ML091260527

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2008 Annual Radioactive Effluent Release Report
ML091260527
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 04/30/2009
From: Morris J
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML091260527 (55)
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JAMES R. MORRIS, VICE PRESIDENT PDuke dEnergy Duke Energy Carolinas, LLC Catawba Nuclear Station Carolinas 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax April 30, 2009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 2008 Annual Radioactive Effluent Release Report Pursuant to Catawba Nuclear Station Technical Specification (TS) 5.6.3 and Selected Licensee Commitment 16.11-16, please find attached the Catawba Annual Radioactive Effluent Release Report for the period of January 1, 2008 through December 31, 2008.

In accordance with Catawba TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment I Summary of Gaseous and Liquid Effluents Report Attachment II Supplemental Information Attachment III Solid Waste Disposal Report Attachment IV Meteorological Data Attachment V Unplanned Offsite Releases Attachment VI Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

Attachment VII Revisions to UFSAR Section 16.11 Radiological Effluent Controls Attachment VIII Revisions to the Radioactive Waste Process Control Program Manual Attachment IX Information to Support the NEI Groundwater Protection Initiative Enclosure 2008 Offsite Dose Calculation Manual (changes described in Chapter 7) www. duke-energy corn

U.S. Nuclear Regulatory Commission 2008 Annual Radioactive Effluent Release Report April 30, 2009 Page 2 Any questions concerning this report should be directed to Marc Sawicki at (803) 701-5191.

Sincerely, A

James R. Morris Attachments and Enclosure (Offsite Dose Calculation Manual (ODCM))

U.S. Nuclear Regulatory Commission 2008 Annual Radioactive Effluent Release Report April 30, 2009 Page 3 xc (with attachments and enclosure):

L.A. Reyes, NRC Region II Administrator U.S. Nuclear Regulatory Commission-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 J.H. Thompson NRR Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A Rockville, MD 20852-2738 xc (with attachments only):

Russell Keown, Supervisor Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 803-896-0856/KEOWNRHJ dhec.sc.gov Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 803-896-3890/FLEMMI SA(a.dhec.sc. gov

U.S. Nuclear Regulatory Commission 2008 Annual Radioactive Effluent Release Report April 30, 2009 Page 4 bxc:

MJ Sawicki CNOIRC TV Wright CN02RP BN Kimray CN02RP JW Foster CN02RP CD Ingram EC07F NCMPA-1 PMPA NCEMC INPO William Nestel ANI William G. Wendland ELL EC050 RGC Data File Master File CN-801.01, A. T. Sabisch NRC Senior Resident Inspector (with attachments only)

ATTACHMENT I Summary of Gaseous and Liquid Effluents Report This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 I

REPORT FOR 2008 Unit QTR 1 QTR 2- QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 1.04E+00 7.66E-01 7.94E-01 9.93E-01 3.59E+00
2. Avg. Release Rate bLCi/sec 1.32E-01 9.74E-02 9.99E-02 1.25E-01 1.14E-01, B. Iodine-131
1. Total Release Ci 0.OOE+00 0.OOE+i00 0.00E+00 0.OOEi-00 0.OOE..00
2. Avg. Release Rate ,LCi/sec 0.OOE+00 0.OOE+00 0.OOEi-00 0.OOE+00 0.OOE+00 C. Particulates Half Life >= 8 da (s
1. Total Release Ci 0.OOE+00 0.OOE+i00 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg. Release Rate pCi/sec 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 D. Tritium
1. Total Release Ci 8.41E+01 5.58E+01 5.08E+01 6.80E+i01 2.59E+02
2. Avg. Release Rate pCi/sec 1.07E+01 7.10Ei-00 6.39E+00 8.55E+00 8.18E+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOEi-00
2. Avg. Release Rate ACi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+i00 0.OOE+00

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 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
    • No Nuclide Activities **
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities **
2. Iodines
    • No Nuclide Activities ** .o o.... ... .......
3. Particulates Half Life >= 8 days
    • No Nuclide Activities **.......
4. Tritium
    • No Nuclide Activities **
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 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 Ci 8.39E+01 5. 56E+01 5.06E+01 6.69E+01 2.57E+02 Totals for Period... Ci 8.39E+01 5.56E+01 5.06E+01 6. 69E+01 2. 57E+02
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 8.17E-01 6.15E-01 7.29E-01 8.60E-01 3.02E+00 KR-85 Ci 1.49E-02 0.OOE+00 0.OOE+00 0.OOE+00 1.49E-02 XE-133 Ci 1.98E-01 1.47E-01 6.20E-02 1.23E-01 5.30E-01 XE-135 Ci 8.53E-03 4. 31E-03 2.84E-03 9.54E-03 2.52E-02 Totals for Period... Ci 1.04E+00 7.66E-01 7.94E-01 9.93E-01 3.59E+00
2. lodines
    • No Nuclide Activities **
3. Particulates Half Life >= 8 days
    • No Nuclide Activities ** ........
4. Tritium H-3 Ci 1.81E-01 1.98E-01 1. 98E-01 1.04E+00 1. 62E+00 Totals for Period... Ci 1.81E-01 1.98E-01 1.98E-01 1.04E+00 1.62E+00
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

j

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 3.43E-03 8.76E-03 2.69E-02 5.32E-03 4.44E-02
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 0.OOE+00 0. 00E+00 0.OOE+00 0.OOE+00 0.00E+00
b. Batch Releases yCi/ml 1.24E-10' 3.01E-10 8.02E-10 1.99E-10 3.80E-10 B. Tritium
1. Total Release Ci 2.44E+02 1.94E+02 1.50E+02 .8.21E+01 6.70E+02
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 2.07E-07 2.06E-07 3.45E-07 3.56E-07 2.80E-07
b. Batch Releases ACi/ml 8.83E-06 6.65E-06 4.43E-06 3.04E-06 5.71E-06 C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Batch Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 D. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00
b. Batch Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste
1. Continuous Releases liters 9.43E+07 1.26E+08 6.33E+07 9.38E+07 3.77E+08
2. Batch Releases liters 5.42E+05 8.52E+05 1.35E+06 5.86E+05 3.34E+06 F. Volume of Dilution Water
1. Continuous Releases liters 2.76E+09 2.91E+09 3.35E+09 2.67E+09 1.17E+10
2. Batch Releases liters 2.76E+10 2.91E+10 3.35E+10 2.67E+10 1.17E+ll

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID EFFLUENTS - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 5.90E-01 6.24E-01 1. 18Ei-00 9.84E-01 3.38E+00 Totals for Period... Ci 5.90E-01 6.24E-01 1. 18E+00 9.84E-01 3.38E+00
3. Dissolved and Entrained Gases
    • No Nuclide Activities **
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID EFFLUENTS - BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products BA-140 Ci 1.30E-05 0.OOE+00 0. OOE+00 0.OOE+00 1.30E-05 CO- 57 Ci 0. 00E+00 0. OOE+00 2.35E-05 1. 61E-05 3. 96E-05 CO-58 Ci 4. 92E-04 1.73E-03 4.83E-03 2. 60E-03 9. 65E-03 CO-60 Ci 6. 89E-04 4.33E-04 1.67E-03 1.06E-03 3.85E-03 CR-51 Ci 0 OOE+00 2.73E-04 2.28E-04 0.OOE+00 5. O1E-04 CS-137 Ci 0. 00E+00 2.83E-05 0. OOE+00 0.OOE+00 2.83E-05 CS-138 Ci 0 OOE+00 0.OOE+00 2.18E-05 0. OOE+00 2.18E-05 F-18 Ci 0 OOE+00 0.OOE+00 0.OOE+00 9.26E-06 9.26E-06 FE-59 Ci 1. 58E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.58E-05 1-131 Ci 0. 00E+00 0. OOE+00 6.90E-06 0.OOE+00 6.90E-06 MN-54 Ci 9.02E-06 3.19E-05 4.20E-05 3.07E-05 1.14E-04 NA-24 Ci 0.OOE+00 0.OOE+00 3.24E-05 0.OOE+00 3 .24E-05 NB-97 Ci 2.20E-05 9. 66E-06 0.OOE+00 0 OOE+00 3. 17E-05 SB-122 Ci 5.59E-06 0.OOE+00 0.OOE+00 0 OOE+00 5.59E-06 SB-124 Ci 8.50E-05 1.06E-04 5.73E-03 2. 13E-04 6. 14E-03 SB-125 Ci 2.08E-03 6.15E-03 1.43E-02 1. 39E-03 2. 39E-02 Y-91M Ci 0. OOE+00 7.62E-07 0.OOE+00 0 OOE+00 7.62E-07 ZR-95 Ci 1. 03E-05 0.OOE+00 0.OOE+00 0 OOE+00 1. 03E-05 Totals for Period... Ci 3.43E-03 8.76E-03 2.69E-02 5.32E-03 4.44E-02
2. Tritium H-3 Ci 2.44E+02 1.94E+02 1.49E+02 8.11E+01 6.67E+02 Totals for Period... Ci 2.44E+02 1.94E+02 1.49E+02 8.11E+01 6.67E+02
3. Dissolved and Entrained Gases
    • No Nuclide Activities **
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

ATTACHMENT II Supplemental Information To the Gaseous and Liquid Effluents Report

CATAWBA NUCLEAR STATION 2008 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - PER UNIT A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE

1. CALENDAR QUARTER - GAMMA DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 1.5 MREM
2. CALENDAR QUARTER - BETA DOSE = 10 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 5MREM
3. CALENDAR YEAR - GAMMA DOSE = 10 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 3 MREM
4. CALENDAR YEAR - BETA DOSE = 20 MRAD 4. CALENDAR YEAR - ORGAN DOSE = 10 MREM C. GASEOUS EFFLUENTS - IODINE - 131 AND 133, TRITIUM, PARTICULATES WITH HALF-LIVES > 8 DAYS - ORGAN DOSE
1. CALENDAR QUARTER = 7.5 MREM
2. CALENDAR YEAR = 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 ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A

SUMMARY

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

V. BATCH RELEASES A. LIQUID EFFLUENT

1. 6.20E+01 = TOTAL NUMBER OF BATCH RELEASES
2. 4.42E+03 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 8.70E+01 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 7.12E+01 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 3.60E+01 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
6. 5.86E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 5.70E+01 = TOTAL NUMBER OF BATCH RELEASES.
2. 1.02E+06 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 4. 90E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 1.80E+04 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.08E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES = 0
2. TOTAL ACTIVITY RELEASED (CURIES) = 0 B. GASEOUS
1. NUMBER OF RELEASES = 0
2. TOTAL ACTIVITY RELEASED (CURIES) = 0

SUPPLEMENTAL REPORT PAGE 2 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 =- 15%

(3) Sample preparation error - +-3%

ATTACHMENT III Solid Radioactive Waste Disposal Report

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 1/1/2008 TO 12/31/2008 Total Number of Number of Waste Container Burial Vol ume Activity Type of Waste Shipped Shipments (M3)

Containers Class Type (ft) (Curies)

1. Waste from Liquid Systems (A) Dewatered Secondary Resins 0 0 NA NA 0.0 0.00 0.000 (B) Dewatered Primary Resins 1 1 1B 1 HIC 120.3 3.41 56.337 (C) Evaporator Concentrates 0 0 NA NA 0.0 0.00 0.000 (D) Dewatered Mechanical Filters 0 0 NA NA 0.0 0.00 0.000 (E) Dewatered Demineralizers 0 0 NA NA 0.0 0.00 0.000 (F) Solidified (Cement) Acids, Oils, Sludges 0 0 NA NA 0.0 0.00 0.000
2. Dry Solid Waste (A) Dry Active Waste (compacted) 0 0 NA NA 0.0 0.00 0.000 (B) Dry Active Waste (non-compacted) .0 0 NA NA 0.0 0.00 0.000 (C) Dry Active Waste (brokered) NA NA NA NA 7323.4 207.40 3.463 (D) Irradiated Components 0 0 NA NA 0.0 0.00 0.000
3. All Solid Waste 1 1 NA NA 7443.7 210.81 59.800
  • Does not included brokered Dry Active Waste totals.

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2008 TO 12/31/2008 Type of Waste Shipped Radionuclide  % Abundance*

1. Waste from Liquid Systems (A) Dewatered Secondary Resins (None shipped this period)

(B) Dewatered Primary Resins H-3 0.0%

Cr-51 0.0%

Mn-54 0.4%

Co-57 0.1%

Co-58 0.1%

Fe-59 0.0%

Co-60 7.2%

Zn-65 0.0%

Nb-95 0.0%

Zr-95 0.0%

Ag-1 08m 0.0%

Ag-11im 0.0%

Sn-113 0.0%

Sb-124. 0.0%

Sb-125 0.3%

Ba-1 33 0.0%

Cs-1 34 0.2%

Cs-137 1.1%

Np-237 0.0%

Ce-144 0.0%

Pu-238 0.0%

Pu-239 0.0%

C-14 0.0%

Fe-55 18.7%

Ni-59. 0.6%

Ni-63 71.2%

Sr-89 0.0%

Sr-90 0.0%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

(C) Evaporator Concentrates (None shipped this period)

(D) Dewatered Mechanical Filters (None shipped this period)

(E) Dewatered Demineralizers (None shipped this period)

(F) Solidified (Cement) Acids, Oils, Sludges (None shipped this period)

  • Average percent abundance for all shipments during period. Page 1 of 3

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2008 TO 12/31/2008 Type of Waste Shipped Radionuclide  % Abundance *

2. Dry Solid Waste (A) Dry Active Waste (compacted) (None shipped this period)

(B) Dry Active Waste (non-compacted) (None shipped this period)

(C) Dry Active Waste (brokered) H-3 2.6%

Cr-51 0.1%

Mn-54 1.8%

Co-57 0.3%

Co-58 20.6%

Fe-59 0.0%

Co-60 8.1%

Zn-65 0.0%

Nb-95 1.1%

Zr-95 0.6%

Ag-1 08m 0.0%

Ag-11Orn 0.0%

Sn-113 0.0%

Sb-124 0.0%

Sb-1 25 0.0%

Ba-1 33 0.0%

Cs-134 0.1%

Cs-137 0.1%

Np-237 0.0%

Ce-144 0.7%.

Pu-238 0.0%

Pu-239 0.0%

C-14 2.4%

Fe-55 43.5%

Ni-59 0.0%

Ni-63 17.9%

Sr-89 0.0%

Sr-90 0.2%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

(D) Irradiated Components (None shipped this period)

  • Average percent abundance for all shipments during period. Page 2 of 3

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2008 TO 12/31/2008 Type of Waste Shipped Radionuclide % Abundance *

3. All Solid Waste H-3 0.2%

Cr-51 0.0%

Mn-54 0.5%

Co-57 0.1%

Co-58 1.3%

Fe-59 0.0%

Co-60 7.2%

Zn-65 0.0%

Nb-95 0.1%

Zr-95 0.0%

Ag-1 08m 0.0%

Ag-11im 0.0%

Sn-113 0.0%

Sb-124 0.0%

Sb-125 0.3%

Ba-1 33 0.0%

Cs-1 34 0.2%

Cs-137 1.0%

Np-237 0.0%

Ce-144 0.0%

Pu-238 0.0%

Pu-239 0.0%

C-14 0.2%

Fe-55 20.2%

Ni-59 0.6%

Ni-63 68.1%

Sr-89 0.0%

Sr-90 0.0%

Tc-99 0.0%

1-129 0.0%

Am-241 0.0%

Pu-241 0.0%

Cm-242 0.0%

Cm-243 0.0%

  • Average percent abundance for all shipments during period. Page 3 of 3

ATTACHMENT IV Meteorological Data Meteorological Joint Frequency Distributions of Wind Speed, Wind Direction and Atmospheric Stability using-winds at the 10 M Level (Hours of Occurrence).

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A WIND SPEED CLASS I I

------------------------------------ I I 1.00-1 1.25-1 1.50-I 2.00-1 3.00-1 4.00-1 5.00-I 6.00-1 I 1 1.24 1 1.49 1 1.99 1 2.99 I 3._99 I 4.99 I 5.99 I 7.99 ITOTAL I I----------------+- - ------ +--

+-...

.---- - + I+-

I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I - - +-- -+-------- +------ +------+-----+-------- ---- --- -I SECTOR I I I I I I I I I I I --------------------------- I I I I I I I I I-N- I .1 -I .I 51 101 101 41 11 301 I------------------------------------------------------------------------ +-+--+ I l-NNE- I .1 .I '1 5l 41 ill 191 81 481 I - - - - - - - - - - - - - - -- - - -- - - - - - -- - - -------------------------------------- +I I-NE- I .1 -I *1

.1 1i 41 61 .I ill I I ...... ......----.....----.....----.....-- -----------------------. I l-E- 1 *l -1 11 .1 .I 4 .1 11 I -------------------------------------------------------------------- - + I-+

-ESE- 1 .I *1 11 1I .1 .I 21 I----- ----- ----- ---- ----- ----- ----- ---- --- ------------------------- I I-SSE- I-+- -+ ... I .1 1 181

+-....+-....+-....+-....+-....+-- .1 -I 1 .1+- 18I I - - - - - - - - - - - - - - -- - - -- - - - - - - - - ------------------------------------- ++ - +I

-_s- .1 11 71 91 71 . .1 24 1 I ---------------- ------ 7- ---------------------------------------- ++ - +I I-SSW- I *I .1 1i 331 621 161 1 .I 1131 I - - - - - - - - - - - - - - -- - - -- - - - - - -- - - -------------------------------------- +I I-SW- I 1 . '1 521 61I 241 7 21 1471 I - - - - - - - - - - - - - - -- - - -- - - - - - -- - - -------------------------------------- +I l-wsw- I *I .1 3I 251 331 91 1i .I 711 1I- - - - - - - - - - - - - - -- - - -- - - - - - - - - - -------------------------------------- +I I-w- 1. 14 271 121 41 .1 .1 441 I ---- --- --- --- --- ...... --- --- --- --- --- --- --- -----------------------+-

I-WNW- I .1 .1 11 61 131 71 31 .1 301 1I- - - - - - - - - - - - - - -- - - -- - - - - - - - - - -------------------------------------- +I I-MW- I 11 41 .1 41 51 21 31 i1 201 I- - - - - - - - - - - - - -- - - - - - - - - - - - ---------------------------------------- + -

I-NNW- I .1 .1 21 11 71 El 71 s5 281 1I--- - - ----------- ---- --- - - - ----------------------------------- ++ -- - I TOTAL 1 1f 41 121 1891 2181 loll 511 171 5931

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASS I

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

1 1.50-f 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1 1.99 1 2.99 I 3.99 1 4.99 1 S.99 I 7.99 I 9.99 ITOTAL

- +--------+-......+...-...-+...-...-+....-..-+....-..+- I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

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

SECTOR I I I I I I I I I I ---------------------- I I I I I I I I f-N- I .1 61 191 161 21 21 .1 451 1I- - - - - - - - - - - - - - -- - - - - - ------------------------------------------

I-NNE- I 11 sf 71 231 15f 21 .1 531 1 -- - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------...- +- .+. .- . I f-NE- I .1 .1 sf 101 iil 11 .1 27f 1I - - - - - - - - - - - - - - - - - - - - - - -----------------------------------------

-ENE- I .1 1f 31 I if .I ,f 1

-ESE- ' -1 31 11 . .f 1 41 f-SE- 1 31 5f 21 .f .f .f 1of I.-

-- - - . - - - -- -- -- -- --- -- -- -- - - - .-- . .+ .

- -- .---- . - .- I..

1 I-SSE- 241 11 .f .f .f .f 301 1 -------------------------------------------------- ++- - -+- ----- -

-s- f 21 16f 31 21 . 1 f 23f

-ssW- 1 sf 43f 20f 9f .f .f .f 77f f-Sw- 1 31 411 71 8f 21 21 . 63 f-wsw- 1 21 91 61 1f .f .f 18f wf 11 s 31 .1 11 . .f 2of f-wNw- I .f 121 41 1f 11 1f .f 19f f-NW- 1 .1 41 41 21 71 21 .f 19f I- - - - - - - - - - - - - - - - - - ---- - +---- -- -- - - - - - -- -------- - +-- - - -I f-NNW- 1 .f 21 51 51 41 61 11 23f TOTAL 1 221 1861 901 771 441 16f if 436f

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C WIND SPEED CLASS I I

I I 11.00-I 1.25-1 1.50-I 2.00-F 3.00-F 4.00-1 5.00-F 6.00-I 8.00-I 1 F 1.24 1 1.49 1 1.99 I 2.99 1 3.99 F 4.99 F 5.99 F 7.99 1 9.99 ITOTAL I I- - - +---. . . . + .- . . . . .+ - . . ..- -- +-- - ----- - -+-. .-. . . .+ . . . . ..--+ . . . ..- F I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. [. NO. I NO. I I- - - - - - - - - - - - - - - - - - -- - - - - - - - - - -------------------------------- + --------- + -

SECTOR I I I F I I F I I

FI I-------- I I-N- 1 -1 11 21 191 281 141 41 iI .* 691 1I-------------------- +- ++ ------- - ++ --------------------------

-- +--+ +---- -I I-NNE- -1 1 . 11 91 221 531 81 i 31 981 1 -- - -- - - -- -- -- - -- - ---

+- - --- + -- -- + - --+ -- -- -- - ----------------------- ------ I F-NE- 1 I .1 . 31 F31 361 91 .1 .l 611 1I----------------+- ---- + ------- -- + -----------------------------

-- + -- + -- + - I I7ENE- 1 . .1 21 iF 21 s5 1F *1 .1 ill I ------ +- +__"

+.++.+.++ ---------------------- - +- +-+ - I F-E- I .F .1 .F 31 F 1 .1 .1 *F 31 F-- ----------------------------- ----------------------- ++. .- I

-ESE- I ' i] 21 21 1F F *F .1 .1 61 F-- -

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

-- + -++- + - I F-SE- 1 . 1 81 9! 31 .1 *1 .1 .1 201 1 --- +- ++ -------------- -- ------ + .....-

-++ +- --------------------- - + - I I-SSE- 1 .1 .1 141 271 21 *I .1 .1 .1 431 1I----------------+- ---- ++ 7--- ---------------------------------

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

-s- -1 .1 131- 301 5I 21 .1 .1 *F S0i 1----------------------------------------------------+--+-+-+--+--+-+- +- -- F F-SSW- .1 i 181 501 121 7] ii .1 .1 891 F - - - - - - - -

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

- - --+-- - - - - - - - - - - ---------------------- -- -- I F-SW- .1 .1 141 311 91 71 1i 21 .1 641 F------- + -+- +.+-

-... *--+- + - .+ - .+-

F-WSW- 1 iF 31 141 91 21 41 .1 .1 1 3 1 ---------------------- -+-+-.+-. .+-. .+..-+- +- +--- -I I-w- 1 'F iF 41 101 1I F .1 .1 F 171 1I - - - - - - - - - - - - - - -- - - --+- - - -+ - -- --+ - - - -------------------------- + - + - + - + - + - + -

I-WNW- 71 ...... ...... 21 . F 161 I---------------------- + - + - - ......- + -......- + .--- + ..-.- --

+- +- +- - - +-F I-NW- 1 .1 11 .1 141 61I 61F 31 3l 371 1I -- --- - - ---- ----- +- ---- + ---- -- -- ----- + -- --------------------------

+ -- + -- + - I I-NNW- 1 .1 i1 ii 131 81 31 61 sj .1 371 I------------------------------------

+ + -- I ITOTAL I 21 101 95I 2371 1181 1381 37I 141 31 6541

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY D WIND SPEED CLASS I I

I I 1 0.45- 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-I 4.00-1 5.00-1 6.00-1 8.00-1 I 0.74 0.99 1 1.'24 1 1.49 1 1.99 1 2.99 1 3.99 I 4.99 I 5.99 I 7.99 1 9.99 ITOTAL I I - ------

+-- +.- ....- +......--+.- .... +......--+.- ....------ . --------------------

+--+ - +I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I- +---- -------- +- +---- +--+-------- +------- +--------+--------+--....I SECTOR I I I I I I I I I I I I I ---------------------- I I I I I I I I I I I I-N- I .1 31 101 131 371 1321 1581 851 241 ill 11 4741 1I--- - - --- -------- ---- ---- --- -- -- --- ------------------------------------------ ++ ---- I I-NNE- I .1 21 21 31 161 59l 1551 1931 611 161 71 514J I.. .. -+-- - . . .+ -... .+ -... .+ -... .+ -... .+ -... .+ -... .+ -... .+ - I...

I-NE- 1 *1 1 2j 21 7[ 271 671 711 301 61 I 2121 I - - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - - -- - ------------------------------------------- I

-ENE- I ".

1 11 .1 61 131 191 171 171 51 *1 781 I ---------------------.. +- -- - - -- - -- -- - - - -- - - - ---- . . .-+-.. .- +- .+-. . +.-. .I I-E- 1 .1 *1 41 31 81 81 121 31 .1 .1 .1 381 I. . .+.

+-......+. . -... .+ -... .+- -+ - -+ . . .+ -... .+ -... .+ -... .+--* -

-ESE- I .1 11 21 5j 161 131 41 21 *1 . . 431 I-- --- ----------------------------------------------------------

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

I-SE- I 11 11 61 131 151 161 91 10i *1 .1 *1 711 I -- - - - - - - - - - - - - -- - - - - -- - - - - - --+-- - - - - - --+ - - -------------------------------

++ ---- + - I l-SSE- I 21 31 101 151 321 651 171 51 .1 .1 *1 1491 I ----------------------

- I --...----- _- +_-+- - -------- m .+ ..-.. +..-.-+..-..I 1-s- I .1 121 121 261 601 841 441 171 31 .1 .1 2581 I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -*-- ------------------------------------- ++ - ++ - +I

]-SSW- I -11 ill 181 391 95I 1091 561 211 131 11 *I 3641 I-- - -------------------------......----- + - .+ -. .+- . .I

-SW- I 11 61 171 301 631 75I 311 301 61 11 *I 2601 I----------------- +------------------------......----- + - .+ -. . +- . .I

-WSW- 1 21 101 121 151 261 291 91 61 .1 "i *1 1091 I- -+- +-+ --------------------------------------------------------------------------------- I-l-w- I 11 61 7l 201 17i 221 31 31 .1 .1 *I 791 I-- - - - --------------------------------------------------------------------- + -I+- I I-WNW- I .l 91 71 181 251 25 101 14 11 11 *1 1001 I- - - -- -- --------------+-. -- -- - - -- - - - - --- - - ----- . . . ..- +-.. . . . .- +- . . . . I I-NW- 1 .l 31 91 181 211 191 211 181 131 41 .1 1261 I--- - - - - --- - - -- --- -- -- -- - -- -- --- -- ------------------......- -- --- -- -- --- -- -- - -- -- - - ------ +-. . I I-NNW- 1 .l '1 61 51 341 61I 391 271 181 ii[ 2021 I- - - - - - - - - - - - - - -- - - - -- - - - - -- - - - - - -- - - - - ------ 7-------------------------------------I TOTAL I 81 681 1251 2251 4781 757I 6541 5121 1861 561 81 30771

CATAWBA NUCLEAR STN.. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I

I I 10.45-1 0.75-I 1.00-1 1.25-I 1.S0-I 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 1 0.74 I 0.99 1 1.24 I 1.49 I 1.99 I 2.99 I 3.99 I 4.99 I 5.99 I 7.99 ITOTAL I I ----

+-- -- +.- ...- +.....-.+.....-.-+......- - +......-+-.------+......--- -------- +- .

I NO. I NO. I NO. I NO. j NO. I NO. I NO. I NO. I NO. I NO. I NO. I I.-.--

ISECTOR I I I I I I I I I I I I

- I I I I I I I I I I I-N- I 11 . 41 5I 181 941 571 9j .1 61 1941

-NNE- I 1 11 21 , 4 121 191 _17 31 11 601

- -------------------------------------- --------------------------- - ------ I I-NE- I .1 .1 21 21 11 31 4l 121 131 21 391 I-- - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - -----------------------------------

+-- + -- - I

-ENE- I .1 11 .1 21 .1 41 51 11 21 .I 151 I- - - - - - - - - - - - - - -- - --- - - - - - -- - - - - - -- - -----------------------------------

+-- + -- I I-E- I 11 11 21 21 31 51 31 .1 .1 171 I- - - - - - - - - - - - - - -- - --- - - - - - -- - - - - - -- - -----------------------------------

+-- + -- I

-ESE- j I .1 . 21 41 31 41 71 41 .1 .1 241 I- - - - - - - - - - - - - - -- - --- - - - - - -- - - - - - -- - ----------------------------------------- +I I-SE- I .1 21 21 21 91 181 181 121 3i1 1 661 I- - - - - - - - - - - - - - -- - - - - - -- - - -+--- - -- - - - ----------------------------- --------- +- +I I-SSE- I 31 121 71 151 491 511 321 101 -

.1 1791 I

I-S- -- --- - ---------- + - -------------------

I 151 301 521

- 71 981 901 371 101 21 11 335I I- - - - - - - - - - - - - - --+---------------++ - --- - - - - - -- - - - - - -- ------------------------ - +I I-ssw- I 1I 211 391 621 1181 1381 581 131 31 .*1 531

----------------------------------------------------- + ----.I I-SW- I 41 301 351 51j 441 481 131 41 11 11 2311 I-- +- +------- ......--- ...------------- +-......-+-.... +....-..+...-.-+-.-. I I-WSW- I 31 241 311 281 221 101 31 .1 .1 .1 1211 I.....+- -+ - -+ . . .+ -... .+ -... .+ -... .+ -... .+ -... .+ -... .+ - I...

I-w- I 51 171 1i9 261 281 iIj 21 .1 I .1 1081 I------------ ------------ ------------ ------------ --------------. -- ---- --------------------- I-I-WNW- I 3! 131 221 191 481 34I 151 41 .1 *I 1581 I - - - - - - - - - - - --- - - - - -- - - - - - -- - - - - - -- - ----------------------------------------- +I I-NW- I 5I 81 161 171 301 501 151 51 . .I 1461 I - - - - - - - - - - - - - - -- - -- - - - - - - -- - - - - - - - - ----------------------------------------- +I I-NNW- I .I 10l 61 181 £21 1121 291 121 21 -1 2411 I------------------------------------------------------------------------+--+- + - ++ - I TOTAL I 251 1551 2171 3071 £261 6821 3191 1161 291. 11 23871

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I

I l I 0.45-1 0.75-I 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 I 1 0.74 I 0.99 1 1.24 1 1.49 I 1.99 j 2.99 I 3.99 i 4.99 1 5.99 ITOTAL I I.--- +-*---- -- -- - --......- +-......-+-.....--.-+-....- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I.. ..-------------------------------------------------------------------

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

ISECTOR I I I I I I I I I I I I ------------------------ I I I I I I I I I I I I-N- I I .1 .I 11 ill 441 161 .I I 721 1 ----I---------- --- ---. --- -----------------------------

+---+- + I+-

I-NNE- 1 I *I .1I I 1 41 *I 1 51 1I - - - - - - - - - - - - - -- - - - - - -- - - - - - -- ------------------------------------------

I . --+ - +- - . . .+ -... .+ -... . -... .+ -... .+ -... .+ -... .+ -...

-ENE- - EI 1 .. . .1 1 . . .1 .+ . . . .1... I ... 1I.. .... .1 ... . .1 ... . ,I I

.. +I. . . [.+ .. . 11 1

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

-ESE- 1 *1 *1 1* . 1 21 .1 .I 1 31 I - - - - - - - - - - - - - - --- - -- - - - - - -- - - - - ------------------------------------- + ---- I I-SE- - I .1 *1 *1 .1 5I E1 .I 11 *1 13j 1I - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - --------------------------------------- + - +I

-1 s-- - - - - - - - - - -- - - -I - - -*1

-SSE- - - -- 21 - -- 41 - - - 1 - 61 - - -3I-- - 1 - - 1 - - - -.- ---

11 1 231 3I I-S- 21 101 201 341 381 1 . ..1 1 1041 I-- - --- ----------------------------------- +-......----...-+-. .I

-SSW- I 21 131 321 411 461 61 .1 .1 *I 1401 I--------------------------------------------------------+ - + - - + -I+- +

F-Sw- I 21 291 241 231 81 11 11 .1 1 881 I - - - - - - - - - - - - -- - -- - - - - - -- - - - - - -- ------------------------------------

+- + ---- I l-WSW- 1 51 161 251 171 1o0 31 .1 1 761 I1-w-1 - - - - --

.I ill - - - - - --

81 61 - ------------------------------------

131 91 +

.1 ----

1 . 471I I- - - - - - - - - - - - - - --- - -- - - - - - -- - - - - ------------------------------------- + ---- I I-WNW- I 41 61 7I 231 181 161 1 .1 1 41

- . -- - -- - - - - - - -- - - - - -- -- - - -- - -+- . . . . ..--

- . . . . . .- +-. . . . . .- - -.. . . . .

I-NW- I 21_ 101 ill 211 181 121 .1

.1 .1 741 I-NNW- I .I 11 91 81 391 37I 51 1 .1 991 I-- - - - - - - - - - - - - - - - - - - - - - - - - - - ----------------------------------------------

I-CALM- I 11 1 .I .I .I .1 .1 11 I *----------------------------------------------------------------------------+ - I-TOTAL I 181 981 1411 1791 2131 1401 301 21 11 8221

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY G WIND SPEED CLASS 1 0.4s-1 0.75-I.1.00-1 1.25-I 1.50-I 2.00-1 3.00-1 4.00-1 0.74 1 0.99 1 1.24 [ 1.49 1 1.99 1 2.99 I 3.99 I 4.99 ITOTAL I - -----

+-- -+-......+....-..+.....-.-+..-..+.- ------- +-- --- I I NO. I NO. I NO. I NO. I NO. I NO. NO. I NO. I NO. I I -+--+- ------ ..------------------------ -+-.+..-.I SECTOR I I I I I I I I I I I ---------------------- I I I I I I I I I I I-N- 1 *1 i .1 11 sl 'oI 31 .1 201 1 -- - -- - -- - -- - -- - -- - -- - +---- - -- - -- - -- - - --------------------------- - I+

I-SE- I .I .1 I 1 .I 1i 11 11 3I I ------------------- ---------- -- 7 - +-...-...+....-..-+-....-I I-SSE- I 11 .1 11 1 1 21 *1 1 I1 +--- ------------------------------

+- + I+-

-S- I 21 81 191 30I 171 i1 *I *I 771 I - - - - - - - - - +-- -

- - - - -----------------------+---------+- .+-. .+-

1-SSW- 1 sI 181 231 28I i5j .1 .1 *1 891

+ ....... +------- -- +---+------ +----- I I-SW- I 101 251 241 191 sI 21 .1 .1 851 1 -- I- ---------------------------------- + + - I I-wsw- 1 71 211 201 141 8 1I *I .1 711 I -------------- -+-------------- ---.------------------------ +- I+

-w- 16 14I 121 91 l 71 1 .I 641 1I - - - - - - - - - - - - - - -- - - - - - - - - - - - - --------------------------------------- +I

--WNW- I 91 15I 121 121 81 71 .1 631 I -- - -- - -- - -- - -- - -- - -- - -- - -- - -- - -- - -- - - ------------------------- I+

I-NW- I 101, 221 181 221 31 21 *1 .1 771 I- - - - - - - - - - -- --- ---------------------- + --.....-- I+-.

I-NNW- I il. 11 61 i8j 281 201 21 *1 761 I-- -------------------------------------------

+-+-+ + - I I-CALM- I 61 I .*1 .1 1 *1 .*1 *1 6 I - - - - - - - - - - - - - - -- - - -- - - - - - -- - - -------------------------------------- +I TOTAL I 671 1251 1351 1531 961 531 61 1I 6361

CATAWBA NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I I

7---------------- I I F 0.45-1 0.75-F 1.00-1 1.25-F 1.50-1 2.00-1 3.00-F 4.00-1 5.00-1 6.00-1 8.00-1 I F-...0.74 +-....+-....+-....+-....+-....+-

j 0.99 <Q1.24 1 1.49 1 1.99 1 2.99 1 3.99 4.99 1 5.99 I 7.99 F 9.99 ITOTAL

+- .. +-... +- +- .. + - I...

I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I F--------- -------- ------- -------- -----------------------------------------+-+--+-+- + -

SECTOR I* I I I I I I I I I I I I I-*----------------------- F F F F1 F I I I I F-N- F 11 41 141 211 731 3101F 291F 1341 341 211 11 9041 F----------------------- - -------------------------------------------------------------------- + + I+-

I-NNE- F I 31 31 6S 231 901 2111 2971 1071 281 101 7781 F------------------------------------------- - +- . ----

-+- +-----+-- -+..-.- +..-.-+.-.- +..-.-+..-.- +..- I F-NE- 1 .*1 41 41 81 331 91 1331 691 91 .1 1 F - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - ------------------------------------------- +- + -

F-ENE- F 1 11 1F 2 F91 191 29F 231 211 sl *I 1101 F-----------------------------------------------------------------.------------------------+I -

[-E- I 'F 1F sF 5 1 151 1F 6F I *I 601 F - - -- - - -- ---- - -- - - -- - - - -- - - -- - - -- - - -- - - - --- ------------------------------

+--I+- + - + - +

-ESE- F 11 51 10F 21F 251 14F 6F .F F 1 821 F---------------------------------------------------------.------------------------ + - + - + - + I+-

F-SE- F I 31 81 15F 401 601 34 2S 31 *F 1891 F - - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - - -- - ------------------------------------------- I I-SSE- 1 6I 171 221 35 1 107F 191o 541 1S6 .1 . 4471 I-SF

- - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - - -- - ------------------------------------------- I 41 4 1 811 1421 2291 228F 981 381 5I 1F .1 8711 I- - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - - -- - -----------------------------------

++ - ++ -- I 1-Ssw- F 91 631 1121 171F 2981 379 2081 665 181 i1 *F 13251 1I- - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - ------------------------------------------- +- + -

F-SW- 171 901 o00F 1231 138F 2501 1221 731 171 8F .1 9381 F- - - - - - - - - - - - - - - - - - - - -- - -w- - - - - - - - - - - - - - - ------------------------------------------ + -

F-wsw- I 171 711 891 77F 8S1 86 531 201 11 . . 4991 F-------------------------------------------------------------------------------------+--+- - -+ I+

-W- F 221 481 471 62F 701 101F 21F 7F 1i *1 1 3791 F- - - - - - - - - - - - - - - - -- -- - - - - - - - - - - - - - - - ---------------------------------------------- + -

-WNW- F 161 431 481 72F lo F 107F 461 17F 61 41 .1 4601 F- - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - ------------------------------------------- +- + -

F-NW- 1 l 431 5117 83 731 105 5h 331 29F 10l F 4991 F- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------------ +I F-NNW- 1F 131 271 50 1561 246S 95 531 371 271 1i 706S F -.....--- -.. --------------

F-CALM- . I 71 .1 *F *1 *F *1 .1 *F

-1 1 .F 71 F- - - - - - - - - - - - - - -- - - - - - - - - - - - - -- - - - - - - - - ------------------------------------------ +I TOTAL F 1181 4461 6211 8781 14421 2244F 143s1 9471 348F 1141 121 *86051

ATTACHMENT V Unplanned Offsite Releases

There were no unplanned liquid or gaseous radioactive effluent releases to the environment in 2008.

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

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 the 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 ten 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 -andgaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 1 st Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 3.02E-01 1.50E+01 2.01E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Quarter 1 2008 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 8.55E-03 1.OOE+01 8.55E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.89E+01 Ql - Maximum Beta Air Dose 3.27E-03 2.OOE+01 1.63E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.12E+01 XE-133 7.07E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (torem) Limit Q2 - Maximum Organ Dose CHILD LIVER 2.OOE-01 1.50E+01 1.34E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS==..........=============== Quarter 2 2008 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 6.43E-03 1.00E+01 6.43E-02 Maximum Gamma Air Dose Receptor Location:. 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.90E+01 Q2 - Maximum Beta Air Dose 2.43E-03 2.OOE+01 1.21E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.24E+01 XE-133 7.08E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3rd Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.82E-01 1.50E+01 1.22E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Quarter 3 2008 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Ganmma Air Dose 7.58E-03 1.OOE+01 7.58E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage ARL 41 9.96E+01 Q3 - Maximum Beta Air Dose 2.74E-03 2.OOE+01 1.37E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.71E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2

-N 4th Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2008 ====

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.44E-01 1.50E+01 i.63E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Quarter 4 2008 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 8.97E-03 1.OOE+01 8.97E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.92E+01 Q4 - Maximum Beta Air Dose 3.31E-03 2.00E+01 1.65E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.49E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 9.29E-01 3.OOE+01 3.10E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS======================== Annual 2008 ========

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 3.15E-02 2.00E+01 1.58E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.92E+01 Yr - Maximum Beta Air Dose 1.17E-02 4.00E+01 2.94E-02, Maximum Beta Air Dose ReceptorlLocation: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.39E+01 XE-133 5.27E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1' & 2 ist Quarter 2008

= BATCH LIQUID RELEASES == Quarter 1 2008 ===-

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD GI-LLI 1.34E-02 1.00E+01 1.34E-01 Q1 - Total Body Dose CHILD 1.34E-02 3.00E+00 4.46E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.88E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.91E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2008 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose CHILD LIVER 3.10E-04 1.00E+01 3.10E-03 Ql - Total Body Dose CHILD 3.10E-04 3.OOE+00 1.03E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2008

=== BATCH LIQUID RELEASES Quarter 2 2008 .

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q2 - Maximum Organ Dose CHILD LIVER 1.lIE-02 1.OOE+01 1.lIE-01 Q2 - Total Body Dose CHILD 1.02E-02 3.OOE+00 3.42E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.99E+01 CS-137 9.43E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.75E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2008 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 3.09E-04 1.OOE+01 3.09E-03 Q2 - Total Body Dose CHILD 3.09E-04 3.OOE+00 1.03E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2008

=== BATCH LIQUID RELEASES Quarter 3 2008 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q3 - Maximum Organ Dose ADULT GI-LLI 7.46E-03 1.OOE+01 7.46E-02 Q3 - Total Body Dose CHILD 7.04E-03 3.OOE+00 2.35E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide / Percentage H-3 8.25E+01 CO-60 9.01E+00 CO-58 7.96E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.57E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2008 ===-==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 5.24E-04 1.00E+01 5.24E-03 Q3 - Total Body Dose CHILD 5.24E-04 3.OOE+00 1.75E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2008

BATCH LIQUID RELEASES Quarter 4 2008 ===

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose ADULT GI-LLI 5.19E-03 1.OOE+01 5.19E-02 Q4 - Total Body Dose CHILD 4.85E-03 3.00E+00 1.62E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.13E+01 CO-60 1.03E+01 CO-58 7.74E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.52E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2008 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q4 - Maximum Organ Dose CHILD LIVER 5.41E-04 1.OOE+01 5.41E-03 Q4 - Total Body Dose CHILD 5.41E-04 3.00E+00 1.80E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2008

BATCH LIQUID RELEASES Annual 2008 ======

Critical Critical Dose Limit Max % of Period-Limit Age 'Organ (mrem) (mrem) Limit U Yr - Maximum Organ Dose CHILD LIVER 3.61E-02 2.00E+01 1.80E-01 Yr - Total Body Dose CHILD 3.54E-02 6.OOE+00 5.90E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.55E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.74E+01 CONTINUOUS LIQUID RELEASES (WC) Annual 2008 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 1.69E-03 2.OOE+01 8.45E-03

'Yr - Total Body Dose CHILD 1.69E-03 6.OOE+00 2.82E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.00E+02

Catawba Nuclear Station 2008 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Catawba Nuclear Station only includes liquid and gaseous effluent dose contributions from Catawba and direct and air-scatter dose from Catawba's Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to Catawba's maximum exposed individual. The dose to a maximum exposed individual from Catawba's effluent releases is well below 40CFR190 limits as shown by the following summary:

I. 2008 Catawba 40CFR190 Effluent Dose Summary The 40CFR190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 9.83E-01 mrem Maximum Location: 0.5 Mile, East7Northeast Sector Critical Age: Child Gas non-NG Contribution: 94%

Gas NG Contribution: 2%

Liquid Contribution: 4%

Maximum Organ (other than TB) Dose = 9.65E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 96%

Liquid Contribution: 4%

II. 2008 Catawba 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Catawba have been calculated and documented in the "Catawba Nuclear Station IOCFR72.212 Written Evaluation" report. The estimated ISFSI cask loading schedule is given in three phases. For Phase I initial ISFSI cask loading began in July 2007 and is scheduled to be completed in October 2009. Estimated dose rates at 50 specific locations including the Exclusion Area Boundary (EAB) are provided in the 10CFR72.212 evaluation report. The maximum dose rate at the EAB for Phase I from the Catawba ISFSI is calculated to be less than 0.1 mrem/yr. The following excerpt, "C. 10CFR72.212(b) (2)(i)(C)- Requirements of 72.104", from the "Catawba Nuclear Station IOCFR72.212 Written Evaluation" report is provided to document the method used to estimate the Catawba ISFSI dose to the nearest "real individual".

The following four pages are taken from the Catawba Nuclear Site, "Independent Spent Fuel Storage Installation",

10CFR72.212 Evaluation report.

CNS 10CFR72.212 Evaluation NAC-UMS Universal Storage System Page 29 of 55, 7.3 10CFR72.212(b)(2)(i)(C).- Requirements of §72.104

"(C) the requirementsof.§'72.104 have been met. A copy of this recordshall be retaineduntil spent fuel is no longer stored under the general license issued under §'72.210."

The requirements of §72.104 are as follows:

(a) During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the controlled area must not exceed 0.25 mSv (25 mnrem) to the whole body, 0.75 mSv (75 mrem) to the thyroid and 0.25 mSv (25 mrem) to any other critical organ as a result of exposure to:

(1) Planned discharges of radioactive materials, radon and its decay products excepted, to the general environment, (2) Direct radiation from ISFSI or MRS operations, and (3) An* other radiation frorn uranium fuel cycle operations within the region.

Doses from storage casks located at the ISFSI have been calculated at the end of each of three storage phases at a number of locations. The three storage phases are (Reference 7.3-3):

CNS IOCFR72.212 Evaluation NAC-UMS Universal Storage System Page 30 of 55 Phase I I Pad 24 Casks Filled 2009 Phase II 7 Pads 168 Casks Filled 2042 Phase III 11 Pads 264 Casks Filled 2047 The best estimate loading schedule by cask is shown below (Reference 7.3-3, as supplemented by revised cask loading schedule prepared by Catawba Reactor Engineering). This loading schedule may change as plant needs dictate.

Storage Unit Unit Storage Unit Unit Phase Year Month 1 2 Phase Year 1 2 Phase I 2007 April Phase II 2011 5 4 2007 May 2012 4 5 2007 June 2013 2007 July 2 2014 2007 August 1 2015 5 4 2007 September 2016 4 5 2007 October 2017 2007 November 1 2018 2007 December 2 2019 5 4 2008 January 1 2020 4 5 2008 February 2 2021 2008 March 2022 2008 April 2023, 5 4 2008 May 2024 4 5 2008 June 2025 2008 July 2026 2008 August 2027 5 4 2008 September 2028 4 5 2008 October 2029 2008 November 2 2030 2008 December 1 2031 5 4 2009 January 2 2032 4 5 2009 February 1 2033 2009 March 2034 2009 April 1 2035 5 4 2009 May 2 2036 4 5 2009 June 2037 2009 July 2038 2009 August 2 2039 5 4 2009 September 2 2040 4 5 2009 October 2 2041 2042 Phase III 2043 20 2044 20 2045 8 12 2046 20 2047 16 NI

CNS 10CFR72.212 Evaluation NAC-UMS Universal Storage System Page 31 of 55 The methodology and results of the dose calculations are discussed in detail in References 7.3 7.3.6. A summary of the methodolgy and results is presented below.

There are four calculations that are used to estimate the doses. The first calculation (Reference 7.3-3) determines the source term for the base canister. The results of this calculation include the fractional probability energy spectra for photons and neutrons, the photon and neutron release rates per canister as a function of bumrup and decay, and the release rates for each filled canister at the end of Phase 1, II and III as a fraction of the base canister release rate. This calculation uses the representative design basis PWR fuel assembly characteristics for a Westinghouse 17x 17, assembly as described in the NAC-UMS FSAR.

The next calculation (Reference 7.3-4) uses the results from Reference 7.3-1 to generate the photon surface source and neutron-to-photon ratios as a function of distance for a base canister to be used to generate dose contours for the various phases of the CNS ISFSI Project.

A detailed MCNP model of the NAC UMS with the Duke specified loading scheme is developed to collect a photon and neutron surface source for use in radiological analysis for the various phases of the ISFSI project. The representative PWR fuel assembly dimensions (standard WE I 7x 17) based on UMS FSAR are used to calculate photon and neutron energy spectra, release rates and fractional release rates for use as source term inputs for MCNP5. The zone specific photon and neutron energy spectra are used in the detailed cask model to assimilate the zone loading scheme. The surface source is generated on the surface of an ellipsoid that can be overlaid onto each cask position on the ISFSI pad.

The third calculation (Reference 7.3-5) uses the photon surface source generated in Reference 7.3-4. Each cask is modeled in MCNP as a simple solid concrete cylinder with the same dimension of an actual NAC-UMS cask with an ellipsoid over the cylinder for the placement of the surface source. Theorigin of the problem (X = 0, Y = 0) is located at the lower left corner of ISFSI pad 1. Therefore all dimensions in the model are relative to that point. For Phase I, detectors of various sizes are placed out from - 1000 ft to 1800 ft in the X and - 1200 ft to 1200 ft in the Y direction to collect dose tally in the units of torero/hr.

CNS IOCFR72.212 Evaluation NAC-UMS Universal Storage System Page 32 of 55 A photon case is run and the dose tally is calculated for each detector of interest. A cask specific neutron-to-photon ratio is then applied to the photon dose tally to account for the neutron contribution to the total dose.

It is important to note that fractional release rates are used only for the casks analyzed for that phase. Therefore, the Phase II dose is a summation of the Phase 11 dose tallies and Phase I dose tallies adjusted with a time decay factor. Phase III dose is a summation of dose tallies of all three phases at each detector location along with the appropriate decay factors for Phases I and II.

Phases II and III are modeled using the same detector layout so the dose from each phase can be added to determine the total dose at a specific location. The tallies are collected in the same manner for the dose contour maps. The resulting dose contours are shown on FANP drawings 5055506E-00, 5055507E-00, and 5055508E-00 (Reference 7.3-7 through 7.3-9).

The final calculation (Reference 7.3-6) provides dose rates at 50 specific locations, including the Exclusion Area Boundary (EAB). Doses are calculated at 3 locations on the EAB for each phase:

2500' Exclusion Occupancy X Y Area Boundary (hrs/yr) Point Coord. Coord.

  • Entrance Road 8766 RP 12 26+50 44+00
  • Crepe 8M0yrtle Road 8766 RP_13 75+00 48+00
  • Security Practice Range 144 RP14 254-00 89+00 The dose rates at these locations are:

Description of data Phase 1* Phase 2* Phase 3*

point location Imrem/yrI Imrem/vrt [mrem/yrl 2500' Exclusion Area Boundary

    • Entrance Road 0.06 0.29 0.85
  • Crepe Myrtle Road 0.08 0.32 0.79
  • Security Practice Range Pai 0.01 0.03 0.03
  • Maximum values from Fable 2 or 3, Reference 7.3-6 The above information will be added to the plant generated dose to prove compliance with 72.104. General Office Radiological Protection has responsibility for this function.

ATTACHMENT VIII Revisions to the Radioactive Waste Process Control Program Manual

The following letter dated April 8, 2009 from David L. Vaught, Senior Engineer, Nuclear Chemistry, documents that no changes were made to the Process Control Program (PCP) during the period of January 1,2008 through December 31, 2008.

April 8, 2009 RD Hart Regulatory Compliance Manager Catawba Regulatory Compliance ATTENTION: MJ Sawicki

SUBJECT:

Catawba Nuclear Station 2009 Submittal Annual Radioactive Effluent Release Report Process Control Program Changes 1/1/08-12/31/08 File: GS-764.25, CN-215.06 This memo documents that no chanues were made to the Process Control Program (PCP) during the period of January 1,2008 through December 31, 2008. This information is to be included in the Annual Radioactive Effluent Release Report for Catawba Nuclear Station.

CNS SLC 16.11-16 "Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report requires that the Radioactive Effluent Release Reports shall include any changes made to the PCP during the reporting period.

If you have any questions, please call David Vaught at 980-373-5302.

Dewey P Rochester Technical Manager II Nuclear Chemistry by: David L Vaught Senior Engineer xc: Barry N. Kimray (CNS)

Edgar B. Greene (CNS)

Rufus Wallace (CNS)

Caryl D. Ingram (NGO)

ATTACHMENT IX Information to Support the Nuclear Energy Institute (NEI)

Groundwater Protection Initiative

ARERR Groundwater Well Data Section Duke Energy implemented a Ground Water Protection program in 2007. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, Catawba has forty-six ground water monitoring wells in place. These wells are currently sampled quarterly (with the exception of the five LMW wells which are sampled semi-annually). All samples are being analyzed for tritium and gamma emitters. No gamma activity (other than naturally occurring radionuclides) was identified in any of the well samples during 2008.

Results from sampling during 2007 identified ground water contamination at location C-213. This contamination was identified as coming from backflow from the Monitor Tank Building (MTB) truck bay sump into the WL trench entering the MTB from the east side. Additional wells were installed near C-213 to identify the extent of the contamination and determine the direction of ground water flow in the affected area.

Ground water, and therefore the contamination, appears to be moving toward the turbine building drain system where it is collected. The contamination and resulting investigation activities were reported to the NRC and to state and local officials.

Monitoring of this area is on-going.

Results from sampling during 2008 are shown in the table below.

Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples ClOOR U-1 SFP *0 C100DR U-1 SFP 126 <- 126 2 C1O1R U-1 SFP 931 846- 1,010< 3 CO10DR U-1 SFP 355 285 - 428< 3 C102 E of U1 SFP O/S 387' < - 424< 3 protected area C103 E of U1 SFP @ Cooling 408 < - 601 3 Towers C104 U-1 RMWST 648 638 - 838< 4 C105 Engr. Bldg. 1,094 903 - 1,550< 4 C105R Engr. Bldg. 1,124 987 - 1330< 4 C106 W Parking Lot < < 4 C106R W Parking Lot 229 < - 239 4 C107 MET Tower Hill 655 592 - 703 4 C200R U-2 SFP 1,025 907 - 1,200 4 C200DR U-2 SFP 527 457- -587 4 C201R, U-2 SFP 2,553 2,290 - 3,040 4 C201DR U-2 SFP 640 521 -788 4 C202 S of RMC Tent 817 737-866 4 C203 E of RMC tent @ Cooling 671 458-955 4 Towers

ARERR Groundwater Well Data Section C204 S of RMC Tent 295 < - 318 4 C205 Adm. Parking < < 4 C205R Adm Parking 355 < - 355 4 C206 W Parking Lot < < 4 C207R Mon. Tank B 502 409 - 638 4 C207 Mon. Tank B 384 326 - 466 4 C208 N of MTB 175 < - 175 4 C209 MTUville S of light pole < < 4 23A C210 N of U2 Mech Equip Bldg 244 < - 370 4 C211 W of RL intake O/S 1,300 553-2,840 4 protected area C212 Behind Aquatic Center < < 4 C213 Mon. Tank B 36,500 45,400 - 25,400 4 C213R Mon. Tank B < < -4 C214 N of U2 TB 673 589-719 3, C215 N of U2 TB 6,500 2,740 - 10,900 4 C217 N of U2 TB 742 660-812 4 C218 N of U2 TB 6,223 1,320 - 11,000 4 C220 N of U2 TB 16,525 10,300 - 19,100 4 C221 N of U2 TB 243 163-343 4 WCMW-2 WC Ponds 4,023 3,490 - 4,760 4 WCMW-3 WCPonds 515 402-612 4 WCMW-4 WC Ponds 377 325 - 448 4 WCMW-5 WC Ponds ' 393 <- 393 4 LMW 2A Landfill < < 2 LMW 3A Landfill < < 2 LMW 4 Landfill < < 2 LMW 5S Landfill < < 2 LMW 5D Landfill < < 2

  • Well dry.

pCi/i - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/l - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to water that is used for drinking.

1,000,000 pCi/l - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.

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