81 31 51

.1 1I 21 1I

1 221 l-WNW-I

.l

f 21 21 31 i1 31 71 10o 21 1I 31I l-NW*

I

1

1 21 51 1I 31 21 21 21 1I f1 181 l-NNW-f

.f 21

.f 31 31 1

1I 1

.1

.f

10f lTOTAL l

31 91 351 136f 2391 82f 241 131 16f 41 1I 562f

OCONEE NUCLEAR STN. METEOROLOGY (2005)

PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C I

WIND SPEED CLASS I

I I.I1 0.75-1 1.00-I 1.25-I 1.50-j 2.00-I 3.00-f 4.00-I 5.00-I 6.00-1 8.00-1>9.99 I I

l 0.99 l 1.24 l 1.49 l 1.99 l 2.99 l 3.99 l 4.99 l 5.99 l 7.99 I 9.99 l M/S lTOTAL I I---+-+-+-+-

+-+-+-+-+-+-+-

I NO.

I I--+-+-+-

++---+---+-+-+-+-

ISECTOR I

I I

I-N-I 1I 31 41 41 41 1I I

.1

l

1

1 15I lNNE_

l 21 1I 121 19I 31 21

l

l

l

l

l 391 I

+

4

+

I I-NE-I

1 1I 11 17I 291 15I 31

1

.1

1 661 I-ENE-I

1

.1 31 11l 401 171 71

.1

.1 781 l-E-I

l

l 21 31 121 1I

l

l

l

l

l 18l l-ESE-I

l 1I 21 51 81 1I

l

l

l

l

l 171 I-SE-I

I

.1 21 61 21

.1 1

l1.1

.1

1 ill l-SSE-I

1

1

.21 31 51

1

1

1

1

1

1 101 l-S-I

1

1 1I 51 61 21

1

1

1

1

1 141 l-SSW-I

1 21 31

'17I 361 251 61

1

.1

1 891 I-SW-I

.1 41 81 261 371 121 41 91 21

1

.1 1021 l-WSW-I

.1 31 71 301 81 21 31

1 51 1I

.1 591 l-W-I

.1 41 31 191 21 31 21 21 41 41

1 431 I-WNW-I l1 11 41 101 1I 21 21 81 101 1I 1I 401 I-NW-I 11 21 41 41 21 41 21 41 41 11

I 281 I-NNW-I

.1 1I 51 1I 21

.1 1I 1I

l1 *

.1 ill ITOTAL I

41 211 631 1801 1971 871 311 241 251 71 1I 6401

OCONEE NUCLEAR STN. METEOROLOGY (2005)

PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY D l,

l WIND SPEED CLASS I

I 1 0.45-1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-!

I l 0.74 l 0.99 l 1.24 l 1.49 l 1.99 l 2.99 l 3.99 I 4.99 I 5.99 l 7.99 l 9.99 ITOTAL I I-----

+-4

-4 4-

+-+

-4 4-

+

I NO. I NO.

I NO.

I lSECTOR I

I I

II-

-I-- - -I-- - -I-

-I-- ----I-- --I I

l-N-I 71 241 431 381 211 231 81 1ij

.1

.1 1651 I-NNE-l 21 201 291 421 511 291 91 21

1

.1

.1 1841 I-+-+-+-4-+-4-4-+-+-4-4-+-I I-NE-I

l 71 131 281 105!

1861 851 16!

1

l1.1 4411 l-ENE-I 21 141 1331 441 120!

2191 101!

161

1

1

1 5291 l-E-I 61 16l 231 311 58!

661 41

1

.1

1

.1 2041 l-ESE-I 31 71 121 16!

331 231 81

1

1

1

.1 1021 I-SE-l 21 51 141 16!

521 271 SI

.1

.1 1

.*I 1211 I-SSE-I

.1 51 131 221 471 401 51

l

.1

l

.1 1321 1-S-I 21 81 131 281 431 381 21

1

1

.1

.1 1341 1-SSW-1 21 101 161 211 531 991 621 301 31 1!

.1 2971 I-------------------------------------------------------

+

I I-SW-I 41 101 251 291 481 741 841 831 341 ill

.1 4021 l-WSW-I 5I 181 281 311 521 371 461 341 391 211 51 3161 l-W-I 11 291 321 20!

261 141 381 411 151 121 41 2321 I-WNW-I 10!

271 431 251 16!

18!

28!

301 201 15!

1l 2331 I-NW-I 61 21!

201 16!

12!

14!

12!

61 71 1l 127!

l-NNW-I 31 251 441 421 19!

271 12!

1l 1

l

!l 1741 l-CALM-I

.21

1 ll*

l U1l

l 21 I TOT' 1

57l 2'!SI 1 311 119 1 75Sl 9322l 511 22 --

11SI rG-,

il ;

,5,;

OCONEE NUCLEAR STN.

METEOROLOGY (2005)

PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E I l WIND SPEED CLASS I

I 1 0.45-1 0.75-) 1.00-) 1.25-) 1.50-) 2.00-) 3.00-) 4.00-) 5.00-l 6.00-)

I I

1 0.74 l 0.99 ) 1.24 1 1.49 l 1.99 1 2.99 l 3.99 l 4.99 1 5.99 l 7.99 lTOTAL I I NO l NO.

I NO.

I NO. IwO.

INO.

I NO.

I lSECTOR I

I I

I I-------------------------------I I

I I

)-N-I 211 641 551 301 201 1I

l

.1

)

1911 I-NNE-I 161 461 381 291 191 41 21

.1

.1 1541

)-NE-l 81 251 351 361 361 141 41

.1 *lI *1 1581 l-ENE-l 61 211 361 461 si) 341 31

.1

1 1971

)-E-l 61 291 321 281 231 91

I

.1

I

1 1271 l-ESE-I 71 231 221 371 321 161

.1

.l 1371 I-SE-I 51 241 191

27) 381 51 11

.1

.1 119) l-SSE-I 51 91

14)

21) 481

12)

1

.1

I

1 1091 l-S-I 31

13) 161 15I 341 ill 1I

.1

1

.1 931 l-SSW-I 71 231 211 251 271 361 ill 1I

1

1 1511 l-SW-I

10) 211 241 241 291 251 121 41 41 21 155I l-WSW-I

14)

31) 201 161

17) 211

14) 91 41 11 147) l-W-I

13) 691 391 121 61 81 91 51

.1 11 1621 l-WNW-I 251 108o 561

31)

14) 81 51

.1 1I

1 248) l-NW-I

18) 88a 731 371

12) 51 21

.1

1 2351 I

+

l l-NNW-I

26) 81l

68) 521

13) 81 1I

.1

.1 2491 l-CALM-l 1

l l

l 1

IT=.L-I 1

.f

'I e

191 2

1

7.

s 1 41

El '

OCONEE NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I

I I 0.45-1 0.75-I 1.00-I 1.25-I 1.50-I 2.00-I 3.00-I 4.00-I I

l 0.74 l 0.99 l 1.24 l 1.49 l 1.99 l 2.99 l 3.99 l 4.99 lTOTAL I I---+-+-+-+-+-+-+-+-

I NO.

I ISECTOR I

I I

- - - - - - - - -- - - - - - - -I I

I IIIIIII I-N-I

.1 51 31 1I 1I

.1

.1 101 l-NNE-I

.1 11

1 21 21

.1

I

.1 51 I-NE-l 21 21

1

1 11

1

.1

.1 51 l-ENE-I 1I 1I

1 21 31

.1

.1 71 l-E-I

.1 41

1 1I 1I 1I

1

.1 71 l-ESE-I 21 11 1I 21 41 31

.1

.1 131 I-SE-I

.1 31 1I 51 41 21

l

1 151 l-SSE-

- I

l 21 1I 21

.1 *1

.1 *1 51 I-s-I

1 21

1

1

1

1

1

1 21 I-SSW-I

1

41.

31 31 11

1

.1 *1 ill I-SW-I 21 81 51 61 61 51 11

.1 331 f-WSW-I 1I 61 31 21 31 21 21 1I 201 l-W-I 51 171 ill 1I

1 11

.1 *1 351 l-WNW-I 51 401 571 241 31

1

.1

.1 1291 f-NW-I 71 171 241 181 31

.1

.1 691 I-NNW-I 41 71 91 131

1

.1

.1 331 l-CALM-I 21

1

1

.1

1

1

.1 21 IlT^TAL I

31l 12^l 112l 22l

41

l

l-4+-

C' I OCONEE NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ loM WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY G WIND SPEED CLASS I

I 1 0.45-1 0.75-I 1.00-I 1.25-I 1.50-I 3.00-I I

l 0.74 l 0.99 l 1.24 l 1.49 l 1.99 l 3.99 lTOTAL I I-----++-+-+------

I I NO.

I NO.

I I--+-+-+-+-+-+

+-

lSECTOR I

I I

I I - - - - - - - - -- - - - - - - -I I

I I

I-N-I

1 11 Ii

1

.1

1 21 I-NE-I

l 1I

l 1I

l

l 21 1-ENE-I 1

.1

l 1

.1 1I l-ESE-I

l

l

l

l

l 1I 1I I-S-I

1

1

1 11

.1

.1 11 l-SW-I

1 31I 1I 1I

1

1 31 I-WSW-I 1

1 1

.1

.1 1

21 I-W-I 21 71 71 1I 1I

1 181 I-WNW-I 1I 141 81 61 1I

1 301 I-NW-I 41 81 31 51

.1

.1 201 I-NNW-I 21 21

.1 31

.1

.1 71 I-CALM-I 21

1

.1

.1 21 T-OTA j

12+ +

I 20I l+ l 2j +-

+

9 I lTOTAL l1 121 361 201 18l 21 1I 891

sol

-d 0g OCONEE NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ iOM WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I

I I 0.45-f 0.75-f 1.00-f 1.25-f 1.50-f 2.00-f 3.00-f 4.00-f 5.00-f s.00-I 8.00-1>9.99 I I

f 0.74 f 0.99 f 1.24 f 1.49 f 1.99 f 2.99 1 3.99 1

4.99 I 5.99 1

7.99 1

9.99 I

M/S l

TOTAL I I

-- +-+-+-+-+-+-+-+-+-+-

+--

I f

NO.

I NO.

f NO.

I NO.

f NO.

I l

SECTOR I

I I

1I I

I I

I f-N-I 281 9 1s 10sf 80f 6 01 301 of 1 I f

l

l1

.1 4101 l

-NNE-I 1 f 691 691 88 f

1041 s1I 15 f

31

1

1

.1 *l 4171 f-NE-I 10l 371 501 71 1

1871 28sf 134f 301 21

1

.1

.1 80sf l

-ENE-I 91 37f 5s1 1031 2031 3491 152f 341

1

.1

.1 9371 l-E-l 12f1 sof 55s 64 921 123f 61

1 l1

.f

.1 4021 f-ESE-l 121 331 361 571 81f 531 10f

1

1

.1

1

.1 2821 f-SE-f 71 331 351 51 105s 391 71 1

1

.1 *l

.1 278f l

-SSE-l 51 16f 28[

481 1031 591 71

1

.1

.1 *l

.1 266f l-S-I 51 231 31f 461 901 651 61

.1

.1 2661 I

+

-+

-+-+-+-+-+

-l l-SSW-I 91 371 421 581 1281 2711 1411 451 3

1 1

1

.1 7351 f-SW-I 161 41f 601 771 1631 2741 1291 1011 481 15s

1

-.1 9241 f-WSW-I 211 561 551 621 1391 104f 681 491 471 31f 9f

.1 6411 f-W-f 211 1221 931 391 631 321 601 521 19f 211 121

.1 5341 l-WNW-f 411 189f 165s 921 491 31f 391 39S 401 441 61 21 7371 f-NW-f 351 136s 122f 831 381 201 241 201 16s 15s 51 1I 515s l-NNW-l 351 1161 127f 115s 371 431 15s 41 21

1

.1

.1 4941 f-CALM-f71 *l

l

I.1

l

.1

l

l

l

.1 71 ITOTLT.

l 291l 10901 112., I 31 I IC4iI A

l29ln I2-3 379 177j 127j 32j 3;

oS5ij

Attachment III Oconee Nuclear Site Solid Waste Disposal Report

OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT 412012006 DUKE POWER COMPANY OCONEE NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPFn TO A nli5PnqAI FAC.IITV TYPES OF WASTE SHIPPED

1) WASTE FROM LIQUID SYSTEM (A) DEWATERED POWDEX RESIN (B) DEWATERED BEAD RESIN (C) EVAPORATOR CONCENTRATES (D) DEWATERED MECHANICAL FILTERS

1. PRIMARY FILTER MEDIA

2. SECONDARY FILTER MEDIA (E) DEWATERED DEMINERALIZERS (F) SOLIDIFIED (CEMENT) OIL, ACIDS,SLUDGES

2) DRY SOLID WASTE (A) DRY ACTIVE WASTE (COMPACTED)

REPORT PERIOD: JANUARY - DECEMBER YEAR:

NUMBER OF NUMBER OF WASTE CLASS SHIPMENTS CONTAINERS A-U A-S B

C 3

2 0

2 1

4 0

9 2

0 9

0 0

0 1

0 0

0 1

0 0

0 3

0 0

0 2

0 0

2005 CONTAINER TYPE STC TYPE A TYPE A STC TYPE A BURIAL VOLUME CU. FT.

CU. M.

1680.20 240.60 0.00 240.60 19.30 481.20 0.00 2

4 0

1 0

47.58 6.81 0.00 6.81 0.00057 13.63 0.00 62.48 67.20 0.00 0.00 0.00 TOTAL ACTIVITY CURIES 2.43 113.08 0.00 163.89 0.3561 178.01 0.00 708.33 0.31 0.00 0.00 0.00 0

0 0

STC (1)

(2)

(B) DRY ACTIVE WASTE (NON-COMPACTED)

(C) DRY ACTIVE WASTE (BROKERED)

(D) IRRADIATED COMPONENTS 61 26 0

0 0

61 26 0

0 0

61 26 0

0 0

0 STC 2206.47 STC 2373.18 TYPE A 0.00 0.00 TYPE B 0.00 TOTAL 99 105 97 2

4 2

7241.56 204.52 1166.40 NOTE: (1)

SHIPMENTS FROM DURATEK ENVIROCARE OF UTAH OR CNSI c BARNWELL (DAW)

(2)

SHIPMENTS FROM DURATEK TO ENVIROCARE OF UTAH OR CNSI @ BARNWELL (METAL)

SHIPMENTS MADE FROM OTHER COMPANYS SO INFORMATION IS NOT KNOWN Page 1 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY-DECEMBER WASTE TYPE: POWDEX RESIN ISOTOPE:

% ABUNDANCE/LINER

OF UNERS SHIPPED TO ENVIROCARE 9

OF SHIPMENTS TO ENVIROCARE 3

TOTAL AVE.

CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CO-58 0.00 1.25 1.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.57 0.86 CO-60 1.79 4.19 5.44 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.41 3.80 NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00.

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-134 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.06 RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 AG-110m 2.61 5.26 5.78 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 13.65 4.55 SB-125 29.51 18.62 21.96 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 70.09 23.36 1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-137 26.22 15.08 9.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 50.62 16.87 H-3 25.02 22.25 13.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 60.27 20.09 NI-63 11.94 25.27 33.16 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 70.37 23.46 FE-55 2.68 7.30 9.39 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 19.37 6.46 SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-136 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0 00 0 00 0.00 0.00 0.00 0.00 0.00 SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CE-144 0.24 0.77 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 1.47 0.49 TE-132 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTAL 100 100 100 0

0 0

300.00 100.00 CLASS C 0

0 0

CLASS B 0

0 0

CLASS AS 0

0 0

CLASS AU 3

3 3

0 0

0 9

CURIES 0.538 0.698 1.19 0

0 0

2.426 CU. FT.

503 555 622.2 0

0 0

1680.2 CU. M 14.24364 15.71615 17.61907 0

0 0

47.57886 RSR#

05-2080 05-2081 05-2083 Page 2 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE:

BEAD RESIN

OF LINERS SHIPPED TO CNSI 2

ISOTOPE:

% ABUNDANCEILINER

OF SHIPMENTS TO CNSI 2

TOTAL AVE.

CR-51 MN-54 CO-57 CO-58 CO-60 NB-95 ZR-95 CS-134 RU-106 AG-11Om SB-125 1-131 CS-137 H-3 NI-63 FE-55 SR-90 TE-125m CS-136 XE-1 33 C-14 PU-241 1-129 TC-99 CM-242 AM-241 PU-239140 PU-238 CM-243/44 Be-7 SB-124 0.00 1.05 0.00 46.99 2.88 0.00 0.00 0.51 0.00 0.00 0.00 0.00 2.93 0.00 37.11 8.38 0.05 0.00 0.00 0.00 0.10 0.01 0.00 0.00 0.00 0.0001 0.0001 0.0003 0.0001 0.00 0.00 0.00 1.17 0.00 40.79 4.54 0.00 0.00 0.00 0.00 1.26 1.32 0.00 4.67 0.31 38.37 7.47 0.04 0.00 0.00 0.00 0.01 0.04 0.00 0.00 0.0009 0.0008 0.0005 0.0014 0.0010 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.22 0.00 87.78 7.42 0.00 0.00 0.51 0.00 1.26 1.32 0.00 7.60 0.31 75.48 15.85 0.09 0.00 0.00 0.00 0.11 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 1.1091 0.0000 43.8891 3.7097 0.0000 0.0000 0.2555 0.0000 0.6321 0.6617 0.0000 3.8023 0.1530 37.7380 7.9257 0.0433 0.0000 0.0000 0.0000 0.0532 0.0249 0.0000 0.0000 0.0005 0.0005 0.0003 0.0009 0.0006 0.0000 0.0000 TOTAL 100.00 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 200.00 100.00 CLASS C 0

0 0

CLASS B 1

0 0

0 1

CLASS AS 0

1 0

0 0

0 1

CLASS AU 0

0 0

CURIES CU. FT.

CU. M RSR#

104.3 120.3 3.41 05-2090 8.78 120.3 3.41 05-2095 0

0 0

0 113.08 0

0 0

0 240.6 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 6.81 Page 3 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: COMPACTED DAW (DURATEK)

OF SHIPMENTS FROM ONS TO DURATEK

OF SHIPMENTS FROM PROCESSOR TO ENVIROCARE

OF SHIPMENTS FROM PROCESSOR TO BARNWELL 16 61 0

OF CONTAINERS FROM ONS TO DURATEI

OF CONTAINERS FROM PROCESSOR TO ENVIROCARE

OF CONTAINERS FROM PROCESSOR TO BARNWELL 28 61 0

CU. FT..

SHIPPED CURIES SHIPPED CU. FT. DISPOSAL FACILITY CI TO DISPOSAL FACILITY RSR #

COMPLETED 05-2009 04-2070 04-2075 04-2079 04-2066 04-2078 04-2083 04-2071 04-2112 05-2043 05-2046 05-2052 05-2055 04-2086 04-2102 04-2097 04-2095 04-2110 05-2010 05-2061 05-2064 05-2066 05-2078 05-2093 05-2096 05-2056 05-2051 05-2076 05-2099 05-2100 05-2103 05-2106 05-2111 05-2050 05-2072 1868.8 0

0 0

0 905.09 1868.8 575 1868.8 0

0 0

0 1868.8 1725 862.5 1868.8 1852.98 154.58 0

0 0

1864.52 1868.8 1868.5 1868.8 1868.8 0

0 0

0.056 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.661 0.006 0.677 0.000 0.000 0.000 0.000 0.000 0.000 0.290 0.007 0.003 0.199 0.052 3.640 0.000 0.000 0.000 0.048 0.054 0.033 0.143 0.010 0.000 0.000 0.000 0.000 0.000 104.172 65.035 44.879 148.087 0.615 26.750 115.022 0.244 178.826 21.103 195.703 1.974 102.558 107.241 130.984 122.817 116.633 131.044 0.150 112.930 37.155 0.000 163.273 60.803 15.300 22.230 15.407 0.539 100.800 61.376 0.000 0.000 0.000 0.346 2.477 0.000 0.000 0.000 0.05570 0.04834 0.05371 0.21257 0.00141 0.01311 0.11317 0.00045 0.00515 0.00050 705.40512 0.00555 0.57428 0.09966 0.06761 0.10466 0.09447 0.17832 0.00030 0.29021 0.00101 0.00000 0.19602 0.11393 0.67622 0.00059 0.00028 0.00037 0.00510 0.01483 0.00000 0.00000 0.00000 0.00003 0.00085 0.00000 0.00000 0.00000 V B.

m~w TOTAL 24758.57 5.879 2206.47 708.33349 Page 4 of 11

Oconee Nuclear Station Annual Report TOTAL CURIES BURIED TOTAL CUBIC FEET BURIED TOTAL CUBIC METERS 708.333 2206.47 62.48 OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: UNCOMPACTED DAW

OF SHIPMENTS FROM ONS TO CNSI

OF CONTAINERS FROM ONS TO CNSI 0

0 RSR NUMBER TOTAL CUBIC FEET 0

0 0

0 CURIES 0

0 0

0 A-U A-S B

TOTAL CUBIC METERS 0.00 Page5of11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: METAL (CNSI,DURATEK,ENVIROCARE)

OF SHIPMENTS TO DECON FACILITY

OF CONTAINERS TO DECON FACILITY 19 24

OF SHIPMENTS TO DISPOSAL FACILITY:

OF CONTAINERS TO DISPOSAL FACILITY 26 26 DECONIDISP.

CU. FT..

RSR #

FACILITY TO PROCESSOR CURIES CU. FT. TO TO PROCESSOR DISPOSAL FACILITY CURIES TO DISPOSAL FACILITY COMPLETED 05-2010 04-2070 04-2059 04-2066 04-2067 04-2078 04-2086 04-2071 05-2043 05-2049 05-2050 05-2051 05-2052 05-2056 04-2083 04-2044 04-2097 04-2112 05-2058 05-2071 05-2067 05-2072 05-2073 05-2074 05-2075 05-2076 04-2110 05-2082 05-2084 05-2085 05-2064 05-2009 05-2098 05-2097 05-2099 862.5 0

0 0

460 323.9 391 977.5 287.5 977.5 0

0 0

0 431.25 1150 720 384 934.4 333.3 336 359.4 0

379.25 576 989.46 DAW 0

DAW 0

874.5 736 DAW 0

0 0.05 0

0 0

0.00335 0.00404 0.00361 0.019 0.00425 0.00947 0

0 0

0 0.00509 0.00243 0.00401 0.0203 0.00645 0.229 0.0329 0.0423 0

0.0459 0.0531 0.192 0

0 0.0051 0.01 0

0 95.97 4.17 311.58 379.32 94.80 25.77 2.51 369.98 29.68 65.34 53.98 123.92 1.96 101.80 1.08 3.99 3.60 20.18 0.00 2.44 0.00 51.50 0.00 1.30 0.00 429.69 3.20 0.00 116.16 9.30 54.70 1.33 0.00 0.00 13.93 0.00 0.01201 0.00307 0.00616 0.04019 0.00476 0.02710 0.00109 0.02779 0.00152 0.00226 0.00062 0.00389 0.00005 0.00175 0.00032 0.00000 0.00510 0.00021 0.00000 0.00002 0.00000 0.00397 0.00000 0.00374 0.00000 0.03822 0.00241 0.00000 0.05315 0.06630 0.00081 0.00063 0.00000 0.00000 0.00108 0.00000 0.308 TOTAL 12483.46 0.7423 TOTAL CUBIC METERS 2373.18 67.20234 Page 6 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOUID R.ADWASTE REPORT REPORT PERIOD: JANUARY -DECEMBER WASTE TYPE: DEMIN RESIN

OFULNERS SHIPPED TO CNSI 4

ISOTOPE:

% ABUNDANCEILINER U OF SHIPMENTS TO CNSI 4

TOTAL AVE.

CR-Si MN-54 CO-ST CO-58 CO-60 NB-95 ZR-95 CS-i134 RU-i103 AG-11rn SB-125 1-131 CS-137 H-3 NI-83 FE-55 SR-90 TE-125m CS-I138 XE-i133 C-14 PU-241 TRU FE-59 U-234/238 TC-99 CE-144 PU-238 PU-239\\40 ALM-241 CM-242 CM-243144 BA-133 CD-109 SN-i13 SR-85 RU-108 CE-139 HC-203 ZN-65 BE-7 SB-124 0.000 0.000 0.000 34.963 7.233 0.133 0.066 0.971 0.000 3.365 2.767 0.000 6.063 0.052 21.296 22.071 0.022 0.000 0.000 0.000 0.251 0.624 0.000 0.000 0.000 0.000 0.000 0.017 0.005 0.010 0.019 0.017 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.056 0.000 0.000 0.008 1.008 1.022 0.989 0.000 0.000 0.000 10.499 18.265 58.217 4.868 4.884 2.376 0.028 0.035 0.000 0.002 0.000 0.000 0.909 0.729 0.000 0.000 0.000 0.000 0.438 1.048 0.137 1.006 0.673 0.024 0.000 0.000 0.000 5.583 4.040 1.780 0.000 0.000 0.000 60.053 56.657 29.387 14.252 14.364 6.960 0.090 0.061 0.028 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.169 0.169 0.083 0.020 0.051 0.011 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.001 0.0003 0.0002 0.00040 0.0001 0.0002 0.00070 0.0001 0.0001 0.001 0.0002 0.0003 0.001 0.0002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.074 0.000 0.000 0.001 0 000 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0-00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 000O 000O 0.00 0.00 0.00 0900 0.00 0.00 0.00 0.00 0900 0.00 0.00 0.00 0.00 0.00 0.00 o00 000 0.00 0.00 0.00 0.00 0900 0900 0.00 0.90 0.00 0.90 0.90 0.90 0.90 0.90 0.90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0~00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000D 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0~00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0~00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.008 0.002 0.00 3.019 0.755 0.00 0.000 0.000 0.00 119.945 29.986 0.00 19.359 4.840 0.00 0.196 0.049 0.00 0.067 0.017 0.00 2.609 0.652 0.00 0.000 0.000 0.00 4.984 1.248 0.00 4.470 1.117 0.00 0.000 0.000 0.00 17.466 4.367 0.00 0.052 0.013 0.00 187.393 41.848 0.00 57.647 14.412 0.00 0.201 0.050 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.672 0.168 0.00 0.706 0.176 0.00 0.090 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.019 0.005 0.00 0.006 0.001 0.00 0.011 0.003 0.00 0.021 0.005 0.00 0.019 0.005 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 0.000 0.000 0.00 1.074 0.268 0.00 0.057 0.014 TOTAL 100.00 100.00 190000 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 400.00 100.00 CLASS C 0

0 0

0 CLASS B 0

1 1

1 0

0 0

3 CLASS AS I

0 0

1 CLASS AU 0

0 0

0 CURIES 3.51 30,3 lOS 39.2 0

CU. FT.

120.3 120.3 120.3 120.3 0

CU. M 3.406581 3.406581 3.406581 3.406581 0

RSRX 05-2003 05-2004 05-2905 05-2088 o

o 0

0 0

0 178.01 0

0 0

0 481.2 0

0 0

0 13.628 Page7 of 11I

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE:

IRRADIATED COMPONANT

OF CONTAINERS SHIPPED TO CNSUDURATEK 0

ISOTOPE:

% ABUNDANCEINER

OF SHIPMENTS TO CNSVDURATEK 0

TOTAL AVE.

CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O0 MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/OI NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I CS-134 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DfV/0I SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I 1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I NI-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!

C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!

PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0I TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/OI FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV1/0 SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00.

0.00 0.00 #DIVM0O TA-182 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV1/0 PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/01 CM-243 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0I TOTAL 0.00 0.00' 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I CLASS C 0

0 0

CLASS B 0

0 0

CLASS AS 0

0 0

CLASS AU 0

0 0

CURIES 0

0 0

CU. FT.

0 0

0 CU. M 0

0 0

RSR#

Page 8 of 11

OCONEE NUCLEAR STATION SOLID RADWO inF*RWdear Station Annual Report REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: PRIMARY FILTERS

OF DRUMVS/LINERS TO CNSI 2

ISOTOPE:

OF SHIPMENTS TO CNSI 2

TOTAL AVE.

CR-61 O.OuU

.U.00

.(f U.UU U.U

.UU 0jUfi 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 MN-54 1.95 2.25 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.20 2.099 CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CO-58 1.37 1.69 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.06 1.530 CO-60 5.37 5.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 10.78 5.392 NB.94 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 TC-99 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CS-I 34 2.56 2.70 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 5.26 2.629 RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 SB-125 1.50 1.56 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.06 1.530 1-129 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 CS-i137 44.78 43.97 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 88.75 44.374 H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 NI-63 27.09 26.56 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 53.65 26.826 FE-55 15.38 15.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 31.24 15.621 SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-239 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 RU-i106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 Nf-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-141 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 AM-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CM-243/44 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 HG-203 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00000 0.0000000 SN-113 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.000 CD-109 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 TOTAL 100.00 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 200.00 100.00 CLASS C 1

1 0

0 0

0 2

CLASS B 0

0 0

CLASS AS 0

0 0

CLASS AU 0

0 0

CURIES 81.9 81.99 0

0 0

0 163.89 CU. FT.

120.3 120.3 0

0 0

0 240.6 CU. M 3.406581 3.406581 0

0 0

0 6.813162 KSHX U5-2014 05-2094 Page 9 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY -DECEMBER WASTE TYPE: SECONDARY FILTERS

OF CONTAINERS SHIPPED TO DURATEK

OF SHIPMENTS TO DURATEK 4

s OF CONTAINERS SHIPPED TO CNSIIENVIROCARE 2

OF SHIPMENTS TO CNSI I ENVIROCARE 1

ISOTOPE:

TOTAL AVE.

CR-51 MN-54 CO-57 CO-58 CO-60 NB-95 ZR-95 CS-1 34 RU-1 03 AG-1 10m SB-125 1-131 CS-1 37 H-3 NI-63 FE-SS SR-90 TE-1 25m CS-136 XE-1 33 C-14 PU-241 TRU FE-59 SB-24 RU-1 06 CE-144 CM-243 PU-238 PU-239 AM-241 CM-242 0.00 0.00 0.00 12.28 4.66 0.00 0.00 1.47 0.00 0.00 0.00 0.00 29.92 0.00 47.97 3.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.56 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 76.93 1.60 3.40 2.85 0.00 0.00 0.00 0.00 0.00 4.02 0.00 6.37 4.83 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

'0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O0 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 89.21 6.26 3.40 2.85 1.47 0.00 0.00 0.00 0.00 33.94 0.00 54.34 7.97 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 44.61 3.13 1.70 1.43 0.73 0.00 0.00 0.00 0.00 16.97 0.00 27.17 3.98 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTAL 100.00 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 199.44 99.72 CLASS C 0

0 0

0 CLASS B 0

0 0

0 CLASS AS 0

0 0

0 CLASS AU 1

1 0

0 0

2 CURIES 0.07213 0.284 0

0 0

0.35613 FT3 Shipped 15.4 15 0

0 0

30.4 CU. M Shipped 0.4361 0.4248 0.0000 0.0000 0

0 0

0.860848 Curies Buried 0.0000 0.0000 0.0006 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000 0.0000 0.0000 0.0000 0.0006 FT3 Buried 0

0 19.3 0

0 0

0 19.3 CU. M Buried 0.0000 0.0000 0.5465 0.0000 0.0000 0.0000 0.00D0 0.0000 0.0 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.546525 RSR#

05-2093 05-2109 04-2083 Page 10 of 11

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER WASTE TYPE: SOLIDIFIED (CEMENT) OIL, ACIDS, SLUDGES

OF CONTAINERS SHIPPED 0

ISOTOPE:

% ABUNDANCEILINER

OF SHIPMENTS 0

TOTAL AVE.

CR-51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/01 CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DfVIO1 CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

D0V/01 NB-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIVI0!

ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CS-1 34 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I 1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV0IO NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIVIOI FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/IO!

XE-1 33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/01 C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV/0I TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

DIV10I CLASS C 0

0 0

0 CLASS B 0

0 0

0 CLASS AS 0

0 0

0 CLASS AU 0

0 0

0 CURIES 0

0 0

0 CU. FT.

0 0

CU. M 0

0 0

0 RSR#

Page 11 of 11

Attachment IV Oconee Nuclear Site Inoperable Monitoring Equipment IRIA-40 and the Hot Machine Shop Ventilation System Effluent Sampler Totalizer were considered out of service for greater than 30 davs.

Attachment Oconee Nuclear Unplanned Offsite V

Site Releases There were no unplanned offsite releases for the year 2005.

Attachment VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public

OCONEE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (January 1, 2005 through December 31, 2005)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, as well as the total dose for the calendar year.

This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 10 miles of Oconee for the calendar year of this report to show conformance with 40 CFR 190.

Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 1 St Quarter 2005

.

IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2005

=

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Ql -

Maximum Organ Dose CHILD THYROID 4.82E-03 2.25E+01 2.14E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

=. NOBLE GAS DOSE LIMIT ANALYSIS-=-==--.==.=== Quarter 1 2005

=

Dose Limit

% of Period-Limit (mrad)

Cmrad)

Limit Ql -

Maximum Gamma Air Dose 5.30E-06 1.50E+01 3.54E-05 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 7.80E+0l XE-133 1.55E+01 XE-135 5.15E+00 Q1 -

Maximum Beta Air Dose 1.01E-05 3.00E+01 3.38E-05 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage KR-85 5.71E+01 XE-133 2.42E+01 AR-41 1.44E+0l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2nd Quarter 2005 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2005

==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Q2 - Maximum Organ Dose CHILD THYROID 5.79E-03 2.25E+01 2.57E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Nuclide H-3 1-131 Contributors (5% or greater to total)

Percentage 9.40E+01 5.91E+00

.- NOBLE GAS DOSE LIMIT ANALYSIS=-==-------=----= Quarter 2 2005

==

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q2 -

Maximum Gamma Air Dose 2.66E-05 1.50E+01 1.77E-04 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Nuclide XE-133 AR-41 Contributors (5% or greater to total)

Percentage 6.72E+01 2.60E+01 Q2 -

Maximum Beta Air Dose 1.68E-04 3.OOE+01 5.60E-04 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage KR-85 6.59E+01 XE-133 3.16E+01

b EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT.

Oconee Nuclear Station Units 1, 2, & 3 3rd Quarter 2005

-- IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS------ Quarter 3 2005 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Q3 - Maximum Organ Dose CHILD LIVER 5.05E-03 2.25E+01 2.24E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

=.= NOBLE GAS DOSE LIMIT ANALYSIS Quarter 3 2005

===.

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q3 - Maximum Gamma Air Dose 5.66E-05 1.50E+01 3.77E-04 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.52E+01 AR-41 1.42E+01 Q3 - Maximum Beta Air Dose 1.76E-04 3.OOE+01 5.86E-04 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 8.15E+01 KR-85 1.67E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4 th Quarter 2005

== IODINE, 83, and PARTICULATE DOSE LIMIT ANALYSIS -- =--- Quarter 4 2005

==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Q4 -

Maximum Organ Dose CHILD THYROID 1.92E-02 2.25E+01 8.53E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Nuclide H-3 I-131 Contributors (5% or greater to total)

Percentage 6.32E+01 3.68E+01

-== NOBLE GAS DOSE LIMIT ANALYSIS========-===-=-=======-== Quarter 4 2005==-

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q4 -

Maximum Gamma Air Dose 7.78E-04 1.50E+01 5.19E-03 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Nuclide XE-133 Contributors (5% or greater to total)

Percentage 9.98E+01 Q4 -

Maximum Beta Air Dose 2.43E-03 3.OOE+01 8.11E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 9.49E+01 KR-85 5.06E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2005

=

IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=-=====

Critical Critical Dose Annual Limit 2005

=....

Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Y-_Maximu________Org____n___Dose_____C__ILD____T___Y___OID____________-______-

Yr - Maximum Organ Dose CHILD THYROID 3.43E-02 4.50E+01 7.62E-02 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Nuclide H-3 1-131 Contributors (5%.or greater to total)

Percentage 7.84E+01 2.16E+01 NOBLE GAS DOSE LIMIT ANALYSIS====---

-============-=-== Annual 2005

=

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Yr -

Maximum Gamma Air Dose 8.66E-04 3.OOE+01 2.89E-03 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 9.73E+01 Yr -

Maximum Beta Air Dose 2.79E-03 6.OOE+01 4.65E-03 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XE-133 9.OOE+01 KR-85 9.66E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 1 8t Quarter 2005

,=- BATCH LIQUID RELEASES ago Period-Limit Q1 -

Maximum Organ Dose Q1 -

Total Body Dose Critical Critical Dose Age Organ (mrem)

TEEN LIVER 6.03E-02 ADULT 4.45E-02 Quarter 1 2005 -----

Limit Max % of (mrem)

Limit 1.50E+01 4.02E-01 4.50E+00 9.90E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS_-137 CS-137 CS-134 H-3 7.15E+01 1.42E+01 1.24E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 6.08E+01 H-3 2.28E+01 CS-134 1.55E+01

-- CONTINUOUS LIQUID RELEASES (CTP 3)

Critical Period-Limit Age Q1 -

Maximum Organ Dose CHILD Q1 - Total Body Dose CHILD

--=-,.====-===-

.... Quarter 1 Critical Dose Limit Organ (mrem)

(mrem)

LIVER 5.29E-05 1.50E+01 5.29E-05 4.50E+00 2005......

Max % of Limit 3.53E-04 1.18E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2005 BATCH LIQUID RELEASES Period-Limit Q2 -

Maximum Organ Dose Q2 -

Total Body Dose Critical Critical Dose Age Organ (mrem)

TEEN LIVER 1.47E-01 ADULT l.0lE-01 Quarter 2 Limit (mrem) 1.50E+0l 4.50E+00 2005.====

Max % of Limit 9.80E-01 2.24E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 8.44E+01 H-3 7.35E+00 CS-134 5.99E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 7.73E+0l H-3 1.46E+0l CS-134 7.04E+00

--- CONTINUOUS LIQUID RELEASES (CTP 3)

Critical Period-Limit Age Q2 -

Maximum Organ Dose CHILD Q2 -

Total Body Dose CHILD

.=

=

.=..====.==

Critical Dose Organ (mrem)

LIVER 2.29E-05 2.29E-05 Quarter 2 Limit (mrem) l.50E+0l 4.50E+00 2005======

Max % of Limit 1.53E-04 5.l0E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage H-3 l.OOE+02 greater to total) greater to total)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3rd Quarter 2005 a..

BATCH LIQUID RELEASES.=...=.....................-

..n Critical Critical Dose Period-Limit Age Organ (mrem) 03 - Maximum Organ Dose ADULT LIVER 8.13E-02 Q3 -

Total Body Dose ADULT 6.20E-02 Quarter 3 Limit (mrem) 1.50E+01 4.50E+00 2005 ------

Max % of Limit 5.42E-01 1.38E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 6.51E+01 H-3 2.62E+01 CS-134 8.22E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 H-3 CS-134 5.60E+01 3.43E+01 8.81E+00

=- CONTINUOUS LIQUID RELEASES (CTP 3)

Critical Period-Limit Age Q3 -

Maximum Organ Dose CHILD Q3 -

Total Body Dose CHILD Quarter 3 Critical Dose Limit Organ (mrem)

(mrem)

LIVER 3.34E-05 1.50E+01 3.34E-05 4.50E+00 2005 n===n=

Max % of Limit 2.22E-04 7.41E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4 th Quarter 2005

=== BATCH LIQUID RELEASES........

====................=-

Critical Critical Dose Period-Limit Age Organ (mrem)

Q4 -

Maximum Organ Dose TEEN LIVER 1.60E-01 Quarter Limit (mrem) 4 2005......

Max % of Limit 1.50E+01 1.07E+00 4.50E+00 2.50E+00 Q4 -

Total Body Dose ADULT 1.12E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 7.67E+01 CS-134 1.67E+01 H-3 6.10E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS_-137 CS-137 CS-134 H-3 6.85E+01 1.92E+01 l.19E+01

== CONTINUOUS LIQUID RELEASES (CTP 3)

Critical Period-Limit Age Q4 - Maximum Organ Dose CHILD Q4 -

Total Body Dose CHILD

=.=.=..........

Critical Dose Organ (mrem)

LIVER 3.86E-05 3.86E-05 Quarter 4 Limit (mrem) 1.50E+01 4.50E+00 2005 ------

Max % of Limit 2.57E-04 8.58E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 1.00E+02, H-3 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 AMMAL 2005 BATCH LIQUID RELEASES Critica Period-Limit Age Yr -

Maximum Organ Dose TEEN Yr -

Total Body Dose ADULT

........=....

e===

al Critical Dose Organ (mrem)

Annual Limit (mrem) 2005.==-==---

Max % of Limit LIVER 4.46E-01 3.OOE+01 1.49E+00 3.20E-01 9.OOE+00 3.55E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 7.74E+01 CS-134 1.14E+01 H-3 9.78E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CS-137 H-3 CS-134 6.77E+01 1.86E+01 1.28E+01 CONTINUOUS LIQUID RELEASES (CTP 3)

Critical Period-Limit Age Yr -

Maximum Organ Dose CHILD Yr -

Total Body Dose ADULT

..=.=..===...======

Critical Dose Organ (mrem)

LIVER 1.48E-04 1.48E-04 Annual 2005........

Limit Max % of (mrem)

Limit 3.OOE+01 4.93E-04 9.OOE+00 1.64E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

Oconee Nuclear Station 2005 Radioactive Effluent Releases 40CFRl90 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, the annual dose commitment: to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems.

The fuel cycle dose assessment for Oconee Nuclear Station only includes liquid and gaseous effluent dose contributions from Oconee and direct and air-scatter dose from Oconee's onesite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exposed individual.

The combined dose to a maximum exposed individual from Oconee's effluent releases and direct and air-scatter dose from Oconee's ISFSI is well below 40CFRl90 limits as shown by the following summary:

I.

2005 Oconee 40CFRI90 Effluent Dose Suummary The 40CFRl90 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 3.38E-01 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age:

Adult Gas non-NG Contribution:

5.5%

Gas NG Contribution:

0.2%

Liquid Contribution:

94.3%

Maximum Organ Dose =

4.66E-01 mrem Maximum Location: 1.0 Mile, South-West Sector Critical Age:

Teen Critical Organ:

Liver Gas Contribution:

4%

Liquid Contribution:

96%

II.

2005 Oconee 40CFRI90 ISFSI Dose Snumnary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report.

The maximum dose rate to the nearest resident from the Oconee ISFSI is conservatively calculated to be 0.0268 mrem/year.

The attached excerpt, "C. 10CFR72.212(b)(2)(i)(C)- Requirements of 72.104",

from tae "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report is provided to document the method used to calculate the Oconee ISFSI 0.0268 mrem/year dose estimate.

use of the DSCs/HSMs that were loaded prior to the effective date of Amendment

2. There are no requirements to be addressed in this evaluation.

B.

10CFR72.212(b)(2)(i)(B)- Cask Storage Pad Design

"...cask storage pads and areas have been designed to adequately support thestatic load of the stored casks;"

Per Section 3.4.3 of the NUHOMS FSAR8, the ISFSI storage pad is not considered important to safety and is designed, constructed, maintained, and tested as a commercial grade item. The concrete storage pad for Phase III wa; designed by Transnuclear West based on a Duke performed shake analysis and input on soil parameters (density, response characteristics, etc.) The storage pad was designed and constructed in accordance wvith ACI-318 and analyzed for seismic accelerations in both the horizontal and vertical directions. The seismic loads are applied as equivalent static loads.

The average dynamic soil spring stiffness and tributary area for each spring utilized in the analysis of the storage pad were obtained from previous Duke calculations, OSC-24994 2 and OSC..

263943, performed for the Site-Specific ISFSI. The basemat is located within the double fenced boundaries of the existing Site-Specific ISFSI. The storage pad ancd associated approach slabs were constructed using concrete with a 28 day compressive strength (fe) of 5000 psi. The reinforcing is ASTM A615 Grade 60 (fy = 60,000 psi). The stotage pad for Phase III is 3' thick by 40.0' wide by 106'-

0" long and is separated from the adjacent Site-Specific ISFSI structure by a 3' expansion joint. The storage pad for Phase IV is 3' thick by 40.0' wide by 126'-

0" long and is separated from thie Phase IIl storage pad by a 3" expansion joint.

These storage pad dimensions are documented in drawing 0-39-01-0554. Based on the preceding discussion, it is concluded the storage pad is designed adequately to support the static load of the stored casks. The Transnuclear West analysis for Phase 11. is detailed in 9-354-030038.

The Duke analysis for Phase IV is documented in OSC-745955. which incorporates Reference 38, in its entirety.

C.

10CFR72.212(b)(2)(i)(C)- Requirements of 72.104

"...thle requirements of § 72.104 have been met."

The previous 10CFR72.10413 evaluations are not affected by CoC 72-1004, Amendment 2. As shown in Table 7.4-2 of the NUHOMS FSAR8, dose rates attributable to direct radiation (nomial operation) of the ISFSI are not changed.'

This is attributable to the fact that fuel assembly maximum source terms were maintained despite the increase in allowable bumup and addition of BPRAs. This is achieved by requiring longer cooling times to offset the affect of higher allowable burnup. Direct evidence of the source term maintenance is found by comparing the Tecimical Specification 1.2.1 Fuel Specifications of Amendment I of CoC 72-1004 to Occnee Nuclear Site IOCFR72.212 Written Evaluations, Rev. I Page 21 of 34

Since the original 10CFR72.104 Evaluation considered the previously loaded Site-Specific HSMs, the planned loading of up to 46 General License HSMs, and maximum source terms for the most recently loaded HSMs, it remains bounding and does not require revision.

Requirements of 72.104 "Criteria for radioactive materials in effluents and direct radiation from ISFSI or MRS" are met and documented in the Transnuclear West report, "Duke Oconee ISFSI Phase m 10CFR72.104 and Cask Thermal Evaluation Report"13.

The annual dose equivalent to any individual who is located beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any critical organ. This dose equivalent must include contributions from planned releases to the environment, direct radiation from ISFS1 operations, and any other radiation from uranium fuel cycle operations within the region.

The controlled area is defined as the Oconee Nuclear Site Exclusion Area Boundary (EAB). The dose for a maximally exposed individual at this boundary must be below 25 mrem.

For a conservative determination the individual is assumed to have a 100% occupation time at the boundary.

As the NUHOMLS system does not produce any effluents, the dose at the EAB will consist of the direct dose from ISFSI operations and the other uranium fuel cycle operations.

Secondly, the dose at the ISFSI restricted area boundary must be below 2 mreni per hour, 10CFR20.1301(a)(2). Lastly, due to the Oconee EAB being traversed by public roads and waterways, the dose within the EAB but external to the Oconee, restricted area must be below 100 mrem per year, an occupancy time of 2080 hours0.0241 days 0.578 hours 0.00344 weeks 7.9144e-4 months (a standard work year) is used as no residences exist within the EAB.2 '

This requirement is to comply with I OCFR20.1301 (a)(l).

The dose at the site boundary was calculated using existing TLD data33'34 for the ISFSI current complement of 40 DSCs, the Oconce power generation contribution of 0.1 mrem, and the contribution from the additional 46 GL DSCs using the MCNP monte-carlo transport code. The maximum resulting dose at the Exclusion Area Boundary was calculated to be 0.0268 mrem per year, within the 25 mrern allowable limit.

The maximum dose rate at the ISFSI restricted area was determined to be 1.84 mrem per hour, within the 2 mrem per hour allowable limit.

Finally the maximum annual dose at the Oconee controlled area boundary was determined to be 54.5 mrem, within the 100 mrem allowable limit.

Amendment 2. It may be seen that the maximum pemitted decay heat, neutron source, and gamma source are maintained.

Oconee Nuclear Site 1OC'FR72.212 Written Evaluations, Rev. I Page 22 of 34

These calculations show that the Oconee ISFSI meets the radiological requirements of 10CFR72.104 and 10CFR20.1301.

The calculations were performed assuming no further decay or dose rate reduction from the existing 40 Phase I and II HSMs.

D.

10CFR72.212(b)(2)(ii)-

10CFR72.48 Applicable to Written Evaluations Required by 10CFR72.212 "The licensee shall evaluate any changes to the Written evaluations required by this paragraph using the requirements of§72. 48(c). 4 copy ofthis record shall be retained until spent fitel is no longer stored under the general license issued under §72.210.

The changes to these written evaluations were evaluated under NSD-211, I OCFR72.48 Process22. It is included as Attachment 4.

IX.

OCFR72.212(b)(3)- Evaluation of Reactor Site Parameters "Review the Safety Analysis Report (SAR) referenced in the Certificate efs Conmpliance and the related NRC Safety Evaluation Report, prior to use of the general license, to deter,,line whether or not the reactor site paranmeters, including analyses of earthquake intensity and tornado missiles, are enveloped by the cask design bases considered in these reports. The results of this review nwnt be documented in the evaluation made in paragraph (b)h2,! of this section.

A.

Earthquake Intensity The maximum horizontal and vertical ground acceleration (MHE) specified for the Oconee site is 0.15g (Section 2.5.2.8 of Oconee UFSAR4). Therefore the Oconee site accelerations are less than the values of 0.17g vertical and 0.25g horizontal used in the Transnuclear West analysis, and are therefore bounded8.

B.

Tornado Transnuclear West completed a design analysis, NUH-004.0219 "NUHOMS 20 HSM Tornado Missile Impact Analysis", to ensure the tornado missile impact analysis is bounded for the Oconee site. The Oconee site is analyzed for 2 specific tornado missiles (I) a 2000 Ibm automobile traveling at 100 mph with 20 square foot contact area and (2) a 12 foot long 8" diameter wooden pole traveling at 250 mph (Oconee UFSAR 3.5.1.34).

The first case is bounded by the Standardized NUHOMS FSAR8 massive missile impact analysis of a 3967 Ibm automobile traveling at 126 mph with a frontal area of 20 square feet against the HSM. For the second case, the Transnuclear West analysis is for a 13.5" diameter Oconee Nuclear Site 10CIFR72.212 Written Evaluations, Rev. I Page 23 of 34

Attachment VII SLC 16.11 Radiological Effluent Controls

G Radioactive Liquid Effluents 16.11.1 16.11. RADIOLOGICAL EFFLUENTS CONTROL 16.11.1 Radioactive Liquid Effluents COMMITMENT Establish conditions for the controlled release of radioactive liquid effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, 40 CFR 141 and 40 CFR 190.

a. Concentration The concentration of radioactive material released at anytime from the site boundary for liquid effluents to Unrestricted Areas [denoted in Figure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] shall be limited to 10 times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2 x 10-4 [iCVml total activity.

b. Dose The dose or dose commitment to a Member Of The Public from radioactive materials in liquid effluents to Unrestricted Areas shall be limited to:

1. during any calendar quarter:

< 4.5 mrem to the total body

< 15 mrem to any organ; and

2. during any calendar year:

< 9 mrem to the total body

< 30 mrem to any organ.

c. Liquid Waste Treatment The appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge, if the projected dose due to liquid effluent releases to unrestricted areas, when averaged over 31 days would exceed 0.18 mrem to the total body or 0.6 mrem to any organ.

16.11.1-1 07/12/0-1 l

Radioactive Liquid Effluents 16.11.1

d. Chemical Treatment Ponds (CTP 1 and 2)

1. The quantity of radioactive material in the Chemical Treatment Ponds (CTP) shall be limited so that, for all radionuclides identified, excluding noble gases and tritium, the sum of the ratios of activity (in curies) to the limits in 10 CFR 20, Appendix B, Tabla 2, column 2 shall not exceed 1.7 x 106.

£ Ail 1.7x106 jCj Where Aj = pond inventory limit for single radionuclide 'j" (curies)'

Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide nj" (curies)

2. No powdex resin shall be transferred to the CTPS unless the sum of the activity of the radionuclides identified is less than 0.1% of the limit identified in Commitment d.1.

Qj) 1.0 x 10-3 j

Aj where Qj = radionuclide activity in resin Aj = pond inventory limit for radionuclide "j"

3. The total radionuclide inventory of used powdex resin transferred to the Chemical Treatment Ponds over the previous 13 weeks, shall not exceed 0.4% of the pond radionuclide inventory limit.

Decay of radionuclides may be taken into account in determining inventory levels.

QjO + Qj2 + Qj3 + ------ -Qj, <.004 x Aj where, Qj = Total inventory of radionuclide j in a transfer n = Number of transfers to the Chemical Treatment Ponos during the previous 13 - week period.

NOTE----------------------

Appendix I dose limits for radioactive liquid effluent releases are applicable only during normal operating conditions which include expected operational occurrences, and are not applicable during unusual operating conditions that result in activation of the Oconee Emergency Plan.

1 6.11.1 -2 07/12/01 l

Radioactive Liquid Effluents 16.1 1.1 APPLICABILITY:

At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.

released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.

1 6.11.1 -3 07/12/01 l

Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C.

Radioactive liquid C.1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:

in excess of the specified limit.

a.

Cause of equipment or subsystem inoperability.

b.

Corrective action to restore equipment and prevent recurrence.

D.

Total radioactive D.1 Submit report to the 30 days inventory of used regional NRC Office pcwdex resins describing the reason(s) transferred to the for exceeding the limit and Chemical Treatment plans for future operation.

Ponds over previous 13 weeks greater than 0.4% of the pond radionuclide inventory limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 1 6.11.1 -5 07/12/01 l

Radioactive Liquid Effluents 16.11.1 BASES The concentration commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the effluent concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 'e. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in 10 CFR 50.36a. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302).

The requirements contained in 10 CFR 50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. Therefore, to accommodate operational flexibilit, needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 mrem/year to apply at all times. Compliance with the limits of the new 10 CFR 20.1001 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I, 40 CFR 141 and 40 CFR 190.

Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objective; for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that result in the activation of the Oconee Emergency Plan.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept 'as low as is reasonably achievable.' This SLC implements the requirements of 10 CFR Part 50.36a.

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section ll.()

of Appendix A to 10 CFR Part 50.

1 6.11.1 -6 07/12/1 1l

Radioactive Liquid Effluents 16.11.1 The inventory limits of the chemical treatment ponds are based on limiting the consequences of an uncontrolled release of the pond inventory. The short term,rate limit (2 mrem/hr) of 10 CFR 20.1301 is applied to 10 CFR 20.1302 in the following expression:

Ai x

106 IO.

ci x

gal

< 2mrem/hr x 8760 hr 1.3 x 10 cal Curie 3785 ml 500 mrem/yr yr 10 x Cj A

< 1.7X106 Cj Where Aj = pond inventory limit for radionuclide "j" (curies)

Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration radionuclide "j" 1.3 x 106 gal = estimated volume of smaller chemical treatment pond The transfer limits provide assurance that activity input to the CTP will be minimized.

REFERENCES:

1.

10 C FR Part 20, Appendix B.

2.

40 CFR Part 141.

3.

10 C(FR Part 50, Appendices A and 1.

4.

40 CFR Part 190.

5.

Offsite Dose Calculation Manual.

6.

Regulatory Guide 1.109.

7.

NUFIEG-1 301 1 6.11.1 -7 07/12/01 l

Radioactive Gaseous Effluents 16.11.2 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.1 1.2 Radioactive Gaseous Effluents COMMITMENT Establish conditions for the controlled release of radioactive gaseous effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, and 40 CFR 190.

a.

Dose Rate The instantaneous dose rate at the site (exclusion area) boundary for gaseous effluents [Figure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

1.

The dose rate limit for noble gases shall be:

500 mrem/yr to the total body

3000 mremfyr to the skin; and

)

2.

The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be

1 i00 mrem/yr to any organ.

b.

Dose

1.

The air dose due to noble gases released in gaseous effluent from the site shall be limited to the following:

i.

During any calendar quarter

15 mrad for gamma radiation

30 mrad for beta radiation ii.

During any calendar year:

30 mrad for gamma radiation

60 mrad for beta radiation

2.

The dose to a Member Of The Public from radioiodines, tritiurm and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site, shall be limited to the following:

16.11.2-1 01/31.'00 l

Radioactive Gaseous Effluents 16.11.2

i.

During any calendar quarter:

22.5 mrem to any organ ii.

During any calendar year:

< 45 mrem to any organ.

c.

Gaseous Radwaste Treatment

1.

The Gaseous Radwaste Treatment System shall be used tD reduce the noble gases in gaseous wastes prior to their discharge, if the projected gaseous effluent air dose due to gaseous effluent release from the site, when averaged over 31 days exceeds 0.6 mrad for gamma radiation and 1.2 mrad for beta radiation.

2.

The Ventilation Treatment Exhaust System shall be used to reduce radioactive materials other than noble gases in gaseous waste prior to their discharge when the projected doses due to effluent releases to unrestricted areas when averaged over 31 days would exceed 0.9 mrem to any organ.

d.

Used Oil Incineration During incineration of used oil contaminated by radioactive material in the Station Auxiliary Boiler, the dose to a Member Of The Pub!ic from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the Station Auxiliary Boiler shall be c 0.045 mrem to any organ in any calendar year.

--- NOTE----a -

a-The requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.

APPLICABILITY:

At all times 16.11.2-2 03/27/99

Radioactive Gaseous Effluents 16.11.2

/I i

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Dose rate exceeds the A.1 Restore release rate to Immediately limits specified in within limits.

Commitment a.

B. Calculated dose B.1 Submit report to the 30 days from the end of exceeds specified limits.

regional NRC Office which the quarter during which includes the following:

the release occurred

a. Cause(s) for exceeding the limit(s),

and

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable.

I

)

16.11.2-3 01/31/00 l

Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C.

Radioactive gaseous C.1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:

specified in Commitment c.1 or

a.

Cause of equipment c.2.

or subsystems inoperability, and AND

b.

Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.

more than 31 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.2.1 N/A N/A 16.11.2-4 0312'7199

Radioactive Gaseous Effluents 16.11.2 BASES The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in IOCFR50.36. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old IOCFR20.106 (new IOCFR20.1302). The requirements contained in IOCFR50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old IOCFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem to the total body, 3000 mrem to the skin, and 1500 mrem to an infant via the milk animal-milk-infant pathway. It is further indicated in IOCFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in IOCFR50 Appendix I. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrem/year to the total body and 3000 mrem/year to the skin; and for lodine-1 31, for lodine-1 $3, for tritiurn, and for all radionuclides in particulate form with half-lives greater than 8 days. an instantaneous dose rate limit of 1500 mrem/year.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109, OCalculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1,. October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."

Equations in the ODCM are provided for determining the actual doses based upon the historical average atmospheric conditions. The release rate commitments for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides into green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50.

16.11.2-5 01/31/00 l

Radioactive Gaseous Effluents 16.

11.2 REFERENCES

1 10 CFR Part 20, Appendix 8.

2.

10 CFR Part 50, Appendices A and 1.

3.

Regulatory Guide 1.109.

4.

40 CFR Part 190.

5.

Of Isite Dose Calculation Manual.

16.11.2-6 01/31100 l

Io I Radioactive Effluent Monitoring Instrumentation 16.11.3 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.3 Radioactive Effluent Monitoring Instrumentation COMMITMENT Radioactive Effluent Monitoring Instrumentation shall be OPERABLE as follows:

a.

Liquid Effluents The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.1.a are not exceeded.

b.

Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.

c.

The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.

NOTE--------------------

Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.

,)

APPLICABILITY:

According to Table 16.11.3-1 and Table 16.11.3-2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Alatm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.

required for one or more effluent OR monitoring instrument channels.

A.2 Suspend release of Immediately effluent monitored by the channel.

1 6.11.3-1 11/10/04 l

Radioactive Effluent Monitoring instrumentation 16.11.3 i

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately liquid effluent monitoring referenced in Table instrument channels 16.11.3-1 for the inoperable, function.

AND B.2 Restore the 30 days instrument(s) to OPERABLE status.

C. One or more required C.1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11.3-2 for the channels inoperable.

function.

AND C.2 Restore the 30 days instrument(s) to OPERABLE status.

D. Required Action and D.1 Explain in next Annual April 30 of following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why B.2 or 0.2 not met.

inoperability was not corrected in a timely manner.

16.11.3-2 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.1 1.3

\\

)

,~)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action B.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1. (RIA-33)

SLC 16.11.4.

AND E.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR E.2 Suspend release of Immediately radioactive effluents by this pathway.

F. As required by Required F.1 Suspend release of Immediately Action B.1 and radioactive effluents by referenced in Table this pathway.

16.1 1.3-1. (RIA-54)

OR F.2 Collect and analyze Prior to each discrete grab samples for gross release of the sump radioactivity (beta and/or gamma) at a lower limit of detection of at least 10 7 gtCi/ml.

1 6.11.3-3 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3

=

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required Action B.1 and referenced in Table 16.1 1.3-1. (Liquid Radwaste Effluent Line Flow Rate Monitor)

NOTE-------

Not required during short, controlled outages of liquid effluent monitoring instrumentation. Short controlled

-outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

)

G.1 Suspend release of radioactive effluents by this pathway.

OR G.2 Estimate flow rate during actual releases.

Immediately Immediately AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter I

.5 I

1 6.11.3-4 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 2

CONDITION l

REQUIRED ACTION I

COMPLETION TIME H. As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-35, #3 Chemical Treatment Pond Cornmosite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent))

NOTE------------------

Not required during short, controlled outages of liquid effluent monitoring instrumentation. Short controlled

.outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

H.1 Suspend release of radioactive effluents by this pathway.

OR H.2 Collect and analyze grab samples for gross radioactivity (beta and/or gamma) at a lower limit of detection of at least 10'7 gCi/ml.

Immediately Immediately AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 16.11.3-5 11110/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME I.

As required by Required Action C.1 and referenced in Table 16.1 1.3-2 for effluent releases from waste gas tanks (RIA-37, RIA-38) or containment purges (RIA-45).

NOTE-------------

Not required during short, controlled outages of gaseous effluent monitoring instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

)

1.1.1 Analyze two independent samples.

A AND 1.1.2 Conduct two independent data entry checks for release rate calculations AND 1.1.3 Conduct two independent valve lineups of the effluent pathway.

OR Prior to initiating subsequent release Prior to initiating subsequent release Prior to initiating subsequent release Immediately 1.2 Suspend release of radioactive effluents by this pathway.

16.11.3-6 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 I

CONDITION REQUIRED ACTION COMPLETION TIME J.

As required by Required Action C. 1 and referenced in Table 16.11.3-2. (Effluent Flow Rate Monitor (Unit Vent, Containment Purge, Interim Raclwaste Exhaust, Hot Machine Shop Exhaust, Raclwaste Facility Exhaust, Waste Gas Discharge))

NOTE------------------

Not required during short, controlled outages of gaseous effluent monitoring instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

I J.1 Suspend release of radioactive effluents by this pathway.

OR J.2 Estimate flow rate Immediately Immediately AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter tI 16.11.3-7 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3

)

CONDITION REQUIRED ACTION COMPLETION TIME

.I K. As required by Required Action C.1 and referenced in Table 16.11.3-2. (RIA-45, RIA-53, 4RIA-45)

NOTE-----------------

Not required during short, controlled outages of gaseous effluent monitoring instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive-short, controlled outages is always at least equal to duration of immediately preceding outage.

)

K.1 Suspend release of radioactive effluents by this pathway.

'OR K.2.1 Collect grab sample.

AND K.2.2 Analyze grab samples for gross activity (beta and/or gamma).

Immediately Immediately AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 24 hours from collection of sample 16.11.3-8 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Unit Vent Monitoring Iodine Sampler, Unit Vent Monitoring Particulate Sarnpler, Interim Racdwaste Building Ventilation Monitoring lodize Sampler, Interim Radwaste Building Ventilation Monitoring Particulate Sampler, Hot Machine Shop Iodine Sampler, Hot Machine Shop Particulate Sampler, Radwaste Facility Iodine Sampler, Radwaste Facility Particulate Sampler)

NOTE----------------

Not required during short, controlled outages of gaseous effluent monitoring instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

I L.1 Suspend release of radioactive effluents by this pathway..

OR L.2.1 -NOTE------

The collection time of each sample shall not exceed 7 days.

Collect samples continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample.

Immediately Immediately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from end of each sample collection 16.11.3-9

.11/10104 l

Radioactive Effluent Monitoring Instrumentation 1 6.11.3 I

)

CONDITION I

REQUIRED ACTION COMPLETION TIME M. As required by Required Ac tion C. 1 and referenced in Table 16.11.3-2 for effluent from ventilation system or condenser air ejectors. (RIA-40)

NOTE--------------

Not required during short, controlled outages of gaseous effluent monitoring instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

M.1 Continuously monitor release through the unit vent.

OR M.2 Suspend release of radioactive effluents by this pathway.

OR M.3.1 Collect grab sample.

AND M.3.2 Analyze grab sample for gross activity (beta and/or gamma).

Immediately Immediately I Immediately AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 24 hours from collection of grab sample I

___a a___

16.11.3-10 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3

)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1*

SR 16.11.3.1

NOTE------------------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check.

During each release via*

this pathway 4

SR 16.11.3.2

NOTE--------------------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.3 Perform Source Check.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.1 1.3.4 Perform Source Check.

31 days SR 16.1 1.3.5 Perform Source Check.

92 days 16.11.3-1 1 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.:3.

SURVEILLANCE FREQUENCY SR 16.11.3.6

NOTE -------------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

Circuit failure (downscale only).

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 16.11.3.7

NOTE----------------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:.

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

Circuit failure (downscale only).

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 16.11.3.8 Perform CHANNEL FUNCTIONAL TEST.

92 days I.

.)

16.11.3-12 1 1/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9

NOTE---------------------------

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)

12 months Perform CHANNEL CALIBRATION.

SR 16.11.3.10 Perform CHANNEL CALIBRATION.

12 months SR 16.1 1.3.11 Perform leak test.

When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to each release via associated pathway

)

16.11.3-13 1 -11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS 2)

CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABIULTY REQUIREMENTS ACTION B.1

1.

Mon tors Providing Automatic Termination of i Release

a. IJquid Radwaste Effluent 1

At all times SR 16.11.3.1 E

lIne Monitor, RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9

b. Turbine Building Sump, 1

At all times SR 16.11.3.2 F

RIIA-54 SR 16.11.3A SR 16.11.3.7 SR 16.11.3.9

2.

Montors not Providing Automatic Termination of Release Low Pressure Service Water 1

At all times SR 16.11.3.2 H

RIA-,:5 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

3.

Flow Rate Measuring Devices

a. Uquid Radwaste Effluent I

At all times SR 16.11.3.1 G

Une Flow Rate Monitor SR 16.11.3.10 (CLW CR0725 or 01.W SS0920)

b. Ujuid Radwaste Effluent NA NA SR 16.11.3.1 NA Lie Minimum Flow SR 16.11.3.10 Davice

c.

Turbine Building Sump NA NA SR 16.11.3.1 NA M nimum Flow Device SR 16.11.3.10

d.

Lcw Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Davice

)

16.11.3-14 1 1/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS II-I CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

e.

Keovtee Hydroelectric NA NA SR 16.1 I.S.1 1 NA Tailalce Discharge (a)

4.

Continuous Composite Sampler

3 Chemical Treatment 1

At all Umes SR 16.11.3.2 H

Pond Composite Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turb'ne Building Sumps Effluent)

(a)

Flov Is determined from the number of hydro units operating. If no hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data.

, I )

16.11.3-15 11/10/04 l

Radioactive Effluent.Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION

)-

OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS I

MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH)

APPLICABILITY REQUIREMENTS ACTION C.1

1.

Unit VSent Monitoring System

-)

a.

Uloble Gas Activity Monitor Providing Alarm rind Automatic Termination of containment Purge lrelease (RIA Purge I3olatlon Function)

b.

faoble Gas Activity Monitor Providing Alarm.

(tlA Vent Stack flonitor Function)

c.

iodine Sampler

d.

Farticulate Sampler

e.

Effluent Flow Rate Nlonitor (Unit Vent Flow)

(GWD CR0037)

f.

Sampler Flow Rate N!onitor(a) (Annunciator)

g.

Effluent Flow Rate W onitor (Containment Purge) (PR CR0082)

h.

CSAE Off Gas Monitor (FIIA-40)

2.

Interim Radwaste Building Ventila lon Monitoring System

a.

Nable Gas Activity Monitor (RIA -53)

b.

Iodine Sampler

c.

Particulate Sampler

d.

Elfluent Flow Rate M nitor (Interim Radwaste Exhaust)

(CLWD FT0082)

e.

Sampler Flow Rate MWnltora') (Annunciator)

I I

At all times At All Times At All Times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 At All Times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 1

I 1

At All limes.

SR 16.11.3.2 SR 16.11.3.10 K

L L

J NA At All Times SR 16.11.3.2 SR 16.11.3.10 1

During Containment Purge Operation SR 16.11.3.2 SR 16.11.3.10 J

1 During Operation of CSAE SR 16.11.3.2 SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9 M

1 1

At All Times At All Times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9.

SR 16.11.3.2 At All Times SR 16.1 1.3.2 K

L L

J.

NA At All Times SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10

.1 At All Times 16.11.3-16 11/l 0/04 l

Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS i

)

MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH)

APPLICABILITY REQUIREMENTS ACTION C.1

3.

Hot Machine Shop Ventilation Sampling System

a.

Iodine Sampler

b.

Particulate Sampler

c.

Efflueni Flow Rate Monitor (Hot Machine w3hop Exhaust)

(Totalizer)

d.

S3ampler Flow Rate Monitor (a) (Annunciator)

4.

Radwaste Facility Ventilation Monitoring System

a.

I loble Gas Activity Monitor (4-RIA-45)

. 1 At All Times SR 16.11.3.2 SR 16.11.3.2 L

L 1

At All Times I

At All Times SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 J

NA 1

At All Times 1

At All Times SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 K

I

.b.

Iodine Sampler

c.

Ffrticulate Sampler

d.

Effluent Flow Rate Monitor (Radwaste Facility Exhaust) (OVS CR2060)

e.

Sampler Flow Rate IV onitor (a) (Annunciator) 1 1

At All Times SR 16.11.3.2 At All Times SR 16.11.3.2 I

Al All Times SR 16.11.3.2 SR 16.11.3.10 L

L NA.

1 At All Times SR 16.11.3.2 SR 16.11.3.10

5.

Waste Gas Holdup Tanks a.

N)ble Gas Activity Monitor-Providing Aami and Automatic Tormination of Release (F.lA-37,-38)b I

I During Waste Gas Holdup Tank Releases During Waste Gas Holdup Tank Releases SR 16.11.3.1 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.12 SR 16.11.3.1 SR 16.11.3.10

b.

Effluent Flow Rate

MonItor (Waste Gas Discharge Flow) (GWD Cl 033)

J (a)Alarms indicating low flow may be substituted for flow measuring devices.

(b)Either Normal or High Range monitor Is required dependent upon activity in tank being released.

I i

16.11.3-17 11/10/04 l

Radioactive Effluent Monitoring Instrumentation 16.11 3

)

BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarn/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases.. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Pail 50.

For certain applicable cases, grab samples or flow estimates are required at frequencies between every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months end every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months upon RIA removal from service. SLC 16.11.3 does not explicitly require Action (grab samples or flow estimates) to be initiated immediately upon RIA removal from service, when removal is for the purposes of sample filter changeouts, setpoint adjustments, service checks, or routine maintenance. Therefore, during the defined short, controlled outages, Action is not required.

For the cases in which Action is defined as continuous sampling by auxiliary equipment (Action L) initiation of continuous sampling by auxiliary sampling equipment requires approximately 1

hour. One hour is the accepted reasonable time to initiate collect and change samples.

Therefore. for the defined short, controlled outages (not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), Action is not required.

Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of Independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate.

REFERENCES:

1. 10CF:RPart20.

2. 10 CFR Part 50, Appendix A.

3. Offsite Dose Calculation Manual.

4. UFSAR, Section 7.2.3.4.

16.11.3-18 11/iO/04 I

Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY:

At all times ACTION_)

CONDITION REQUIRED ACTION COMPLETION TIME A.

NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A

)

I 16.11.4-1 1 i6/10/04 l

Operational Safety Review 16.11.4

-Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program I

I

.=

Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste

1.

Condensate Test Tank, Condensate Monitoring Tank, Laundry-Hot Shower Tank, Waste and Recycle Monitor Tanks

a.

Principal Gamma Emitters(c) Including Dissolved Noble Gases Composite Grab Sample prior to release of each batch(h)

<5E-06 ptCVml (Ce-144)

<5E-07 pCVml (Other Gamma Nuclides)

<1 E-05 pCVml (Dissolved Gases)

<1E-06,uCVml (1-131)

b.

Radiochemical Analysis Sr-89 and Sr-90

c.

Tritium Quarterly from all composited batches(f)

Monthly Composite

<5E-08 ptCVml

<1 E-05 tiCi/ml

d.

Gross Alpha Activity

a.

Iodine Spectrum (a)

2.

Unit Vent Samipling (Includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary Building Ventilation.

Spent Fuel Pocl Ventilation, Air Electors)

')

Monthly Composite Continuous monitor, weekly sample(e)

<1 E-07 tCVmIl

<1E-10 Cicc (1-133)0)

<1E-12 pCIcc (1-131)0)

b.

Particulates (a)

i.

Ce-144 & Mo-99 ii.

Other Principle Gamma Emitters (d)

Weekly Composite(e)

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample

<5E-10 p~i/cca)

1 E-11 I tCVccU

<1IE-04 iiCVcc lii.

Gross Alpha Activity iv.

Radiochemical Analysis Sr-89, Sr-GO

c.

Gases by Principle Gamma Emitters(d)

d.

Tritium Weekly Grab Sample

<1 E-06 pCVcc

3.

Waste Gas Decay -

Tank

a.

Principle Gamma Emitters(d)

Grab Sample prior to release of each batch

<1 E-04 pCicc (gases)

<1 E-1 0 pCicc (particulates and lodines)

<5E-09 9Cicc (Ce-144 and Mo-99)

<1 E-06 pCicc

b.

Tritium Grab Sample prior to release of each batch

4.

Reactor Building

a.

Principle Gamma Emitters(d)

Grab sample each purge

<1 E-04 piCVcc (gases)

<1E-1 0 tpCcc (particulates and lodines)

<5E-09 tLCVcc (Ce-144 and Mo-99)

<1 E-06 VCicc

b.

Tritium Grab sample each purge I

I 16.11.4-2 11/10/04 1

. Operational Safety RevieN 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program I I Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste

5.

Backwash Receiving Tanks

6.

3 Chemical Treatment Pond E~fluentQ)

Principle Gamma Emitters including dissolved Noble Gases

a.

Principle Gamma Emitters(c)

Grab Sample prior to release of each batch Weekly Continuous

Composite(g)

NA

<5E-07 pCiml

b.

1-131

c.

Tritium

d.

Gross Alpha Act vity Weekly Continuous Composite(g)

Monthly Continuous.

Composite(g)

Monthly Continuous Composite(g)

<1 E-06 pCilml

<1 E-05 pCimil

<1 E-07 pCimI

<5E08 iiCVml

<1 E-05 pCiml

e.

Sr-89 & Sr-90 Quarterly Continuous Composite(g)

I.

Dissolved and Entrained gases (Gamma Emitters)

Monthly Grab

)

Radwaste Facility

)

Ventilation a.

Iodine Spectrum(a)

Particulate(a)'

Continuous monitor.

weekly sample(e)

(1-133) <1E-09 pCVcc (1-131) <1E-1l1 pCVcc b.

i.

Ce-1 44 and Mo-99 Hi.

Other Principle Gamma Emitters(d)

Weekly Composite(e)

Weekly Composhe(e)

<5 E-1O0 pC~cco)

<1 E-1 I p~iccoj) iit.

Gross Alpha Activity Iv.

Radiochemical Analysis Sr-89, Sr-90

c.

Gases by Principle

. Gamma(d)

Emitters Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample c1 E-11 piCVcc

<1 E-01 pCiUcc

<1 E-04,pCicc

d.

Tritium Weekly Grab Sample

<1 E-06 pCicc I

16.11.4-3 11/10/04 l

Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for W'aste

8.

Hot Machine Shop Ventilation

a.

Iodine Spectrum Weekly Sample(e)

(1-133) <IE-10 pCVcca)

(1-131) <1E-12 pCVcco) b.

Particulate I.

Ce-144 and Mo-99 if.

Other Principle Gamma Emitters (d)

Iii.

Gross Alpha Activity Iv.

Radiochemical Analysis Sr-89, Sr-90 Weekly Composite(e)

Weekly Composite(e)

Monthly, using composite samples of one week.

Quarterly Composite

<5E-10 plC.cca)

<1 E-1 1 pCi/cc(j)

<1E-1l1 pCVcc

c.

Gases by Principle Gamma Emitters

d.

Tritium NA NA NA Weekly sample(e)

Interim RadwE ste

)

Building Ventilation a.

Iodine Spectrum NA (1-133) <lE-1O p.iCtccoj)

(1-131) <1E2-12 lpCiccoj) b.

Particulate I.

Ce-144 and Mo-99 iI.

Other Principle Gamma Emitters(d) iii.

Gross Alpha Activity Iv.

.Radlochemical Analysis Sr-89, Sr-90 Weekly Composite(e)

Weekly Composite(e)

Monthly, using composite samples of one week' Quarterly Composite

<5E-1 0 itCVcco)

<1E-11,gCVccq)

<1 E-1 I CVcc

<1E-I1 gCVcc

c.

Gases by Principle Gamma(d)

Emitters

d.

Tritium Weekly Grab Sample Weekly Grab Sample

<1 E-04 ItCVcc

<1 E-06 jiCVcc I

.}

16.11.4-4 11110104 1

Operational Safety Review 16.11.4 (a)

Samples shall be changed at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analysis shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing ion or after removal from sampler).

(b)

The LLD is defined for purposes of these commitments as the smallest concentration of radioactive material In a sample theA would be detected with 95% probability with 5% probabillty of falsely concluding that a blank observation represents a Preal' signal.

For a particular measurement system (which may include radiochemical separation):

LLD 4.66 sb E x V x 2.22E06 x Y x exp (-Apt)

Where:

LLD Is the 'a priorr lower limit of detection as defined above (as micro Curies per unit mass or volume),

)

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

-E is the counting efficiency (as counts per disintegration),

V Is the sample size (in units of mass or volume),

2.22Er6 Is the number of disintegrations per minute per micro Curie, Y Is the fractional radiochemical yield (when applicable),

A Is the radioactive decay constant for the particular nuclide A t Is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, riot environmental samples). NOTE: This assumes decay correction Is applied (at the time of analysis) for the duration of sample collection, for the time between collection and analysis, and for the duration of the counting.

Additionally, It does not apply to Isolated systems such as Waste Gas Decay Tanks and Waste Monitor Tanks.

Typical values of E, V. Y and A t should be used In the calculation.

It should be recognized that the LLD Is an a Iiori (before the fact) limit representing the capability of a measurement system and not an a oosterlori (after the fact) limit for a particular measurement.

(c)

The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn-54. Fe-59, Co-58, Co-130. Zn-65, Mo-99, Cs-134, Cs-137. and Ce-141. Ce-144 shall also be measured, but with a LLD of 5E.06 ttCVml. This list (loes not mean that only these nuclides are to be considered. Other gamma peaks that are Identifiable. together with the above nuclides shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

(d)

The principal gamma emitters for which the LLD commitment applies exclusively are the following radionuclides: Kr-87. Kr.

88, Xe-1133. Xe-133m, Xe-135. and Xe-138 for gaseous emissions and Mn-54, Fe-59. Co-58, Co-60, Zn-65.

Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulates. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and Identifiable, together with the above nuclides shall also be Idertifled and reported.

(e)

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made In accordance with SLC 16.11.2.a, SLC 16.11.2.b.1, and SLC 16.11.2.b.2.

A composite sample is one In which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and In which the method of sampling employed results In a specimen which Is representative of the liquids released.

(g)

To be representative of the quantities and concentrations of radioactive materials In liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the comrosite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

1 6.11.4-5 11/10/04 l

Operational Safety Review 16.11.4 (h)

A batch release Is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be Isclated, and then thoroughly mixed; to assure representative sampling.

I (i)

A continuous release Is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an Input flow during the continuous release.

(3)

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be Increased by a factor of 10.

1 6.11.4-6 11/10/04 l

Operational Safet,1 Review 16.11.4 EASES t )

IN/A F-EFERENCES:

N/A

/

16.11.4-7 11/10/04 l

Solid Radioactive Waste 16.11.5 16.11. RADIOLOGICAL EFFLUENTS CONTROL 16.11.5 Solid Radioactive Waste COMMI1MENT Radioactive wastes shall be processed and packaged to ensure compliance with the applicable requirements of 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71, and State regulations governing the transportation and disposal of radioactive wastes.

The Solid Radwaste System or an approved alternative process shall be used in accordance with a Process Control Program (PCP), for the solidification of liquid or wet radioactive wastes or the dewatering of wet radioactive wastes to be shipped for direct disposal at a 10 CFR 61 licensed disposal site. Wastes shipped for off site processing in accordance with the processors specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements.

The PCP describes administrative and operational controls used for the solidification of liquid or wet solid radioactive wastes in order to meet applicable 10 CFR 61 waste form requirements.

The PCP describes the administrative and operational controls used for the dewatering of wet radioactive wastes to meet 10 CFR 61 free standing water requirements.

The process parameters used in establishing the PCP shall be based

)

on demonstrated processing of actual or simulated liquid or wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.

APPLICABILITY:

At all times 1 6.11.5-1 10/30/02 l

Solid Radioactive Waste 16.111.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes wastes are not from the site.

satisfied.

AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.

B. A solidification test as B.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification.

test failures until solidification of the batch is verified by subsequent tests.

AND B.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.

16.11.5-2 16.115-2 0/30/02? I

. Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C.1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements.

inadequately processed accordance with the waste that requires PCFO.

OR solidification or C.2 Follow PCP or dewatering procedure guidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.

D. With, the solid waste D.1 Restore the equipment to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service.

capability to process*

wastes as necessary to satisfy all applicable disposal requirements.

SURVEILLANCE REQUIREMENTS

__=

SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.

every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.

I 1 6.11.5-3 10/30/02 l

Solid Radioactive Waste 16.11.5 BASES This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of 10 CFR Part 50, Appendix A and requirements to use a Process Control Program to meet applicable 1 OCFR61 waste form criteria for solidified and dewatered radioactive wastes.

REFERENCES:

1.

10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities".

2.

10 C1FR Part 50, Appendix A.

3.

10 CFR20, 'Standards for Protection Against Radiation".

4.

10 GFR61, 'Licensing Requirements for Land Disposal of Radioactive Waste".

5.

10 (1FR71, "Packaging and Transportation of Radioactive Materials".

6.

DPCo Process Control Program Manual.

7.

NR(C Generic Letter 87-12, "Compliance with 10 CFR Part 61 And Implementation Of the!

Radiological Effluent Technical Specifications (Rets) and Attendant Process Control Program (POP)".

8.

NRC, Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications In the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Rets to the Offsite Dose Calculation Manual or to the Process Control Program".

16.11.5-4 10/30/02 l

Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT

a.

The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1, 16.11.6-2 and 16.11.6-3.

b.

A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

c.

Analyses shall be performed on radioactive materials supplied as, part of an Interlaboratory Comparison Program. A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. The Interlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.

d.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

NOTE---------------------------------------------

If samples required by Commitment part a, become permanently unavailable from any of the required sample locations, the locations from which samples were unavailable may then be deleted from the program provided replacement samples were obtained and added to the environmental monitoring program, If available. These new locations will be identified in the Annual Radioactive Effluent Release Report.

APPLICABILITY:

At all times 1 6.11.6-1 02/0`1105 I

Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required.

prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.

B. Land use census B.1 NOTE-----------

identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained.

year in which this land use census was conducted.

Add new location to the 30 days radiological environmental monitoring program.

AND B.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release Report.

I

)

t 16.11.6-2 02/01105 l

Radiological Environmental Monitoring 16.11,6 i

I)

CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following C Dmparison Program actions in the Annual calendar year analyses not performed Radiological a<; required.

Environmental Operating Report.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

)

16.11.6-3 02/01/C'5 I

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program i

Exposure Pathway and/or Number of Sampling and Collection Time and Frequency of Analysis Sample Locations (b)

Frequency (d)

Loain b

1. AIREIORNE Radiolodine and 2 articulates

2. DIRECT RADIATION 5

Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.

40 Quarterly.

Radiolodine canister:

1-131 analysis weekly. Particulate sampler. Gross beta radioactivity analysis following filter change; and gamma Isotopic analysis of composite (by location) quarterly. (c)

Gamma dose quarterly.

3. WATERBORNE

a. Surface

,.)

2 Composite (a) sample over a 1 -month period.

3 Composite (a) sample over a 1-month period.

Gamma isotopic analysis monthly.

Composite for tritium analysis quarterly.

Conposite for gross beta and gamma Isotopic analyses monthly.

b. Driking Composite for tritium analysis quarterly.

c.

Sediment from Shoreline 2

Semiannually.

Gamma isotopic analysis semiannually.

I I

16.11.6-4 02/01/05 l

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program

=

Exposure Pathway and/or Number of Sampling and Collection Sample Sample Frequency {d)

Time and Frequency of Analysis Sample

~~Locations (b)

Frqec(d

4. INGIESTION

a.

Milk 4(e)

Semimonthly when Gamma Isotopic and 1-131 analysis animals are on pasture; semimonthly when animals are on monthly at other times.

pasture; monthly at other times.

b.

Fish 2

Semiannually. One Gamma Isotopic analysis sample each semiannually on edible portion.

commercially and recreatlonally Important species.

c.

Elroad-leaf 2

Monthly.

Gamma Isotopic analysis monthly.

Vegetation

==

(a)

Composite samples shall be collected by collecting an aliquot at Intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

(b)

Sample locations are Identified in the ODCM.

I

?

(c)

Ali tome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow radon and thoron daughter decay. If gross beta activity in air particulate samples is greater thein 10 times the yearly mean of control samples, gamma Isotopic analysis shall be performed on the individual samples.

(d)

Deviations are permitted from the required sampling schedule If specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period, (e)

Samples from milking animals in three locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals In each of three areas between 5 to 8 km distant Where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

1 16.11.6-5 02/01/05 l

Radiological Environmental Monitoring 16.11.6 Maximum Values for the Table 16.11.6-2 Lower Limits of Detection (LLD) (a) (c)

=

Water Particulate or Fish Milk Broad-leaf Sediment Analysih Gases pCrikg Vegetation (pCi/i)

(pCam3) wet)

(pCi/i)

(pCikg wet)

(pC/kg, dry)

Gross Eeta 4

1E-02 H3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) 7E-02 1

60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 15 60 La-140 15 15

==

(a)

The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample with 95% probability of detection and with 5% probability of falsely concluding that a blank observation represents a 'real' signal.

For a particular measurement system (which may include radiochemical separation):

LLD =

4.66 Sb ExVx2.22xYxexp (-XAt)

Where:

LII) is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

I I

1 6.11.6-6 02/01/05 I

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

E Is the counting efficiency (as counts per disintegration)

V Is the sample size (in units of mass or volume) 2 22 is the number of disintegrations per minute per picocurie Y Is the fractional radiochemical yield (when applicable)

X Is the radioactive decay constant for the particular radionuclide A t is the elapsed time between sample collection (or end of the sample collection period) and time of counting Typical values of E, V, Y and A t should be used In the calculation.

The LLD Is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LIDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of Interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described In the Annual Radiological Environmental Operating Report.

(b)

LLD for gamma Isotopic analysis for 1-131 in drinking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 in drinking water at all locations Is less than 1 mrem per year. Low level 1-131 analyses will be performed If abnormal releases occur which coild reasonably result in > 1 pCiliter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of I pCi/liter will be achieved.

(c)

Other peaks which are measurable and Identifiable, together with the radionuclides in Table 16.11.6-2, shal be Identified and reported.

16.11.6-7 02/01/05 l

Radiological Environmental Monitoding 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples

)

Airborne Broad-leaf Water Particulate or Fish Milk Vegetation Analysis (pCi/)

Gases (pCVkg, wet)

(pCi/l)

(pCVkg, wet)

(pCVM3)

(Ckwt H-3 2E04(a)

Mn-54 1 E03 3E04 Fe-59 4E02 1 E04 Co-58 1 E03 3E04 Co-60 3E02 1 E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3

1 E02 Cs-134 30 10 1 E03 60 1 E03 Cs-137 50 20 2E03 70 2E03 Ba-La-1.10 2E02 3E02

==

I

)

(a)

(b)

For drinking water samples. This Is 40 CFR Part 141 value.

If low level 1-131 analyses are performed.

I ?

1 6.11.6-8 02/01/05 l

Radiological Environmental Monitoring 16.11.6 BASES The environmental monitoring program required by this commitment provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which load to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories. The specified lower limits of detection corresp nd to less than the 10 CFR 50. Appendix I, design objective dose-equivalent of 45 mrem/y3ar for atmospheric releases to the most sensitive organ and individual. The land use census commitment is provided to assure that changes in the use of unrestricted.areas are identified and that modifications to the monitoring program are provided if required by the results of this census.

The requirements for participation in an Interlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

The following requirement(s) were relocated from the CTS 6.4.4.f during the conversion to ITS.

The station shall have a program to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1.

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM;

2.

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE EBOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census; and,

3.

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

16.11.6-9 02/01/05 l

Radiological Environmental Monitoring 16.

11.6 REFERENCES

1.

10 CFR Part 50, Appendix I.

.2.

011site Dose Calculation Manual.

16.11.6-10 02/01/05 l

Dose Calculations 16.1 ii.7

)

16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member cf the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to

25 mrems to the total body or to any organ, except the thyroid, which shall be limited to

75 mrems.

I APPLICABILITY:

At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Calculated doses from A.1 Determine by None the release of calculation, including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11.1.b, SLC whether the limits of 16.11.2.b.1, or SLC Commitment 16.11.7 16.11.2.b.2 have been exceeded.

)

16.11.7-1 01/31/00 I

Dose Calculations 16.11.7 f

I CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose exceeds limits of Commitment 16.11.7.

NOTE This Special Report, as defined in 10 CFR Part 20.2203(a), shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, (including all effluent pathways and direct radiation), for the calendar year that includes the release(s) covered by this report.

It shall also describe the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.

I

)

B.1 Prepare and submit to the Commission a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.

30 days I+

16.11.7-2 01/31/00 l

Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C.1 NOTE-eCceeds limit of Submittal of the report Commitment 16.11.7.

is considered a timely request, and a variance AND is granted until staff action on the request is Release condition complete.

resulting in violation of

40) CFR 190 not corrected at time of Include a request for a 30 days from exceeding report submittal.

variance in accordance the limit with the provisions of 40 CFR Part 190.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.7.1 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.

SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.

,)

BASES The dose commitment is provided to assure that the release of radioactive material in liquid and gaseous effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section IlI.A of Appendix I in that conformance with the guides of Appendix I is to be shown by calculations and procedures based on models and data sLch that the actual exposure of an individual through appropriate pathways is unlikely -to be substantially underestimated.

16.11.7-3 03127'/99

Dose Calculations 16.11.7 5

REFERENCES:

1.

IO1CFR Part 20.

2.

40 CFR Part 190.

3.

Off-3ite Dose Calculation Manual.

4.

10 CFR Part 50, Appendix I.

16.11.7-4 01/31/00 l

Reports 16.11.8 f'j)

.16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable SLC:

a.

Radioactive Liquid Effluents, Dose, SLC 16.11.1.b Liquid Waste Treatment, SLC 16.11.1.c Chemical Treatment Ponds, SLC-16.11.1.d

b.

Radioactive Gaseous Effluents, Dose, SLC 16.11.2.b Gaseous Radwaste Treatment, SLC 16.11.2.c

c.

Radiological Environmental Monitoring Program, SLC 16.11.6.a, b, and c

d.

Land Use Census, SLC 16.11.6.d

e.

Dose Calculations, SLC 16.11.7

)

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Individual milk samples A.1 Submit plan advising 7 days show 1-131 the NRC of the concentrations of 10 proposed action to picocuries per liter or ensure the plant related greater.

annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

II 1 6.11.8-1 09/25/03 1

Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected B.1 Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater within the design objective of 45 mrem/yr to the thyroid of any Individual.

=

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16. 11.8.1 NA NA I

)

BASES Reference applicable commitments.

REFERENCES:

1.

10 CFR Part 20.

2.

40 CFR Part 190.

3.

Offuite Dose Calculation Manual.

16.11.8-2 09/25/03 1

Radioactive Effluent Release Report 16.1 1.9 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.9 Radioactive Effluent Release Report COMMITMENT The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

A single submittal may be made for a multiple unit station. The submittal shall combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the station during the reporting period.

The annual Radioactive Effluent Release Report shall include a summa-y of the meteorological conditions concurrent with the release of gaseous effluents during each quarter.

The Annual Radioactive Effluent Release Report shall include an assessment of the radiation dose from radioactive effluents to members of

)

the public due to their activities inside the unrestricted area boundary during the reporting period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.

The Annual Radioactive Effluent Release Report shall include the followirg information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a.

A description of the event and equipment involved;

b.

Cause(s) for the unplanned release;

c.

Actions taken to prevent recurrence; and,

d.

Consequences of the unplanned release.

The Annual Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the station during each calendar quarter. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The annual average meteorological conditions shall be used for determining the gaseous pathway doses. Approximate and conservative approximate methods are acceptable. The assessment of radiation doses shall be performed in 16.11.9-1 111/14/00 I

Radioactive Effluent Release Report 16.11.9

)

accordance with the Offsite Dose Calculation Manual.

The Annual Radioactive Effluent Release Report shall include an explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation out of service for greater than 30 days was not corrected in a timely manner per SLC 16.11.3.

The Annual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Total container volume (cubic meters);

b.

Total curie quantity (determined by measurement or estimate);

c.

Principal radionuclides (determined by measurement or estimate);

d.

Type of waste, (e.g., spent resin, compacted dry waste evaporator bottoms);

e.

Number of shipments; and,

)

f.

Solidification agent (e.g., cement, or other approved agents (media)).

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to Unrestricted Areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census.

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed Member of the Public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

APPLICABILITY:

At all times.

1 6.11.9-2 01/31/00 l

Radioactive Effluent Release Report 16.11.9 II I

ACTION'S_

=

CONDITION REQUIRED ACTION COMPLETION TIME A.

N/A A.1 N/A N/A

=

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.9.1 NIA N/A I

I

)

BASES N/A

REFERENCES:

1.

Oconee ITS.

2.

Offsite Dose Calculation Manual.

I I

16.1 1.9-3 01/31/00 I

Radiological Environmental Operating Report 16.11.10 too 16.11 FADIOLOGICAL EFFLUENTS CONTROL

)

16.11.1 ) Radiological Environmental Operating Report COMMITMENT Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year.

The Annual Radiological Environmental Operating Report shall include summaries, interpretations. and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating Report shall include a summary of the results obtained as part of the required Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the radiological environmental samples required by SLCs taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practical in a supplementary report.

The Initial report shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of. each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses. Subsequent reports shall describe all substantial changes in these aspects.

APPLICAI31LITY:

At all times.

16.11.10-1 02/25001 1

Radiological Environmental Operating Rep )rt 16.11.10 I->

I.

ACTION S CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA

)

BASES NA

REFERENCES:

1.

2.

Oconee ITS Offsite Dose Calculation Manual I

16.11.10-2 02/25/03 1

t h

Iodine Radiation Monitoring filters 16.11.11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.

APPLIC(ABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NA A.1 NA NA SURVE ILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.

SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters.

life.

)

BASES The purpose of this commitment is to assure the reliability of the iodine radiation monitoring charcoal filters.

REFERENCES:

1.

Oconee CTS Amendment No. 3/3 SER date July, 1974.

16.11.11-1 03/27/99

Radioactive Material In Outside Temporary Tanks Exceeding Limit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material In Outside Temporary Tanks Exceeding Limit t

I COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.1 3.c.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.

storage tank not within limit.

SURV[-EILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material contained in each of the outside temporary tanks Is within the limit by analyzing a representative sample of the tanks' contents.

OR Verify the quantity of radioactive material In

..each of the. outside-temporary-tanks does -not result in exceeding the limit by analyzing a representative sample of radioactive material to be added.

Within 7 days after addition of radioactive materials to an outside temporary tank Prior to addition of tadioa'ctiv'materials to an outside temporary tank.

16.11.12-1 04/10/0)3I

Radioactive Material In Outside Temporary Tanks Exceeding Limit 113.1 1.12 BASES The requirement(s) of this SLC section were relocated from CTS 3.9.1.c during the conversion to ITS.

The tanks included in this specification are all those outdoor radwaste liquid storage tank; that are riot surrounded by liners, dikes, or walls capable of holding the tank contents and thai: do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the quantity of radioactive material contained in the specified tanks; provides assurance that in the event of an uncontrolled release of a tank's contents, the resulting concentrations would be less than the limits of IOCFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

REFERENCES N/A

)

16.11.12-2 04/10/03

Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13

i 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.13 Radioactive Material in Waste Gas Holdup Tank Exceeding Limit COMMITMENT APPLIC: ABI LITY:

The quantity of radioactive material in the Waste Gas Holdup tanks shall not exceed the limit specified in ITS 5.5.13.b.

At all times.

ACTIONS r-Separal:e Condition Entry is allowed for each tank.

)

CONDITION REQUIRED ACTION COMPLETION TIME A.

The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.

tank not within limit.

AND A.2 Reduce tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when tank is tank is within limit.

being filled BASES The requirement(s) of this SLC section were relocated from CTS 3.10.1.b and 3.10.1.c during the conversion to ITS.

16.11.13-1 03/27'/99

Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 Restricting the quantity of radioactivity contained in each waste gas holdup tank provides assurance that in the event of an uncontrolled release of the tank contents, the resulting total body exposure to an individual at the exclusion area boundary will not exceed 0.5 rem.

REFERENCE UFSAR, Section 15.10 16.11.13-2 0312 7199

Explosive Gas Mixture 16.11.14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture COMM ITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall tie

< 3% by volume.

APPLIC ABILITY:

At all times.

ACTIONS

-NO' Separate Condition Entry is allowed for each tank.

I---

)

CONDITION REQUIRED ACTION COMPLETION TIME:

A.

concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Hydrogen in Waste Gas of Hydrogen to within Holdup tank is > 3%

limit.

and

4% by volume.

B.

Concentration of B.1 Suspend addition of Immediately Hydrogen in Waste Gas waste gases to tank.

Holdup tank is > 4% by volume.

AND B.2 Reduce Concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Hydrogen to within limit.

16.11.14-1 03/27/99

Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank is < 3% by volume.

tank when in service AND once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank BASES The requirement(s) of this SLC section were relocated from CTS 3.10.2 and Table 4.1-3, Item 13 during the conversion to ITS.

This Commitment is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup Tanks is maintained below the flammability limits of hydrogen. (Administrative controls are used to prevent the hydrogen concentrations from reaching the flammability limit.) These controls include sampling each tank 5 times a week while in service, and/or once in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank; injection of dilutants to reduce the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive material will be controlled in conformance with the requirements of GDC 60 of Appendix A to CFR Part 50.

REFERENCES N/A 16.11.14-2 03/27/99

Enclosures

PCP Manual on CD:

For a summary of changes see APPENDIX H "Revision Summary -

Licensee Initiated Changes"

. ODCM Manual on CD: For a summary of changes see Chapter 7.0 "Licensee Initiated Changes"

ML061210398

Contents

Text

Subject:

SUMMARY

SUMMARY

.

=

=

SUMMARY

==

==

SUMMARY

SUMMARY

==

SUMMARY

=

SUMMARY

SUMMARY

.=..====.==

SUMMARY

SUMMARY

SUMMARY

..=.=..===...======

REFERENCES:

11.2 REFERENCES

REFERENCES:

REFERENCES:

11.6 REFERENCES

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

ML061210398

Text

Subject:

SUMMARY

SUMMARY

.

=

=

SUMMARY

==

==

SUMMARY

SUMMARY

==

SUMMARY

=

SUMMARY

SUMMARY

.=..====.==

SUMMARY

SUMMARY

SUMMARY

..=.=..===...======

REFERENCES:

11.2 REFERENCES

REFERENCES:

REFERENCES:

11.6 REFERENCES

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

Search