Text

2007 Annual Radioactive Effluent Release Report
	ML081420757
Person / Time
Site:	Catawba
Issue date:	04/30/2008
From:	Morris J; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081420757 (64)
	v • d • e

PDuke EEnergy Carolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station 4800 Concord Road / CNO1 VP York, SC 29745 803-701-4251 803-701-3221 fax April 30, 2008 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 2007 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, 2007 through December 31, 2007.

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

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

Revisions to UFSAR Section 16.11 Radiological Effluent Controls Revisions to the Radioactive Waste Process Control Program Manual [CD-ROM]

Information to Support the NEI Groundwater Protection Initiative 2008 Offsite Dose Calculation Manual (changes described in Chapter 7) [CD-ROM]

Enclosure

-Ii~c~

www. duke-energy. corn

U.S. Nuclear Regulatory Commission 2007 Annual Radioactive Effluent Release Report April 30, 2008 Page 2 Any questions concerning this report should be directed to Marc Sawicki at 803 701-5191.

Sincerely, James R. Morris Attachments and Enclosures (Process Control Program (PCP) Revision Compact Disc (CD) and Offsite Dose Calculation Manual (ODCM))

U.S. Nuclear Regulatory Commission 2007 Annual Radioactive Effluent Release Report April 30, 2008 Page 3 xc (with attachment and enclosure):

V. M. McCree, Acting, NRC Region II Administrator U.S. Nuclear Regulatory Commission-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 J. F. Stang, Jr., Senior NRR Project Manager U.S, Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop O-H4A Washington, D.C. 20555

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 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 1.07E+00 2.-Avg. Release Rate uCi/sec 1.38E-01 1.07E+00 1.77E+00 7.28E-01 1.37E-01 2.23E-01 9.16E-02 4.65E+00 1.47E-01 B.

Iodine-131

1. Total Release

2.

Avg. Release Rate C. Particulates Half Life

1. Total Release

2.

Avg. Release Rate D.

Tritium

1. Total Release

2.

Avg.

Release Rate Ci 0.OOE+00 0.OOE+00 0.OOE+00 pCi/sec 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00

>= 8 days Ci 0.+00E+00 pCi/sec 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.OOE+00 Ci 3.08E+01 4.39E+01 5.17E+01 6.15E+01 ACi/sec 3.96E+00 5.59E+00 6.51E+00 7.74E+00 1.88E+02

5. 96E+00 E. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00

2.

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

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS -

ELEVATED RELEASES BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1

1. Fission and Activation Gases No Nuclide Activities

2.

lodines No Nuclide Activities

3.

Particulates Half Life >= 8 days No Nuclide Activities

4.

Tritium No Nuclide Activities

5.

Gross Alpha Radioactivity No Nuclide Activities QTR 2 QTR 3 QTR 4 YEAR

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS ELEVATED RELEASES CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1

1. Fission and Activation Gases No Nuclide Activities

2.

lodines No Nuclide Activities

3.

Particulates Half Life >= 8 days No Nuclide Activities

4.

Tritium No Nuclide Activities

5.

Gross Alpha Radioactivity No Nuclide Activities QTR 2 QTR 3 QTR 4 YEAR

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS GROUND RELEASES CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases No Nuclide Activities

2.

lodines No Nuclide Activities

3.

Particulates Half Life >= 8 days No Nuclide Activities

4.

Tritium H-3 Totals for Period...

Ci 3.04E+01 Ci 3.04E+01 4.37E+01 4.37E+01 4.82E+01 4.82E+01 5.81E+01 5.81E+01 1..

80E+02 1..

80E+02

5.

Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS GROUND RELEASES -

BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007

1. Fission and Activation AR-41 KR-85 KR-85M KR-88 XE-133 XE-135 Totals for Period...

Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR Gases Ci 6.99E-61 Ci 0.OOE+00 Ci 0.OOE+00 Ci 0.OOE+00 Ci 3.55E-01 Ci 1.92E-02 Ci 1.07E+00

7. 65E-01 1.40E-02 1.35E-03

2. 87E-03 2.73E-01 1.87E-02 1.07E+00 7.65E-01.

0. 00E+00 0.0OE+00 0.OOE+00 9.17E-01 9.27E-02 1.77E+00 5.06E-01 0.OOE+00 0.00E+00 o.OOE+00 2.14E-01 7.88E-03 7.28E-01 2.73E+00 1.40E-02 1.35E-03 2.87E-03 1.76E+00 1.38E-01 4.65E+00

2.

Iodines

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

3. Particulates Half Life >= 8 days

- No Nuclide Activities

4.

Tritium H-3 Totals for Period...

Ci

3. 18E-0 1 Ci 3.18E-01.

2.17E-01 2.17E-01

3. 54E+00 3.54E+00 3.40E+00 3.40E+00 7.48E+00 7.48E+00

5.

Gross Alpha Radioactivity

- No Nuclide Activities

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 1.33E-02

2.

Average Diluted Concentration

a.

Continuous Releases ACi/ml 0.OOE+00

b.

Batch Releases ACi/ml 5.34E-10 B.

Tritium

1. Total Release Ci 4.11E+02

2.

Average Diluted Concentration

a.

Continuous Releases ACi/ml 3.60E-07

b.

Batch Releases ACi/ml 1.65E-05 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

Ci/ml 0.OOE+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00

2.

Average Diluted Concentration

a.

Continuous Releases ACi/ml 0.OOE+00

b.

Batch Releases ACi/ml 0.OOE+00 1.35E-02 1.89E-02 8.64E-03 5.43E-02 0.OOE+00 0.60E+00 0.00E+00 0.OOE+00 4.26E-10 4.47E-10 3.54E-10 4.41E-10 4.74E+02 3.06E+02 1.97E+02 1.39E+03 1.71E-07 1.18E-07 2.94E-07 2.16E-07 1.49E-05 7.23E-06 8.03E-06 1.12E-05 7.31E-06 3.02E-06 0.OOE+00 1.03E-05 0.OOE+00 0.OOE+00 0.009+00 0.OOE+00 2.31E-13 7.14E-14 0.OOE+00 8.38E-14 0.OOE+00 0.OOE+00.0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.25E+07 1.13E+08 8.24E+07 4.37E+08 1.53E+06 2.21E+06 1.28E+06 6.31E+06 E. Volume of Liquid Waste

1. Continuous Releases

2.

Batch Releases liters 1.49E+08 liters 1.28E+06 F. Volume of Dilution Water

1. Continuous Releases liters 2.49E+09

2.

Batch Releases liters 2.49E+10 3.17E+09 4.23E+09 3.17E+10 4.23E+10 2.44E+09 1.23E+10 2.44E+10 1.23E+11

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS -

CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products No Nuclide Activities

2.

Tritium H-3 Ci Ci 9.51E-01 5.59E-01 9.51E-01 5.59E-01 5.12E-01 5.12E-01 7.42E-01 2.76E+00 7.42E-01 2.76E+00 Totals for Period...

3.

Dissolved and Entrained Gases

- No Nuclide Activities **

4.

Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS BATCH MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR,4 YEAR

1. Fission and Activation Products AG-108M Ci O.OOE+00 0.OOE+0O 0.00E+00 7.34E-06 7.34E-06 AG-liOM Ci 0.OOE+00 2.31E-05 0.OOE+00 2.88E-05 5.19E-05 BE-7 Ci 2.39E-04 2.51E-04 0.00E+00 0.OOE+00 4.90E-04 CO-57 Ci 0.OOE+00 5.67E-06 8.88E-06 0.OOE+00 1.45E-05 CO-58 Ci 7.05E-03 3.32E-03 4.40E-03. 2.77E-03 1.75E-02 CO-60 Ci 7.68E-04 2.44E-03 5.73E-03 1.69E-03 1.06E-02 CR-51 Ci 7.97E-04 1.29E-04 8.96E-04 3.37E-03 5.20E-03 CS-134 Ci 0.OOE+00 0.OOE+00 8.03E-07 0.OOE+00 8.03E-07 CS-137 Ci 1.27E-05 1.14E-05 1.08E-04 3.90E-05 1.71E-04 F-18 Ci 0.00E+00 0.OOE+00 2.66E-06 7.25E-06 9.90E-06 FE-59 Ci 1.32E-04 0.00E+00 5.73E-04 4.06E-04 1.1lE-03 K-40 Ci 0.OOE+00 0.00E+00 0.OOE+00 4.98E-05 4.98E-05 MN-54 Ci 3.18E-05 1.48E-04 5.04E-04 9.52E-05 7.79E-04 NB-95 Ci 3.28E-05 0.OOE+00 9.51E-05 2.19E-05 1.50E-04 NB-97 Ci O.OOE+00 4.40E-05 0.OOE+00 5.65E-05 1.01E-04 RB-86 Ci O.OOE+00 0.00E+00 3.81E-05 0.00E+00 3.81E-05 SB-124 Ci 7.66E-04 7.73E-04 2.26E-04 0.OOE+00 1.76E-03 SB-125 Ci 3.41E-03 6.35E-03 6.28E-03 8.28E-05 1.61E-02 SN-113 Ci O.OOE+00 0.OOE+00 2.85E-05 3.96E-06 3.24E-05 ZR-95 Ci 5.29E-05 0.OOE+00 1.85E-05 0.OOE+00 7.14E-05 Totals for Period...

Ci 1.33E-02 1.35E-02 1.89E-02 8.64E-03 5.43E-02

2.

Tritium H-3 Ci 4.10E+02 4.73E+02 3.06E+02 1.96E+02 1.38E+03 Totals for Period...

Ci 4.10E+02 4.73E+02 3.06E+02 1.96E+02 1.38E+03

3.

Dissolved and Entrained Gases XE-133M Ci 0.OOE+00 0.OOE+00 3.02E-06 0.OOE+00 3.02E-06 XE-135 Ci 0.OOE+00 7.31E-06 0.OOE+00 0.00E+00 7.31E-06 Totals for Period...

Ci 0.OOE+00 7.31E-06 3.02E-06 0.OOE+00 1.03E-05

4.

Gross Alpha Radioactivity No Nuclide Activities

ATTACHMENT II Supplemental Information.

To the Gaseous and Liquid Effluents Report

CATAWBA NUCLEAR STATION 2007 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 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 ORGAN DOSE TOTAL BODY ORGAN DOSE DOSE =

DOSE =

1.5 MREM 5 MREM 3 MREM 10 MREM C.

GASEOUS EFFLUENTS IODINE -

131 AND 133,

TRITIUM, PARTICULATES WITH HALF-LIVES > 8

1. CALENDAR QUARTER = 7.5 MREM

2.

CALENDAR YEAR

=

15 MREM DAYS -

ORGAN DOSE 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.

2.

3.

4' 5.

6.

1.15E+02 8.39E+03 1.01E+02 7.29E+01 3.60E+01 6.18E+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.

6.60E+01 9.87E+05 4.44E+04 1.50E+04 1.10E+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)

B.

GASEOUS

1. NUMBER OF RELEASES

=

0

2.

TOTAL ACTIVITY RELEASED (CURIES)

=

0

=

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%

(3) Sample preparation error

ATTACHMENT III Solid Radioactive Waste Disposal Report

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 1/1/2007 TO 12/31/2007 Number of Number of Waste Container Burial Voli Type of Waste Shipped

1. Waste from Liquid Systems (A) Dewater.ed 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 Shipments Containers Class Type (ft3) ume(m)/

0 5

0 2

0 0

0 5

0 2

0 0

NA 3AS 2B NA 2C NA NA NA 5 HIC NA 2 HIC NA NA 0.0 0.00 858.0 24.30 0.0 0.00 240.6 6.81 0.0 0.00 0.0 0.00 Total Activity (Curies) 0.000 242.150 0.000 47.100 0.000 0.000 0

NA 0

0 NA 0

NA 1AS NA NA NA 1 HIC NA NA 0.0 120.3 21,510.8 0.0 0.00 3.41 609.19 0.00 0.000 0.957 2.808 0.000 8

8 NA NA 22,729.7 643.70 293.015

3.

All Solid Waste

Does not included brokered Dry Active Waste totals.

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2007 TO 12/31/2007 Type of Waste Shipped Radionuclide

% Abundance *

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

H-3 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Zn-65 Nb-94 Nb-95 Zr-95 Ag-108m Ag-110m Sn-113 Sb-1 22 Sb-1 24 Sb-1 25 Te-125m 1-131 Ba-133 Cs-134 Cs-137 Np-237 Ba/La-140 Ce-141 Ce-144 Pu-238 Pu-239 C-14 Fe-55 Ni-59 Ni-63 Sr-89 Sr-90 Tc-99 1-129 Am-241 Pu-241 Cm-242 Cm-243 0.5%

0.0%

0.7%

0.2%

0.5%

0.0%

5.7%

0.0%

0.1%

0.0%

0.2%

0.7%

0.0%

0.1%

16.9%

0.6%

73.9%

0.0%

(C) Evaporator Concentrates (None shipped this period)

Average percent abundance for all shipments during period.

Page 1 of 5

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2007 TO 12/31/2007 Type of Waste Shipped Radionuclide

% Abundance*

(D) Dewatered Mechanical Filters H-3 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Zn-65 Nb-94 Nb-95 Zr-95 Ag-108m Ag-.10m Sn-113 Sb-122 Sb-124 Sb-125 Te-125m 1-131 Ba-1 33 Cs-1 34 Cs-1 37 Np-237 Ba/La-140 Ce-141 Ce-144 Pu-238 Pu-239 C-14 Fe-55 Ni-59 Ni-63 Sr-89 Sr-90 Tc-99 1-129 Am-241 Pu-241 Cm-242 Cm-243 0.0%

3.4%

3.2%

0.2%

36.7%

0.1%

17.8%

0.2%

0.0%

0.7%

1.3%

0.0%

0.7%

0.0%

0.3%

0.0%

0.2%

0.0%

0.3%

24.1%

0.0%

10.2%

0.0%

0.7%

0.0%

(E) Dewatered Demineralizers (None shipped this period)

(None shipped this period)

(F) Solidified (Cement) Acids, Oils, Sludges

Average percent abundance for all shipments during period.

Page 2 of 5

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2007 TO 12/31/2007 Type of Waste Shipped Radionuclide

% Abundance *

2.

Dry Solid Waste (A) Dry Active Waste (compacted)

(B) Dry Active Waste (non-compacted)

(None shipped this period)

H-3 Cr-51 Mr-54 Co-57 Co-58 Fe-59 Co-60 Zn-65 Nb-94 Nb-95 Zr-95 Ag-i08m Ag-110m Sn-113 Sb-i22 Sb-124 Sb-125 Te-125m 1-131 Ba-133 Cs-134 Cs-137 Np-237 Ba/La-140 Ce-141 Ce-144 Pu-238 Pu-239 C-14 Fe-55 Ni-59 Ni-63 Sr-89 Sr-90 Tc-99 I-129 Am-241 Pu-241 Cm-242 Cm-243 0.0%

0.0%

2.1%

0.3%

27.8%

0.0%

9.1%

0.0%

1.7%

0.8%

0.0%

0.1%

0.0%

0.8%

0.0%

41.2%

0.0%

15.7%

0.0%

0.2%

0.0%

Average percent abundance for all shipments during period.

Page 3 of 5

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2007 TO 12/31/2007 Type of Waste Shipped Radionuclide

% Abundance*

(C) Dry Active Waste (brokered)

H-3 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Zn-65 Nb-94 Nb-95 Zr-95 Ag-108m Ag-11Om Sn-113 Sb-122 Sb-1i24 Sb-125 Te-125m 1-131 Ba-133 Cs-1 34 Cs-137 Np-237 Ba/La-140 Ce-141 Ce-144 Pu-238 Pu-239 C-14 Fe-55 Ni-59 Ni-63 Sr-89 Sr-90 Tc-99 1-129 Am-241 Pu-241 Cm-242 Cm-243 0.0%

0.0%

2.1%

0.3%

25.8%

0.0%

9,4%

0.0%

1.5%

0.8%

0.0%

0.1%

0.0%

0.8%

0.0%

42.5%

0.0%

16.4%

0.0%

0.2%

0.0%

(D) Irradiated Components (None shipped this period)

Average percent abundance for all shipments during period.

Page 4 of 5

CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE

SUMMARY

OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/2007 TO 12/31/2007 Type of Waste Shipped Radionuclide

% Abundance*

3.

All Solid Waste H-3 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Zn-65 Nb-94 Nb-95 Zr-95 Ag-108m Ag-110m Sn-1 13 Sb-.122 Sb-124 Sb-125 Te-125m 1-131 Ba-133 Cs-134 Cs-137 Np-237 Ba/La-140 Ce-141 Ce-144 Pu-238 Pu-239 C-14 Fe-55 Ni-59 Ni-63 Sr-89 Sr-90 Tc-99 1-129 Am-241 Pu-241 Cm-242 Cm-243 0.5%

0.5%

1.1%

0.2%

6.6%

0.0%

7.7%

0.0%

0.1%

0.2%

0.0%

0.2%

0.0%

0.1%

0.6%

0.0%

0.1%

18.3%

0.5%

63.0%

0.0%

0.1%

0.0%

Average percent abundance for all shipments during period.

Page 5 of 5

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 (2007)

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 10.45-1 1.00-1 1.50-1 2.00-1 3.00-f 4.00-1 5.00-I 6.00-f 8.00 I 1

0.74 f 1.24 f 1.99 f 2.99 f 3.99 1 4.99 I 5.99 I 7.99 I 9.99 ITOTAL I

,NO.

I NO.

NO.

I NO.

f NO.

I NO.

I I

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

+-------

SECTOR.

I I

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

I I

-N-.

1

.1 61 61 321 171 if

-f 621 I -

4 -

f-NNE-

.fI if

f 41 371 121 161

1 701 1 -

+

f-NE-I 11 21 2f 31 6f 31

1 161 1 - - - - - - - - - - - - - - -- - -- - ---------------------------------

+

-ENE-1 I1 I if if 1

.1 I1 21 1

+

+ -

+

-+

+----

+--+-

I-E-1

.1

.1 f1

.1 if

.1 I

.1 I if I

+

+ -

+

-+

+--+--+-

-ESE-1 1

I I

I 21 I

.I 2 1 1

+

+ -

+

-+

+----

+-

I f-SE-1 I

I 31 41 4f

.1 I 1

.1 i l

+

.+

+-

f-SSE-1 if I

11 381 12f

.1

.1 521

-s-1

.1

.1 if 281 7f 21

.1I 381 1I - - - - - - - - - - - - -- - - - - - - - - - - - -----------------------------------

+-

+

I

-ssW-1

1

1 6f 721 52f 12f if

.1

1 1431

-1

+

-.....- +

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

+--'---+--

+-

f-SW-1

1

.1 sf 971 531 291 61 f

1* 1911 f-WsW-1 if 1f 371 27f 71 31

.1

f 811

+.....

+

+-....-.+

+-..-

+--+-

f-w-1

f

.1 if 191 ill 21

.f

f 331

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

+-

f-WNW-f

.f

.1 if 71 8f 71 5f

.f

1 281

+

-.....- +

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

+----

-+-

f-Nw-f

.f

.1 31 71 71 31 41 5f 291

+

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

.+--+---

+--+-

f-NNW-1

f

.1

1 71 61 a1 51 51

1 311

+

.+

.+-

+-

TOTAL 1

a-f if 2Sf 3211 203S 1461 5sf 301 sf 7901

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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 I

1 1.2S-1 1.50-1 2.00-1 3.00-1 4.00-1 S.00-1 6.00-1 8.00-j 1.49 1 1.99 I 2.99 1 3.99 1 4.99 I S.99 1 7.99 I 9.99 ITOTAL I

+----

I NO.

NO.

I--

+-+---+-++

+

I SECTOR I

I I

I-N-I

.I 31 81 331 161 61

.1 661 1I - - - - - - - - - - - -- - - - - - - - - - -----------------------------------------

j-NNE-1

.1 21 19!

221 11!

31

.1 s71 1

+-.

.+-

+----+-

I I-NE-1

.1 I1 31 51 81 41 1

211 I-ENE-1 I 3[

11 i1 1!

.1

.11 61 1I---------------- ------------------------------------------------

I-E-1 1

61 11

.1 2

I 1

8 I

+-.

.+-.

!-ESE-1 I

3J 11

1 I

.1 1

1 41 I -------------------------------

---~-

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

-+---I----

-SE-41 11 21

.1 I

1 1

74 I ---------------------------------------------------------------

!-SSE-1 61 351 1!

6!

3[

1

.1 471 1--

+---++

+

I-SW-I i

0 12 34I 28

.1 21

.1

1 462 I -------------------------------------------------

+-

+------

I-sSW-I 24 6

o 211 21 61 31 1 3 96 1I----------------

+

I-sw-I 12 1 3 1 81 41 21 11 62 1I---------------------------------------------+----------- -

+-- ---

I I-WsW-I 11 211 41 3j 1j

.1

.1 321 1I - - - - - - - - - - - - -- --- - -- - -- - ------------------------------------

++

+

I I-NW-I

.I 3

121 28 11

.1 l

1 125 1 - -

+--

-+

+.+

.+-.

I-NNW-I

.1 12 10 71 31 2!

.I 1

23s 1 -

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

.I T-OAW-I

.1 26 2

l 3l 21 36 11 312 ITOTAL 1

l 1 651 2381 1251 711 361 ill 21 549

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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

~-F F 1.2S-1 1.50-F 2.00-1 3.00-1 4.00-1 5.00-F 6.00-F 8.00-1 1

1.49 1.99 F 2.99 3.99 499 5.99 F 7.99 1 9.99 ITOTAL NO.

I NO.

NO.

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

+-+-+--+-

+

+-

+

I SECTOR I

I I

I F

I I -

F I

I I

I F I-N-1 2F 261 381 101 31 F

F1 791 I - - - - - - - - - - -- - - - - - - - - - ------------------------------------------ +

I-NNE-1

1 3F 221 2SF 341 131 98' F - - - - - - - - - - -- - - - - - - - - - ------------------------------------------

+

FNE-F 11 11 61 91 211 4

1 43' F - - - - - - - - - - - - -- - - - - - - - - -

+-

+

-ENE-F

.1 51 6

31 F F

F 14 F - - - - - - - - - - -- - - - - - - - - - ------------------------------------------

+

-_E -

1 1

- I 1 1 "1

1 1

2 1 F

+-+

+

.+-.

.+-

-ESE-F I

F

.F 41F

-I 9F I ----------------------

+..-.-

+

+----+-

-+----

+--

+-.

+.-

F-SE-F

.F 4

8j 21

.F F

F F

14[

F ------------------------------

+-+-+

+--

-+-.+.-.I F-ss -

16F 3 1 41

.I F

1 F - - - - - - - - - - - - --- - - - - - - - - - -------------------------------------

+-

+

I Fs- '1 18 26F 1

I 46 1I----------------------------+

I I-SSw-41 26 44F i

101 21 F 97 F-Sw-41 201 271 91 41 11

F

.F 6SF I - - - - - - - - - - -- - - - - - - - - - ------------------------------------------

+

I-wsw-1 41 16 10 2F 1

.F F

F 321 1

+---+--r--+-----------+----------+--+-+---

+-

FI F-W F

.F 81 12F 11 F

.21F F-----------------------+---------- -.--.

+-

+--

F-I F-W F

.1 41 61 31 1

3F 21 191 F------------------------+---++-.

+-

+------+-

+-

F F-NW-F 21 71 51 41 41

'F 21 25S F - - - - - - - - - - - - -- - - - - - - - - - - -------------------------------------

+-

+

I F-NW 1

'F 21 9F 9F 4F 21 21 I1 291 F - - - - - - - - - - -- - - - - - - - - - -------------------------------

+

JTOTAL F

16F 126F 249F 12SF 91I 32F 71 21 648

--- +-

+-.....--

-+-.

-+- -.

+-.....-

-+- -

-+ -.

7+- - -

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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

1 1 0.74 1 0.99 1 1.24 1 1.49 I 1.99 I 2.99 1 3.99 4.99 [ 5.99-7.99 [TOTAL I

+--....

I I NO. [ NO.

j NO.

I NO.

NO.

I-

+

I+

ISECTOR I

I

[

I I

I I - - - - - - -

I-N-

[

.1

.1 3j 101 291 140[

1241 501 18[

16[

390[

1---------------------------------------------------+-----+-

+-.

I

-N E-/

.1 I

.I I

10o 61i 1991 121J 49[

12[

457[

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

+

+-

I

[-NE-1

.[

1j 1[

1[

9[

221 801 441 ii[

3[

1721

-ENE-I

'I "I

'I 4

31 41 29[

161 6[

21 641 1 -

+-

[- -

[

.1 11 31 2[

21 8[

4[

.[

1 201 1-------------------------------------------------------+-

+

+-

+

-- +

+-.

.+-

I I-ESE-1

.1

'1 21 41 61 101 31 11 1

1 271 1I - - - - - - - - - - - - - - -- - -- - -- - -- - -- ----------------------------------------

+

I1.

[-SE-I

.I 11 3

6 131 381 1o0 21 1

[

73[

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

+

I I-SSE-I

.1 31 s[

12[

561 881 241 11 1

4 189[

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

+

I

[-s-I

.I 8[

221 301 541 801

'SI 7[

1

.1 219[

1

+--

-+--

-+ :- -- I

-SsW-I

.1 s

201 321 9 1o 1121 491 231 41 1[

3361 1I - - - - - - - - - - - - - - -- - - - - - - - - - - - - - ------------------------------

I I-SW-

.1 7[

17[

341 63j 701 28j 12[

2[

.14 233[

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

---I

-WSW-1 41 101

[

24[

36[

29[

ill 2[

21 1

I i[

I

-+

+---

I I

i1 41 isl 22[

18[

13[

21 I

I 75[

I -

+--

J-WNW-I

.1

.I 91 18[

16j i91 4[

81 6[

I1 84j I

I I-NW-I

.J 21 31 41 1sl 271 ii[

191 7[

91 971 I---------- ------------ -----------

+-

I

[-NNW-I

.I 31 21 81 421 611 25[

15I 17[

61 179[

I I

[TOTAL 1

11 401

.11S1 216[

462I, 782[

621[

3211 1221 S31 2733[

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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

1 0.4s-1 0.75-I 1.00-1 1.25-I 1.50-1 2.00-1 3.00-1 4.00-i 5.00-1 6.00-1 8.00-1 1 0.74 10.99 1.24 1 1.49 1 1.99 1 2.99 1 3.99 1 4.99 1 5.99 1 7.99 i 9.99 ]TOTAL I------+-.....+....+....--

+-

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

I NO.

NO.

I NO.

I.NO.

I NO.

NO.

+

+-

-+-+-

+

+.----+--

I SECTOR I

I I

I

-N-I

,.I 41 41 231 711 5O 91 21 41 1671 1I - - - - - - - - - - - - - - - - - -- - -- - -- - -- - -- -----------------------------

+

j-NNE-1 1

1 31 21

.1 i1j 101 91 11 1I 1

371 1 -

+--

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

I I-NE-I 11

1

.1 11 51 11 121 9I 61 31

1 381 I-

+

+.

.- I

-ENE-21

.1 11 61 31 1

I1

.1

.1 3

1- - -

+--- -

I-E-1 I

1

.1 31 31 31

.1 2

1 121 1

+----

-+ -

-+-

-+

I

-ESE-1 1

31 21 11 21 61 41 21 1

.1 201 1

+-+

-+

--. I I-SE-I 1 1

1 41 31 9[

24!

131 31

.1 1

.1 561 1I-------------

I I-SSE-I 1

61 81 281 581 601 251 6

31 1I

l 195I 1

I+

IS- -1 8

231 691 1111 1051 81 3I 11

1

1 3281 1------------------------------------------------------------------------------------++

+.-.

I

[-SSW-I 21 16!

591 911 1361 1261 271 4

11

.1 1

4621 1 -

+-

+--

-I I-SW-1 1[

251 401 461 441 331 151 5

1 1

2091 I - - - - - - - - - - - - - - -- -- - - - - - - - - - - - - - - ---------------------------------

++

+

-I I-WSW-I 31 201 251 35 311 101 1j 1

1 11 1261 1- -

+--

-- I I-W-31 181 161 221 211 16j 21

.1

.1 98!

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

+

I I-WNW-1

'I 121 171 20!

371 31j 71 "1

1 1

1251 1I----------------

+

+-

--- I I-NW-I I

41 10!

22!

41j 52I 191 8!

1I 21

1 1591 I - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- - -----------------------------------

++

+

I

!-NNW-1 I

21 91 15!

48!

93 51 8

'I 1

1 2261 1

+-+-+-+-

+-

-+

I I-CALM-I 11

-1I

-*1

.I 1

.1 I

.1 1

i I

141--------------------------------------------

ITOTAL 1

141 11SI 2201 3621 5701 6481 247!

691 151.

ill 11 2272!

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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

WIND SPEED CLASS I--------------------------------------------I 1 0.45-1 0.75-f 1.00-1 1.25-f 1.50-f 2.00-1 3.00-1 4.00-1>9.99 1

1 0.74 f 0.99 I 1.24 f 1.49 1 1.99 f 2.99 I 3.99 I 4.99 I M/S ITOTAL I ------------------------------------

+-

+

+ -

I I NO.

I NO.

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

+-+-

+

+ -

I SECTOR I

I I

I II I

I I

I-N-I I

31 I

31 71 301 81 1

511 I------------------------------------------------------+---+-

-+

E-I

.1.1 11 1

21 21 51

1 sf

+--+

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

+----

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

I I-NB -

1

.1 1 1i1 1

.1.1 1.

2 1

+--+

+

+---

+--

+---

+...-..

-ENE-I I

I I

I f

-ESE-1

f

.f

.1

.1 I1 if if

f

1 21

+-

+

.+

f-SE-

.if if if 2f if 41 21 if

I 131 f-SSE-1

I 21 21 6f 23f 71 11 if

-1 421

+--

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

I

-s-1 i1 il 39f 4sf 27 1

1-

.1

.f 1241

+---------

+--

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

-ssW-1 21 181 521 59f 34 11

.f 1 167

+ r

+- -

+-...+.

.+

f-SW-1 Sf 311 2Sf 261 Sf 21

.1

.1 11 9sf 17

+

I f-WSW-1 2f 201 13f 20f 161 61f

.1

.f

1 771

+--

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

I I

f-W 2

121 142 1f i

isf 131 2

o of 1

66f 1 - - - -

f-W3w-1 31 141 17f 19i 191 1sf

.i1

f 821 1+--

-7.-.-- - - --

-NW-I

'I af 19f 18f 261 81 11

1

.f 81f

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

+--

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

+.-

f-NNW-I

f 4f 16I 23f 421 331 31

.1 1

121f T

- -i-+f s+....

f 23.... f 213....+

+-

f..

+...

f.

4f.....

If 930 ITOTAL 1 171 12SI 1981 2381 2131 1151 191 41 11 9301

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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 I

-- - - - - - - - - - - - - - - - - - - - - - - - - - - II 1 0.45-I 0.75-I 1.00-I 1.25-1 1.50-I 2.00-1 3.00-1>9.99 1 1 0.74 1 0.99 I 1.24 1 1.49 1 1.99 1,2.99 1 3.99 I M/S ITOTAL I I --

+--

+-

+-.-

I I NO.

I NO.

I NO. I NO.

NO.

I..............

+--

-+--

+

-+- --- I SECTOR I

I I

I 1 I

1 SI I

I I

-N-I

.1 1I

.I

.I 91 181 31

1 311 1

+

+--+--+-

-+

+

I-NNE-I I

I.1 1

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

+

I I-NE-I 1I

.1I

. I

.1 1.1 1

I 4

I

-+- +--+.

+

.+

I..

I-ESE-11 1

.1 1

1 1

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

+-

4

+

+-

+

I I-SE-I

.1 11

-I 251

.1 1

.*1 1

91 I-

++

+-+

I

-SSE-I s1 2 1 30 1

61

.1I 1 271 I

4+

+

-. + -.

+-.

.I I-SW 51 21 311 251 101 A

I 901 I----------------- -------------------------------

4

+

4 4-

-4

+

I-ssW -

I 7j 271 301 451 1 1 1

.1 1251 I---------------------------+-+

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

I-sW-I 21 2

1 101 211 10[

81 1

.1 821 I-7

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

I I-WSW-I j7 261 198 91 71 1

"I

.1 681 I

4 4-

+

-. +

I I

I-w-I il 201 241 22l 81 8I

.1 681 I

+

+--+-

+

+-

I I-WNW-1 21 10 181 91 61 311

.1 481 I-N -

I sl 161 241 221 ill 11

-1 791 I-NNW-I

.41 81 221 371 201

.1 I

911 I

+-+-

+-

I+-

+

I-CALM-I

'1

1

-I

'1 I1 T

I 4..

1

+1-1 6 51-1 64--

1 2 31--

5 0 1.....

6 9 ITOTAL 1

401 1471 1651 1641 1231.

501 41 11 6941

CATAWBA NUCLEAR STN.

METEOROLOGY (2007)

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 I

I 0.45-1 0.75-1 1.00-1 1.25-[ 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1>9.991 1

0.74 j 0.99 1 1.24 1 1.49 j 1.99 J 2.99 j 3.99 4.99 I 5.99 I 7.99 I 9.99 j M/S ITOTAL I --------

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

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

+.....---

I I NO.

I NO.

NO.

I NO.

NO.

I NO.

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

+-

I ISECTOR I

I I

I II I

I I

I

I1--

- - -I I

I I

I-N-I

.1 41 71 171 731 2991 2621 1171 461 211

1

1 8461 I------------.-------------------- ------

r+

+----

I-NNE-I

.I.

1 1

81 141 981 2591 2231 861

. 331

I i

7251 1 -

I I-NE-I 21 21 11 31 161 34[

1081 861 311 101

.1

.L 2931 I ------------------------------------------------------------------

+

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

-ENE-I 21 I

41 71 171 401 221 61 21 1

100j I------------------------------------------------------------------------------------ --

+-

I I-E-I

.1 21 31 71 61 181 6j 21

.1 1

1 I

441 1- -

I

-ESE-1

.1 41 41 sl 151 231 ill 31 1

1 1

I 651

+

+--+-

I I-SE-I 1

31 81 i

3 791 3

61

.1 17 1---------------------------------------...------------------------------------+-

I

-SSE-21 ill 151 461 1711 2631 671

.8 31 11 5871 I-

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

+

+----

+--+-

I I-s-61 5

115i 1701 2321 2741 361 121 1i

.1 8911 I-SSW-I 91 661 1611 2311 3161 41I 1611 51 ill 11

.1 I 14261 I - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- - -- ----------------------------------

+-

+

I I-SW-I 8I 871 1071 1311 1591 2641 1131 54 1

1 21 9371 1-

+-I I-WSW-1 121 701 681 931 1171 1131 45I 91 61

.1 1j I 5341 I---------------------------------------------------------------------------------

+-

I I-W-I 171 541 551 701 721 901 181 31 I1I 1

3791 1----- ----

+------

+-

I J-WNW-I 61 361 61[

661 841 861 291 191 16[

61

.1 1

4091 1----------------------------------------------------------------------------------+-

I I-NW-I 61 301 561 661 9

1021 s1 3 1 201 221 81 1

4951 1

_+.....--

+-+

.+

-..+-

+

I NNW-I

.1 131 3

691 1731 2281 105*

1 261 141 11 1

7081 I----

I I-CALM-I 21

-I

.1

-Il

.I I.

.1

.1 21 I

+--

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

+-

I ITOTAL I

731 4271 6991 9971 1584j 24031 13441 702j 263!

1121 10!

21 86161

ATTACHMENT V Unplanned Offsite Releases

A sample obtained from groundwater monitoring well 213 contained tritium levels that triggered the communication protocol of the NEI initiative on groundwater protection on October 8, 2007. Attached is the 30 day report to the NRC made on November 7, 2007.

Duke JAMES R MORRIS U Energy.

Vice President Catawba Nuclear Station 4800 Concord Road I CNO.I VP York, SC 29745-9635 803 831 4251 803 831 3221 tax November 7, 2007 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413, 50-414 30-Day Report Pursuant to the Groundwater Protection Initiative Concerning Catawba Nuclear Station Groundwater Monitoring Well 213 Duke Power Company, LLC (Duke) is submitting the attached 30-day Report pursuant to NEI 07-07 (Industry Groundwater Protection Initiative). A sample obtained from groundwater monitoring well 213 contained tritium levels that triggered the communication protocol of the NEI initiative on groundwater protection on October 8, 2007.

There are no regulatory commitments contained in this letter. Any questions concerning this report may be directed to Anthony Jackson at 803-831-3742.

Very truly yours, ames R. Morris Attachment IVw/.

u k e -of ml p, y. c. o [p

U.S. Nuclear Regulatory Commission November 7, 2007 Page 2 xc: w/attachments W. D. Travers, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 J. F. Stang, Jr., Senior Project Manager (CNS & MNS)

U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8 G9A Rockville, MD 20852-2738 A. T. Sabisch Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Station S. E. Jenkins, Section Manager Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201

U.S. Nuclear Regulatory Commission November 7, 2007 Page 3 bxc (with attachments):

R. D. Hart R. L. Gill T.W. Hamilton K. E. Nicholson NCMPA-i NCEMC

PMPA

SREC Catawba Document Control File: 801.01 - CN04DM iCatawba RGC Date File ELL-EC050

ATTACHMENT 30-DAY REPORT PER NEI 07-07, INDUSTRY GROUNDWATER PROTECTION INITIATIVE, CATAWBA NUCLEAR STATION, UNITS 1 AND 2

i. This report is being submitted in support of the NEI 07-07 Groundwater Protection Initiative.

This report was generated as a result of the groundwater monitoring results for well 213. These results triggered the communication protocol of the NEI initiative on groundwater protection on October 8, 2007.

ii.

A sample obtained from groundwater monitoring well 213 contained tritium in-a concentration of 42,335 pico curies per liter (pCi/I).

iii. On October 8, 2007 Duke analyzed a sample obtained from groundwater monitoring well 213. The sample contained tritium levels that triggered the communication protocol of the NEI initiative on groundwater protection on October 8, 2007. On Tuesday October 9, 2007, Duke verbally advised the NRC and appropriate agencies of an on-site environmental monitoring well sample result of 42,335 Pico curies per liter of tritium.

Since October 9, 2007 for plant structures, systems, and components in proximity of well 213, Duke has (1) performed a visual inspection of nearby plant trenches and in-trench piping; (2) performed hydrostatic testing of piping that could not be visually verified; and (3) implernented design reviews of sump pumping systems and drainage systems. In each of these instances, no active or intermittent source of leakage was detected.

Existing hydro-geologic model indicates that the flow of the groundwater at and around well 213 is in the direction of the plant turbine building. CNS has procured an independent expert opinion which arrived at the same conclusion. Duke has contracted with a vendor to develop a 3-dimensional hydrology model with a time variable to better quantify the underground transport times.

Four additional groundwater monitoring wells have been drilled. Two additional wells are planned. These wells are located in strategic proximity to the 213 well and were located to obtain more detailed information regarding the potential migration of the groundwater in question. Results Page 1 of 2

from samples that will be obtained from these well locations are expected by mid-November.

iv. The well displaying activity is a groundwater monitoring well and not a drinking water well. Other groundwatei" monitoring wells which bound this well do not indicate that the groundwater from this location has migrated to the site boundary. Rather the migration path is in the direction of the plant turbine building. Therefore there is no public exposure pathway and Duke determined that there is no estimated annual dose to any member of the public associated with this event.

v. Since there is no estimated annual dose to a member of the public from this event, no corrective actions are necessary to reduce the projected annual dose to a member of the public to less than the limits of 10 CFR 50 Appendix I.

Page 2 of 2

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 and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 1st Quarter 2007

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit 01 - Maximum Organ Dose CHILD LIVER 1.46E-01 1.50E+01 9.76E-01 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS==.........==================

Quarter 1 2007 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q1 - Maximum Gamma Air Dose 7.41E-03 1.OOE+01 7.41E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.76E+01 Q1 - Maximum Beta Air Dose 3.02E-03 2.00E+01 1.51E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 Contributors (5% or greater to total)

Percentage 8.45E+01 1.37E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2007

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q2 - Maximum Organ Dose CHILD LIVER 2.09E-01 1.50E+01 1.39E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

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

Quarter 2 Dose Limit Period-Limit (mrad)

(mrad) 2007

% of Limit Q2 -

Maximum Gamma Air Dose 8.11E-03 1.OOE+01 8.11E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.76E+01 Q2 -

Maximum Beta Air Dose 3.20E-03 2.OOE+01 1.60E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 Contributors (5% or greater to total)

Percentage 8.71E+01 9.95E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2007

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2007 Critical ýCritical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q3 - Maximum Organ Dose CHILD LIVER 2.46E-01 1.50E+01 I.64E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS===-.............==========

Dose Period-Limit (mrad)

Quarter 3 2007 Limit

% of (mrad)

Limit Q3 -

Maximum Gamma Air Dose 8.47E-03 1.OOE+01 8.47E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.34E+01 Q3 -

Maximum Beta Air Dose 4.12E-03 2.OOE+01 2.06E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide,

Percentage AR-41 XE-133 XE-135 6.78E+01

2. 60E+01 6.16E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2007

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q4 -

Maximum Organ Dose CHILD LIVER 2.93E-01 1.50E+01 1.95E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS-------------------------

Quarter 4 2007 Dose Limit

% of

Period-Limit (mrad)

(mrad)

Limit Q4 -

Maximum Gamma Air Dose 5.34E-03 1.00E+01 5.34E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.81E+01 Q4 -

Maximum Beta Air Dose 2.12E-03 2.00E+01 1.06E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 Contributors (5% or greater to total)

Percentage 8.72E+01

-1.18E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2007

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Yr - Maximum Organ Dose CHILD LIVER 8.95E-01 3.00E+01 2.98E+00 Maximum Organ Dose Receptor Location: 0.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide H-3 Contributors (5% or greater to total)

Percentage 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Annual 2007 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Yr - Maximum Gamma Air Dose 2.93E-02 2.OOE+01 1.47E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.65E+01 Yr - Maximum Beta Air Dose 1.25E-02 4.OOE+01 3.11E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 Contributors (5% or greater to total)

Percentage 8.01E+01 1.65E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 Ist Quarter 2007 BATCH LIQUID RELEASES---------------------------

Critical Critical Dose Period-Limit Age Organ (mrem)

Q1 - Maximum Organ Dose ADULT GI-LLI 2.83E-02 Q1 - Total Body Dose CHILD 2.48E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Quarter Limit (mrem) 1 2007==....

Max % of Limit l.00E+01 2.83E-01 3.OOE+00 8.27E-01 H-3 NB-95

7. 90E+01 1.49E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.84E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Ql - Maximum Organ Dose CHILD LIVER 5.35E-04 Q1 - Total Body Dose CHILD 5.35E-04 Quarter Limit (mrem) 1 2007======

Max % of Limit l.00E+01 5.35E-03 3.OOE+00 1.78E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%

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

Nuclide Percentage H-3 1.00E+02 or greater to total) or greater to total)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 2 nd Quarter 2007

=== BATCH LIQUID RELEASES Period-Limit Q2 - Maximum Organ Dose Q2 -

Total Body Dose Critical Critical Dose Age Organ (mrem)

CHILD LIVER 2.31E-02 CHILD 2.29E-02 Quarter 2

.Limit (mrem) 1.00E+01 3.00E+00 2007 =-

Max % of Limit 2.31E-01 7.63E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.69E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage I

H-3 9.80E+01 CONTINUOUS LIQUID RELEASES (WC)-......................

Critical Critical Dose Period-Limit Age Organ (mrem)

Quarter 2 Limit (mrem) 2007 --

Max % of Limit Q2 -

Maximum Organ Dose Q2 - Total Body Dose CHILD CHILD LIVER 2.57E-04 1.00E+01 2.57E-03 2.57E-04 3.OOE+00 8.57E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 3 rd Quarter 2007 BATCH LIQUID RELEASES Critical Critical Dose Period-Limit Age Organ (mrem)

Q3 -

Maximum Organ Dose ADULT GI-LLI 2.04E-02 Q3 - Total Body Dose ADULT 1.27E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Quarter Limit (mrem) 3 2007 =-....

Max % of Limit l.00E+0l 2.04E-01 3.OOE+00 4.23E-01 H-3 NB-95 CO-60 4.93E+01 3.61E+01 8.98E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 CS-137 7.90E+01 1.52E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q3 -

Maximum Organ Dose CHILD LIVER 1.79E-04 Q3 - Total Body Dose CHILD 1.79E-04 Quarter 3 Limit (mrem) 1.00E+01 3.OOE+00 2007......

Max % of Limit 1.79E-03 5.97E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.OOE÷02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.OOE+02 greater to total) greater to total)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 4 th Quarter 2007

=== BATCH LIQUID RELEASES Period-Limit Q4 - Maximum Organ Dose Q4 - Total Body Dose Critical Critical Dose Age Organ (mrem)

ADULT GI-LLI 1.60E-02 CHILD 1.29E-02 Quarter 4 Limit (mrem) 1.00E+01 3.00E+00 2007 Max % of Limit

1. 60E-01 4.29E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 NB-95 CO-60 6.95E+01 1.83E+01 5.83E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.47E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q4 - Maximum Organ Dose CHILD LIVER 4.46E-04 Q4 - Total Body Dose CHILD 4.46E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Quarter 4 Limit (mrem) 1.00E+01 3.00E+00 2007 =-

Max % of Limit 4.46E-03 1.49E-02 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 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 2007 BATCH LIQUID RELEASES Critical Critical Dose Period-Limit Age Organ (mrem)

Yr -

Maximum Organ Dose ADULT GI-LLI 8.62E-02 Yr - Total Body Dose CHILD 7.07E-02 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.17E+01 NB-95 1.83E+01 CO-60 5.35E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Annual Limit (mrem) 2007=========

Max % of Limit 2.OOE+0l 4.31E-01 6.OOE+00 1.18E+00 H-3 9.57E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Yr -

Maximum Organ Dose CHILD LIVER 1.30E-03 Yr - Total Body Dose CHILD 1.30E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02 Annual Limit (mrem) 2007.........

Max % of Limit 2.OOE+0l 6.52E-03 6.OOE+00 2.17E-02

Catawba Nuclear Station 2007 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.

2007 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 =

9.89E-01 mrem Maximum Location: 0.5 Mile, Northeast Sector Critical Age:

Child Gas non-NG Contribution:

91%

Gas NG Contribution:

2%

Liquid Contribution:

7%

Maximum Organ (other than TB) Dose =

9.71E-01 mrem Maximum Location: 0.5 Mile, Northeast Sector Critical Age:

Child Critical Organ:

Liver Gas Contribution:

92%

Liquid Contribution:

8%

I1.

2007 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 IOCFR72.212 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 I OCFR72.212 Evaluation NAC-UMS Universal Storage System.

Page 28 ot."54 7.3 10CFR72.212(b)(2)(i)(C) - Requirements of §72.104

"(C) the requirements of'§72.104 have beenu met.. A copy ofthis record shall be retained until,spent [fel is no lon ger stored under the general license iss'ued 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 mrem) to the whole body, 0.75 mSv (75 orerm) 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) Any other radiation friom 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 10(010R72.212 Evaluation NAC-UM4S Universal Storage System Page 29 of 54 Phase I 1 Pad 24 Casks Filled 2009 Phase If 7 Pads 168 Casks Filled 2042 Phase Ill II 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 1 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

CNS I OCFR72.212 Evaluation NAC-UMS Universal Storage System Page 30 of 54 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 (loses. The first calculation (Reference 7.3-3) determines the source term for the base canister. The results of this calculation include the firactional probability energy spectra for photons and neutrons, the photon and neutron release rates per canister as a function of burnup 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 MCNIP model of the NAC UMS with the l)uke 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 17x 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. The origin-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 mrem/hr.

CNS 1O}CF1`<72.2 12 F, valuation NAC-JMS Universal Storage System3 l1a0e 3 1 of 54 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 tIr 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. II 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 11.

Phases 11 and III are modeled using the same detector layout so the dose from each phase can be added todetermine the total (lose 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 i(hrs/vr)

Point Coord.

Coord.

Entrance Road 8766 RPl12 26+50 44+00

Crepe Myrtle Road 8766 RP13 75+00 48+00

Security Practice Range 144 RP 14 25+00 89+00 The dose rates at these locations are:

Description of data Phase V*

Phase 2*

Phase 3*

point location

[inremn/yrI Imr/yrl Imnre/inyr]

2500' Exclusion Area Bounday-_

Entrance Road 0.06 0.29 0.85

Crepe Myrtle Road 0.08 0.32 0.79

Security Practice Range 0.01 0.03 0.03

Maximum values from Table 2 or 3, Reference 7.3-6 The above information will be added to the plant generated dose to prove compliance with 72. 04. General Office Radiological Protection has responsibility for this function.

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

There were no revisions to the Catawba Nuclear Station Updated Final Safety Analysis Report, Section 16.11, Radiological Controls, in 2007.

ATTACHMENT VIII Revisions to the Radioactive Waste Process Control Program Manual

The following letter dated April 16, 2008 from David L. Vaught, Senior Engineer, Nuclear Chemistry, summarizes how the Process Control Program (PCP) manual has been revised. The updated version of the manual contains all the changes implemented during 2007 and is designated as the "2007 Update" on the enclosed Compact Disc.

April 16 2008 RD Hart Regulatory Compliance Manager Catawba Regulatory Compliance ATTENTION: MJ Sawicki

SUBJECT:

Catawba Nuclear Station 2007 Annual Radioactive Effluent Release Report Process Control Program Changes File: GS-764.25, CN-215.06 Enclosed are 7 CD copies of the Radioactive Waste Process Control Program Manual to be included in the Annual Radioactive Effluent Release Report for Catawba Nuclear Station for the period of January 1, 2007 through December 31, 2007. This version of the Manual contains all the changes implemented during 2007 and is designated as the "2007 Update".

The PCP Manual is revised using the review and approval process in APPENDIX F of the Manual, "Administration of the PCP and Support Documents" prior to publication on the NEDL Portal.

The attachment summarizes the scope of the changesduring 2007.

The PDF files on the CDs were reviewed and verified against the control copies of the PCP Manual published on the NEDL Portal. Because of the NRC electronic record screening process, the PDF file for the NRC was revised to remove all graphics. The graphics were non technical images that did not meet the resolution requirements, e.g., the Duke Logo, NGD image and site pictures, etc.

Three CD copies containing graphics are for internal distribution and 4 CDs without graphics are for the NRC as follows:

NRC File NRC_ 2008 Duke Energy Radioactive Waste PCP Manual.pdf

1. NRC Document Control Desk

2. Catawba NRC Project Manager

3.

Catawba Senior Resident Inspector

4. NRC Regional Administrator Duke File: AEERR CDDPCo-2008-PCP-Manual.pdf

5.

ELL - CD

6. Master File - CD

7.

Regulatory Compliance Files - CD If you have any questions, please call David Vaught @ 980-373-5302.

Dewey P Rochester Technical Manager II Nuclear Chemistry by:

David L Vaught Senior Engineer Nuclear Chemistry - Radwaste ATTACHMENT xc:

BN Kimray (CNS)

EB Green (CNS)

CD Ingram (NGO)

ATTACHMENT Duke Energy Radioactive Waste Process Control Program Manual Summary of 2007 Changes A brief summary of the 2007 changes to the Duke Energy Radioactive Waste PCP Manual is found below. These are described in more detail in APPENDIX H "Revision Summary -

Licensee Initiated Changes" REVISED SECTIONS Rev 15 Corporate PCP

Revl3 APPENDIX A "Oconee Nuclear Station Process Control Program" Revl8 APPENDIX B "McGuire Nuclear Station Process Control Program" Rev 12 APPENDIX C "Catawba Nuclear Station Process Control Program" Rev 2 APPENDIX D "Approved Suppliers of PCP Services"

" Rev 1 APPENDIX F "Administration of the PCP Manual and Associated Documents" The Duke Energy Radioactive Waste PCP Manual was revised to address the issues described below:

PIP G06-00560: Summarized findings and Areas For Improvement (AFI) from the 2006 Annual Chemistry Functional Area Evaluation. The Duke Energy Process Control Program Manual and associated documents were audited during this assessment and-the administrative changes were implemented.

PIP G-7-00244: Revised ADDENDIX D to reflect the vendor name change from Duratek to Energy Solutions per PIP G-07-00244 that documents the Vendor Technical Impact evaluation of Energy Solutions procedure FO-OP-023 rev 23.

Non-technical editorial changes were also made to each revised section as appropriate to improve wording clarity, grammatical and punctuation errors. Some administrative process flow changes were made in APPENDIX F to reflect updated Duke administrative processes 0 PIP G-07-0841: Documents the only technical change to the Corporate PCP Section:

Deleted section 11.3.3.6 that required initial liner unwatering upon completion of final waste transfer to liner (e.g., dewater to loss of vacuum in bottom dewatering laterals to establish capillary dewatering conditions). This change was based on reevaluation of the original basis for this requirement updated with industry OE and communications with the manufacturer.

More details of the changes are described in Appendix H by section.

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

Groundwater Protection Initiative

ARERR Groundwater Well Data Section Rev. 1 Duke Energy has implemented the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (June 2007), a voluntary groundwater investigation project adopted by the United States commercial nuclear power industry. 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, the Catawba Nuclear Station installed thirty-seven ground water monitoring wells. With the existing nine wells there are now a total of forty-six ground water monitoring wells in place at Catawba. These wells are currently being sampled quarterly (with the exception of the five LMW wells which are semi-annually). All samples are being analyzed for tritium and gamma emitters, with selected wells being analyzed for Strontium 89 and 90. No gamma activity (other than naturally occurring radionuclides) or Strontium was identified in any of the well samples.

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. Monitoring of this area is on-going. The contamination and resulting investigation activities were reported to the NRC and to state and local officials.

Results from sampling during 2007 are shown in the table below.

Well Name Well Location Annual Average Tritium Concentration in pCi/1 ClOOR U-1 SFP No sample available.

C100DR U-1 SFP

<MDA C1OIR U-1 SFP 736 C101DR U-1 SFP 541 C102 E of Ul SFP O/S protected area 343 C103 E of U1 SFP @

Cooling Towers 244 C104 U-I RMWST 536 C105 Engr. Bldg.

2,020 C105R Engr. Bldg.

1,466 C106 W Parking Lot

<MDA C106R W Parking Lot 514 C107 MET Tower Hill 841 C200R U-2 SFP 1,145 C200DR U-2 SFP 469 C201R U-2 SFP 2,245 C201DR U-2 SFP 1,420

ARERR Groundwater Well Data Section Rev. 1 C202 S of RMC Tent 779 C203 E of RMC tent @

Cooling Towers 1,585 C204 S of RMC Tent 498 C205 Adm. Parking

<MDA C205R Adm Parking 464 C206 W Parking Lot

<MDA C207R Mon. Tank B 393 C207 Mon. Tank B 347 C208 N ofMTB 188 C209 MTUville S of light pole 23A 558 C210 N of U2 Mech Equip Bldg 799 C211 W of RL intake O/S protected area 459 C212 Behind Aquatic Center

<MDA C213 Mon. Tank B 25,867 C213R Mon. Tank B 199 C214 NofU2 TB 696 C215 N of U2 TB 12,510 C217 N of U2 TB 677 C218 N of U2 TB 10,990 C220 N of U2 TB 44,600 C221 N of U2 TB 217 WCMW-2 WC Ponds 3,560 WCMW-3 WC Ponds 531 WCMW-4 WC Ponds 450 WCMW-5 WC Ponds 228 LMW 2A Landfill

<MDA LMW 3A Landfill

<MDA LMW 4 Landfill

<MDA LMW 5S Landfill

<MDA LMW 5D Landfill

<MDA pCi/l - pico curies per liter MDA - Minimum detectable activity 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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