ML13324A392
| ML13324A392 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/06/2013 |
| From: | Armstrong L Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, NRC/FSME |
| References | |
| 13-215A | |
| Download: ML13324A392 (11) | |
Text
Dominion Nuclear Connecticut, Inc.
4Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 W06erlord, CT 06385 NOV 06 2013 dom.corn U.S. Nuclear Regulatory Commission Serial No.
13-215A Attention: Document Control Desk MPS Lic/GJC R0 Washington, DC 20555-0001 Docket Nos.
50-245 50-336 50-423 License Nos.
DPR-21 DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 1, 2. AND 3 ERRATA TO THE 2012 RADIOACTIVE EFFLUENT RELEASE REPORT In accordance with 10 CFR 50.36a, this letter transmits the errata to the annual Radioactive Effluent Release Report (RERR) for the period January 2012 through December 2012. The report met the provisions of Section 5.7.3 of the Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (PDTS), and Sections 6.9.1.6b and 6.9.1.4 of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively. The RERR contains information regarding airborne, liquid, and solid radioactivity released from Millstone Power Station, including the off-site dose from airborne and liquid effluents. transmits the errata and corrigenda to the 2012 RERR. It contains six replacement pages to the 2012 RERR. These pages should be replaced with the same numbered page in the current copy of the report.
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444 4301.
Sincerely, L. J. Armstromg Director, Nuclear Station Safety and Licensing
Attachment:
1 Errata to the 2012 Radioactive Effluents Release Report i-i§ez-B
Serial No. 13-215A Errata to the 2012 Radioactive Effluent Release Report Page 2 of 3 Commitments made in this letter:
- 1. None.
cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 S. J. Giebel NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F5 11545 Rockville Pike Rockville, MD 20852-2738 L. A. Kauffman NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. G. Rolph NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 J. S. Kim NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-C2A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring & Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No. 13-215A Errata to the 2012 Radioactive Effluent Release Report Page 3 of 3 A. Honnellio Regional Radiation Representative (EPA Region 1, Boston)
U. S. Environmental Protection Agency (Region 1) 5 Post Office Square Suite 100 Boston, MA 02109 G. Allen Jr.
Department of Health and Human Services U. S. Food and Drug Administration 90 Madison Street Room 402 Worcester, MA 18608 Mr. Robert Stein Chairman Connecticut Siting Council 10 Franklin Square New Britain, CT 06051 Mr. Pat Kelley Waterford-East Lyme Shellfish Commission Waterford Town Hall Waterford, CT 06385 Mr. Jason A. Martinez American Nuclear Insurers 95 Glastonbury Blvd.
Glastonbury, CT 06033 D. Carey Connecticut Department of Agriculture Aquaculture Division P. O. Box 97 Millford, CT 06460 Mr. Dan Steward First Selectman Town of Waterford Waterford Town Hall Waterford, CT 06385 Mr. Paul Formica First Selectman Town of East Lyme PO Box 519 Niantic, CT 06357 University Of Connecticut Library Serials Department Storrs, CT 06268
Serial No. 13-215A Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 ATTACHMENT 1 ERRATA TO THE 2012 RADIOACTIVE EFFLUENTS RELEASE REPORT MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)
Errata to 2012 Millstone Radioactive Effluents Release Report A) Instructions:
Replace each of the following pages with the same numbered page in the current copy of the report. Pages to be replaced include Pages 7, 10, 17, 20, 24 and 26.
B) Explanation of revisions Section 1.2.3 and Tables 1-3, 2.2-Al, 2.2-A4, 2.3-Al and 2.3-A3 of the 2012 Radioactive Effluents Release Report are resubmitted. A new first paragraph is added to Section 1.2.3 to discuss the C-14 dose and to explain why airborne doses in 2012 were lower than prior years. Revisions to the tables were made to correct the following errors:
- 1) In Table 1-3, the Total Off-Site Dose from Millstone Station was revised for Direct Shine and totals with and without C-14. This was a transcription error on the entry for Direct Shine dose.
- 2) In Tables 2.2-Al and 2.2-A4, the total activity of Fission & Activation Gases were revised for all four quarters because the activity for Ar-41 was not included in each quarter. The annual total activity for Fission & Activation Gases was correct and did not need revision.
- 3)
In Table 2.2-Al, the total activity of lodines/Halogens were revised for the third and fourth quarters because the activity for Br-82 was not included for those quarters.
- 4) In Table 2.3-Al, the total activity of Tritium was revised for the third and fourth quarter because of a transcription error.
- 5)
In Tables 2.3-Al and 2.3-A3, the particulates in 3 rd quarter were revised because activity for Sc-46 was not included.
Beginning with this report (2012), doses are reported with and without dose from C-14.
To determine compliance with 10 CFR 50, Appendix I (Reference 7), the maximum individual whole body and organ doses include all applicable external pathways (i.e., plume and ground exposure) as well as the internal pathways (inhalation and ingestion).
1.2.2 Liquid Effluents OpenEMS performs calculations for the following pathways: fish, shellfish, shoreline activity, swimming, and boating.
Doses are calculated for the whole body, skin, thyroid, and maximum organ (GI, bone, liver, kidney, and lung).
1.2.3 Analysis of Results There are two general changes in doses from airborne effluents shown in Table 1-1 compared to doses given in prior years. This year, for the first time, the increment in dose due to C-14 is shown. This was done because of the significance of the dose from C-14. The second change is a significant reduction in airborne dose compared to previous years. This reduction is due to using more accurate meteorological parameters for elevated releases from the Millstone 0
Stack. In prior years, doses due to releases from the Millstone Stack were calculated using rooftop meteorology which gave conservatively higher doses.
Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. The data indicates that the total whole body and organ doses to the maximum offsite individual from Millstone Power Station including all sources of the fuel cycle are well within the limits of 40 CFR 190 (Reference 8). On-site radioactive waste and spent fuel storage during this year was within storage criteria and the maximum dose to a member of the public was approximately 0.18 mrem/yr. The doses from airborne and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40 CFR 190.
The Offsite Dose Comparison, Table 1-4, provides a perspective on the maximum offsite individual dose received from Millstone Power Station with the natural background radiation dose received by the average Connecticut resident. The total dose to the maximum individual received from Millstone Power Station is small (< 0.1%) in comparison to the dose received from natural background radiation.
7
Table 1-3 2012 Off-Site Dose Comparison to Limits Millstone Units 1, 2, 3 Airborne Effluents Dose (without C-14)
Whole Body (mrem)
Thyroid (mrem)
Max Organ*
(mrem)
Skin (mrem)
Beta Air (mrad)
Gamma Air (mrad)
Unit 1 5.31E-05 5.31E-05 5.31 E-05 4.08E-05 O.0OE+00 O.OOE+00 Unit 2 3.14E-03 1.20E-02 3.15E-03 2.09E-03 8.72E-05 4.18E-05 Unit 3 1.24E-02 1.24E-02 1.67E-02 7.69E-03 1.85E-05 1.92E-06 Millstone Station 1.56E-02 2.44E-02 1.99E-02 9.81E-03 1.06E-04 4.38E-05 Airborne Effluents Dose (with C-14)
Whole Body Thyroid Max Organ*
Skin Beta Air Gamma Air (mrem)
(mrem)
(mrem)
(mrem)
(mrad)
(mrad)
Unit 1 5.31 E-05 5.31 E-05 5.31 E-05 4.08E-05 O.OOE+00 O.OOE+00 Unit 2 5.34E-02 6.24E-02 2.52E-01 2.09E-03 8.72E-05 4.18E-05 Unit 3 1.36E-02 1.36E-02 1.67E-02 7.69E-03 1.85E-05 1.92E-06 Millstone Station 6.71E-02 7.60E-02 2.69E-01 9.81E-03 1.06E-04 4.38E-05 IOCFR5 App I Liit
,5 15 15 15 20 10 Liquid Effluents Dose Whole Body (mrem)
Thyroid (mrem)
Max Organ*
(mrem)
Unit I 1.66E-05 3.69E-06 5.13E-05 Unit 2 1.28E-03 2.47E-04 1.72E-02 Unit 3 9.10E-04 5.64E-04 3.23E-03 Millstone Station 2.21E-03 8.14E-04 2.04E-02 Total Off-Site Dose from Millstone Station Whole Body Thyroid Max Organ *
(mrem)
(mrem)
(Orem)
Airborne without C-14 1.56E-02 2.44E-02 1.99E-02 Airborne with C-14 6.71 E-02 7.60E-02 2.69E-01 Liquid 2.21E-03 8.14E-04 2.04E-02 Direct Shine 1.80E-01 1.80E-01 1.80E-01 Total without C-14 1.98E-01 2.05E-01 2.20E-01 Total with C-14 2.49E-01 2.57E-01 4.70E-01 40-9
-iit
-5752 C)
C" 0
- Maximum of the follow ing organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung Direct shine is radiation exposure from onsite storage of radw aste and spent fuel 10
Table 2.2-Al Millstone Unit 2 Airborne Effluents-Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases I.-
C-02 C. Particulates
- 1.
Total Activity Released
- 2.
Average Period Release Rate D. Gross Alpha Release E. Tritium
- 1. Total Activity Released
- 2. Average Period Release Rate F. C-14
- 1. Total Activity Released*
- 2. Average Period Release Rate
%" denotes less than Mnirnum Detectable Activity (MDA)
- Calculated value per "Estimation of Carbon-14 in Nuclear Pbwer Plant Gaseous Effluents" EFPRI Final Report, 12/2010.
17
Table 2.2-A4 Millstone Unit 2 Airborne Effluents -Elevated Batch Containment Vents and Purges, Waste Gas Decay Tanks Discharges Release Point - Millstone Site Stack Nuclides Released I Units I 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases Ar-41 Ci 4.51E-02 4.84E-02 4.29E-02 2.14E-02 1.58E-01 Kr-85 Ci 2.86E-O1 6.01E-02 2.82E-02 3.47E-01 7.21E-01 Kr-85m Ci 8.53E-06
-8.53E.6 3U--131m Ci 6.20E-04 1.64E-04
-7.84E.4 Xe-133 Ci 1.19E-01 6.19E-02 3.64E-02 2.92E-03 2.20E-01 Xe-133m Ci 1.38E-03 4.49E-05 1.42E-03 Xe-135 Ci 4.82E-03 1.38E-03 1.31E-03 2.46E-04 7.76E-03 Other y Ermitters Ci
-a-Total Activity Ci 4.57E-01 1.72E-01 1.09E-01 3.72E-01 1.11E+00 B. lodinesl Halogens 1-131 Ci
-a-1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates ly Emitters I
-i I
Total Activity Ci I
I D. Gross Alpha
[Gross Alpha I CiI na I
na na na na E. Tritium
[H-3 I ciI 2.46E-01 3.60E-01-I 1.43E-01 1.42E-02 I
7.63E-0 03 (N
"-" denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 20
Table 2.3-Al Millstone Unit 3 Airborne Effluents-Release Summary Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases O3 0-D. Gross Alpha 1.Released E. Tritium
- 1. Total Activity Released
- 2. Average Period Release Rate O2 C-F. C-14
- 1. Total Activity Ci 3.10E+00 3.10E+00 3.10E+00 3.10E+00 1.24E+01 Released-
- 2.
Average Period uCi/sec 3.99E-01 3.94E-01 3.90E-01 3.90E-01 3.93E-01 Release Rate
%" denotes less than Minimum Detectable Activity (MDA)
-Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010.
24
Table 2.3-A3 Millstone Unit 3 Airborne Effluents-Ground Continuous ESF Building Ventilation, Reactor Water Storage Tank (RWST)
Release Point - ESF Building Vent, RWST Vent Nuclides Released IUnits I1st tr 2nd Qtr 3rd Qtr 4th Qtr Total A. Fission & Activation Gases i
EmittersI I
I Total Activity I U I
I B. lodines/ Halogens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates Sc-46 Ci 5.63E-08
-5.63E-08 Cr-51 Ci 5.27E-12 1.18E-12 5.90E-13 2.56E-13 7.30E-12 Mn-54 Ci 2.45E-12 9.90E-13 1.22E-12 1.29E-12 5.95E-12 Fe-59 Ci 1.60E-12 4.60E-13 3.30E-13 2.14E-13 2.60E-12 Co-58 Ci 2.52E-11 8.50E-12 7.90E-12 6.1OE-12 4.77E-11 Co-60 Ci 4.18E-12 1.77E-12 2.34E-12 2.63E-12 1.09E-11 Zr-95 Ci 6.25E-13 2.06E-13 1.82E-13 1.37E-13 1.15E-12 Nb-95 Ci 4.97E-13 1.27E-13 7.90E-14 4.28E-14 7.46E-13 Sb-125 Ci 2.40E-12 1.02E-12 1.34E-12 1.48E-12 6.24E-12 Cs-134 Ci 1.46E-12 6.10E-13 8.1OE-13 8.90E-13 3.77E-12 Cs-137 Ci 1.72E-12 7.50E-13 1.00E-12 1.15E-12 4.62E-12 Other y Emitters Ci Total Activity Ci 4.54E-11 1.56E-11 5.63E-08 1.42E-1 I D. Gross Alpha IGrossAlpha I Ci II I
I E. Tritium H-3 I CiI 1.24E-04 I
7.50E-05 1.01 E-04 I
9.90E-05 3.9 9-I 0(N C
C 0(N C
0I
"-" denotes less than Minimum Detectable Activity (MDA) 26