ML021510480

1. Total Release

2.

Avg. Release Rate Ci 0.00E+00 0.00E+00 wCi/sec 0.00E+00 0.00E+00

>= 8 days Ci 0.00E+00 pCi/sec 0.00E+00 3.19E-01 2.30E-01 4.01E-02 2.89E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 YEAR 1.02E+00 3.23E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ci 5.77E+01 5.37E+01 pCi/sec 7.43E+00 6.83E+00 3.89E+01 5.30E+01 4.89E+00 6.66E+00 2.03E+02 6.45E+00 REPORT FOR 2001

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS EFFLUENTS -

ELEVATED RELEASES CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1

1. Fission and Activation Gases

- No Nuclide Activities

2.

Iodines

- No Nuclide Activities

3.

Particulates Half Life >= 8 days

- No Nuclide Activities

4.

- No Nuclide Activities QTR 2 QTR 3 QTR 4 YEAR

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS EFFLUENTS -

ELEVATED RELEASES -

BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1

1. Fission and Activation Gases

- No Nuclide Activities

2. Iodines

- No Nuclide Activities

3. Particulates Half Life >= 8 days

- No Nuclide Activities

4.

- No Nuclide Activities QTR 2 QTR 3 QTR 4 YEAR

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS EFFLUENTS -

GROUND RELEASES -

CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities

2.

Iodines

- No Nuclide Activities

3.

Particulates Half Life >= 8 days

- No Nuclide Activities

4.

Tritium H-3 Totals for Period...

Ci 5.75E+01 5.35E+01 Ci 5.75E+01 5.35E+01 3.87E+01 5.28E+01 3.87E+01 5.28E+01 2.02E+02 2.02E+02

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS EFFLUENTS -

GROUND RELEASES -

BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001

1. Fission and Activation AR-41 KR-85 KR-85M XE-133 XE-135 Totals for Period...

Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR Gases Ci 1.86E-01 Ci 0.OOE+00 Ci 2.59E-05 Ci 1.21E-02 Ci 8.OOE-04 Ci 1.99E-01

2. Iodines

- No Nuclide Activities

3. Particulates Half Life >= 8 days

- No Nuclide Activities

4.

Tritium H-3 Totals for Period...

Ci 2.28E-01 Ci 2.28E-01 2.44E-01 6.53E-03

0. 00E+00

1. 84E-02 2.20E-04

2. 69E-01 2.13E-01

2. 44E-02 0.OOE+00

7. 85E-02

2. 40E-03 3.18E-01

1. 97E-01

0. OOE+00

0. OOE+00 3.16E-02

1. 32E-03 2.30E-01 8.41E-01 3.09E-02 2.59E-05

1. 41E-01 4.74E-03

1. 02E+00 2.33E-01 2.33E-01 2.18E-01 2.18E-01

1. 80E-01

1. 80E-01 8.59E-01 8.59E-01

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 1.81E-02

2. Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.OOE+00

b.

Batch Releases pCi/ml 7.52E-10 B.

1. Total Release Ci 1.71E+02

2. Average Diluted Concentration

a.

Continuous Releases pCi/ml 2.79E-07

b.

Batch Releases pCi/ml 7.05E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00

2.

Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.OOE+00

b.

Batch Releases pCi/ml 0.OOE+00 D.

Gross Alpha Radioactivity

1. Total Release Ci O.OOE+00

2.

Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.OOE+00

b.

Batch Releases PCi/ml 0.OOE+00 E.

Volume of Liquid Waste

1. Continuous Releases

2. Batch Releases liters 1.40E+08 liters 6.03E+05 F. Volume of Dilution Water

1. Continuous Releases liters 2.41E+09

2.

Batch Releases liters 2.41E+10 1.79E-02 2.65E-02 3.41E-02 9.66E-02 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 7.82E-10 1.07E-09 1.36E-09 9.97E-10 1.96E+02 1.45E+02 2.21E+02 7.33E+02 5.27E-07 7.83E-07 1.30E-06 7.32E-07 8.49E-06 5.81E-06 8.68E-06 7.50E-06 0.OOE+00 4.74E-04 3.93E-04 8.67E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.92E-11 1.56E-11 8.96E-12 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.25E+08 1.lIE+08 1.60E+08 5.35E+08 5.79E+05 1.36E+06 1.79E+06 4.33E+06 2.29E+09 2.47E+09 2.51E+09 9.68E+09 2.29E+10 2.47E+10 2.51E+10 9.68E+10

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID EFFLUENTS -

CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities

2.

Tritium H-3 Totals for Period...

Ci 7.12E-01 Ci 7.12E-01 1.27E+00

1. 27E+00 2.02E+00 3.47E+00 2.02E+00 3.47E+00

3. Dissolved and Entrained Gases

- No Nuclide Activities

4.

Gross Alpha Radioactivity

- No Nuclide Activities 7.47E+00 7.47E+00

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID EFFLUENTS -

BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2001 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR and Activation Totals for Period...

2.

Tritium H-3 Ci 1.81E-02 1.79E-02 2.64E-02 3.41E-02 9.66E-02 Ci Totals for Period...

Ci

3. Dissolved and Entrained Gases KR-85 Ci Totals for Period...

1.70E+02 1.95E+02 1.43E+02 2.18E+02 7.26E+02 1.70E+02 1.95E+02 1.43E+02 2.18E+02 7.26E+02

0. OOE+00 Ci 0.OOE+00

0. OOE+00

0. OOE+00 4.74E-04 4.74E-04

3. 93E-04

8. 67E-04

4.

Gross Alpha Radioactivity

- No Nuclide Activities

1. Fission AG-I1OM BA-140 BE-7 CO-57 CO-58 CO-60 CR-51 CS-134 CS-137 FE-59 1-131 1-133 MN-54 MN-56 NA-24 NB-95 NB-97 RU-103 SB-124 SB-125 SN-113 TC-99M W-187 ZN-65 ZR-95 ZR-97 Products Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

1. 91E-05

0. 00E+00 4.89E-04 9.83E-05 6.87E-03

7. 91E-03 5.40E-04

2. 01E-05

3. 65E-05 5.53E-05

0. OOE+00

1. 16E-03

0. OOE+00

o. OOE+00 5.83E-05 9.51E-05 0.OOE+00 0.OOE+00 7.59E-04

0. OOE+00

0. OOE+00 1.59E-06

0. OOE+00 2.50E-05 1.71E-06 3.29E-04 8.87E-05 4.48E-03

8. 98E-03 6.25E-04

1. 76E-05 2.44E-05 2.73E-05

0. OOE+00 0.OOE+00 8.23E-04 1 22E-05

0. OOE+00

4. 66E-05 2.14E-05

0. 00E+00 0.OOE+00

2. 37E-03

0. OOE+00

2. 17E-05

0. OOE+00

2. 01E-04

0. 00E+00

0. OOE+00

1. 07E-04

3. 59E-03

1. 83E-02

5. 95E-04

0. OOE+00

1. 68E-04

1. 27E-04 9.06E-07

7. 97E-07

2. OOE-03

0. OOE+00

3. 23E-05

2. 13E-05

1. 45E-06

0. OOE+00

1. 13E-03

0. OOE+00

2. 39E-05 9.34E-06

9. 81E-05

1. 45E-05 0.OOE+00 3.23E-05

0. OOE+00 7.55E-04 8.29E-05 1.59E-02 9.02E-03 2.89E-03

0. OOE+00

1. 41E-04 4.42E-04

0. OOE+00

1. 02E-03

8. 81E-07

5. 61E-06 2.19E-04 2.14E-05

0. OOE+00 7.75E-04

2. 60E-03

1. 02E-06

0. OOE+00

1. 12E-04 4.50E-05

2. 77E-04

1. 71E-06

1. 57E-03

3. 77E-04

3. 09E-02

4. 43E-02

4. 65E-03

3. 77E-05

3. 69E-04

6. 52E-04

9. 06E-07

7. 97E-07

5. OOE-03

1. 30E-05

5. 61E-06 3.56E-04

1. 59E-04

1. 45E-06

7. 75E-04

6. 86E-03

1. 02E-06

2. 39E-05 9.34E-06

9. 81E-05

1. 49E-04

4. 50E-05

ATTACHMENT fI Supplemental Information to the Liquid and Gaseous Effluents Report

CATAWBA NUCLEAR STATION 2001 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I.

REGULATORY LIMITS -

PER UNIT A.

NOBLE GASES -

AIR DOSE B.

LIQUID EFFLUENTS -

DOSE

1.

CALENDAR QUARTER

2.

CALENDAR QUARTER

3.

CALENDAR YEAR

4.

CALENDAR YEAR C.

IODINE -

131 AND 133,

1. CALENDAR QUARTER =

2.

CALENDAR YEAR

=

GAMMA DOSE =

5 MRAD BETA DOSE

= 10 MRAD GAMMA DOSE = 10 MRAD BETA DOSE

= 20 MRAD

1.

CALENDAR QUARTER

2.

CALENDAR QUARTER

3.

CALENDAR YEAR

4.

CALENDAR YEAR TOTAL BODY DOSE =

ORGAN DOSE

=

TOTAL BODY DOSE =

ORGAN DOSE

=

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

ORGAN DOSE 7.5 MREM 15 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 INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL V.

BATCH RELEASES A.

LIQUID EFFLUENT

1.

2.

3.

4.

5.

6.

1. 66E+02

8. 76E+03

8. 80E+01 5.28E+01 3.30E+01

4. 87E+04 TOTAL NUMBER OF BATCH RELEASES TOTAL TIME (MIN.)

FOR BATCH RELEASES.

MAXIMUM TIME (MIN.)

FOR A BATCH RELEASE.

AVERAGE TIME (MIN.)

FOR A BATCH RELEASE.

MINIMUM TIME (MIN.)

FOR A BATCH RELEASE.

AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B.

GASEOUS EFFLUENT

1.

2.

3.

4.

5.

9. 10E+01 9.98E+05

4. 40E+04

1. 10E+04

3. 10E+01 TOTAL NUMBER OF BATCH RELEASES.

TOTAL TIME (MIN.)

FOR BATCH RELEASES.

MAXIMUM TIME (MIN.)

FOR A BATCH RELEASE.

AVERAGE TIME (MIN.)

FOR A BATCH RELEASE.

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 1.5 MREM 5 MREM 3 MREM 10 MREM

SUPPLEMENTAL REPORT PAGE 2 CATAWBA NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at Catawba Nuclear Station has been determined to be +/- 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

=

+ 20%

(2) Counting error (3) Sample preparation error

=- +15%

= +-3%

ATTACHMENT HI Solid Waste Disposal Report

CATAWBA NUCLEAR STATION -

SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 1/1/2001 THROUGH 12/31/2001 Type of Waste Shipped

1. Waste from Liquid Systems (A)

Dewatered Secondary Resins (B)

Dewatered Primary Resins (C)

Evaporator Concentrates (D)

Dewatered Mechanical Filters (E)

Dewatered Demineralizers (F)

Solidified (Cement) Acids, Oils, Sludges

2.

Dry Solid Waste (A)

Dry Active Waste (compacted)

(B)

Dry Active Waste (non-compacted)

(C)

Dry Active Waste (brokered)

(D)

Irradiated Components Number of Number of Shipments Containers 0

3 0

1 0

0 0

1 0

0 3

0 1

0 0

0 1

0 Waste Container Class Type N/A 3B N/A iC N/A N/A N/A IAS N/A N/A 3HIC N/A IHIC N/A N/A N/A IHIC N/A Burial Volume (ft 3) (M 3L 0

360.9 0

120.3 0

0 0

120.3 800.0 0

0 10.22 0

3.41 0

0 0

3.41 22.65 0

3.

All Solid Waste 5 a 5a 1401.5 39.69 542.807 aoes not include brokered Dry Active Waste totals Total Activity (Curies) 0 241.2 0

291.1 0

0 0

8.628 1.879 0

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2001 THROUGH 12/31/2001 Type of Waste

1. Waste from Liquid Systems (A)

Dewatered Secondary Resins (B)

Dewatered Primary Resins (C)

Evaporator Concentrates (D)

Dewatered Mechanical Filters (E)

Dewatered Demineralizers (F)

Solidified Acids, Oils, Sludges Radionuclide (none shipped this Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Sn-113 Sb-125 Cs-134 Cs-137 C-14 Fe-55 Ni-59 Ni-63 (none shipped this Mn-54 Co-57 Co-58 Co-60 Zn-65 Ag-11Cm Sb-125 Fe-55 Ni-63 (none shipped this (none shipped this Abundance period) 0.7 4.8 0.2 1.8 0.1 12.1 0.1 0.2 0.2 0.7 0.2 37.9 0.3 40.6 period) 1.3 0.1 0.1 15.4 0.3 0.1 0.6 67.7 14.6 period) period)

Averaqe percent abundance for all shipments durinq period (unlisted if

<0.1%)

Page 1 of 3

CATAWBA NUCLEAR STATION -

SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2001 THROUGH 12/31/2001 Type of Waste

2.

Dry Solid Waste (A)

Dry Active Waste (compacted)

(B)

Dry Active Waste (non-compacted)

(C)

Dry Active Waste (brokered)

(D)

Irradiated Components Radionuclide

% Abundance (none shipped this period)

H-3 1.5 Cr-51 1.7 Mn-54 1.9 Co-57 0.1 Co-58 12.4 Co-60 13.9 Nb-95 0.4 Zr-95 0.3 Ag-il0m 0.2 Sb-124 0.1 Sb-125 0.5 Cs-134 0.1 Cs-137 0.1 Ba/La-140 0.2 Ce-144 0.1 Fe-55 57.4 Ni-63 9.1 H-3 1.5 Cr-51 1.3 Mn-54 1.9 Co-57 0.1 Co-58 11.3 Co-60 14.2 Nb-95 0.3 Zr-95 0.2 Ag-il0m 0.2 Sb-124 0.1 Sb-125 0.5 Cs-134 0.1 Cs-137 0.1 Ba/La-140 0.1 Ce-144 0.1 Fe-55 58.4 Ni-63 9.3 (none shipped this period)

Averaqe percent abundance for all shipments durinq period (unlisted if

<0.1%)

Page 2 of 3

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2001 THROUGH 12/31/2001 Type of Waste

3.

All Solid Waste Radionuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Zn-65 Sb-125 Cs-134 Cs-137 C-14 Fe-55 Ni-59 Ni-63

% Abundance 0.4 2.9 0.1 1.1 13.9 0.1 0.4 0.1 0.3 0.1 54.2 0.1 26.1 Averaqe percent abundance for all shipments durinq period (unlisted if

<0.1%)

Page 3 of 3

ATTACHMENT IV Meteorological Data

CATAWBA NUCLEAR STATION 2001 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 M LEVEL (Hours of Occurrence)

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ATTACHMENT V Unplanned Offsite Releases

CATAWBA NUCLEAR STATION UNPLANNED RELEASES (January 1, 2001 through December 31, There were no unplanned liquid or gaseous radioactivity releases to the environment in 2001.

2001)

ATTACHMENT VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

CATAWBA NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (January 1, 2001 through December 31, 2001)

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 Catawba 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 1/1/01 TO 1/1/02 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 1 st Quarter 2001

=-

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=

Quarter 1 2001 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q1 -

Maximum Organ Dose CHILD LIVER 2.78E-01 1.50E+01 1.85E+00 Maximum Organ Dose Receptor Location: 0.5 Mile N Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.00E+02

==

NOBLE GAS DOSE LIMIT ANALYSIS==-:====-

Quarter 1 2001 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Ql -

Maximum Gamma Air Dose 1.93E-03 1.00E+01 1.93E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41

9. 97E+01 Q1 -

Maximum Beta Air Dose 6.96E-04 2.OOE+01 3.48E-03 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.77E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2001

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS-== Quarter 2 2001 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q2 -

Maximum Organ Dose CHILD LIVER 2.58E-01 1.50E+01 1.72E+00 Maximum Organ Dose Receptor Location: 0.5 Mile N Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

-= NOBLE GAS DOSE LIMIT ANALYSIS=

ý Quarter 2 Dose Limit 2001

% of Period-Limit (mrad)

(mrad)

Limit Q2 -

Maximum Gamma Air Dose 2.53E-03 1.00E+01 2.53E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.97E+01 Q2 -

Maximum Beta Air Dose 9.27E-04 2.00E+01 4.64E-03 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.61E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2001

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=

Quarter 3 2001 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q3 - Maximum Organ Dose CHILD LIVER 1.87E-01 1.50E+01 1.25E+00 Maximum Organ Dose Receptor Location: 0.5 Mile N Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS-=

Quarter 3 2001

==

Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q3 - Maximum Gamma Air Dose 2.25E-03 1.00E+01 2.25E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.84E+01 Q3 - Maximum Beta Air Dose 9.30E-04 2.OOE+01 4.65E-03 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 8.37E+01 XE-133 9.86E+00 KR-85 5.69E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2001

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS--= Quarter 4 2001 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q4 -

Maximum Organ Dose CHILD LIVER 2.55E-01 1.50E+01 1.70E+00 Maximum Organ Dose Receptor Location: 0.5 Mile N Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3

1. OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS-Quarter Dose Limit 4 2001

% of Period-Limit (mrad)

(mrad)

Limit Q4 -

Maximum Gamma Air Dose 2.05E-03 l.00E+01 2.05E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.93E+01 Q4 - Maximum Beta Air Dose 7.59E-04 2.OOE+01 3.80E-03 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.47E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2001

=

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=

--= Annual 2001 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Yr - Maximum Organ Dose CHILD LIVER 9.78E-01 3.OOE+01 3.26E+00 Maximum Organ Dose Receptor Location: 0.5 Mile N Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.00E+02

==

NOBLE GAS DOSE LIMIT ANALYSIS:

Annual 2001 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Yr -

Maximum Gamma Air Dose 8.77E-03 2.OOE+01 4.39E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.92E+01 Yr -

Maximum Beta Air Dose 3.31E-03 4.OOE+01 8.28E-03 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.26E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 1 't Quarter 2001

=== BATCH LIQUID RELEASES Period-Limit Q1 -

Maximum Organ Dose ADULT Q1 - Total Body Dose TEEN Critical Critical Dose Age Organ (mrem)

Quarter Limit (mrem) 1 2001 Max % of Limit GI-LLI 2.12E-02 1.00E+01 2.12E-01 1.14E-02 3.OOE+00 3.80E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NB-95 3.65E+01 H-3 3.07E+01 CO-60 2.02E+01 MN-54 6.62E+00 CO-58 5.35E+00 Total Body Critical Pathway: Shoreline Sediment Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CO-60 H-3 CS-137 CS-134 4.38E+01 4.23E+01 5.53E+00 5.32E+00 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Ql -

Maximum Organ Dose ADULT LIVER 2.58E-04 Ql -

Total Body Dose ADULT 2.58E-04 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3

1. OOE+02 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Quarter 1 Limit (mrem) 1.OOE+01 3.OOE+00 2001

ý==

Max % of Limit 2.58E-03

8. 60E-03 1.00OE+02 H-3

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2001

=-

BATCH LIQUID RELEASES Period-Limit Q2 - Maximum Organ Dose Q2 - Total Body Dose Critical Age ADULT TEEN Critical Organ GI-LLI Quarter 2 Dose Limit (mrem)

(mrem) 2001.....

Max % of Limit 2.16E-02 1.00E+01 2.16E-01 1.31E-02 3.OOE+00 4.37E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 NB-95 CO-60 3.67E+01 3.05E+01 2.39E+01 Total Body Critical Pathway: Shoreline Sediment Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CO-60 4.58E+01 H-3 4.46E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q2 -

Maximum Organ Dose ADULT LIVER 4.92E-04 Q2 -

Total Body Dose ADULT 4.92E-04 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage Quarter 2 2001 Limit Max % of (mrem)

Limit 1.OOE+01 4.92E-03 3.OOE+00 1.64E-02 H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2001

=

BATCH LIQUID RELEASES Critical Critical Dose Period-Limit Age Organ (mrem)

Q3 -

Maximum Organ Dose TEEN GI-LLI 2.59E-02 Q3 -

Total Body Dose TEEN 1.91E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CO-60 H-3 NB-95 MN-54 Quarter Limit (mrem) 3 2001 Max % of Limit 1.00E+01 2.59E-01 3.00E+00 6.37E-01 6.24E+01 1.57E+01 1.17E+01 6.38E+00 Total Body Critical Pathway: Shoreline Sediment Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CO-60 6.03E+01 H-3 2.12E+01 CS-137 1.51E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q3 -

Maximum Organ Dose ADULT LIVER 7.39E-04 Q3 -

Total Body Dose ADULT 7.39E-04 Quarter 3 Limit (rem) 2001 Max % of Limit 1.OOE+01 7.39E-03 3.OOE+00 2.46E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or Nuclide Percentage H-3 greater to total) 1.OOE+02 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.OOE+02 greater to total)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4t Quarter 2001

=

BATCH LIQUID RELEASES Period-Limit Q4 -

Maximum Organ Dose Q4 - Total Body Dose Critical Age ADULT TEEN Critical Organ GI-LLI Dose (trem) 4.58E-02

1. 46E-02 Quarter 4 Limit (mrem) 1.00E+01 3.00E+00 2001 Max % of Limit 4.58E-01 4.87E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or Nuclide Percentage NB-95 H-3 CO-60 CO-58 greater to total) 6.22E+01

1. 79E+01

1. 05E+01 5.63E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 CO-60 CS-137 4.14E+01 3.81E+01

1. 63E+01 CONTINUOUS LIQUID RELEASES (WC)

=-

Quarter 4 2001 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Q4 -

Maximum Organ Dose ADULT LIVER 1.23E-03 1.OOE+01 1.23E-02 Q4 -

Total Body Dose ADULT 1.23E-03 3.OOE+00 4.10E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.00E+02 greater to total)

Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/01 TO 1/1/02 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2001 BATCH LIQUID RELEASES Annual 2001 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Yr - Maximum Organ Dose ADULT GI-LLI 1.13E-01 2.OOE+01 5.65E-01 Yr - Total Body Dose TEEN 5.83E-02 6.OOE+00 9.72E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage NB-95 4.23E+01 H-3 2.49E+01 CO-60 2.15E+01 MN-54 5.42E+00 Total Body Critical Pathway: Shoreline Sediment Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage CO-60 4.83E+01 H-3 3.56E+01 CS-137 1.10E+01

== CONTINUOUS LIQUID RELEASES (WC)

Annual 2001 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem)

(mrem)

Limit Yr - Maximum Organ Dose ADULT LIVER 2.74E-03 2.OOE+01 1.37E-02 Yr - Total Body Dose ADULT 2.74E-03 6.OOE+00 4.57E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3

1. 00E+02

Catawba Nuclear Station 2001 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose* Calculation Results Maximum Total Body Dose = 1.02E+00 mrem Maximum Location: 0.5 Mile, North Sector Critical Age = Child Liquid and Gas Effluent Contribution to Maximum Total Body Dose Liquid Effluent Dose = 3.97E-02 mrem = 4% of total Critical Path = Potable Water Major Contributors H-3 (68.9%)

Co-60 (20.0%)

Cs-137 (6.2%)

Gas Effluent Dose 9.78E-01 mrem = 96% of total Critical Path = Vegetation Major Contributor = H-3 (100%)

Maximum Organ Dose = 1.03E+00 mrem Maximum Location: 0.5 Mile, North Sector Critical Age = Child Critical Organ = LIVER Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 5.46E-02 mrem = 5% of total Critical Path = Fresh Water Fish Major Contributors H-3 (50.0%)

Cs-137 (30.2%)

Co-60 (11.5%)

Gas Effluent Dose 9.78E-01 mrem = 95% of total Critical Path = Vegetation Major Contributor = H-3 (100%)

Annual dose limits from 40CFR190.10(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

ATTACHMENT VII Revisions to the Updated Final Safety Analysis Report Radiological Effluent Controls Section 16.11

16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-1 LIQUID EFFLUENTS COMMITMENT:

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 16.11-1) shall be limited to ten 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 104 microCurie/ml total activity.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

TESTING REQUIREMENTS:

Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 16.11-1.

The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of SLC 16.11-1.

REFERENCES:

1.

2.

10 CFR Part 20, Appendix B BASES:

The basic requirements for Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10 CFR 50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of Chapter 16.11-1 Page 1 of 7 01/16/99

BASES (con't) the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302). These requirements 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 is reasonably achievable (ALARA) as set forth in 10 CFR 50, Appendix I.

As stated in the Introduction to Appendix B of the new 10 CFR 20, the liquid effluent concentration (EC) limits given in Appendix B, Table 2, Column 2, are based on an annual dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 mrem/year has been acceptable as a SLC limit for liquid effluents, which applies at all times as an assurance that the limits of 10 CFR 50, Appendix I are not likely to be exceeded, it should not be necessary to reduce this limit by a factor of 10.

Operational history at Catawba has demonstrated that the use of the concentration values associated with the old 10 CFR 20.106 as SLC limits has resulted in calculated maximum individual doses to a MEMBER OF THE PUBLIC that are small percentages of the limits of 10 CFR 50, Appendix I. Therefore, the use of concentration values which correspond to an annual dose of 500 mrem (ten times the concentration values stated in the new 10 CFR 20, Appendix B, Table 2, Column 2) should not have a negative impact on the ability to continue to operate within the limits of 10 CFR 50, Appendix I and 40 CFR 190.

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10 CFR 20, Appendix B, Table 2, Column 2, relate to a dose of 50 mrem in a year. When applied on an instantaneous basis, this corresponds to a dose rate of 50 mrem/year. This low value is impractical upon which to base effluent monitor setpoint calculations for many liquid effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.

Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11-1 are based on ten times the concentrations stated in the new 10 CFR 20, Appendix B, Table 2, Column 2, to apply at all times. The multiplier of ten is proposed because the annual dose of 500 mrem, upon which the concentrations in the old 10 CFR 20, Appendix B, Table II, Column 2, are based, is a factor of 10 higher than annual dose of 50 mrem, upon which the concentrations in the new 10 CFR 20, Appendix B, Table 2, Column 2, are based. Compliance with Chapter 16.11-1 Page 2 of 7 01/16/99

BASES (con't) the limits of the new 10 CFR 20.1301 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I and 40 CFR 190. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

This commitment applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Annal. Chem. 40, 586 93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Chapter 16.11-1 Page 3 of 7 01/16/99

TABLE 16.11-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPE

1. Batch Waste Release Tanks(2)

Any tank which discharges liquid wastes by either liquid effluent

monitor, EMF-49 or EMF-57 SAMPLING FREQUENCY P

Each Batch MINIMUM ANALYSIS FREQUENCY P

Each Batch TYPE OF ACTIVITY ANALYSIS Principle Gamma Emitters (3) 1-131 LOWER LIMIT OF DETECTION (LLD)(1)

(.Ci/ml) 5x1 07 1x X10-P M

Dissolved and lxi 05 One Batch/M Entrained Gases (Gamma emitters)

P M

H-3 lx1i0 Each Batch Composite(4)

Gross Alpha lx107 P

Each Batch Q

Composite(4)

Sr-89, Sr-90

2. Uontinuous Releases(5)

a. Conventional Waste Water Treatment Line Continuous(6)

W Composite(6)

Principal Gamma Emitters(3) 1-131 Chapter 16.11-1 Page 4 of 7 5x1 0-8 5xl 0-7 lxli 0-9/20/99 I

r

M M

Dissolved and lxi 10 Grab Sample Entrained Gases (Gamma Emitters)

M H-3 1 xl 0 Continuous(6)

Composite(6)

Gross Alpha I xi 01 Continuous(6)

Q Composite(6)

Sr-89, Sr-90 Chapter 16.11-1 Page 5 of 7 5xl 0 9/20/99

TABLE 16.11-1 (Page 2 of 3)

TABLE NOTATIONS (1)

The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 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 E. V-2.22 x 106 Y -exp (-.At)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

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

E = the counting efficiency (counts per disintegration),

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

2.22 x 106 = the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable,

?, = the radioactive decay constant for the particular radionuclide (sec&), and At = the elapsed time between midpoint of sample collection and time of counting (sec).

Typical values of E, V, Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an a rior (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Chapter 16.11-1 Page 6 of 7 01/16/99

TABLE 16.11-1 (Page 3 of 3)

TABLE NOTATIONS (Continued)

(2)

A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

(3)

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs 134, Cs-137, and Ce-141. The LLD for Ce-144 is 5x106 0gCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(4)

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 that is representative of the liquids released.

(5)

A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6)

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 analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

Chapter 16.11-1 Page 7 of 7 01/16/99

RADIOLOGICAL EFFLUENTS CONTROLS 16.11-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION COMMITMENT:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11-2 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of SLC 16.11-1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times.

REMEDIAL ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 16.11-2. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 why this inoperability was not corrected within the time specified.

TESTING REQUIREMENTS:

Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 16.11-3.

REFERENCES:

1.

2.

10 CFR Part 20

3.

10 CFR Part 50, Appendix A Chapter 16.11-2 Page 1 of 6 09/13/01 16.11

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 of liquid effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding 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.

Chapter 16.11-2 Page 2 of 6 09/13/01

TABLE 16.11-2 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT

1. Radioactivity Monitors Providing Alarm And Automatic Termination of Release

a. Waste Liquid Discharge Monitor (Low Range - EMF-49)

b. Turbine Building Sump Monitor (Low Range - EMF-31)

c. Deleted

d.

Monitor Tank Building Liquid Discharge Monitor (EMF-57)

2. Continuous Composite Samplers And Sampler Flow Monitor

a. Conventional Waste Water Treatment Line (no alarm/trip function)

3. Flow Rate Measurement Devices

a. Waste Liquid Effluent Line (no alarm/trip function)

b. Conventional Waste Water Treatment Line (no alarm/trip function)

c. Low Pressure Service Water Minimum Flow Interlock

d. Monitor Tank Building Waste Liquid Effluent Line (no alarm/trip function)

MINIMUM CHANNELS OPERABLE 1 per station 1

1 per station 1 per station 1 per station 1 per station 1 per station 1 per station Chapter 16.11-2 Page 3 of 6 ACTION C

E C

E D

D D

D I 1 09/13101

TABLE 16.11-2 (Page 2 of 2)

REMEDIAL ACTION STATEMENTS ACTION C -

ACTION D ACTION E -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with SLC 16.11-1; and

b. At least two technically qualified members of the facility staff independently verify:

1) The discharge line valving; and,

2) The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calculations if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 10i7 microCurie/ml:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131, or

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131.

Chapter 16.11-2 Page 4 of 6 09/13/01

TABLE 16.11-3 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHEC

1.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a.

Waste Liquid Discharge Monitor (Low Range - EMF-49) D

b.

Turbine Building Sump Monitor (Low Range - EMF-31)

D

c.

Deleted

d.

Monitor Tank Building Liquid Discharge Monitor (EMF-57) D

2.

Continuous Composite Samplers and Sampler Flow Monitor

a.

Conventional Waste Water Treatment Line D(3)

(no alarm/trip function)

3.

Flow Rate Measurement Devices

a.

Waste Liquid Effluent Line (no alarm/trip function)

D(3)

b.

Conventional Waste Water Treatment Line D(3)

(no alarm/trip function)

c.

Low Pressure Service Water Minimum Flow D(3)

Interlock

d.

Monitor Tank Building Waste Liquid Effluent Line D(3)

(no alarm/trip function)

K CHECK CALIBRATION TEST P

M P

N.A.

R(2)

Q(1)

R(2)

Q(1)

R N.A.

R R

N.A.

Q N.A.

Chapter 16.11-2 Page 5 of 6 09/13/01

TABLE 16.11-3 (Page 2 of 2)

TABLE NOTATIONS (1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm/Trip Setpoint; or,

b.

Circuit failure/Instrument downscale failure (alarm only)

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRAITON, sources that have been related to the initial calibration shall be used.

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

"For EMF-57, the alarm annunciation is in the Monitor Tank Building Control Room and on the MTB Control Panel Remote Annunciator panel.

Chapter 16.11-2 Page 6 of 6 09/13/01

16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-3 DOSE COMMITMENT:

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 16.11-1) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and

b.

During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.

TESTING REQUIREMENTS:

Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

The requirements of REMEDIAL ACTION (1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles downstream of the plant discharge.

Chapter 16.11-3 Page I of 2 01/16/99

REFERENCES:

1.

2.

40 CFR Part 141

3.

This commitment is provided to implement the requirements of Sections II.A, IiI.A and IV.A of Appendix i, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies that 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 Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation 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 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.

This commitment applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to commitments, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

Chapter 16.11-3 Page 2 of 2 01/16/99

16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-4 LIQUID RADWASTE TREATMENT SYSTEM COMMITMENT:

The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 16.11-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3.

Summary description of action(s) taken to prevent a recurrence.

TESTING REQUIREMENTS:

Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting SLC 16.11-1 and 16.11-3.

Chapter 16.11-4 Page 1 of 2 01/16/99

REFERENCES:

1.

10 CFR Part 50, Appendix A

2.

3.

The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement 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 commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1, 10 CFR Part 50, for liquid effluents.

This commitment applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to SLCs, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

Chapter 16.11-4 Page 2 of 2 01/16/99

16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-5 CHEMICAL TREATMENT PONDS COMMITMENT:

The quantity of radioactive material contained in each chemical treatment pond shall be limited by the following expression:

264. Y Ai

<1.0 V

j (Cj x 10) excluding tritium and dissolved or entrained noble gases, Where:

A j

pond inventory limit for single radionuclide "j", in Curies c j

10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", microCuries/ml; V

= design volume of liquid and slurry in the pond, in gallons; and 264

= conversion unit, microCuries/Curie per milliliter/gallon.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the quantity of radioactive material in any of the above listed ponds exceeding the above limit, immediately suspend all additions of radioactive material to the pond and initiate corrective action to reduce the pond contents to within the limit.

TESTING REQUIREMENTS:

The quantity of radioactive material contained in each batch of resin/water slurry to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of the batch to be Chapter 16.11-5 Page 1 of 3 08/01/94

TESTING REQUIREMENTS (con't) transferred to the chemical treatment ponds and shall be limited by the expression:

-< 0.006 j (C1 x10)

Where:

c j radioactive resin/water slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA chemical treatment ponds, in microCuries/milliliter; and Cj 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", in microCuries/milliliter.

REFERENCES:

1.

10 CFR Part 20, Appendix B

2.

3.

The inventory limits of the chemical treatment ponds (CTP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in this commitment assumes the pond inventory is uniformly mixed, that the pond is located in an uncontrolled area as defined in 10 CFR Part 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR Part 20 applies.

The batch limits of resin/water slurry transferred to the CTP assure that radioactive material transferred to the CTP are "as low is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in SLC 16.11-5 assures no batch will be transferred to the CTP unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than the ratio of the 10 CFR Part 50, Appendix I,Section II.A, total body dose level to the instantaneous whole body dose rate limitation, or that:

cj 3mrem/yr

- 0.006 (Cjxl0) 500mrem/yr Chapter 16.11-5 Page 2 of 3 02/07/01

BASES (con't)

Where:

c

radioactive resin/water slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA CTP, in microCuries/milliliter; and, C*

10 CFR Part 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", in microCuries/milliliter.

The filter/demineralizers using powdered resin and the blowdown demineralizer are backwashed or sluiced to a holding tank. The tank will be agitated to obtain a representative sample of the resin inventory in the tank. A known weight of the wet, drained resin (moisture content approximately 55 to 60%, bulk density of about 58 pounds per cubic foot) will then be counted. The concentration of the resin slurry to be pumped to the chemical treatment ponds will then be determined by the formula:

c QjWR VT Where:

Q

= concentration of radioactive materials in wet, drained resin for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life. The analysis shall include at least Ce-144, Cs-1 34, Cs-1 37, Co-58 and Co-60, in microCuries/gram. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent monthly composite analysis (within 3 months);

W R = total weight of resin in the storage tank in grams (determined from chemistry logs procedures); and, VT

= total volume of resin water mixture in storage tank to be transferred to the chemical treatment ponds in milliliters.

The batch limits provide assurance that activity input to the CTP will be minimized, and a means of identifying radioactive material in the inventory limitation of this commitment.

Chapter 16.11-5 Page 3 of 3 08/01/94

RADIOLOGICAL EFFLUENTS CONTROLS 16.11-6 GASEOUS EFFLUENTS DOSE RATE COMMITMENT:

The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrem/yr to the whole body and less than or equal to 3000 mrem/yr to the skin; and,

b.

For Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

TESTING REQUIREMENTS:

The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

The dose rate due to Iodine-1 31, Iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 16.11-4.

Chapter 16.11-6 Page I of 7 16.11 01/16/99

REFERENCES:

1.

10 CFR Part 20, Appendix B

2.

3.

10 CFR Part 20 BASES:

The basic requirements for Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10 CFR 50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1301). These requirements 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 mrems. 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 is reasonably achievable (ALARA) as set forth in 10 CFR 50, Appendix I.

As stated in the Introduction to Appendix B of the new 10 CFR 20, the gaseous effluent concentration (EC) limits given in Appendix B, Table 2, Column 1, are based on an annual dose of 50 mrems for isotopes for which inhalation or ingestion is limiting or 100 mrems for isotopes for which submersion (noble gases) is limiting.

Since release concentrations corresponding to limiting dose rates less than or equal to 500 mrems/year to the whole body, 3000 mrems/year to the skin from noble gases, and 1500 mremslyear to any organ from Iodine-1 31, Iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than eight days at the site boundary has been acceptable as a SLC limit for gaseous effluents to assure that the limits of 10 CFR 50, Appendix I and 40 CFR 190 are not likely to be exceeded, it should not be necessary to restrict the operational flexibility by incorporating the dose rate associated with the EC value for isotopes based on inhalation/ingestion (50 mrems/year) or the dose rate associated with the EC value for isotopes based on submersion (100 mrems/ year).

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10 CFR 20, Appendix B, Table 2, Column 1, relate to a dose of 50 or 100 mrems in a year. When applied on an instantaneous basis, this corresponds to a dose rate of 50 or 100 mrems/year.

Chapter 16.11-6 Page 2 of 7 01/16/99

BASES (con't)

These low values are impractical upon which to base effluent monitor setpoint calculations for many gaseous effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.

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 mrems/year to the whole body and 3000 mrems/year to the skin; and for Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days, an instantaneous dose rate limit of 1500 mrems/year to any organ.

Compliance with the limits of the new 10 CFR 20.1301 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I and 40 CFR 190. Operational history at Catawba has demonstrated that the use of the dose rate values listed above (i.e., 500 mrems/year, 3000 mrems/year, and 1500 mrems/year) as SLC limits has resulted in calculated maximum individual doses to MEMBERS OF THE PUBLIC that are small percentages of the limits of 10 CFR 50, Appendix I and 40 CFR 190. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

This commitment applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques", Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Chapter 16.11-6 Page 3 of 7 01/16/99

TABLE 16.11-4 (Page l of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Minimum Type of Activity Analysis Lower Limit of Frequency Analysis Detection (LLD)(1)

Frequency (RtCi/ml)

1. Waste Gas Storage Tank P

P Principal Gamma Emitters 2V lxi0-4 Each Tank Each Tank Grab Sample

2. Containment Purge P

P Each PURGE(3)

Each PURGE(3)

Principal Gamma Emitters(2) 1x10 4 Grab Sample M

H-3 (oxide) lxi 15"

3. Unit Vent W (3)4)

W(J)

Principal Gamma Emitters*z) lx1i04 Grab Sample________________________

H-3 (oxide) lxl1 Ob

4. Containment Air Release and D(j)(**

Db Principal Gamma Emitters P 1x10-4 Addition System Grab Sample M

H-3 (oxide) l xi 05

5. All Release Types as listed In 3 Continuous(')

D 1-131 1x10"11 above.

Charcoal Sample 1-133 1 xli 0Q Continuous(')

DV Principal Gamma Emitters")*

lxi 0lu Particulate Sample Continuous(')

M Gross Alpha(

lx 10"1 Composite Particulate Sample Continuous N)

Q Sr-89, Sr-90 1x10 11 Composite Particulate Sample Chapter 16.11-6 Page 4 of 7 01 /16/9 9

TABLE 16.11-4 (Page 2 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Minimum Type of Activity Analysis Lower Limit of Frequency Analysis Detection (LLD)(1)

Frequency (gCi/ml)

6. Waste Monitor Tank Building W

W Principal Gamma Emitterstz 1x10.4 Ventilation Exhaust Grab Sample H-3 (oxide) lX10"b ContinuousIj)

W 1-131 1x10"11 Charcoal Sample 1-133 1 xi 0"9 Continuous(U)

W Principal Gamma Emitters~z) lxi "U Particulate Sample Continuous(b)

M Gross Alpha 1x1 01 1 Composite Particulate Sample Continuous")

Q Sr-89, Sr-90 lxl0i11 Composite Particulate Sample Chapter 16.11-6 Page 5 of 7 01/16/99

TABLE 16.11-4 (Page 3 of 4)

TABLE NOTATIONS (1)

THE LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =466sb E.V-2.22 x 106 -Y" exp (-).*t)

Where:

LLD

= the "a priori" lower limit of detection (microCurie per unit mass or volume);

Sb

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

E

= the counting efficiency (counts per disintegration);

V

= the sample size (units of mass or volume);

2.22 X 106 -

the number of disintegrations per minute per microCurie; Y

= the fractional radiochemical yield, when applicable; X

= the radioactive decay constant for the particular radionuclide (sec1 ); and At

= the elapsed time between midpoint of sample collection and time of counting (sec).

Typical values of E, V, Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an a pror (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Chapter 16.11-6 Page 6 of 7 01/16/99

TABLE 16.11-4 (Page 4 of 4)

TABLE NOTATIONS (Continued)

(2)

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe 138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I 131, Cs-134, Cs-137, and Ce-141 in Iodine and particulate releases. The LLD for Ce-1 44 is 5xl 0-9 [Ci/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3)

Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER stabilization (power level constant at desired power level) after a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, for at least one of the three gaseous release types with this notation.

(4)

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5)

Required sampling and analysis frequency during effluent release via this pathway.

(6)

The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLCs 16.11-6, 16.11-8, and 16.11-9.

(7)

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

(8)

The composite filter(s) will be analyzed for alpha activity by analyzing one filter per week to ensure that at least four filters are analyzed per collection period.

Chapter 16.11-6 Page 7 of 7 01/16/99

RADIOLOGICAL EFFLUENTS CONTROLS 16.11-7 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION COMMITMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 16.11-5 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of SLC 16.11-6 are not exceeded. The Alarm/Trip Setpoints of these channels meeting SLC 16.11-6 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 16.11-5.

REMEDIAL ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 16.11-5. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 why this inoperability was not corrected within the time specified.

TESTING REQUIREMENTS:

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 16.11-6.

REFERENCES:

1.

2.

10 CFR Part 20 Chapter 16.11-7 Page 1 of 11 10/11/01 16.1__.1

BASES:

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 of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 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 sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of SLC 16.11-8 shall be such that concentrations as low as 1 x 10-6 gCVcc are measurable.

Chapter 16.11-7 Page 2 of 11 10/11/01

TABLE 16.11-5 (Page 1 of 5)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Operable Applicability

1.

Waste Gas Holdup System

a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (Low Range - EMF-50)

b.

Effluent System Flow Rate Measuring Device

2.

Condenser Evacuation System Noble Gas Activity Monitor (Low Range - EMF-33)

3.

Vent System

a.

Noble Gas Activity Monitor (Low Range - EMF-36)

b.

Iodine Sampler (EMF-37)

c.

Particulate Sampler (EMF-35)

d.

Unit Vent Stack Flow Rate Meter (no alarm/trip function)

e.

Unit Vent Radiation Monitor Flow Meter 1 per station 1 per station 1

1 1

Chapter 16.11-7 Page 3 of 11 Instrument Action 1,2,3,4,#

C D

H E

G G

D G

10/11/01

TABLE 16.11-5 (Paae 2 of 5)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Operable Applicability

4.

Containment Purge System Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (Low Range - EMF-39)

5.

Containment Air Release and Addition System Noble Gas Activity Monitor - Providing Alarm (Low Range - EMF-39)

6.

Monitor Tank Building HVAC

a.

Noble Gas Activity Monitor Providing Alarm (EMF-58)

b.

Monitor Tank Building Effluent Flow Rate Measuring Device 1

At all times outside of modes 1,2,3,4 1

1,2,3,4,5,6 1 per station 1 per station Chapter 16.11-7 Page 4 of 11 Instrument Action F

"**k E

D 10/11/01 I

TABLE 16.11-5 (Paae 3 of 5)

TABLE NOTATIONS At all times except when the isolation valve is closed and locked.

At all times.

Apply Action Hb in Modes 5 and 6 ACTION STATEMENTS ACTION C -

ACTION D ACTION E -

With the number of channels OPERABLE less than required the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release either:

a. Vent system noble gas activity monitor providing alarm and automatic termination of release (Low Range - EMF-36) has at least one channel OPERABLE; or,

b.

At least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the facility staff independently verify:

1. The discharge valve lineup; and

2.

The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calculations if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples Chapter 16.11-7 Page 5 of 11 1 0/11/01

TABLE 16.11-5 (Page 4 of 5)

ACTION F ACTION G ACTION H -

TABLE NOTATIONS are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation may continue with EMF-39 inoperable for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with the affected unit below MODE 4, provided the following conditions are satisfied:

(a) EMF-36 for the affected unit is OPERABLE and in service, (b) The Reactor Coolant System for the affected unit has been vented, and (c) If the reactor vessel head is not in place (bolts not required),

one of the following two conditions shall be met:

(c0)

All irradiated fuel assemblies have been removed from the containment structure, or (c2)

The lifting of heavy loads over the reactor vessel and the movement of irradiated fuel assemblies within containment have been suspended.

Otherwise, immediately suspend PURGING of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 16.11-4.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:

a.

Effluent release via the CSAE System (ZJ) may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

b.

Gaseous effluent releases via the BB system atmospheric vent valve (BB27) in the off normal mode may continue for up to 30 days provided grab samples of steam generator water are Chapter 16.11-7 Page 6 of 11 10/11/01

TABLE 16.11-5 (Page 5 of 5)

TABLE NOTATIONS analyzed for radioactivity at a lower limit of detection of no more than 1 E-7 microCurie/ml:

1. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01: microCurie/gram DOSE EQUIVALENT 1-131, or

2.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131.

ACTION I -

With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, containment releases to the environment through this pathway may continue provided that prior to initiating the release:

a.

Vent system noble gas activity monitor providing alarm and automatic termination of release (Low Range - EMF-36) has at least one channel OPERABLE; or,

b.

At least two independent samples of the containment atmosphere are analyzed, and at least two technically qualified members of the facility independently verify:

1.

The discharge valve lineup; and

2.

The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calculations if such calculations are performed manually.

Restore the inoperable instrumentation to OPERABLE status within 30 days, or explain in the next Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3, why this.

inoperability was not corrected within the time specified.

If the instrumentation remains, or is anticipated to remain, inoperable for 90 days or longer, re-evaluate the configuration of the affected unit in accordance with the applicable portions of 1 OCFR50.59 and 1 OCFR50.65(a)(4), prior to expiration of the 90 days.

Chapter 16.11-7 Page 7 of 11 10/11/01

TABLE 16.11-6 (Page 1 of 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Modes For Channel Which Channel Source Channel Operational Surveillance Instrument Check Check Calibration Test Is Required

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (Low Range-EMF-50)

P P(4)

R(3)

Q(1)

b. Effluent System Flow Rate Measuring P

N.A.

R N.A.

Device

2. Condenser Evacuation System Noble Gas Activity Monitor (Low Range - EMF-33)

D M(4)

R(3)

Q(1) 1,2,3,4 (BB27 is only isolation function required)

3. Vent System

a. Noble Gas Activity Monitor (Low Range - EMF-36)

D M(4)

R(3)

Q(2)

b. Iodine Sampler (EMF-37)

W N.A.

N.A.

c. Particulate Sampler (EMF-35)

W N.A.

N.A.

Chapter 16.11-7 Page 8 of 11 10/11/01

TABLE 16.11-6 (Page 2 of 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument

d. Unit Vent Stack Flow Rate Meter (no alarm/trip function)

e. Unit Vent Radiation Monitor Flow Meter

4. Containment Purge System Noble Gas activity Monitor - Providing Alarm and Automatic Termination of Release (Low Range - EMF-39)

Channel Check D

D S

Source Check N.A.

N.A.

P(4)

Channel Calibration R

R R(3)

Channel Operational Test N.A.

N.A.

R(1)

Modes For Which Surveillance Is Required During movement of irradiated fuel assemblies in containment; During CORE ALTERATIONS

5. Containment Air Release and Addition System Noble Gas Activity Monitor - Providing Alarm (Low Range - EMF-39)

S P(4)

R(3)

Q(1) 1,2,3,4,5,6 Chapter 16.11-7 Page 9 of 11 10/11/01

TABLE 16.11-6 (Page 3 of 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Channel Check Source Check Channel Calibration Channel Operational Test Modes For Which Surveillance Is Required

6. Monitor Tank Building HVAC

a. Noble Gas Activity Monitor - Providing Alarm (EMF-58)

b. Discharge Flow Instrumentation Chapter 16.11-7 Page 10 of 11 D

D M

N.A.

R(3)

R Q(2)

N.A.

- ~

10/11/01

TABLE 16.11-6 (Page 4 of 4)

TABLE NOTATIONS At all times except when the isolation valve is closed and locked.

At all times.

1.

For noble gas activity monitors providing automatic termination of release, the CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm/Trip Setpoint; or,

b.

Circuit failure/Instrument downscale failure (Alarm only)

2.

The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation# occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm Setpoint; or,

b.

Circuit failure/Instrument downscale failure

3.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

4.

A source check for these channels shall be the qualitative assessment of channel response when the channel sensor is exposed to a light emitting diode.

For EMF-58, the alarm annunciation is in the Monitor Tank Building Control Room and on the MTB Control Panel Remote Annunciator Panel.

Chapter 16.11-7 Page 11 of 11 10/11/01

RADIOLOGICAL EFFLUENT CONTROLS 16.11-8 DOSE - NOBLE GASES COMMITMENT:

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrad for beta radiation; and,

b.

During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

TESTING REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

REFERENCES:

1.

2.

10 CFR Part 50, Appendix I Chapter 16.11-8 Page 1 of 2 01/16/99 16.11

BASES:

This commitment is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.B of Appendix 1. The REMEDIAL ACTION statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The Testing Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation 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 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactives waste producing units sharing the Radwaste Treatment System. For determining conformance to commitments, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

Chapter 16.11-8 Page 2 of 2 01/16/99

16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11-9 DOSE - IODINE-131. IODINE-133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM COMMITMENT:

The dose to a MEMBER OF THE PUBLIC from Iodine-1 31, Iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 mrem to any organ;

and,

b.

During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the calculated dose from the release of Iodine-1 31, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

TESTING REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-1 31, Iodine-1 33, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

REFERENCES:

1.

2.

10 CFR Part 50, Appendix I Chapter 16.11-9 Page 1 of 2 01/16/99

BASES:

This commitment is provided to implement the requirements of Sections II.C, lIl.A and IV.A of Appendix I, 10 CFR Part 50, and are the guides set forth in Section II.C of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation 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 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate commitments for Iodine-1 31, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airbome radionuclides, (2) deposition of radionuclides onto 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.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to commitments, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

Chapter 16.11-9 Page 2 of 2 01/16/99

16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11-10 GASEOUS RADWASTE TREATMENT SYSTEM COMMITMENT:

The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) would exceed either:

a.

0.2 mrad to air from gamma radiation; or,

b.

0.4 mrad to air from beta radiation; or,

c.

0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report that includes the following information:

1.

Identification of any inoperable equipment or subsystems, and the reason for the inoperability;

2.

Action(s) taken to restore the inoperable equipment to OPERABLE status;

and,

3.

Summary description of action(s) taken to prevent a recurrence.

TESTING REQUIREMENTS:

Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

Chapter 16.11-10 Page 1 of 2 01116/99

TESTING REQUIREMENTS (con't)

The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting SLCs 16.11-6, 16.11-8, or 16.11-9.

REFERENCES:

1.

2.

The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This commitment implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 1I.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to commitments, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

Chapter 16.11-10 Page 2 of 2 01/16/99

16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11-11 SOLID RADIOACTIVE WASTES COMMITMENT:

Radioactive wastes shall be solidified or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

a.

With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the Solid Radwaste System as necessary to prevent recurrence.

b.

With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.

TESTING REQUIREMENTS:

SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, altemative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed Chapter 16.11-11 Page 1 of 2 01/16/99

TESTING REQUIREMENTS (con't) using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM;

b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required to assure SOLIDIFICATION of subsequent batches of waste; and,

c.

With the installed equipment incapable of meeting SLC 16.11-11 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.

REFERENCES:

1.

10 CFR Part 50, Appendix A

2.

3.

10 CFR Part 50 BASES:

This commitment implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

Chapter 16.11-11 Page 2 of 2 01/161699

RADIOLOGICAL EFFLUENT CONTROLS 16.11-12 TOTAL DOSE COMMITMENT:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of SLCs 16.11-3a, 16.11-3b, 16.11-8a, 16.11-8b, 16.11-9a, or 16.11-9b, calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of this commitment have been exceeded. If such is the case, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, 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 levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

TESTING REQUIREMENTS:

Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SLCs 16.11-3, 16.11-8 and 16.11-9, and in accordance with the methodology and parameters in the ODCM.

Chapter 16.11-12 Page 1 of 2 16.11 01116/99

TESTING REQUIREMENTS: (cont'd)

Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in the REMEDIAL ACTION of this commitment.

REFERENCES:

1.

2.

10 CFR Part 20

3.

40 CFR Part 190 BASES:

This commitment is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The commitment requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in SLC 16.11-1 and 16.11-6. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Chapter 16.11-12 Page 2 of 2 01/16/99

16.11 RAIOLOGICAL EFFLUENT CONTROLS 16.11-13 MONITORING PROGRAM COMMITMENT:

The Radiological Environmental Monitoring Program shall be conducted as specified in Table 16.11-7.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

a.

With the Radiological Environmental Monitoring Program not being conducted as specified in Table 16.11-7, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11-7 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11-3, 16.11-8, and 16.11

9. When more than one of the radionuclides in Table 16.11-7 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) +

>1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 16.11-7 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*

to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11-3, 16.11-8 and 16.11-9. This report is not required if the measured level of radioactivity was not the The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

Chapter 16.11-13 Page 1 of 14 01/16/99

REMEDIAL ACTION (con't) result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2.

c.

With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 16.11-7, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.5.1, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

TESTING REQUIREMENTS:

The radiological environmental monitoring samples shall be collected pursuant to Table 16.11-7 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 16.11-7 and the detection capabilities required by Table 16.11-8.

REFERENCES:

1.

2.

10 CFR Part 50 Appendix I BASES:

The Radiological Environmental Monitoring Program required by this commitment provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The initially specified monitoring program will be effective for at least the first 3 years of commercial Chapter 16.11-13 Page 2 of 14 01/16/99

BASES (con't) operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 16.11-8 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a Ddod (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem.

40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques", Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Chapter 16.11-13 Page 3 of 14 01/16/99

TABLE 16.11-7 (Page 1 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

1. Direct Radiation(2)

NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(')

Forty routine monitoring stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6-to 8-km range from the site;

and, The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

SAMPLING AND COLLECTION FREQUENCY Quarterly TYPE AND FREQUENCY OF ANALYSIS Gamma dose quarterly Chapter 16.11-13 Page 4 of 14 01/16/99

TABLE 16.11-7 (Page 2 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

2.

Airborne Radioiodine and Particulates NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(')

Samples from five locations.

Three samples from close to the three SITE BOUNDARY locations, in different sectors, of the highest calculated annual average ground level D/Q; One sample from the vicinity of a community having the highest calculated annual average ground level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

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

TYPE AND FREQUENCY OF ANALYSIS Radioiodine Canister:

1-131 analysis weekly.

Particulate Sampler:

Gross beta radioactivity analysis following filter change; (3) and gamma isotopic analysis (4) of composite (by location) quarterly.

Chapter 16.11-13 Page 5 of 14 01/16/99

TABLE 16.11-7 (Page 3 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

3. Waterborne

a. Surface(5)

b. Ground

c. Drinking

d. Sediment from Shoreline NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(')

One sample upstream.

One sample downstream.

Samples from one or two sources only if likely to be affected(7)

One sample of each of one to three of the nearest water supplies that could be affected by its discharge.

One sample from a control location.

One sample from downstream area with existing or potential recreational value.

SAMPLING AND COLLECTION FREQUENCY Composite sample over 1-month period (6).

Quarterly Composite sample over 2-week period (6) when 1-131 analysis is performed; monthly composite otherwise.

Semiannually.

TYPE AND FREQUENCY OF ANALYSIS Gamma isotopic analysis (4) monthly. Composite for tritium analysis quarterly.

Gamma isotopic (4) and tritium analysis quarterly.

1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year(6 ).

Composite for gross beta and gamma isotopic analyses (4) monthly. Composite for tritium analysis quarterly.

Gamma isotopic analysis (4) semiannually.

Chapter 16.11-13 Page 6 of 14 01/16/9 9

TABLE 16.11-7 (Page 4 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

4. Ingestion

a. Milk

b. Fish and Invertebrates NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1 )

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 P reater than 1 mrem per year(8. One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

One sample each of a predatory species, a bottom feeder and a forage species in vicinity of plant discharge area.

One sample each of a predatory species, a bottom feeder and a forage species in areas not influenced by plant discharge.

SAMPLING AND COLLECTION FREQUENCY Semimonthly when animals are on pasture; monthly at other times.

Sample in season, or semiannually if they are not seasonal.

TYPE AND FREQUENCY OF ANALYSIS Gamma isotopic (4) and 1-131 analysis semi-monthly when animals are on pasture; monthly at other times.

Gamma isotopic analysis (4) on edible portions.

Chapter 16.11-13 Page 7 of 14 01/16/99

TABLE 16.11-7 (Page 5 of 8)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE

4.

Ingestion (Continued)

c. Food Products NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(')

One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged.

Samples of three different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in the least prevalent wind direction if milk sampling is not performed.

SAMPLING AND COLLECTION FREQUENCY At time of harvest (9).

Monthly, when available.

TYPE AND FREQUENCY OF ANALYSIS Gamma isotopic analyses (4) on edible portion.

Gamma isotopic (4) and 1-131 analysis.

Chapter 16.11-13 Page 8 of 14 01 /16/9 9

TABLE 16.11-7 (Pa-qe 6 of 8)

TABLE NOTATIONS Specific parameters of distance and direction sector from the centerline of the station, and additional description where pertinent, shall be provided for each and every sample location in Table 16.11-7 in a table and figure(s) in the ODCM. Refer to NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of any Licensee Event Report required 10 CFR 50.73 and pursuant to Technical Specification 5.6.3, identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

2.

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. (The 40 stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

Chapter 16.11-13 Page 9 of 14 01/16/99

TABLE 16.11-7 (Page 6 of 8)

TABLE NOTATIONS (Cont'd)

3.

Airborne 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 for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

4.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

5.

The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

6.

A composite sample is one in which the rate at which the liquid sampled is uniform and in which the method of sampling employed results in a specimen that is representative of the time averaged concentration at the location being sampled. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

7.

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

8.

The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

9.

If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

Chapter 16.11-13 Page 10 of 14 01/16/99

TABLE 16.11-7 (Page 8 of 8)

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBOURNE PARTICULATE OR GASES (pCi/m 3)

FISH (pCi/kg, wet)

Milk (pCi/I)

FOOD PRODUCTS (pCi/kg, wet) 30,000 10,000 30,000 10,000 20,000 ANALYSIS H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 WATER (pCi/1) 20,000(1) 1,000 400 1,000 300 300 400 2

30 50 200 3

60 70 300 100 1,000 2,000 (1) For drinking water samples. This pCi/I may be used.

is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 Chapter 16.11-13 Page 11 of 14 01/16/99 0.9 10 20 1,000 2,000

LOWER LIMIT OF DETECTION (LLD)13)

ANALYSIS WATER AIRBORNE FISH MILK FOOD SEDIMENT (pCi/I)

PARTICULATE (pCi/kg, wet)

(pCi/I)

PRODUCTS (pCi/kg, dry)

OR GASES (pCi/kg, wet)

(pCi/m 3)

Gross Beta 4

0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1(4) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/I may be used.

Chapter 16.11-13 Page 12 of 14 01 /16/9 9

TABLE 16.11-8 (Page 2 of 3)

TABLE NOTATIONS

1.

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

2.

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

3.

The LLD is defined, for purposes of these commitments, as the smallest concentrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD4.66s b

LLD=

E. V-2.22 Y -exp (-A t)

Where:

LLD

= the "a priori" lower limit of detection (picoCuries per unit mass or volume);

Sb

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

E

= the counting efficiency (counts per disintegration);

V

= the sample size (units of mass or volume);

2.22

= the number of disintegrations per minute per picoCurie; Y

= the fractional radiochemical yield, when applicable; x

= the radioactive decay constant the particular radionuclide (sec&);

and, Chapter 16.11-13 Page 13 of 14 01/16/99

TABLE 16.11-8 (Page 3 of 3)

TABLE NOTATIONS (Cont'd)

At

= the elapsed time between environmental collection, or end of the sample collection period, and time of counting (sec).

Typical values of E, V, Y and At should be used in the calculation.

It should be recognized that the LLD is defined as an a prior (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

4.

LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

Chapter 16.11-13 Page 14 of 14 01/16/99

RADIOLOGICAL EFFLUENT CONTROLS 16.11-14 LAND USE CENSUS COMMITMENT:

A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m 2 (500 ft2) producing broad leaf vegetation.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

a.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in SLC 16.11-9, identify the new location(s) in the next Radioactive Effluent Release Report pursuant to Technical Specification5.6.3.

b.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with SLC 16.11-13, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 5.5.1, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s), with information supporting the change in the sampling locations.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Commitments for broad leaf vegetation sampling in Table 16.11-7.4.c shall be followed, including analysis of control samples.

Chapter 16.11-14 Page 1 of 2 16.1._.1 01/16/99

TESTING REQUIREMENTS:

The Land Use Census shall be conducted during the growing season at least once per 12 months 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. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

REFERENCES:

1.

2.

This commitment is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Apl endix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantify (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2.

Chapter 16.11-14 Page 2 of 2 01/16/99

RADIOLOGICAL EFFLUENT CONTROLS 16.11-15 INTERLABORATORY COMPARISON PROGRAM COMMITMENT:

Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 16.11-7.

APPLICABILITY:

At all times.

REMEDIAL ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

TESTING REQUIREMENTS:

The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

REFERENCES:

1.

2.