ML13161A201

Annual Radioactive Effluent Release Report for 2012

ML13161A201
Person / Time
Site:	Byron
Issue date:	04/26/2013
From:	Exelon Nuclear, Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML13161A201 (88)

Text

BYRON NUCLEAR POWER STATION ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT (ARERR) 2012 Page 1 of 79

BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT January 2012 - December 2012 Supplemental Information

1.

Regulatory Limits

a.

Fission and activation products:

Tech Spec Whole Body

=

500 mrem/year Skin

=

3000 mrem/year 10CFR50 Gamma

=

5 mrad/quarter; 10 mrad/year Beta =

10 mrad/quarter; 20 mrad/year

b.

Iodine: (summed with particulate, see below)

c.

Particulates with half-lives > 8 days:

Tech Spec Organ

=

1500 mrem/year 10CFR50 Organ

=

7.5 mrem/quarter; 15 mrem/year

d.

Liquid Effluents:

10CFR50 Whole Body =

1.5 mrem/quarter; 3 mrem/year Organ

=

5 mrem/quarter; 10 mrem/year

2.

Maximum Permissible Concentration

a.

Fission and Activation Products: 10CFR20 Appendix B Table 2

b.

Iodine: 10CFR20 Appendix B Table 2

c.

Particulates: 1 OCFR20 Appendix B Table 2

d.

Liquid Effluents: 10 X 10CFR20 Appendix B Table 2

3.

Average Energy: This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.

4.

Measurements and Approximations of Total Radioactivity

a.

Fission and activation products: Prior to release, the isotopic content is determined.

Released activity is calculated using volume of release, which is determined by the change in tank or containment pressure. Additional methods of calculation utilize historical data and assign an isotopic mix, which is representative of normal vent stack isotopics.

b.

Particulate, tritium and iodine sampling media for the plant vent stacks are collected and isotopically analyzed weekly.

c.

Liquid effluents: Isotopic analysis is performed on each batch release prior to its release.

Total release activity is calculated using volume of release. Total tritium activity released is calculated from the highest of a monthly circulating water blowdown composite activity or a sum of the input composite activities.

Page 2 of 79

d.

Analysis results that are less than the lower limit of detection (<LLD) are reported in units of uCi/cc or uCi/ml unless otherwise noted. All LLD values are listed in Attachment A.

5.

Batch Releases:

a.

Liquid:

1.

Number of batch releases = 87

2.

Total time period for batch releases = 15,141 minutes

3.

Maximum time period for a batch release = 555 minutes

4.

Average time period for a batch release = 174 minutes

5.

Minimum time period for a batch release = 22 minutes

6.

Average stream flow during periods of release of effluent into a flowing stream = 102 m3/sec, based on information from the U.S. Geological Survey Byron Gauging Station.

b.

Gaseous:

1.

Number of batch releases = 345

2.

Total time period for batch releases = 38,478 minutes

3.

Maximum time period for a batch release = 4,936 minutes

4.

Average time period for batch releases = 112 minutes

5.

Minimum time period for a batch release = 10 minutes

6.

Abnormal Releases:

a.

Liquid - None

b.

Gaseous - One (Unit 2,1/30/12 10:01 - 1/31/12 05:29)

7.

There were two Off Site Dose Calculation Manual (ODCM) revisions made in 2012.

ODCM Revision 8 was issued on 6/15/12. The revision incorporated several changes. A statement was added to the Auxiliary Building Vent Effluent monitors section that allows the variation of allocation percentages between the two vent stack noble gas radiation monitors not to exceed a total of 90% of the maximum permissible release rate. To align with current release procedures, a statement was added to the Containment Purge Effluent Monitors section that uses a higher multiplier to calculate containment purge rad monitor setpoints when the containment atmosphere rad monitor is not operational to prevent a spurious alarm based on a grab sample that may not be as representative of the containment atmosphere as monitored by the containment purge rad monitor during non-release periods. The Rated Thermal Power (RTP) definition was updated to reflect a power uprate that was performed in 2012, increasing the RTP from 3586.6 megawatts thermal (MWT) to 3645 MWT for each unit. A large number of administrative changes were made, including the change from thermoluminescent (TLD) dosimeter to "dosimeter" as a result of a recent dosimeter type change, the addition of Carbon-14 (C-14) to tritium (H-3) in the notes of several dose factor tables that describe the units of these isotopes as different from others, a typo in a Global Positioning Satellite (GPS) coordinate location for an air sample station, change of Radiological Effluent Controls (RECS) references to Radiological Effluents (RE) for consistency with the existing TRM, addition of month/year of revision to the document, removal of isopleths from the Annual Radiological Environmental Operating Report (AREOR), and other administrative changes including typos, figure/table titles, incorrect references, and the change of section numbers, table numbers, and page numbers.

ODCM Revision 9 was issued on 10/24/12. The revision incorporated several changes. The reference to Onsite Meteorological Programs was updated from NRC Regulatory Guide 1.23 Page 3 of 79

Revision 0 to Revision 1. The revision was prompted by identification that dew point sensors were being calibrated to the Reg Guide 1.23 Rev 1 standard instead of the Reg Guide 1.23 Rev 0 standard that Byron was committed to in the Updated Final Safety Analysis Report (UFSAR). Since dew point is not used in any off site dose calculations, the change did not impact any calculations or the ability to maintain REMP program requirements. REMP indicator milk sample location BY-30-1 went out of business and was removed from the ODCM. A replacement that meets the distance requirements specified in TRM Table T3.12.a-1 was not found. The change did not impact any off site dose calculations or the ability to maintain REMP program requirements. Administrative changes were made to the REMP sample location map due to discovery of existing errors that still showed old milk sample locations.

8.

2012 Radiological Groundwater Protection Program (RGPP) Results Summary:

In 2012, fifteen (15) Radiological Groundwater Protection Program (RGPP) monitoring wells were sampled. The samples were obtained in March, May, August, and October and analyzed for tritium.

In addition, a study of gamma, beta, and alpha radioisotopes was performed in accordance with Nuclear Energy Institute (NEI) 07-07, Groundwater Protection Initiative, for the samples obtained in May. None of the May samples showed concentrations of radionuclides above what is considered background levels. Three wells contained levels of tritium above the lower limit of detection (LLD) of 200 pCi/L. They were: AR-4 (861 pCi/L in March, 802 pCi/L in May, 872 pCi/L in August, 830 pCi/L in October), AR-7 (234 pCi/L in January), and AR-11 (1,100 pCi/L in March, 1,110 pCi/L in May, 1,210 pCi/L in August, 994 pCi/L in November). Wells AR-4 and AR-11 are near the Circulating Water Blowdown piping, where historical leakage through vacuum breakers was known to have occurred. Both of these wells are showing a slow but gradual decrease in tritium concentration since first sampled in 2006. In May 2012, the area around well AR-7, located just west of the plant structures, was excavated and re-packed with clay-based soil. This well had detected tritium just above the LLD (234 - 291 pCi/L) in 2011/2012 that was believed to have originated from precipitation recapture of permitted gaseous releases of tritium from the plant that had entered the well during rainfall events as a result of improperly compacted soil around the well during original installation.

Tritium has not been detected in this well above the 200 pCi/L LLD since January 2012. The off site dose consequence from tritium present in wells AR-4 and AR-1 1 is negligible.

Page 4 of 79

SUMMARY

Calculations based on gaseous and liquid effluents and meteorological data indicate that public dose due to radioactive material attributable to Byron Station during the period does not exceed any regulatory or Offsite Dose Calculation Manual (ODCM) limits.

The Total Effective Dose Equivalent (TEDE) due to licensed activities at Byron Station calculated for the maximum exposed individual for the period is 2.75E-01 mrem. The annual limit on TEDE is 100 mrem.

The assessment of radiation doses to the public is performed in accordance with the ODCM.

The results of these analyses confirm that the station is operating in compliance with 10CFR50 Appendix I, 10CFR20 and 40CFR190.

There were no additional operational controls implemented in 2012 that affected radiological effluents.

There were no measurements which exceeded the reporting levels, including any that would not have been attributable to station effluents.

The results of the current radiological environmental monitoring program are approximately the same as those found during the pre-operational studies conducted at Byron Station.

RELEASES Gaseous Effluents to the Atmosphere A total of 1.98E+02 curies of fission and activation gases were released with a maximum average quarterly release rate of 2.51 E+01 pCi/sec.

A total of 1.37E-05 curies of 1-131 were released during the year with a maximum average quarterly release rate of 1.59E-06 pCi/sec.

A total of 1.13E-06 curies were released as airborne particulate matter with a maximum average quarterly release rate of 1.43E-07 pCi/sec.

A total of 8.47E+00 curies of other (C-14) radioisotopes were released with a maximum average quarterly release rate of 2.89E-01 pCi/sec.

A total of 5.56E+01 curies of tritium were released with a maximum average quarterly release rate of 2.20E+00 pCi/sec.

Gross alpha-emitting radionuclides were below detectable limits.

Liquids Released to Rock River A total of 2.60E+10 liters of radioactive liquid wastes containing 1.79E-02 curies of fission and activation products were discharged with a maximum quarterly average concentration of 1.95E-09 pCi/ml.

Page 5 of 79

A total of 2.68E+03 curies of tritium were discharged with a maximum quarterly average concentration of 3.34E-04 uCi/ml.

A total of 3.06E-03 curies of dissolved and entrained gases were discharged with a maximum quarterly average concentration of 6.88E-1 0 uCi/ml.

Gross alpha-emitting radionuclides were below detectable limits.

DOSE TO MAN GASEOUS EFFLUENT PATHWAYS Noble Gas - Gamma Dose Rates Offsite Gamma air and whole body dose rates for the period were calculated based on measured release rates, isotopic composition of the noble gases, and average meteorological data. The maximum gamma air dose was 1.83E-03 mrad based on measured effluents and average meteorological data, and 4.42E-04 mrad based on measured effluents and concurrent meteorological data.

Noble Gas - Beta Air and Skin Dose Rates The range of beta particles in air is relatively small (on the order of a few meters or less).

Consequently, plumes of gaseous effluents may be considered "semi-infinite" for the purpose of calculating the dose from beta radiation incident on the skin. However, the actual dose to sensitive skin tissues is difficult to calculate due to the effect of the beta particle energies, thickness of inert skin, and clothing covering sensitive tissues. For purposes of this report the skin is taken to have a thickness of 7.0 mg/cm 2 and an occupancy factor of 1.0 is used. The skin dose was 2.21 E-04 mrem based on measured effluents and average meteorological data, and 1.66E-03 mrem based on measured effluents and concurrent meteorological data.

The maximum offsite beta air dose for the year based on measured effluents and average meteorological data was 3.14E-03 mrad, and 3.08E-03 mrad based on measured effluents and concurrent meteorological data.

Radioactive Iodine & Particulate The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine.

1-131 released during routine operation of the station may be made available to man resulting in dose to the thyroid. C-14 is also included in this category. 0-14 exhibits a capacity to concentrate in bone. 0-14 is released in gaseous form and is absorbed into vegetation through photosynthesis. The principal pathways of interest for 0-14 are the consumption of vegetation by humans and milk from which animals have ingested 0-14 through the consumption of vegetation. With the requirement to begin reporting 0-14 dose in 2011 and the addition of C-14 to plant effluents, human dose in this category is primarily driven by the release of 0-14 from the plant.

The hypothetical dose to the maximum exposed individual living near the station via ingestion of milk and vegetation was calculated. The source of milk and vegetation was assumed to be at the nearest site boundary with the cows pastured and vegetation grown Page 6 of 79

from May through October. The maximum organ dose from radioactive iodine and particulate (including C-14) to any organ was 6.90E-01 mrem (child/bone) based on measured effluents and average meteorological data, and 8.63E-01 mrem (child/bone) based on measured effluents and concurrent meteorological data. The maximum dose from radioactive iodine and particulate (including C-14) to the whole body was 1.41 E-01 mrem (child) based on measured effluents and average meteorological data, and 1.77E-01 mrem (child) based on measured effluents and concurrent meteorological data.

Gaseous Total Dose The maximum total dose from gaseous releases to any organ was 6.90E-01 mrem (child/bone) based on measured effluents and average meteorological data, and 8.63E-01 mrem (child/bone) based on measured effluents and concurrent meteorological data. The maximum total dose from gaseous releases to the whole body was 1.41 E-01 mrem (child) based on measured effluents and average meteorological data, and 1.77E-01 mrem (child) based on measured effluents and concurrent meteorological data.

LIQUID EFFLUENT PATHWAYS The principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water and eating aquatic foods. Liquid dose was calculated based on the ingestion of potable water and sport fish. It should be noted, however, there are currently no communities within 10 km downstream of the plant using the Rock River for drinking water. NRC-developed equations are used to calculate the doses to the whole body, bone, liver, thyroid, kidney, lung, lower GI tract, and skin. Specific parameters for use in the equations are given in the Exelon Offsite Dose Calculation Manual (ODCM).

The maximum dose from liquid releases to any organ was 2.75E-01 mrem (adult/gilli). The maximum dose from liquid releases to the whole body was 1.61 E-01 mrem (adult).

GASEOUS + LIQUID TOTAL DOSE The maximum total dose to any organ via both gaseous and liquid effluents is 7.1OE-01 mrem (child/bone). The maximum dose to the whole body via both gaseous and liquid effluents is 2.75E-01 mrem (child).

Dose Limits to Members of the Public Byron Station did not exceed any of the dose limits as shown below based on concurrent or historical meteorological data.

0 The RETS limits on dose or dose commitment to a member of the public due to radioactive materials in liquid effluents from each reactor is 1.5 mrem to the whole body or 5 mrem to any organ during any calendar quarter and 3 mrem to the whole body or 10 mrem to any organ during a calendar year.

• The RETS limits on air dose due to noble gases released in gaseous effluents to a member of the public from each reactor is 5 mrad for gamma radiation or 10 mrad for beta radiation during any calendar quarter and 10 mrad for gamma radiation or 20 mrad for beta radiation during a calendar year.

Page 7 of 79

9 The RETS limits on dose to a member of the public due to radioactive iodine & particulate with half-lives greater than eight days in gaseous effluents released from each reactor is 7.5 mrem to any organ during any calendar quarter and 15 mrem to any organ during a calendar year.

0 The 10CFR20 limit on Total Effective Dose Equivalent to individual members of the public is 100 mrem.

SITE METEOROLOGY Detailed records of the site meteorological measurements taken during each calendar quarter of the year are maintained by the meteorological vendor, retained on site, and are available upon request. The data are presented as cumulative joint frequency distributions of the wind direction for the 250' level and wind speed class by atmospheric stability class determined from the temperature difference between the 250' and 30' levels. Data recovery for all measurements on the meteorological tower was 99.7% during 2012.

Page 8 of 79

SOLID RADIOACTIVE WASTE FOR BURIAL 1ST QUARTER 2012 DISPOSITION OF MATERIAL MODE OF DESTINATION VOLUME (M3)

CURIES*

DATE (DESCRIPTION, CLASS, TYPE AND TRANSPORT PER PER SOLIDIFYING AGENT)

SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 1/18/12 (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE RWS12-001 GENERAL DESIGN PACKAGE (GDP), CASK (1),

Clive, UT 4.53E+00 4.87E+00 NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 1/19/12 LIMITED QUANTITY OF MATERIAL, 7, UN2910 EXCLUSIVE-USE RWS12-002 FISSILE EXCEPTED, CLASS A, GENERAL DESIGN Kingston, TN 1.49E+01 2.91 E-02 PACKAGE (GDP), 20' METAL BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 1/20/12 (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE RWS12-003 GENERAL DESIGN PACKAGE (GDP), 20' METAL Oak Ridge, TN 2.18E+01 2.78E-02 BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 2/28/12 (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE RWS12-004 GENERAL DESIGN PACKAGE (GDP), 20' METAL Oak Ridge, TN 7.16E+01 1.34E-02 BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 3/20/12 (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE RWS12-005 GENERAL DESIGN PACKAGE (GDP), CASK (1),

Clive, UT 4.53E+00 4.66E+00 NONE Number of Quarterly Totals Shipments:

5 1.17E+02 9.60E+00

• Calculated using measured ratios CUBIC M CURIES Page 9 of 79

SOLID RADIOACTIVE WASTE FOR BURIAL 2 ND QUARTER 2012 DISPOSITION OF MATERIAL VOLUME CURIES*

DATE (DESCRIPTION, CLASS, TYPE MODET OF DESTINATION (M3) PER PER AND SOLIDIFYING AGENT)

TRANSPORT SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC 4/18/12 ACV RWS12-006 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 3.40E+01 2.55E-01 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX (1), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 5/23/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 1.89E+00 8.60E-03 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX (1), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 6/6 12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Clive, UT 4.67E+00 3.94E+00 RWS12-008 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), CASK(l), NONE RADIOACTIVE MATERIAL, EXCEPTED 6/12/12 PACKAGE LIMITED QUANTITY OF MATERIAL, EXCLUSIVE-USE RWS12-009 7, UN2910, FISSILE EXCEPTED, CLASS A, Kingston, TN 1.61 E+01 9.85E-03 GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 6/12/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 7.16E+01 2.16E-02 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX (2), NONE RADIOACTIVE MATERIAL, EXCEPTED 6/28/12 PACKAGE LIMITED QUANTITY OF MATERIAL, EXCLUSIVE-USE RWS12-011 7, UN291 0, FISSILE EXCEPTED, CLASS A, Kingston, TN 1.61 E+01 1.10E-02 GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE RADIOACTIVE MATERIAL, EXCEPTED 6/28/12 PACKAGE LIMITED QUANTITY OF MATERIAL, EXCLUSIVE-USE RWS12-012 7, UN2910, FISSILE EXCEPTED, CLASS A, Kingston, TN 1.61E+01 1.08E-02 GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE RADIOACTIVE MATERIAL, EXCEPTED 6/28/12 PACKAGE LIMITED QUANTITY OF MATERIAL, EXCLUSIVE-USE RWS12-013 7, UN2910, FISSILE EXCEPTED, CLASS A, Kingston, TN 1.61E+01 1.10E-02 GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE Number of Quarterly Totals Shipments:

8 1.77E+02 4.27E+00

• Calculated using measured ratios CUBIC M CURIES Page 10 of 79

SOLID RADIOACTIVE WASTE FOR BURIAL 3" QUARTER 2012 DATE DISPOSITION OF MATERIAL MODE OF VOLUME (M3)

CURIES' PER Shipment #

(DESCRIPTION, CLASS, TYPE AND TRANSPORT DESTINATION PER SOLIDIFYING AGENT)

SHIPMENT SHIPMENT 7/24/12 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, 7, RWS12-014 UN2916, FISSILE EXCEPTED, CLASS B, CASK(l),

EXCLUSIVE-USE Andrews, TX 2.58E+00 1.61E+02 NONE 7/31/12 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, 7, R 15 UN2916, FISSILE EXCEPTED, CLASS B, CASK(l),

EXCLUSIVE-USE Andrews, TX 2.58E+00 2.10E+02 RWS 12-0 NONE 8/07/12 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, 7, RWS712 UN2916, FISSILE EXCEPTED, CLASS B, CASK(l),

EXCLUSIVE-USE Andrews, TX 2.58E+00 1.11E+02 RWS12-016 NONE 8/14/12 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, 7, RWS12-017 UN2916, FISSILE EXCEPTED, CLASS B, CASK(l),

EXCLUSIVE-USE Andrews, TX 2.69E+00 5.66E+O1 NONE 8/15/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RWS12-018 (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 7.16E+01 1.09E-02 PACKAGE (GDP), 20' METAL BOX (2), NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 8/15/12 LIMITED QUANTITY OF MATERIAL, 7, UN2910, FISSILE EXCLUSIVE-USE Kingston, TN 1.61E+01 8.62E-03 RWS12-019 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 8/15/12 LIMITED QUANTITY OF MATERIAL, 7, UN2910, FISSILE EXCLUSIVE-USE Kingston, TN 1.61 E+01 8.32E-03 RWS12-020 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE 8/20/12 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, 7, RWS12-021 UN2916, FISSILE EXCEPTED, CLASS B, CASK(l),

EXCLUSIVE-USE Andrews, TX 2.58E+00 8.2gE+01 NONE 8/23/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RWS12-022 (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 5.37E+01 5.59E-03 PACKAGE (GDP), 20' METAL BOX (2), NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 8/23/12 LIMITED QUANTITY OF MATERIAL, 7, UN2910, FISSILE EXCLUSIVE-USE Kingston, TN 1.45E+01 8.46E-03 RWS12-023 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(6), NONE 8/23/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RW (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 5.44E+01 6.25E-03 RWS12-024 PACKAGE (GDP), 20' METAL BOX (1), NONE 8/30/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RWS12-025 (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 3.04E+01 4.63E-03 PACKAGE (GDP), 20' METAL BOX (1), NONE 8/30/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RWS12-026 (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 7.16E+01 1.53E-02 PACKAGE (GDP), 20' METAL BOX (2), NONE 9/6/12 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 9/8/12 LIMITED QUANTITY OF MATERIAL, 7, UN2910, FISSILE EXCLUSIVE-USE Oak Ridge, TN 1.26E+01 4.77E-03 RWS12-027 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(1), NONE 9/28/12 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY RWS12-028 (LSA-II), 7, UN3321, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 6.62E+01 3.12E-02 PACKAGE (GDP), 20' METAL BOX (2), NONE Quarterly Totals Number of 15 4.20E+02 6,22E+02 Shipments:4.0 02 62E2

• Calculated using measured ratios CUBIC M CURIES Page 1I of 79

SOLID RADIOACTIVE WASTE FOR BURIAL 4 TH QUARTER 2012 DATE DISPOSITION OF MATERIAL MODEOF VOLUME(m 3)

CURIES*

Shipment #

(DESCRIPTION, CLASS, TYPE TRANSPORT DESTINATION PER PER AND SOLIDIFYING AGENT)

SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC 10/7/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE RWS12-030 EXCEPTED, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Oak Ridge, TN 3.47E+01 1.24E-01 PACKAGE (GDP), 20' METAL BOX(1), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 10/10/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 2.95E+01 8.33E+00 RWS12-029 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(1), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 11/27/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 5.37E+01 4.32E-03 RWS12-031 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 11/28/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 7.16E+01 1.44E-02 RWS12-032 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 11/28/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 7.16E+01 1.19E-02 RWS12-033 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20' METAL BOX(2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 12/18/12 ACTIVITY (LSA-II), 7, UN3321, FISSILE RW/18/12-3 EXCETE

CLSASS1, A, GENERAL DESSIGN EXCLUSIVE-USE Oak Ridge, TN 4.65E+00 1.08E+01 RWS12-034 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), CASK(l), NONE Number of Quarterly Totals Shipments:

6 2.66E+02 1.93E+01 Calculated using measured ratios CUBIC M CURIES Page 12 of 79

SOUD RADIOACTIVE WASTE FOR BURIAL Estimated Solid Waste Composition 2012 Resins, Filters, Evap Bottoms 2012 Drv Active Waste Volume (m3) 9.20E+00 Class A

Nuclide

% Abund Curies uCi/ml H-3 38.380 3.38E+00 3.67E-01 C-14 0.081 7.11E-03 7.73E-04 Mn-54 0.267 2.35E-02 2.55E-03 Fe-55 11.149 9.81E-01 1.07E-01 Co-57 0.196 1.73E-02 1.88E-03 Co-58 27.186 2.39E+00 2.60E-01 Co-60 4.261 3.75E-01 4.08E-02 Ni-59 0.247 2.17E-02 2.36E-03 Ni-63 17.833 1.57E+00 1.71E-01 Zn-65 0.054 4.73E-03 5.14E-04 Nb-95 0.131 1.16E-02 1.26E-03 Sb-1 25 0.094 8.25E-03 8.97E-04 Cs-137 0.063 5.57E-03 6.05E-04 Ce-144 0.058 5.11E-03 5.55E-04 Resins, Filters, Evap Bottoms 2012 Volume (m3) 1.30E+01 Class B

Nuclide

% Abund Curies uCi/ml H-3 0.770 4.79E+00 3.68E-01 C-14 0.031 1.90E-01 1.46E-02 Mn-54 2.050 1.27E+01i 9.77E-01 Fe-55 10.623 6.60E+01 5.08E+00 Co-57 0.392 2.44E+00 1.88E-01 Co-58 5.090 3.16E+01 2.43E+00 Co-60 17.819 1.11E+02 8.54E+00 Ni-59 0.793 4.93E+00 3.79E-01 Ni-63 60.635 3.77E+02 2.90E+01 Zn-65 0.115 7.16E-01 5.51E-02 Sr-89 0.000 5.45E-04 4.19E-05 Sr-90 0.012 7.41E-02 5.70E-03 Tc-99 0.001 3.91E-03 3.01E-04 Sb-125 0.445 2.76E+00 2.12E-01 Cs-134 0.177 1.10E+00 8.46E-02 Cs-1 37 0.981 6.09E+00 4.68E-01 Ce-144 0.045 2.82E-01 2.17E-02 Pu-238 0.000 7.45E-04 5.73E-05 Pu-239 0.000 2.40E-04 1.85E-05 Pu-241 0.020 1.26E-01 9.69E-03 Am-241 0.000 3.57E-04 2.75E-05 Cm-242 0.000 6.30E-05 4.85E-06 Cm-243 0.000 1.14E-03 8.77E-05 2012 Volume (m3) 9.04E+02 Class A

Nuclide

% Abund Curies uCi/ml H-3 0.336 2.16E-03 2.39E-06 Cr-51 6.267 4.03E-02 4.46E-05 Mn-54 0.972 6.25E-03 6.91 E-06 Fe-55 46.405 2.98E-01 3.30E-04 Fe-59 0.794 5.1OE-03 5.64E-06 Co-57 0.132 8.51E-04 9.41E-07 Co-58 27.163 1.75E-01 1.94E-04 Co-60 7.003 4.50E-02 4.98E-05 Ni-63 5.155 3.31E-02 3.66E-05 Zn-65 0.202 1.30E-03 1.44E-06 Zr-95 1.904 1.22E-02 1.35E-05 Nb-95 3.006 1.93E-02 2.13E-05 Sn-113 0.115 7.41E-04 8.20E-07 Sb-125 0.321 2.06E-03 228E-06 Te-123m 0.003 1.72E-05 1.90E-08 Cs-137 0.129 8.28E-04 9.16E-07 Ce-144 0.092 5.94E-04 6.57E-07 Irradiated Components 2012 - No Shipments Volume (m3) 0 Class N/A

% Abund Curies uCi/ml Other Waste Combined Packages, Oil, Sea Lands 2012 Volume (m3) 5.32E+01 Class A

% Abund Curies uCi/ml H-3 11.799 2.81E+00 5.28E-02 C-14 0.110 2.63E-02 4.94E-04 Cr-51 3.318 7.90E-01 1.48E-02 Mn-54 1.272 3.03E-01 5.70E-03 Fe-55 31.567 7.52E+00 1.41E-01 Fe-59 0.239 5.70E-02 1.07E-03 Co-57 0.158 3.76E-02 7.07E-04 Co-58 22.362 5.33E+00 1.O0E-01 Co-60 14.714 3.50E+00 6.58E-02 Ni-59 0.053 1.27E-02 2.39E-04 Ni-63 11.165 2.66E+00 5.OOE-02 Zn-65 0.061 1.46E-02 2.74E-04 Zn-69m 0.000 1.36E-51 2.56E-53 Kr-88 0.000 1.91 E-24 3.59E-26 Sr-90 0.006 1.48E-03 2.78E-05 Zr-95 0.553 1.32E-01 2.48E-03 Nb-95 1.237 2.95E-01 5.55E-03 Mo-99 0.000 1.62E-23 3.05E-25 Tc-99 0.130 3.10E-02 5.83E-04 Ru-103 0.017 4.00E-03 7.52E-05 Ru-106 0.024 5.68E-03 1.07E-04 Ag-110m 0.009 2.09E-03 3.93E-05 Sn-113 0.136 3.25E-02 6.11E-04 Sb-124 0.001 1.45E-04 2.73E-06 Sb-125 0.693 1.65E-01 3.1OE-03 Te-123m 0.005 1.13E-03 2.12E-05 1-129 0.000 8.12E-06 1.53E-07 1-131 0.000 5.37E-10 1.01E-11 1-133 0.000 1.04E-48 1.95E-50 1-135 0.000 7.58E-56 1.42E-57 Xe-133 0.000 9.08E-15 1.71E-16 Cs-137 0.088 2.09E-02 3.93E-04 Ce-141 0.003 8.17E-04 1.54E-05 Ce-144 0.211 5.02E-02 9.44E-04 Hf-181 0.007 1.78E-03 3.35E-05 W-187 0.000 1.01E-48 1.90E-50 Pu-238 0.001 1.20E-04 2.26E-06 Pu-239 0.000 4.61E-05 8.67E-07 Pu-241 0.059 1.40E-02 2.63E-04 Am-241 0.000 3.14E-05 5.90E-07 Cm-242 0.000 4.32E-05 8.12E-07 Cm-243 0.000 2.42E-05 4.55E-07 L

I

.9.

9 t

+

4 4

4 4

+

4 4

4 4

4 4

4 4

4 4

4

.9.

4 I

[

I Page 13 of 79

Process Control Program (PCP) for Radioactive Wastes Revision 8 of RW-AA-100, Process Control Program (PCP) for Radioactive Waste, was issued in July, 2012. The revision incorporated the following changes:

" Step 4.1.8 was added to allow an Exelon Nuclear plant to store waste from another Exelon Nuclear plant provided formal NRC approval is granted for the transfer of waste. The addition of this procedural step for the transfer and storage of radioactive waste at an Exelon Nuclear plant from another Exelon Nuclear plant to the Process Control Program ensures that if the storage of water from another site is implemented, that a formal NRC review and approval process for the storage of waste from another site will address the site specific effects on the UFSAR and regulatory bases.

" Step 4.2.8 was modified to add "in the pool or loading the processed activated hardware into the Dry Cask storage system." to further clarify the storage of activated hardware. The additional wording has been added to clarify the storage of activated hardware are generic and remain consistent with the UFSAR description of the Spent fuel Pool and Dry Cask Storage Systems.

• Step 4.4.4. was added to state that, "Shipments sent for offsite storage SHALL meet the storage site's waste acceptance criteria." The addition of this procedural step for the transfer and storage of radioactive waste at an Exelon Nuclear plant from another Exelon Nuclear plant to the Process Control Program ensures that if the storage of water from another site is implemented, that a formal NRC review and approval process for the storage of waste from another site will address the site specific effects on the UFSAR and regulatory bases.

" Numerous minor wording and editorial changes were made throughout the document to correct grammatical errors and to improve document readability.

Page 14 of 79

Error Analysis The following is an estimate of the errors associated with effluent monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology.

1.

Gaseous Effluents Qme=3.33%

RM=N/A ECe=5%

Stdcse/Sm plcse=5%

gme=N/A Total error = 7.8%

2.

Liquid Effluents Qme=3.33%

RM=N/A ECe=N/A Stdcse/Sm plcse=5%

qme=2.22%

Total error = 6.4%

3.

Waste Resin Qme=1 0.0%

RM=N/A ECe=5%

Stdcse/Sm plcse=5%

qme=1.0%

Total error = 12.3%

4.

DAW, Mechanical Filters, and Contaminated Metal Qme=1 0.0%

RM=N/A ECe=N/A Stdcse/Sm plcse=5%

qme=N/A Instrument calibration error = 10%

Total error = 11.2%

Qme = the process quantity measurement error associated with the release point (e.g. flow, level measurements)

RM = error associated with the radiation monitor used in quantifying releases through the release point ECe = error associated with the collection efficiency of the sample media Stdcse = one-sigma counting error associated with the counting instrument of interest Smplcse = one-sigma counting error associated with a sample of a given geometry that is used for the release point of interest qme = sample quantity measurement error associated with the sample of interest Page 15 of 79

Miscellaneous Information A. As required by Technical Specification 5.6.2, meteorological and environmental impact information is reported in the 2012 Annual Radiological Environmental Operating Report (AREOR) or is retained on file to be provided upon request.

B. No limits were exceeded in liquid hold up tanks as stated in Technical Specification 5.5.12 or in waste gas decay tanks as stated in Technical Specification 5.5.12 during the 2012 reporting period.

C. There were no irradiated fuel shipments during the 2012 reporting period. Independent Spent Fuel Storage Installation (ISFSI) campaign began in 2010 when used fuel was removed from the Spent Fuel Pool (SFP), placed into six (6) casks, each containing 32 fuel bundles, and transferred to an outdoor storage pad. No additional casks were placed on the pad in 2011. In 2012, eight (8) additional casks were placed on the pad for a total of fourteen (14) casks. In 2010, additional dosimeters were placed at the site boundary nearest to the storage pad (in between the pad and the nearest resident) in order to measure any potential off site dose from the storage pad. Since the dosimeters were placed, data from the dosimeters, when compared to the existing environmental dosimeters, have shown no statistical difference. As a result, there is currently no offsite dose contribution from the ISFSI facility.

D. There were no REMP sample results that exceeded any technical specification limits or analytical results investigation levels during the 2012 reporting period. REMP composite surface water samples from point BY-12, Rock River downstream of the plant liquid effluent discharge, detected tritium results of 2680 pCi/L (1st Quarter) and 570 pCi/L (3 rd Quarter), against a lower detection limit of 200 pCi/L. These positive sample results can be attributed to one or more weekly samples being obtained shortly after a permitted liquid discharge, and are not unexpected. The results are well below the TRM reportable limit of 30,000 pCi/L. There are no communities using the Rock River for drinking water within 10 km downstream of the station. In May, the REMP semi-annual sediment sample from point BY-12 during June 2010, Rock River downstream of the plant liquid effluent discharge, measured a Cs-1 37 result of 196 pCi/L against a detection limit of 180 pCi/L. There was no Cs-1 37 present in any of the liquid release tanks discharged in 2012. Cs-137 can be present in local sediment/soil samples as a result of fallout from weapons testing and/or the Chernobyl and Fukushima accidents and is not attributed to Byron plant effluents.

E. There were no elevated releases during the 2012 reporting period. All planned gaseous releases were via vent stacks and are considered to be mixed mode releases.

F. There were no plant effluent radiation release monitors that exceeded inoperability time limits as stated in Technical Requirements Manual (TRM) TLCO 3.11.a, TRM TLCO 3.11.b, or Technical Specification 5.5.12.

G. There was one unplanned release of radioactivity from the site to unrestricted areas during the 2012 reporting period.

On 1/30/12 10:01, Byron Unit 2 tripped due to a loss of off site power. As designed, auxiliary feedwater (AF) was used to supply cooling to the steam generators. As a result, steam generator power operated relief valves (PORVs), were opened to relieve secondary system pressure. These valves relieve directly to atmosphere. The secondary system contains minor amounts of tritium. The secondary tritium concentration was 2.75E-05 uCi/ml as measured on 1/30/12 prior to the event. The secondary water contained no measurable gamma isotopes. The makeup source for the auxiliary feedwater pumps is clean, non-tritiated water from the condensate storage tanks (CST). Because secondary steam containing tritium at a concentration above ODCM-required limits of detection left the plant via an unmonitored release pathway, the radiological release was quantified, and an abnormal gaseous release permit was generated. The release duration was considered to be the Page 16 of 79

amount of time the aux feed system was in operation and the SG PORVs were open (1168 minutes).

The secondary tritium concentration (2.75E-05 uCi/ml) was assumed to be constant throughout the release although it would have been continuously decreasing because the makeup source was non-tritiated. An Abnormal Batch Gaseous Release Report using Byron's current off site dose calculation software (RETDAS) was prepared using 186,000 gallons as the release volume containing tritium at a concentration of 2.75E-05 uCi/ml. The permit calculated the organ dose to the maximally exposed individual as a result of this release to be 1.09E-06 mrem, which is well below the quarterly limit of 7.5 mrem and annual limit of 15 mrem.

H. Attached are offsite dose calculation reports for January through December of 2012.

Page 17 of 79

The following are the maximum annual calculated cumulative offsite doses resulting from Byron airborne releases in 2012 based on concurrent meteorological data:

Unit 1:

Dose gamma air (1) beta air (2) whole body (3) skin (4) organ (s) (child-bone)

Maximum Value 4.360 x

10-4 3.070 x 10.3 8.261 x10-2 1.650 x

10-3 4.057 x 10-'

mrad mrad mrem mrem mrem Sector Affected North-Northwest North-Northwest North-Northwest North-Northwest North-Northwest Unit 1 Compliance Status 10 CFR 50 Appendix I Yearly Objective gamma air beta air whole body skin organ 10.0 20.0 5.0 15.0 15.0 mradO.00 mradO.02 mrem mrem mrem

% of Appendix I 1.65 0.01 2.70 Unit 2:

Dose gamma air beta air (2) whole body ()

skin (4) organ (5) (child-bone)

Macimum Value 5.870 x 10-6 1.190 x 10-5 9.440 x10-2 8.470 x 10-6 4.565 x 10' mrad mrad mrem mrem mrem Sector Affected North-Northwest North-Northwest North-Northwest North-Northwest North-Northwest Unit 2 Compliance Status 10 CFR 50 Appendix I Yearly Objective

% of Appendix I gamma air beta air whole body skin organ 10.0 20.0 5.0 15.0 15.0 mrad0.00 mrad0.00 mrem mrem mrem 1.89 0.00 3.04 (1) f2)

(3)

(4)

(5)

Gamma Air Dose - GASPAR 1I, NUREG-0597 Beta Air Dose - GASPAR II, NUREG-0597 Whole Body Dose - GASPAR II, NUREG-0597 Skin Dose - GASPAR II. NUREG-0597 Inhalation and Food Pathways Dose - GASPAR II, NUREG-0597 Data recovery: 99.7%

Page 18 of 79

Attachment A, 2012 Radioactive Effluent Release Report 2012 Lower Limits of Detection (LLD's)

Gaseous Liquid Nuclide LLD (uCi/cc)

Nuclide LLD (uCVml)

H3 4.47E-08 H3 1.79E-06 Ar41 3.58E-07 Na24 3.27E-08 Cr51 3.OOE-12 Cr51 2.01E-07 Mn54 3.72E-13 Mn54 3.88E-08 Co58 3.63E-13 Fe55 5.48E-07 Fe59 1.35E-12 Co57 2.20E-08 Co60 1.23E-12 Co58 3.18E-08 Ni63 7.19E-15 Fe59 1.11E-07 Zn65 1.45E-12 Co60 5.67E-08 Br82 6.08E-13 Ni63 5.63E-07 Kr85m 1.72E-07 Zn65 5.30E-08 Kr87 3.71 E-07 Sr85 3.36E-08 Kr88 5.16E-07 Sr89 2.77E-08 Sr89 2.52E-14 Sr-90 7.68E-09 Sr-90 2.96E-15 Sr92 4.08E-08 Mo99 2.56E-13 Nb95 3.14E-08 1131 7.18E-13 Zr95 5.19E-08 Xe131m 5.79E-06 Mo99 1.82E-08 1133 5.94E-13 Ag11Om 3.87E-08 Xe133 2.50E-07 Sb122 5.02E-08 Xe133m 1.17E-06 Te123m 2.01E-08 Cs134 6.06E-13 Sb124 3.07E-08 1135 3.92E-12 Sb125 5.64E-08 Xe135 1.08E-07 Te125m 5.61 E-06 Cs137 5.86E-13 Sb126 2.70E-08 Xe138 6.46E-07 1131 3.05E-08 Ba140 1.70E-12 1132 3.58E-08 La140 2.76E-13 Te132 2.08E-08 Cel41 3.89E-13 1133 2.68E-08 Ce144 1.58E-12 Xe133 4.53E-08 Gross Alpha 4.23E-15 Cs134 4.17E-08 Xe135 2.30E-08 Cs137 3.80E-08 Bal40 9.55E-08 La140 1.45E-08 Cel 41 3.91E-08 Ce144 1.50E-07 Gross Alpha 2.67E-07 Gross Beta 2.31E-07 Page 19 of 79

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS -

BATCH MODE Unit 1 REPORT FOR 2012 Number of releases Total release time Maximum release time Average release time Minimum release time Note: Waste Gas Decay Units QTR 1 50 minutes 4.89E+03 minutes 1.73E+03 minutes 9.77E+01 minutes 2.70E+01 QTR 2 46 2. 50E+03

1. 17E+02 5.43E+01 2.60E+01 QTR 3 59

1. 98E+04

4. 94E+03

3. 36E+02

1. 60E+01 QTR 4 42 2. 37E+03 1.70E+02

5. 65E+01 1.30E+01 YEAR 197 2.96E+04

4. 94E+03

1. 50E+02

1. 30E+01 Tank releases are included with Unit 1 data EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS -

BATCH MODE Unit 2 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 Number of releases 38 38 36 Total release time minutes 3.32E+03 1.87E+03 1.93E+03 Maximum release time minutes 1.17E+03 7.OOE+01 8.80E+01 Average release time minutes 8.74E+01 4.92E+01 5.35E+01 Minimum release time minutes 1.OOE+01 1.10E+01 2.20E+01 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS -

BATCH MODE Unit 1 & Unit 2 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 Number of releases 21 14 35 Total release time minutes 5.60E+03 2.50E+03 5.94E+03 Maximum release time minutes 5.55E+02 3.65E+02 3.89E+02 Average release time minutes 2.67E+02 1.79E+02 1.70E+02 Minimum release time minutes 5.20E+01 5.40E+01 5.80E+01 Avg. dilution water flow gpm 0.OOE+00 0.OOE+00 0.OOE+00 Note: Liquid releases are divided evenly between units QTR 4 36 1.76E+03 6.90E+01

4. 88E+01

2. 10E+01 QTR 4 17

1. 10E+03 1.08E+02 6.49E+01 2.20E+01 0. OOE+00 YEAR 148 8.87E+03

1. 17E+03

6. 00E+01

1. OOE+01 YEAR 87

1. 51E+04

5. 55E+02 1.74E+02 2.20E+01

0. OOE+00 Page 20 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation

1. Total Release

2.

Avg. Release Rate Iodine-131

1. Total Release

2. Avg. Release Rate Particulates Half Life

1. Total Release

2.

Avg. Release Rate Gases Ci uCi/sec 3.89E-01 1.97E+02 4.02E-01 4.08E-02 1.97E+02 4.95E-02 2.50E+01 5.06E-02 5.13E-03 6.24E+00 Ci 6.54E-07 1.16E-07 4.73E-06 8.27E-09 5.51E-06 uCi/sec 8.32E-08 1.48E-08 5.96E-07 1.04E-09 1.74E-07

>= 8 days Ci uCi/sec (1)

(i)

(1)

(i)

(1)

(i)

(1)

(i)

(1)

(i)

Others

1. Total Release Ci 1.03E+00

2.

Avg. Release Rate uCi/sec 1.32E-01 Tritium

1. Total Release Ci 7.36E+00

2.

Avg. Release Rate uCi/sec 9.36E-01 Gross Alpha Radioactivity

1. Total Release Ci (1)

2.

Avg. Release Rate uCi/sec (1) 1.09E+00 7.91E-01 1.06E+00 3.98E+00 1.39E-01 9.95E-02 1.33E-01 1.26E-01 4.47E+00 2.05E+00 3.74E+00 1.76E+01 5.68E-01 2.58E-01 4.70E-01 5.57E-01 (1)

(i)

(1)

(I)

(1)

(i)

(1)

(1)

(1) Less than minimum detectable activity requirements of TRM Section 3.11 which meets the lower limit of detection (LLD)

Page 21 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE IC GASEOUS EFFLUENTS -

MIXED MODE RELEASES -

CONTINUOUS MODE Unit 1 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-131M Ci XE-133 Ci Totals for Period...

Ci Iodines 1-131 Ci Totals for Period...

Ci (1) 3.77E-01

3. 77E-01 6.54E-07

6. 54E-07

1. 97E+02 5.21E-02

1. 97E+02 1.16E-07

1. 16E-07 Particulates Half Life >= 8 days No Nuclide Activities Totals for Period...

Ci Others C-14 Ci (1)

(1)

(1)

(1)

(1) 2.56E-01

2. 56E-01 4.73E-06

4. 73E-06 (1)

(1)

7. 91E-01

7. 91E-01

1. 63E+00

1. 63E+00 (1)

(1)

(1)

3. 53E-02

3. 53E-02

8. 27E-09

8. 27E-09 (1)

(1 )

1. 06E+00

1. 06E+00 3.70E+00 3.70E+00 (1)

(1)

1. 97E+02 7.20E-01

1. 97E+02 5.51E-06 5. 51E-06 (1)

(1) 3.98E+00 3.98E+00

1. 50E+01

1. 50E+01 (1)

(1)

1. 03E+00

1. 03E+00 Totals for Period...

Ci Ci

1. 09E+00

1. 09E+00

4. 24E+00 4.24E+00 Tritium H-3 5.38E+00 5.38E+00 Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Totals for Period...

Ci (1)

(1)

(1)

(1)

(1) Less than minimum detectable activity requirements of TRM Section 3.11 which meets the lower limit of detection (LLD)

Page 22 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE GASEOUS EFFLUENTS -

MIXED Unit

'C MODE RELEASES -

BATCH MODE REPORT FOR 2012 Units Fission and Activation Gases QTR 1 QTR 2 QTR 3 QTR 4 YEAR AR-41 KR-85M XE-133 XE-133M XE-135 Ci Ci Ci Ci Ci

1. 59E-03 (1) 1.05E-02 1.04E-04 3.35E-05 1.22E-02 (1)

(1)

1. 16E-02 (1)

8. 95E-04 (1)

(1)

1. 25E-02 (1)

(1)

Totals for Period...

Ci Iodines

• • No Nuclide Activities Totals for Period...

Ci Particulates Half Life >= 8 days No Nuclide Activities Totals for Period...

Ci Others No Nuclide Activities Totals for Period...

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

Ci (1)

(1)

(1)

(1)

6. 29E-03

2. 04E-04 1.37E-01 5.37E-04 1. 73E-03 1.46E-01 (i)

(1)

(1)

(1)

(i)

(1)

4. 17E-01

4. 17E-01 (1)

(1)

3. 61E-03 (1) 2.53E-04 1.64E-03 (1) 5.50E-03 (I)

(1)

(i)

(1)

(1)

(1) 3.31E-02 3.31E-02 (1)

(1)

2. 31E-02 2.04E-04 1.49E-01

2. 27E-03

1. 75E-03 1.76E-01 (i)

(1)

(i)

(1)

(1)

(1) 2.66E+00

2. 66E+00 (1)

(1)

(1)

(i)

1. 98E+00

1. 98E+00 (i)

(1) 2.31E-01 2.31E-01 (1)

(1)

Gross Alpha Radioactivity

• • No Nuclide Activities **

Totals for Period...

Ci (1)

(I)

(1) Less than minimum detectable activity requirements of TRM Section 3.11 which meets the lower limit of detection (LLD)

Page 23 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2012 Fission and Activation

1. Total Release

2.

Avg. Release Rate Iodine-131

1. Total Release

2.

Avg. Release Rate Particulates Half Life

1. Total Release

2.

Avg. Release Rate Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Gases Ci uCi/sec Ci uCi/sec 3.91E-01 5.79E-02 2.86E-01 4.31E-02 7.78E-01 4.98E-02 7.36E-03 3.60E-02 5.42E-03 2.46E-02 (1)

(i)

(1)

(1)

(1)

(1) 7.92E-06 3.03E-07 8.22E-06 9.96E-07 3.82E-08 2.60E-07

>= 8 days Ci uCi/sec 1.13E-06

1. 43E-07 (1)

(1)

(1)

(1) 1.13E-06 3.56E-08 Others

1. Total Release Ci

2.

Avg. Release Rate uCi/sec Tritium

1. Total Release Ci

2.

Avg. Release Rate uCi/sec Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Release Rate uCi/sec 9.85E-01 1.14E+00 1.13E+00 1.24E+00 4.49E+00 1.25E-01 1.45E-01 1.42E-01 1.56E-01 1.42E-01 9.93E+00 8.79E+00 1.26E+01 6.60E+00 3.80E+01 1.26E+00 1.12E+00 1.59E+00 8.30E-01 1.20E+00 (1)

(i)

(1)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 24 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE IC GASEOUS EFFLUENTS -

MIXED MODE RELEASES -

CONTINUOUS MODE Unit 2 REPORT FOR 2012 Units Fission and Activation Gases XE-133 Ci QTR 1 QTR 2 QTR 3 QTR 4 YEAR Totals for Period...

Iodines 1-131 1-132 Ci Ci Ci 3.77E-01

3. 77E-01 (1)

(1)

(1) 5.21E-02 5.21E-02 (1)

(1)

(1)

Totals for Period...

Ci Particulates Half Life >= 8 days CO-58 Ci 1.13E-06 (1) 1.13E-06 (1)

Totals for Period...

Others C-14 Totals for Period...

Ci Ci Ci Ci

2. 56E-01 2.56E-01

7. 92E-06 1.13E-04 1.21E-04 (1)

(1)

1. 13E+00

1. 13E+00 1.26E+01 1.26E+01 (1)

(1) 3.53E-02

3. 53E-02

3. 03E-07 (1)

3. 03E-07 (1)

(1 )

1.24E+00 1.24E+00

6. 49E+00

6. 49E+00 (1)

(1) 7.20E-01 7.20E-01

8. 22E-06 1.13E-04 1.21E-04 1.13E-06 1.13E-06

4. 49E+00 4.49E+00 3. 76E+01 3.76E+01 (1)

(1)

Tritium H-3

9. 85E-01

9. 85E-01

9. 86E+00

9. 86E+00 (1)

(1)

1. 14E+00

1. 14E+00

8. 73E+00

8. 73E+00 (1)

(1)

Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Totals for Period...

Ci (1) Less than minimum detectable activity requirements of TRM Section 3.11 which meets the lower limit of detection (LLD)

Page 25 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE GASEOUS EFFLUENTS -

MIXED Unit IC MODE RELEASES -

BATCH MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 XE-133 XE-133M XE-135 Ci Ci Ci Ci 2. 46E-03 1.15E-02

1. 03E-04 3.34E-05 1.41E-02 2. 65E-03

1. 63E-03 1.49E-03 (1) 5.77E-03 Totals for Period...

Ci Iodines No Nuclide Activities Totals for Period...

Ci (1)

(1)

(1)

(1)

Particulates Half Life >= 8 days No Nuclide Activities (1

Totals for Period...

Ci

(

Others No Nuclide Activities (1)

Totals for Period...

Ci (i)

(1)

(1)

(1)

(1) 3. 93E-03 2.38E-02

5. 33E-04

1. 72E-03 3. OOE-02 8.058E-02 (1)

(8)

(1)

(1)

(1)

(1)

8. 58E-02

8. 58E-02 (1)

(i) 7.56E-03

2. 53E-04 (1)

(1) 7.81E-03 (i)

(i) 1.66E-02 3.72E-02

2. 13E-03

1. 76E-03 5.77E-02 (1)

(1)

(1)

(1)

(1)

(1)

Tritium H-3 Ci Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Totals for Period...

Ci 7.29E-02 5.81E-02 7.29E-02 5.81E-02 (1)

(1)

(1)

(1)

(1)

(1) 1.09E-01 1.09E-01 (1)

(1)

(1)

(1) 3.26E-01 3.26E-01 (1)

(1)

(1) Less than minimum detectable activity requirements of TRM Section 3.11 which meets the lower limit of detection (LLD)

Page 26 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2012 Fission and Activation

1. Total Release

2.

Avg. Diluted Conc.

Units Products Ci uCi/ml QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 5.99E-10 6.76E-10 9.74E-10 5.14E-10 6.90E-10 5.22E+02 2.16E+02 5.20E+02 7.74E+01 1.34E+03 1.67E-04 6.39E-05 1.62E-04 2.36E-05 1.03E-04 Tritium

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml 4.21E-04 9.93E-06 1.10E-03 (1) 1.35E-10 2.94E-12 3.44E-10 (1)

1. 53E-03

1. 18E-10 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

Volume of liquid waste liters 3.12E+09 3.38E+09 3.20E+09 3.27E+09 1.30E+10 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 27 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A -

Release Tank LIQUID EFFLUENTS -

SUMMATION BY RELEASE POINT Unit 1 REPORT FOR 2012 Units Fission and Activation Products

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Tritium

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 2.06E-06 3.93E-06 2.07E-06 2.53E-06 2.45E-06 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 5.11E-01 3.41E-01 3.05E-01 1.02E-01 3.25E-01 4.21E-04 9.93E-06 1.10E-03 4.64E-07 1.71E-08 7.30E-07 (i)

(1)

(1)

(1)

1. 53E-03

4. 18E-07 (1)

(1)

(1)

(i)

(1)

(i)

(i)

(i)

Volume of liquid waste liters 9.07E+05 5.82E+05 1.51E+06 6.66E+~05 3.66E+06 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 28 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Circulating Water Blowdown LIQUID EFFLUENTS -

SUMMATION BY RELEASE POINT Unit 1 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Tritium

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc.

uCi/ml Volume of liquid waste liters (1)

(i)

(1)

(1)

(1)

(i)

(1)

(i)

(1)

(i) 5.88E+01 1.76E+01 6.02E+01 9.67E+00 1.46E+02 1.88E-05 5.21E-06 1.88E-05 2.96E-06 1.13E-05 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(1)

3. 12E+09 3.38E+09 3.20E+09 3.27E+09 1.30E+10 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 29 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE LIQUID EFFLUENTS -

Unit 2B CONTINUOUS MODE 1

REPORT FOR 2012 Units Fission and Activation Products No Nuclide Activities Ci Totals for Period...

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

Ci Dissolved and Entrained Gases No Nuclide Activities Ci Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Ci Totals for Period...

Ci QTR 1 QTR 2 QTR 3 QTR 4 YEAR (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(i) 5.88E+01 1.76E+01 6.02E+01 9.67E+00 1.46E+02 5.88E+01 1.76E+01 6.02E+01 9.67E+00 1.46E+02 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(i)

(1)

(1)

(1)

(1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 30 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS BATCH MODE Unit 1 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation CO-57 CO-58 CO-60 CR-51 CS-134 FE-59 1-132 1-133 MN-54 NB-95 NI-63 SB-122 SB-124 SB-125 TE-125M ZN-65 ZR-95 Totals for Period...

Products Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

2. 09E-06 1.27E-03 3.89E-04

1. 07E-04 (1)

2. 51E-06 (1)

(1)

4. 04E-05

4. 54E-05 (1)

(1)

(1) 4.79E-06 (1)

(1) 6.07E-06

2. 26E-06 7.41E-04

5. 58E-04 (1)

(1)

4. 35E-06 (1)

(1)

3. 87E-05 2. 77E-05 5.66E-04 (1)

(1) 4.38E-05

2. 97E-04 (1) 7.92E-06

8. 87E-06 1.07E-03 1.52E-03 1.90E-04 (1)

(1) 2.31E-06

1. 36E-06 7.56E-05 1.80E-05 (1)

6. 87E-06

1. 70E-05

1. 98E-04 (1) 1.09E-05 (1)

(1)

1. 11E-03 2.15E-04 2. 69E-04

6. 1OE-06 3. OOE-05 (1)

(1)

(1)

(1)

(1)

(1) 5.82E-06

4. 50E-05 (1)

(1)

(1) 1.32E-05

4. 19E-03

2. 68E-03

5. 66E-04 6.10E-06

3. 69E-05

2. 31E-06

1. 36E-06 1.55E-04

9. 11E-05 5 66E-04

6. 87E-06 2. 29E-05

2. 92E-04

2. 97E-04

1. 09E-05

1. 40E-05 Tritium H-3 Ci Ci Ci 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 Totals for Period...

Dissolved and Entrained Gases XE-131M Ci XE-133 Ci XE-133M Ci XE-135 Ci Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Ci Totals for Period...

Ci (1) 4.21E-04 (1)

(1)

(1)

9. 93E-06 (1)

(1)

4. 92E-05 1.04E-03

1. 01E-05

3. 87E-06 (1)

(1)

(1)

(i)

4. 92E-05 1.47E-03

1. 01E-05 3.87E-06 4.21E-04 9.93E-06 1.10E-03 (1) 1.53E-03 (i)

(i)

(i)

(i)

(i)

(1)

(1)

(1)

(1)

(1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 31 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2012 Fission and Activation

1. Total Release

2.

Avg. Diluted Conc.

Units Products Ci uCi/ml QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 5.99E-'0 6.76E-10 9.74E-10 5.14E-10 6.90E-10 5.22E+02 2.16E+02 5.20E+02 7.74E+01 1.34E+03 1.67E-04 6.39E-05 1.62E-04 2.36E-05 1.03E-04 Tritium

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Volume of liquid waste liters 4.21E-04 9.93E-06 1.10E-03 (1) 1.35E-10 2.94E-12 3.44E-10 (1)

1. 53E-03

1. 18E-10 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 3.12E+09 3.38E+09 3.20E+09 3.27E+09 1.30E+10 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 32 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A -

Release Tank LIQUID EFFLUENTS -

SUMMATION BY RELEASE POINT Unit 2 REPORT FOR 2012 Units Fission and Activation Products

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Tritium

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc.

uCi/ml Volume of liquid waste liters QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 2.06E-06 3.93E-06 2.07E-06 2.53E-06 2.45E-06 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 5.11E-01 3.41E-01 3.05E-01 1.02E-01 3.25E-01 4.21E-04 9.93E-06 1.10E-03 4.64E-07 1.71E-08 7.30E-07 (i)

(1)

(1)

(i) 1.53E-03

4. 18E-07 (1)

(1)

(1)

(i)

(1)

(i)

(1)

(i) 9.07E+05 5.82E+05 1.51E+06 6.66E+05 3.66E+06 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 33 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A - Circulating Water Blowdown LIQUID EFFLUENTS -

SUMMATION BY RELEASE POINT Unit 2 REPORT FOR 2012 Fission and Activation

1. Total Release

2.

Avg. Diluted Conc.

Units Gases Ci uCi/ml QTR 1 QTR 2 QTR 3 QTR 4 YEAR (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

Tritium

1. Total Release Ci

2.

Avg. Diluted Conc.

uCi/ml Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Diluted Conc. uCi/ml Volume of liquid waste liters 5.88E+01 1.76E+01 6.02E+01 9.67E+00 1.46E+02 1.88E-05 5.21E-06 1.88E-05 2.96E-06 1.13E-05 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(1) 3.12E+09 3.38E+09 3.20E+09 3.27E+09 1.30E+10 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 34 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE LIQUID EFFLUENTS Unit REPORT FOR 2012 Units QTR 1 2B CONTINUOUS MODE 2

QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products No Nuclide Activities Ci Totals for Period...

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

Ci Dissolved and Entrained Gases No Nuclide Activities Ci Totals for Period...

Ci Gross Alpha Radioactivity No Nuclide Activities Ci Totals for Period...

Ci (1)

(1)

5. 88E+01

5. 88E+01 (1)

(1) 1.76E+01 1.76E+01 (1)

(1)

6. 02E+01

6. 02E+01 (1)

(1)

(1)

(1)

(1)

(1) 9.67E+00

9. 67E+00 (1)

(1)

(1)

(1)

(1)

(1 )

1.46E+02

1. 46E+02 (1)

(1)

(1)

(1)

(1)

(1)

(1)

(1)

(i)

(i)

(1)

(i)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 35 of 79

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS -

BATCH MODE Unit 2 REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products CO-57 Ci 2.09E-06 2.26E-06 8.87E-06 (1) 1.32E-05 CO-58 Ci 1.27E-03 7.41E-04 1.07E-03 1.lIE-03 4.19E-03 CO-60 Ci 3.89E-04 5.58E-04 1.52E-03 2.15E-04 2.68E-03 CR-51 Ci 1.07E-04 (1) 1.90E-04 2.69E-04 5.66E-04 CS-134 Ci (1)

(1)

(1) 6.10E-06 6.10E-06 FE-59 Ci 2.51E-06 4.35E-06 (1) 3.OOE-05 3.69E-05 1-132 Ci (1)

(1) 2.31E-06 (1) 2.31E-06 1-133 Ci (1)

(1) 1.36E-06 (1) 1.36E-06 MN-54 Ci 4.04E-05 3.87E-05 7.56E-05 (1) 1.55E-04 NB-95 Ci 4.54E-05 2.77E-05 1.80E-05 (1) 9.11E-05 NI-63 Ci (1) 5.66E-04 (1)

(1) 5.66E-04 SB-122 Ci (1)

(1) 6.87E-06 (1) 6.87E-06 SB-124 Ci (1)

(1) 1.70E-05 5.82E-06 2.29E-05 SB-125 Ci 4.79E-06 4.38E-05 1.98E-04 4.50E-05 2.92E-04 TE-125M Ci (1) 2.97E-04 (1)

(1) 2.97E-04 ZN-65 Ci (1)

(1) 1.09E-05 (1) 1.09E-05 ZR-95 Ci 6.07E-06 7.92E-06 (1)

(1) 1.40E-05 Totals for Period...

Ci 1.87E-03 2.29E-03 3.12E-03 1.68E-03 8.96E-03 Tritium H-3 Ci 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 Totals for Period...

Ci 4.63E+02 1.98E+02 4.60E+02 6.77E+01 1.19E+03 Dissolved and Entrained Gases XE-131M Ci (1)

(1) 4.92E-05 (1) 4.92E-05 XE-133 Ci 4.21E-04 9.93E-06 1.04E-03 (1) 1.47E-03 XE-133M Ci (1)

(1) 1.01E-05 (1) 1.01E-05 XE-135 Ci (1)

(1) 3.87E-06 (1) 3.87E-06 Totals for Period...

Ci 4.21E-04 9.93E-06 1.10E-03 (1) 1.53E-03 Gross Alpha Radioactivity No Nuclide Activities Ci (1)

(1)

(1)

(1)

(1)

Totals for Period...

Ci (1)

(1)

(1)

(1)

(1)

(1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 36 of 79

40CFRl90 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 1 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.16E-05 4.24E-02 4.22E-02 4.22E-02 4.22E-02 7.94E-02 0.OOE+00 4.25E-02 TEEN 1.17E-05 3.19E-02 3.17E-02 3.17E-02 3.17E-02 5.79E-02 0.OOE+00 3.19E-02 CHILD 1.39E-05 3.55E-02 3.53E-02 3.53E-02 3.53E-02 4.47E-02 0.OOE+00 3.56E-02 INFANT 1.54E-08 1.57E-02 1.57E-02 1.57E-02 1.57E-02 1.57E-02 0.OOE+00 1.57E-02 SITE DOSE LIMIT ANALYSIS QUARTER 1 Age Dose Limit Max % of Quarter - Limit Group Organ (mrem)

(mrem)

Limit Qtr 1 Admin.

Any Organ ADULT GILLI 7.94E-02 3.75E+00 2.12E+00 Qtr 1 Admin.

Total Body ADULT TBODY 4.25E-02 1.13E+00 3.77E+00 Qtr 1 T.Spc. Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 5.31E+01 CR-51 2.20E-02 MN-54 3.47E-01 FE-59 1.31E-02 CO-58 1.48E+00 CO-60 1.21E+00 ZR-95 1.05E-03 NB-95 4.38E+01 Qtr 1

- T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 9.94E+01 CR-51 1.63E-04 MN-54 4.04E-02 FE-59 2.82E-03 CO-58 3.07E-01 CO-60 2.65E-01 ZR-95 4.19E-07 NB-95 7.26E-03 7.94E-02 5.OOE+00 1.59E+00 4.25E-02 1.50E+00 2.83E+00 Page 37 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 2 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.94E-02 3.92E-02 3.75E-02 4.06E-02 3.73E-02 8.94E-02 0.OOE+00 3.85E-02 TEEN 2.01E-02 3.OOE-02 2.82E-02 2.80E-02 2.80E-02 6.51E-02 0.OOE+00 2.93E-02 CHILD 2.64E-02 3.31E-02 3.15E-02 3.12E-02 3.11E-02 4.46E-02 0.OOE+00 3.27E-02 INFANT 1.44E-04 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 0.OOE+00 1.38E-02 SITE DOSE LIMIT ANALYSIS QUARTER 2 Age Dose Limit Max % of Quarter - Limit Group Organ (mrem)

(mrem)

Limit Qtr 2 Admin.

Any Organ ADULT GILLI 8.94E-02 3.75E+00 2.38E+00 Qtr 2 Admin. Total Body ADULT TBODY 3.85E-02 1.13E+00 3.42E+00 Qtr 2

- T.Spc.

Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 4.17E+01 MN-54

6. 10E-01 FE-59 4.17E-02 CO-58 1.58E+00 CO-60 3.17E+00 NI-63 3.OOE-01 ZR-95 2.51E-03 NB-95 4.90E+01 TE-125M 3.58E+00 Qtr 2

- T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 9.67E+01 MN-54 8.81E-02 FE-59 1.lIE-02 CO-58 4.06E-01 CO-60 8.64E-01 NI-63 1.61E+00 ZR-95 1.24E-06 NB-95 1.01E-02 TE-125M 2.78E-01 8.94E-02 5.OOE+00 1.79E+00 3.85E-02 1.50E+00 2.57E+00 Page 38 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 3 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.24E-04 4.OOE-02 3.93E-02 3.96E-02 3.93E-02 5.74E-02 0.OOE+00 4.OOE-02 TEEN 1.13E-04 3.02E-02 2.95E-02 2.98E-02 2.95E-02 4.21E-02 0.OOE+00 3.02E-02 CHILD 1.17E-04 3.35E-02 3.29E-02 3.31E-02 3.28E-02 3.73E-02 0.00E+00 3.36E-02 INFANT 3.98E-08 1.46E-02 1.46E-02 1.46E-02 1.46E-02 1.46E-02 0.OOE+00 1.46E-02 SITE DOSE LIMIT ANALYSIS QUARTER 3 Age Dose Limit Max % of Quarter -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 3 Admin.

Any Organ Qtr 3 Admin. Total Body ADULT ADULT GILLI TBODY

5. 74E-02 4.00E-02 3. 75E+00

1. 13E+00

1. 53E+00 3. 55E+00 Qtr 3

- T.Spc.

Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage 5.74E-02 5.00E+00 1.15E+00 H-3 CR-51 MN-54 CO-58 CO-60 ZN-65 NB-95 1-132 1-133 6.85E+01 5.06E-02

8. 42E-01

1. 61E+00

6. 12E+00 4.20E-01 2.25E+01

7. 19E-06

9. 23E-05 Qtr 3

- T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors

(

0% or greater to total)

Nuclide Percentage H-3 9.82E+01 CR-51 2.89E-04 MN-54 7.52E-02 CO-58 2.56E-01 CO-60 1.03E+00 ZN-65 4.33E-01 NB-95 2.86E-03 1-132 1.92E-05 1-133 4.49E-05 4.00E-02 1.50E+00 2.67E+00 Page 39 of 79

40CFRl90 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

QUARTER 4 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 4.57E-03 4.12E-02 2.99E-02 3.34E-02 3.11E-02 3.85E-02 0.OOE+00 3.96E-02 TEEN 4.68E-03 3.39E-02 2.25E-02 2.59E-02 2.38E-02 2.84E-02 0.OOE+00 2.84E-02 CHILD 5.65E-03 3.46E-02 2.50E-02 2.79E-02 2.61E-02 2.71E-02 0.OOE+00 2.80E-02 INFANT 3.OOE-06 1.11E-02 1.11E-02 1.11E-02 1.11E-02 1.11E-02 0.OOE+00 1.1lE-02 SITE DOSE LIMIT ANALYSIS QUARTER 4 Age Dose Limit Max % of Quarter - Limit Group Organ (mrem)

(mrem)

Limit Qtr 4 Admin.

Any Organ ADULT LIVER 4.12E-02 3.75E+00 1.10E+00 Qtr 4 Admin.

Total Body ADULT TBODY 3.96E-02 1.13E+00 3.52E+00 Qtr 4 T.Spc. Any Organ ADULT LIVER Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 7.27E+01 FE-59 4.42E-01 CO-58 5.98E-01 CO-60 3.33E-01 CS-134 2.59E+01 Qtr 4

- T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 7.56E+01 CR-51 2.14E-03 FE-59 1.76E-01 CO-58 1.39E+00 CO-60 7.63E-01 CS-134 2.21E+01 4.12E-02 5.OOE+00 8.24E-01 3.96E-02 1.50E+00 2.64E+00 Page 40 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 Liquid Receptor PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)

ANNUAL 2012 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin ADULT 1.50E-02 1.62E-01 1.56E-01 1.59E-01 1.56E-01 2.75E-01 0.OOE+00 TEEN 1.56E-02 1.23E-01 1.17E-01 1.18E-01 1.17E-01 2.01E-01 0.00E+00 CHILD 2.03E-02 1.35E-01 1.30E-01 1.31E-01 1.30E-01 1.60E-01 0.00E+00 INFANT 1.01E-04 5.76E-02 5.76E-02 5.76E-02 5.76E-02 5.77E-02 0.OOE+00 SITE DOSE LIMIT ANALYSIS ANNUAL 2012 Age Dose Limit Annual - Limit Group Organ (mrem)

(mrem) 2012 Admin.

Any Organ ADULT GILLI 2.75E-01 7.50E+00 2012 Admin. Total Body ADULT TBODY 1.61E-01 2.25E+00 TB

1. 61E-01 1.21E-01 1.34E-01

5. 77E-02 Max % of Limit 3.67E+00

7. 14E+00 2012 T.Spc. Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 5.64E+01 CR-51 4.81E-02 MN-54 5.50E-01 FE-59 7.99E-02 CO-58 2.02E+00 CO-60 3.45E+00 NI-63 6.77E-02 ZN-65 1.34E-01 ZR-95 1.00E-03 NB-95 3.64E+01 TE-125M 8.08E-01 1-132 2.29E-06 1-133 2.94E-05 CS-134 2.OOE-02 2012 T.Spc. Total Body ADULT TBODY Critical Pathway: Fresh Water Fish -

Sport (FFSP)

Major Contributors (

0% or greater to total)

Nuclide Percentage 2.75E-01 1.OOE+01 2.75E+00 1.61E-01 3.OOE+00 5.35E+00 H-3 CR-51 MN-54 FE-59

9. 68E+01

3. 28E-04 5.87E-02

1. 57E-02 Page 41 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT Nuclide Percentage CO-58 3.83E-01 CO-60 6.93E-01 NI-63 2.69E-01 ZN-65 1.65E-01 ZR-95

3. 66E-07 NB-95 5.53E-03 TE-125M 4.65E-02 1-132 7.33E-06 1-133 1.71E-05 CS-134 1.61E+00 Page 42 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 I&P DOSE LIMIT ANALYSIS QUARTER 1 Age Dose Limit Max % of Quarter - Limit Group Organ (mrem)

(mrem)

Limit Qtr 1 Admin.

Any Organ Qtr 1 Admin. Total Body CHILD CHILD BONE TBODY

1. 64E-01 3.39E-02 5.63E+00

5. 25E+00 2.92E+00 6.45E-01 Qtr 1

- T.Spc.

Any Organ CHILD BONE Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 0.00E+00 C-14 1.OOE+02 CO-58 3.10E-05 1-131 7.04E-05 Qtr 1 T.Spc. Total Body CHILD TBODY Receptor: 5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage 1.64E-01 7.50E+00 2.19E+00 3.39E-02 7.50E+00 4.52E-01 H-3 C-14 CO-58 1-131

2. 88E+00 9.71E+01 2.64E-04

1. 97E-04 Page 43 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 NG DOSE LIMIT ANALYSIS QUARTER 1 Dose Limit Max % of Quarter - Limit (mrad)

(mrad)

Limit Qtr 1 Admin.

Gamma 1.81E-05 3.75E+00 4.82E-04 Qtr 1 Admin. Beta 1.18E-05 7.50E+00 1.58E-04 Qtr 1 T.Spc. Gamma Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 1.21E+01 XE-135 4.12E-02 XE-133M 2.17E-02 XE-133 8.79E+01 Qtr 1

- T.Spc. Beta Receptor:

4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage 1.81E-05 5.OOE+00 3.62E-04 1.18E-05 1.00E+01 1.18E-04 AR-41 XE-135 XE-133M XE-133

1. 60E+00 1.98E-02 3.69E-02

9. 83E+01 Page 44 of 79

40CFRI90 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 I&P DOSE LIMIT ANALYSIS QUARTER 2 Age Dose Limit Max % of Quarter -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 2 Admin.

Any Organ Qtr 2 Admin. Total Body CHILD CHILD BONE TBODY

1. 82E-01

3. 71E-02 5. 63E+00 5.25E+00 3. 23E+00 7.07E-01 Qtr 2

- T.Spc.

Any Organ CHILD BONE Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 0.00E+00 C-14 1.OOE+02 1-131 1.13E-05 Qtr 2

- T.Spc. Total Body CHILD TBODY Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors

(

0% or greater to total)

Nuclide Percentage 1.82E-01 7.50E+00 2.42E+00 3.71E-02 7.50E+00 4.95E-01 H-3 C-14 1-131

2. 02E+00

9. 80E+01 3.19E-05 Page 45 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 NG DOSE LIMIT ANALYSIS QUARTER 2 Dose Limit Max % of Quarter - Limit (mrad)

(mrad)

Limit Qtr 2 Admin.

Gamma 1.79E-03 Qtr 2 Admin. Beta 3.11E-03

3. 75E+00 7.50E+00 4.77E-02

4. 15E-02 Qtr 2

- T.Spc.

Gamma Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 4.31E-01 XE-133M 1.58E-03 XE-131M 9.94E+01 XE-133 1.22E-01 Qtr 2 T.Spc. Beta Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 2.15E-02 XE-133M 1.01E-03 XE-131M 9.99E+01 XE-133 5.13E-02 1.79E-03 5.OOE+00 3.58E-02 3.11E-03 1.OOE+01 3.11E-02 Page 46 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 I&P DOSE LIMIT ANALYSIS QUARTER 3 Age Dose Limit Max % of Quarter - Limit Group Organ (mrem)

(mrem)

Limit Qtr 3 Admin.

Any Organ CHILD BONE 1.56E-01 5.63E+00 2.78E+00 Qtr 3 Admin. Total Body CHILD TBODY 3.21E-02 5.25E+00 6.11E-01 Qtr 3 T.Spc. Any Organ CHILD BONE Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 0.OOE+00

SSE 1.56E-01 7.50E+00 2.08E+00 C-14 1-131 1-132

1. 00E+02

1. 43E-03 1.29E-05 Qtr 3

- T.Spc. Total Body CHILD TBODY Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 2.59E+00 C-14 9.74E+01 1-131 4.03E-03 1-132 6.16E-05 3.21E-02 7.50E+00 4.28E-01 Page 47 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 NG DOSE LIMIT ANALYSIS QUARTER 3 Dose Limit Max % of Quarter - Limit (mrad)

Qtr 3

- Admin.

Gamma 1.97E-05 Qtr 3

- Admin. Beta 1.07E-05 (mrad)

Limit 3.75E+00 7.50E+00 5.25E-04 1.43E-04 Qtr 3

- T.Spc.

Gamma Receptor:

4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 KR-85M XE-135 XE-133M XE-133 2.80E+01 7.39E-02

1. 95E+00 1.03E-01 6.99E+01 1.97E-05 5.OOE+00 3.94E-04 1.07E-05 1.00E+01 1.07E-04 Qtr 3 T.Spc. Beta Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 4.47E+00 KR-85M 5.36E-02 XE-135 1.13E+00 XE-133M 2.10E-01 XE-133 9.41E+01 Page 48 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 I&P DOSE LIMIT ANALYSIS QUARTER 4 Age Dose Limit Max % of Quarter -

Limit Group Organ (mrem)

(mrem)

Limit Qtr 4 Admin.

Any Organ CHILD BONE 1.87E-01 5.63E+00 3.33E+00 Qtr 4 Admin. Total Body CHILD TBODY 3.80E-02 5.25E+00 7.24E-01 Qtr 4 T.Spc. Any Organ CHILD BONE Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage 1.87E-01 7.50E+00 2.50E+00 H-3 C-14 1-131

0. 00E+00

1. OOE+02

2. 95E-05 Qtr 4

- T.Spc. Total Body CHILD TBODY Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 1.53E+00 C-14 9.85E+01 1-131 8.37E-05 3.80E-02 7.50E+00 5.07E-01 Page 49 of 79

40CFRI90 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From:

1 To: 2 NG DOSE LIMIT ANALYSIS QUARTER 4 Dose Limit Max % of Quarter - Limit (mrad)

(mrad)

Limit Qtr 4 Admin.

Gamma 7.51E-06 3.75E+00 2.OOE-04 Qtr 4 Admin. Beta 1.62E-06 7.50E+00 2.16E-05 Qtr 4

- T.Spc.

Gamma Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 8.02E+01 XE-133M 4.13E-01 XE-133 1.94E+01 Qtr 4

- T.Spc. Beta Receptor: 4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage 7.51E-06 5.00E+00 1.50E-04 1.62E-06 1.00E+01 1.62E-05 AR-41 XE-133M XE-133 3.23E+01 2. 13E+00 6.56E+01 Page 50 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 I&P DOSE LIMIT ANALYSIS ANNUAL 2012 Age Dose Limit Annual -

Limit Group Organ (mrem)

(mrem)

Max % of Limit 2012 Admiin.

Any Organ 2012 Admin. Total Body CHILD BONE CHILD TBODY 6.90E-01 1.13E+01 6.13E+00 1.41E-01 1.05E+01 1.34E+00 6.90E-01 1.50E+01 4.60E+00 2012 T.Spc. Any Organ CHILD BONE Receptor: 5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage H-3 0.OOE+00 C-14 1.OOE+02 CO-58 7.39E-06 1-131 3.53E-04 1-132 2.92E-06 2012 T.Spc. Total Body CHILD TBODY Receptor:

5 Composite Crit. Receptor -

IP Distance: 800 (meters)

Compass Point: SSE Critical Pathway: Vegetation (VEG)

Major Contributors (

0% or greater to total)

Nuclide Percentage 1.41E-01 1.50E+01 9.40E-01 H-3 C-14 CO-58 1-131 1-132 2.22E+00 9.78E+01

6. 33E-05

9. 94E-04 1.40E-05 Page 51 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 NG DOSE LIMIT ANALYSIS ANNUAL 2012 Dose Limit Annual -

Limit (mrad)

(mrad) 2012 Admin.

Gamma 1.83E-03 7.50E+00 2012 Admin. Beta 3.14E-03 1.50E+01 Max % of Limit

2. 45E-02

2. 09E-02 2012

- T.Spc.

Gamma Receptor:

4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 1.17E+00 KR-85M 7.93E-04 XE-135 2.13E-02 XE-133M 4.55E-03 XE-131M 9.70E+01 XE-133 1.82E+00 2012

- T.Spc. Beta Receptor:

4 Composite Crit. Receptor -

NG Distance: 800 (meters)

Compass Point: SSE Nuclide Percentage AR-41 5.92E-02 KR-85M 1.83E-04 XE-135 3.93E-03 XE-133M 2.96E-03 XE-131M 9.92E+01 XE-133 7.76E-01 1.83E-03 1.OOE+01 1.83E-02 3.14E-03 2.OOE+01 1.57E-02 Page 52 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT Unit 1 & 2 Report for: 2012 Unit Range -

From: 1 To: 2 MAXIMUM DOSE ANALYSIS ANNUAL 2012 Age Dose Dose Type Group Organ (mrem)

Any Organ CHILD BONE 7.10E-01 Liquid Receptor:

0 Liquid R Gaseous Receptor:

5 Composit Distance: 0.00 (meters)

{eceptor

.e Crit.

Receptor -

IP Compass Point: NA Liquid Dose:

Critical Pathway:

Major Contributors Nuclide H-3 CR-51 MN-54 FE-59 CO-58 CO-60 NI-63 ZN-65 ZR-95 NB-95 TE-125M 1-132 1-133 CS-134 Gaseous Dose:

Critical Pathway:

Major Contributors Nuclide H-3 C-14 CO-58 1-131 1-132 2.03E-02

% of Total: 2.85E+00 Fresh Water Fish -

Sport (FFSP) 0% or greater to total)

Percentage 0.OOE+00 0.OOE+00 0 OOE+00

1. 74E-01 0 OOE+00 0 OOE+00

8. 69E+01

8. 46E-01

1. 86E-05

1. 74E-01 3.85E+00

8. 24E-05

3. 60E-04

8. 09E+00 6.90E-01

% of Total: 9.72E+01 Vegetation (VEG) 0% or greater to total)

Percentage 0.OOE+00 1.00E+02 7.39E-06 3.53E-04 2.92E-06 Page 53 of 79

40CFR190 URANIUM FUEL CYCLE DOSE REPORT Unit 1 & 2 MAXIMUM DOSE ANALYSIS ANNUAL 2012 Dose Type Age Group Dose Organ (mrem)

Total Body CHILD TBODY Liquid Receptor:

0 Liquid Receptor Gaseous Receptor:

5 Composite Crit. Receptor -

IP Distance: 0.00 (meters)

Compass Point: NA

2. 75E-01 Liquid Dose:

Critical Pathway:

Major Contributors Nuclide H-3 CR-51 MN-54 FE-59 CO-58 CO-60 NI-63 ZN-65 ZR-95 NB-95 TE-125M 1-132 1-133 CS-134 Gaseous Dose:

Critical Pathway:

Major Contributors Nuclide H-3 C-14 CO-58 1-131 1-132 1.34E-01

% of Total: 4.86E+01 Fresh Water Fish -

Sport (FFSP) 0% or greater to total)

Percentage 9.73E+01 4.34E-04 7.59E-02 2.12E-02 5.04E-01 9.13E-01 4.48E-01 2.13E-01 5.51E-07 7.35E-03 7.78E-02 1.06E-05 2.55E-05 4.25E-01 1.41E-01

% of Total: 5.13E+01 Vegetation (VEG) 0% or greater to total)

Percentage 2.22E+00 9.78E+01 6.33E-05 9.94E-04 1.40E-05 Page 54 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

1 RELEASE DATA Total Release Duration (minutes)......................................

5.609E+05 Total Release Volume (cf).............................................

6.508E+10 Average Release Flowrate (cfm)........................................

1.160E+05 Average Period Flowrate (cfm) 1.235E+05

==NUCLIDE DATA--------------------------------------

Nuclide AR-41 KR-85M XE-13 IM XE-133M XE-133 XE-135 F&AG 1-131 Iodine C-14 Other H-3 H-3 Total uCi 2.31E+04 2. 04E+02

1. 97E+08 2. 27E+03

8. 69E+05 1.76E+03

1. 97E+08 5.51E+00

5. 51E+00

3. 98E+06

3. 98E+06 1.76E+07 1.76E+07 Average uCi/cc 1.25E-11 1.l1E-13 1.07E-07 1.23E-12 4.71E-10 9.53E-13 1.07E-07 2.99E-15 2.99E-15 2.16E-09 2.16E-09 9.56E-09 9.56E-09 EC Ratio

1. 25E-03

1. lE-06

5. 33E-02 2. 06E-06

9. 43E-04 1.36E-05

5. 55E-02

1. 50E-05

1. 50E-05

7. 20E-01 7.20E-01

9. 56E-02

9. 56E-02 EC

1. OOE-08

1. OOE-07 2 OOE-06 6 OOE-07

5. OOE-07

7. OOE-08

2. OOE-10 3. OOE-09

1. OOE-07 2.19E+08 1.19E-07 8.71E-01 Page 55 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

1 MAXIMUM I&P DOSE FOR PERIOD Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem)

Period (mrem) of Limit Admin Any Organ CHILD BONE 3.24E-01 31-day 2.25E-01 1.44E+02 Quarter 5.63E+00 5.76E+00 Annual 1.13E+01 2.88E+00 T. Spec Any Organ CHILD BONE 3.24E-01 31-day Quarter Annual 3. OOE-01 7.50E+00

1. 50E+01

1. 08E+02 4.32E+00 2. 16E+00 Receptor...................

5 Composite Crit. Receptor -

IP Distance (meters).........

800 Compass Point...........

SSE Critical Pathway..........

2 Vegetation (VEG)

Major Contributors......

.0.0

% or greater to total Nuclide Percentage H-3 0.OOE+00 C-14 1.OOE+02 1-131 3.01E-04 Page 56 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

1 PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

GI-Lli Skin TB Age/Path Bone Liver Thyroid Kidney Lung AGPD AINHL AVEG ACMEAT ACMILK TGPD TINHL TVEG TCMEAT TCMILK CGPD CINHL CVEG CCMEAT CCMILK IGPD IINHL ICMILK ADULT TEEN CHILD INFANT

1. 13E-08

1. 03E-03

5. 09E-02

1. 89E-02

2. 06E-02

1. 13E-08

1. 47E-03

8. 22E-02

1. 59E-02

3. 80E-02

1. 13E-08 2.04E-03 1.98E-01

3. OOE-02 9.36E-02 1.13E-08 1.50E-03 1.83E-01

9. 14E-02 1.38E-01 3.24E-01 1.85E-01

1. 13E-08 3 74E-04

1. 05E-02

3. 82E-03

4. 23E-03

1. 13E-08

4. 58E-04

1. 69E-02 3.21E-03 7.74E-03

1. 13E-08 5.42E-04

4. 03E-02 6.04E-03

1. 89E-02

1. 13E-08

3. 94E-04

3. 94E-02

1. 89E-02

2. 83E-02

6. 58E-02

3. 98E-02

1. 13E-08

3. 75E-04 1.05E-02

3. 83E-03

4. 32E-03

1. 13E-08

4. 59E-04 1.69E-02 3.22E-03

7. 89E-03

1. 13E-08 5.44E-04

4. 04E-02

6. 05E-03

1. 92E-02

1. 13E-08

3. 95E-04

4. 01E-02 1.90E-02

2. 85E-02 6.61E-02 4.05E-02 1.13E-08 3.74E-04

1. 05E-02

3. 82E-03

4. 23E-03 1.13E-08

4. 58E-04

1. 69E-02 3.21E-03 7.74E-03 1.13E-08 5.42E-04

4. 03E-02

6. 05E-03 1.89E-02 1.13E-08 3.94E-04 3.94E-02 TOTALS 1.89E-02 2. 83E-02

6. 58E-02 3. 98E-02

1. 13E-08 3.74E-04 1.05E-02

3. 82E-03

4. 23E-03 1.13E-08

4. 58E-04 1.69E-02 3.21E-03 7. 74E-03 1.13E-08 5.42E-04 4.03E-02

6. 04E-03

1. 89E-02

1. 13E-08 3.94E-04 3.94E-02 1.89E-02 2. 83E-02 6.58E-02

3. 98E-02 1.13E-08 3.74E-04 1.05E-02 3.82E-03 4.23E-03 1.13E-08

4. 58E-04 1.69E-02

3. 21E-03 7.74E-03 1.13E-08

5. 42E-04

4. 03E-02

6. 04E-03

1. 89E-02 1.13E-08 3.94E-04

3. 94E-02

1. 89E-02

2. 83E-02

6. 58E-02

3. 98E-02

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

1. 13E-08 3.74E-04

1. 05E-02

3. 82E-03

4. 23E-03

1. 13E-08

4. 58E-04

1. 69E-02 3.21E-03 7.74E-03

1. 13E-08

5. 42E-04

4. 03E-02

6. 04E-03

1. 89E-02

1. 13E-08

3. 94E-04

3. 94E-02 1.89E-02 2. 83E-02

6. 58E-02

3. 98E-02

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway AGPD AINHL AVEG ACMEAT ACMILK TGPD TINHL TVEG TCMEAT TCMILK CGPD CINHL ADULT ADULT ADULT ADULT ADULT TEEN TEEN TEEN TEEN TEEN CHILD CHILD Ground Plane Deposition (GPD)

Inhalation (INHL)

Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Page 57 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

1 AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway CVEG CCMEAT CCMILK IGPD IINHL ICMILK CHILD CHILD CHILD INFANT INFANT INFANT Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Grs/Cow/Milk (CMILK)

Page 58 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID............

Period Start Date....

Period End Date.......

Period Duration (min):

Coefficient Type......

Unit..................

1 All Gas Release Types 01/01/2012 00:00 01/01/2013 00:00 5.270E+05 Historical

==MAXIMUM NG DOSE FOR PERIOD-Limit Type Admin Dose Type Gamma Admin Beta Dose (mrad)

1. 81E-03

3. 12E-03

1. 81E-03 Limit Limit Period (mrad) 31-day 1.50E-01 Quarter 3.75E+00 Annual 7.50E+00 31-day 3.OOE-01 Quarter 7.50E+00 Annual 1.50E+01 31-day 2.OOE-01 Quarter 5.OOE+00 Annual 1.00E+01 Percent of Limit 1.21E+00 4.82E-02 2.41E-02 1.04E+00 4.17E-02 2.08E-02 9.05E-01 3.62E-02 1.81E-02 T. Spec Gamma Receptor...................

4 Distance (meters).........

800 Compass Point.............

SSE Major Contributors......

.0.0 Nuclide Percentage AR-41 6.89E-01 KR-85M 8.04E-04 XE-131M 9.83E+01 XE-133M 2.38E-03 XE-133 9.83E-01 XE-135 1.08E-02 T.Spec Beta Receptor...................

4 Distance (meters).........

800 Compass Point.............

SSE Major Contributors......

.0.0 Nuclide Percentage AR-41 3.46E-02 KR-85M 1.83E-04 XE-131M 9.95E+01 Composite Crit. Receptor -

NG

% or greater to total 3.12E-03 31-day Quarter Annual

4. OOE-01

1. OOE+01

2. OOE+01 7.81E-01 3.12E-02

1. 56E-02 Composite Crit. Receptor -

NG

% or greater to total Page 59 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

1 Major Contributors......

0.0

% or greater to total Nuclide Percentage XE-133M 1.53E-03 XE-133 4.16E-01 XE-135 1.97E-03 Page 60 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type.......

Historical Unit.....................

2 RELEASE DATA Total Release Duration (minutes)......................................

5.704E+05 Total Release Volume (cf)..............................................

7.016E+10 Average Release Flowrate (cfm)........................................

1.230E+05 Average Period Flowrate (cfm).........................................

1.331E+05 NUCLIDE DATA Nuclide AR-41 XE-133M XE-133 XE-135 F&AG 1-131 1-132 Iodine C-14 Other H-3 H-3 CO-58 P>=8 Total uCi

1. 66E+04 2. 13E+03

7. 58E+05 1.76E+03

7. 78E+05

8. 22E+00

1. 13E+02 1.21E+02 4.49E+06

4. 49E+06 3.80E+07 3. 80E+07

1. 13E+00

1. 13E+00 Average uCi/cc 8.35E-12 1.07E-12 3.81E-10 8.84E-13 3.92E-10 4.14E-15 5.68E-14 6.10E-14 2.26E-09 2.26E-09 1.91E-08 1.91E-08 5.67E-16 5.67E-16 EC Ratio

8. 35E-04 1.79E-06

7. 63E-04

1. 26E-05

1. 61E-03

2. 07E-05 2.84E-06 2.3 5E-05 7.53E-01 7.53E-01

1. 91E-01 1.91E-01 5.67E-07

5. 67E-07 EC 1.OOE-08

6. OOE-07 5. OOE-07

7. OOE-08

2. OOE-10

2. OOE-08

3. OOE-09

1. OOE-07 1.OOE-09 4.32E+07 2.18E-08 9.46E-01 Page 61 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID.............

Period Start Date...

Period End Date.......

Period Duration (min):

Coefficient Type...

Unit....................

1 All Gas Release Types 01/01/2012 00:00 01/01/2013 00:00 5.270E+05 Historical 2

==MAXIMUM I&P DOSE FOR PERIOD Limit Type Admin Organ Type Any Organ T.Spec Any Organ Receptor...........

Distance (meters)..

Compass Point......

Critical Pathway...

Major Contributors.

Age Dose Limit Group Organ (mrem)

Period CHILD BONE 3.66E-01 31-day Quarter Annual CHILD BONE 3.66E-01 31-day Quarter Annual 5

Composite Crit.

Receptor -

IP 800 SSE 2 Vegetation (VEG) 0.0

% or greater to total Limit (mrem) 2.25E-01

5. 63E+00

1. 13E+01

3. OOE-01

7. 50E+00

1. 50E+01 Percent of Limit 1.63E+02 6.50E+00 3.25E+00 1.22E+02 4.88E+00 2.44E+00 Nuclide H-3 C-14 CO-58 1-131 1-132 Percentage 0.00E+00 1.00E+02 1.39E-05 3.98E-04 5.51E-06 Page 62 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit....................

2 PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

GI-Lli Skin TB Age/Path Bone Liver Thyroid Kidney Lung AGPD AINHL AVEG ACMEAT ACMILK TGPD TINHL TVEG TCMEAT TCMILK CGPD CINHL CVEG CCMEAT CCMILK IGPD I INHL ICMILK ADULT TEEN CHILD INFANT 8.46E-08 1.16E-03 5.74E-02

2. 13E-02 2.32E-02

8. 46E-08

1. 66E-03 9.28E-02 1.80E-02

4. 29E-02

8. 46E-08 2.30E-03

2. 24E-01 3.39E-02 1.06E-01

8. 46E-08 1.70E-03 2. 07E-01 1.03E-01 1.55E-01 3.66E-01 2.08E-01

8. 46E-08 6.07E-04 1.22E-02

4. 36E-03

4. 88E-03

8. 46E-08 7.04E-04 1.94E-02 3.66E-03

8. 88E-03

8. 46E-08 7.77E-04

4. 61E-02

6. 86E-03

2. 15E-02

8. 46E-08 5.39E-04 4.48E-02 2.20E-02 3.27E-02 7. 53E-02

4. 54E-02

8. 46E-08

6. 09E-04

1. 22E-02 4.37E-03 5. 02E-03

8. 46E-08

7. 06E-04

1. 95E-02

3. 66E-03

9. 1OE-03

8. 46E-08 7. 79E-04

4. 61E-02 6.86E-03 2.20E-02

8. 46E-08 5.41E-04

4. 59E-02 2.22E-02 3.29E-02 7.58E-02

4. 64E-02

8. 46E-08

6. 07E-04

1. 22E-02

4. 36E-03 4.88E-03

8. 46E-08

7. 04E-04

1. 94E-02

3. 66E-03

8. 88E-03

8. 46E-08

7. 77E-04

4. 61E-02 6.86E-03

2. 15E-02

8. 46E-08 5.39E-04

4. 48E-02 TOTALS 2.20E-02 3.27E-02 7.53E-02

4. 54E-02

8. 46E-08

6. 07E-04

1. 22E-02 4.36E-03

4. 88E-03

8. 46E-08

7. 04E-04

1. 94E-02 3.66E-03

8. 88E-03

8. 46E-08

7. 77E-04

4. 61E-02

6. 86E-03 2.15E-02

8. 46E-08

5. 39E-04

4. 48E-02 2.20E-02 3.27E-02 7.53E-02

4. 54E-02

8. 46E-08

6. 07E-04 1.22E-02

4. 36E-03

4. 88E-03

8. 46E-08

7. 04E-04

1. 94E-02 3. 66E-03

8. 88E-03

8. 46E-08

7. 77E-04

4. 61E-02

6. 86E-03 2. 15E-02

8. 46E-08

5. 39E-04

4. 48E-02

2. 20E-02 3.27E-02 7.53E-02

4. 54E-02

0. OOE+00

0. OOE+00 0 OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0 OOE+00 0 OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 8.46E-08

6. 07E-04

1. 22E-02

4. 36E-03 4.88E-03

8. 46E-08

7. 04E-04

1. 94E-02

3. 66E-03

8. 88E-03

8. 46E-08 7.77E-04

4. 61E-02 6.86E-03

2. 15E-02

8. 46E-08

5. 39E-04

4. 48E-02 2.20E-02 3.27E-02 7.53E-02

4. 54E-02 AGE GROUP /

PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway AGPD AINHL AVEG ACMEAT ACMILK TGPD TINHL TVEG TCMEAT TCMILK CGPD CINHL ADULT ADULT ADULT ADULT ADULT TEEN TEEN TEEN TEEN TEEN CHILD CHILD Ground Plane Deposition (GPD)

Inhalation (INHL)

Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Page 63 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

2 AGE GROUP Abbreviation CVEG CCMEAT CCMILK IGPD IINHL ICMILK

/ PATHWAY Age Group CHILD CHILD CHILD INFANT INFANT INFANT DESCRIPTIONS Pathway Vegetation (VEG)

Grs/Cow/Meat (CMEAT)

Grs/Cow/Milk (CMILK)

Ground Plane Deposition (GPD)

Inhalation (INHL)

Grs/Cow/Milk (CMILK)

Page 64 of 79

GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID.............

1 All Gas Release Types Period Start Date....

.01/01/2012 00:00 Period End Date......

.01/01/2013 00:00 Period Duration (min): 5.270E+05 Coefficient Type..... :.Historical Unit.....................

2 MAXIMUM NG DOSE FOR PERIOD Limit Type Dose (mrad)

Limit Limit Period (mrad)

Dose Type Admin Gamma Admin Beta 2.47E-05 31-day Quarter Annual 1.22E-05 31-day Quarter Annual 2.47E-05 31-day Quarter Annual

1. 50E-01 3. 75E+00

7. 50E+00

3. OOE-01

7. 50E+00

1. 50E+01

2. OOE-01

5. OOE+00

1. OOE+01 Percent of Limit 1.65E-02 6.59E-04 3.29E-04 4.07E-03 1.63E-04 8.15E-05 1.24E-02 4.94E-04 2.47E-04 T.Spec Gamma Receptor...................

4 Distance (meters).........

800 Compass Point.............

SSE Major Contributors......

.0.0 Nuclide Percentage AR-41 3.62E+01 XE-133M 1.63E-01 XE-133 6.28E+01 XE-135 7.92E-01 T.Spec Beta Receptor...................

4 Distance (meters).........

800 Compass Point...........

SSE Major Contributors......

.0.0 Nuclide Percentage AR-41 6.35E+00 XE-133M 3.67E-01 XE-133 9.28E+01 XE-135 5.04E-01 Composite Crit. Receptor -

NG

% or greater to total 1.22E-05 31-day Quarter Annual

4. OOE-01 1.00E+01 2. OOE+01

3. 06E-03 1.22E-04

6. lIE-05 Composite Crit. Receptor -

NG

% or greater to total Page 65 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

.01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

1 RELEASE DATA Total Release Duration (minutes).....................................

5.422E+05 Total Undiluted Volume Released (gallons)............................

NA Average Undiluted Flowrate (gpm).....................................

NA Total Dilution Volume (gallons)......................................

NA Average Dilution Flowrate (gpm)......................................

NA NUCLIDE DATA Nuclide uCi CO-57 1.32E+01 SB-122 6.87E+00 SB-124 2.29E+01 SB-125 2.92E+02 CR-51 5.66E+02 MN-54 1.55E+02 FE-59 3.69E+01 CO-58 4.19E+03 CO-60 2.68E+03 ZN-65 1.09E+01 ZR-95 1.40E+01 NB-95 9.11E+01 TE-125M 2.97E+02 1-132 2.31E+00 1-133 1.36E+00 CS-134 6.10E+00 Gamma 8.39E+03 XE-131M 4.92E+01 XE-133M 1.01E+01 XE-133 1.47E+03 XE-135 3.87E+00 D&EG 1.53E+03 H-3 1.34E+09 NI-63 5.66E+02 Page 66 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 NUCLIDE DATA Nuclide uci Beta Total 1.34E+09 1.34E+09 Page 67 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

.01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

1 Receptor.................

0 Liquid Receptor PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr AFWFSp TPWtr TFWFSp CPWtr CFWFSp IPWtr 2.28E-05 7.48E-03

2. 16E-05 7.76E-03

6. 57E-05

1. 01E-02

5. 07E-05

2. 17E-02

5. 91E-02

1. 53E-02

4. 61E-02

2. 94E-02

3. 83E-02

2. 88E-02

2. 17E-02 5 61E-02

1. 53E-02

4. 31E-02 2.93E-02

3. 57E-02

2. 88E-02

2. 17E-02 5.79E-02

1. 53E-02

4. 38E-02

2. 93E-02 3.62E-02

2. 88E-02

2. 17E-02 5.62E-02

1. 53E-02 4.32E-02 2.93E-02

3. 58E-02

2. 88E-02

2. 17E-02 1.16E-01 1.53E-02

8. 53E-02 2.94E-02

5. 07E-02

2. 88E-02 0 OOE+00

0. OOE+00 0 OOE+00

0. OOE+00

0. OOE+00 0 OOE+00

0. OOE+00 2.17E-02

5. 86E-02 1.53E-02

4. 51E-02 2.94E-02 3.74E-02 2.88E-02 ADULT 7.51E-03 8.08E-02 7.78E-02 TEEN 7.78E-03 6.14E-02 5.84E-02 CHILD 1.01E-02 6.77E-02 6.51E-02 INFANT 5.07E-05 2.88E-02 2.88E-02 TOTALS-7.96E-02 7.79E-02 1.38E-01 0.OOE+00 8.03E-02 5.91E-02 5.85E-02 1.01E-01 0.OOE+00 6.04E-02 6.56E-02 6.51E-02 8.01E-02 0.OOE+00 6.68E-02 2.88E-02 2.88E-02 2.88E-02 0.OOE+00 2.88E-02

==AGE GROUP /

PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway APWtr AFWFSp TPWtr TFWFSp CPWtr CFWFSp IPWtr ADULT ADULT TEEN TEEN CHILD CHILD INFANT Potable Water (PWtr)

Fresh Water Fish -

Sport Potable Water (PWtr)

Fresh Water Fish -

Sport Potable Water (PWtr)

Fresh Water Fish -

Sport Potable Water (PWtr)

(FFSP)

(FFSP)

(FFSP)

Page 68 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date.......

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

1 Receptor.................

0 Liquid Receptor PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT H-3 0.OOE+00 7.77E-02 7.77E-02 7.77E-02 7.77E-02 7.77E-02 0.OOE+00 7.77E-02 CR-51 0.OOE+00 0.OOE+00 1.57E-07 5.80E-08 3.49E-07 6.62E-05 0.OOE+00 2.63E-07 MN-54 0.00E+00 2.47E-04 0.OOE+00 7.35E-05 0.OOE+00 7.57E-04 0.OOE+00 4.72E-05 FE-59 1.40E-05 3.30E-05 0.OOE+00 0.OOE+00 9.21E-06 1.10E-04 0.OOE+00 1.26E-05 CO-58 0.OOE+00 1.37E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.78E-03 0.OOE+00 3.08E-04 CO-60 0.OOE+00 2.52E-04 0.OOE+00 0.OOE+00 0.OOE+00 4.74E-03 0.OOE+00 5.57E-04 NI-63 6.44E-03 4.47E-04 0.OOE+00 0.OOE+00 0.OOE+00 9.32E-05 0.OOE+00 2.16E-04 ZN-65 9.22E-05 2.93E-04 0.OOE+00 1.96E-04 0.OOE+00 1.85E-04 0.OOE+00 1.33E-04 ZR-95 1.35E-09 4.34E-10 0.OOE+00 6.82E-10 0.OOE+00 1.38E-06 0.OOE+00 2.94E-10 NB-95 1.48E-05 8.25E-06 0.OOE+00 8.16E-06 0.OOE+00 5.01E-02 0.OOE+00 4.44E-06 TE-125M 2.78E-04 1.01E-04 8.37E-05 1.13E-03 0.OOE+00 1.lIE-03 0.OOE+00 3.73E-05 1-132 6.29E-09 1.68E-08 5.88E-07 2.68E-08 0.OOE+00 3.16E-09 0.OOE+00 5.88E-09 1-133 2.59E-08 4.51E-08 6.63E-06 7.87E-08 0.OOE+00 4.05E-08 0.OOE+00 1.37E-08 CS-134 6.63E-04 1.58E-03 0.OOE+00 5.10E-04 1.69E-04 2.76E-05 0.OOE+00 1.29E-03 TEEN H-3 0.OOE+00 5.83E-02 5.83E-02 5.83E-02 5.83E-02 5.83E-02 0.OOE+00 5.83E-02 CR-51 0.OOE+00 0.OOE+00 1.51E-07 5.95E-08 3.87E-07 4.56E-05 0.OOE+00 2.71E-07 MN-54 0.OOE+00 2.43E-04 0.OOE+00 7.25E-05 0.OOE+00 4.98E-04 0.OOE+00 4.82E-05 FE-59 1.45E-05 3.37E-05 0.OOE+00 0.OOE+00 1.06E-05 7.98E-05 0.OOE+00 1.30E-05 CO-58 0.OOE+00 1.36E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.88E-03 0.OOE+00 3.14E-04 CO-60 0.OOE+00 2.52E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.29E-03 0.OOE+00 5.69E-04 NI-63 6.68E-03 4.72E-04 0.OOE+00 0.OOE+00 0.OOE+00 7.51E-05 0.OOE+00 2.26E-04 ZN-65 8.36E-05 2.90E-04 0.OOE+00 1.86E-04 0.OOE+00 1.23E-04 0.OOE+00 1.35E-04 ZR-95 1.39E-09 4.38E-10 0.OOE+00 6.43E-10 0.OOE+00 1.01E-06 0.OOE+00 3.01E-10 NB-95 1.49E-05 8.29E-06 0.OOE+00 8.03E-06 0.OOE+00 3.54E-02 0.OOE+00 4.56E-06 TE-125M 3.03E-04 1.09E-04 8.47E-05 0.OOE+00 0.OOE+00 8.94E-04 0.OOE+00 4.05E-05 1-132 6.57E-09 1.72E-08 5.79E-07 2.71E-08 0.OOE+00 7.49E-09 0.OOE+00 6.17E-09 1-133 2.79E-08 4.73E-08 6.61E-06 8.30E-08 0.OOE+00 3.58E-08 0.OOE+00 1.44E-08 CS-134 6.79E-04 1.60E-03 0.OOE+00 5.08E-04 1.94E-04 1.99E-05 0.OOE+00 7.42E-04 CHILD H-3 0.OOE+00 6.50E-02 6.50E-02 6.50E-02 6.50E-02 6.50E-02 0.OOE+00 6.50E-02 CR-51 0.OOE+00 0.OOE+00 1.61E-07 4.40E-08 2.94E-07 1.54E-05 0.OOE+00 2.90E-07 MN-54 0.OOE+00 1.90E-04 0.OOE+00 5.34E-05 0.OOE+00 1.60E-04 0.OOE+00 5.07E-05 FE-59 1.76E-05 2.85E-05 0.OOE+00 0.OOE+00 8.25E-06 2.96E-05 0.OOE+00 1.42E-05 CO-58 0.OOE+00 1.10E-04 0.OOE+00 0.OOE+00 0.OOE+00 6.41E-04 0.OOE+00 3.36E-04 CO-60 0.00E+00 2.07E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.14E-03 0.OOE+00 6.09E-04 NI-63 8.80E-03 4.71E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.17E-05 0.OOE+00 2.99E-04 Page 69 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS -

BY UNIT)------

Release ID.............

Period Start Date.....

Period End Date.......

Period Duration (mins):

1 All Liquid Releases 01/01/2012 00:00 01/01/2013 00:00 5.270E+05

==PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

=

Agegroup Bone ZN-65 8.57E-05 ZR-95 1.88E-09 NB-95 1.76E-05 TE-125M 3.90E-04 1-132 8.35E-09 1-133 3.64E-08 CS-134 8.19E-04 Liver Thyroid Kidney Lung GI-Lli Skin TB INFANT H-3 CR-51 MN-54 FE-59 CO-58 CO-60 NI-63 ZN-65 ZR-95 NB-95 TE-125M 1-132 1-133 CS-134

0. OOE+00

0. OOE+00

0. OOE+00

1. 56E-07

0. OOE+00

0. OOE+00

4. 92E-05

2. 75E-08

3. 95E-10 5 25E-10

9. 50E-07 5 26E-10

2. 34E-09

3. 16E-07

2. 28E-04

4. 13E-10

6. 86E-06

1. 06E-04

1. 53E-08

4. 50E-08 1.34E-03 2.88E-02

0. OOE+00

4. 22E-07

2. 72E-07

2. 07E-06 3.98E-06

3. 04E-06

9. 44E-08

9. 63E-11 2 16E-10

3. 18E-07

1. 07E-09

3. 40E-09

5. 89E-07

0. OOE+00

0. OOE+00

0. OOE+00

1. 09E-04

7. 12E-07

8. 37E-06

0. OOE+00

2. 88E-02

7. 14E-10

0. OOE+00 0 OOE+00 0 OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 3.20E-07

5. 01E-08

6. 19E-07

0. OOE+00 1.44E-04

5. 91E-10

6. 45E-06

0. OOE+00 2.35E-08 7.50E-08 4.17E-04

2. 88E-02 1.56E-10

9. 36E-08

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

4. 58E-08 1.04E-10 1.55E-10 0. OOE+00

1. 19E-09

4. OOE-09 1.52E-07

0. OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 1.50E-04 2. 88E-02

1. 39E-09 0. OOE+00

8. 05E-08

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0 OOE+00

0. OOE+00 6.21E-08

4. 01E-05 4.31E-07 1.27E-02

3. 76E-04 1.81E-08 1.82E-08 7.25E-06

2. 88E-02

3. 19E-08

1. 55E-07 1.30E-07

5. 16E-06 9. 46E-06 1.51E-07

7. 97E-08

4. 80E-08 1.82E-07

4. 53E-07

8. 66E-10

5. 76E-10

1. 60E-09

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00 0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

1. 42E-04 3 68E-10

4. 90E-06

5. 19E-05

7. 05E-09

1. 70E-08

2. 84E-04

2. 88E-02

1. 09E-09

9. 57E-08 1.07E-07

5. 16E-06 9.39E-06 1.71E-06 4.35E-08

6. 83E-11 1.25E-10 1.28E-07

3. 80E-10 9.96E-10 5.94E-08 Page 70 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

.01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

1 Receptor.................

0 Liquid Receptor MAXIMUM DOSE FOR PERIOD Limit Type Admin Organ Type Any Organ Age Group ADULT Organ GILLI Dose (mrem) 1.38E-01 Limit Period 31-day Quarter Annual Admin Tot Body ADULT TBODY 8.03E-02 31-day Quarter Annual T.Spec Any Organ ADULT GILLI 1.38E-01 31-day Quarter Annual Critical Pathway..........

1 Fresh Water Fish -

Sport (FFSP)

Major Contributors.......

.0.0

% or greater to total Nuclide Percentage H-3 5.64E+01 CR-51 4.81E-02 MN-54 5.50E-01 FE-59 7.99E-02 CO-58 2.02E+00 CO-60 3.45E+00 NI-63 6.77E-02 ZN-65 1.34E-01 ZR-95 1.OOE-03 NB-95 3.64E+01 TE-125M 8.08E-01 1-132 2.29E-06 1-133 2.94E-05 CS-134 2.OOE-02 T.Spec Tot Body ADULT TBODY 8.03E-02 31-day Quarter Annual Limit (mrem) 1.50E-01 3.75E+00 7. 50E+00

4. 50E-02

1. 13E+00 2.25E+00

2. OOE-01

5. OOE+00

1. OOE+01 Percent of Limit 9.18E+01 3.67E+00 1.84E+00 1.78E+02 7.14E+00 3.57E+00 6.88E+01 2.75E+00 1.38E+00 6. OOE-02

1. 50E+00 3. OOE+00 1.34E+02 5.35E+00

2. 68E+00 Page 71 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)

Release ID..............

1 All Liquid Releases Period Start Date.......

01/01/2012 00:00 Period End Date.........

01/01/2013 00:00 Period Duration (mins): 5.270E+05 Critical Pathway..........

1 Fresh Water Fish -

Sport (FFSP)

Major Contributors.......

.0.0 % or greater to total Nuclide Percentage H-3 9.68E+01 CR-51 3.28E-04 MN-54 5.87E-02 FE-59 1.57E-02 CO-58 3.83E-01 CO-60 6.93E-01 NI-63 2.69E-01 ZN-65 1.65E-01 ZR-95 3.66E-07 NB-95 5.53E-03 TE-125M 4.65E-02 1-132 7.33E-06 1-133 1.71E-05 CS-134 1.61E+00 Page 72 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)

Release ID..............

1 All Liquid Releases Period Start Date.....

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

2

=== RELEASE DATA Total Release Duration (minutes).....................................

5.422E+05 Total Undiluted Volume Released (gallons)............................

NA Average Undiluted Flowrate (gpm).....................................

NA Total Dilution Volume (gallons)......................................

NA Average Dilution Flowrate (gpm)......................................

NA

=== NUCLIDE DATA Nuclide uci CO-57 1.32E+01 SB-122 6.87E+00 SB-124 2.29E+01 SB-125 2.92E+02 CR-51 5.66E+02 MN-54 1.55E+02 FE-59 3.69E+01 CO-58 4.19E+03 CO-60 2.68E+03 ZN-65 1.09E+01 ZR-95 1.40E+01 NB-95 9.l1E+01 TE-125M 2.97E+02 1-132 2.31E+00 1-133 1.36E+00 CS-134 6.10E+00 Gamma 8.39E+03 XE-131M 4.92E+01 XE-133M 1.01E+01 XE-133 1.47E+03 XE-135 3.87E+00 D&EG 1.53E+03 H-3 1.34E+09 NI-63 5.66E+02 Page 73 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS BY UNIT)

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.........

01/01/2013 00:00 Period Duration (mins): 5.270E+05

=:= NUCLIDE DATA Nuclide uCi Beta 1.34E+09 Total 1.34E+09 Page 74 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date.......

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

2 Receptor.................

0 Liquid Receptor PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 2.28E-05 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 0.OOE+00 2.17E-02 AFWFSp 7.48E-03 5.91E-02 5.61E-02 5.79E-02 5.62E-02 1.16E-01 0.OOE+00 5.86E-02 TPWtr 2.16E-05 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E-02 0.OOE+00 1.53E-02 TFWFSp 7.76E-03 4.61E-02 4.31E-02 4.38E-02 4.32E-02 8.53E-02 0.OOE+00 4.51E-02 CPWtr 6.57E-05 2.94E-02 2.93E-02 2.93E-02 2.93E-02 2.94E-02 0.00E+00 2.94E-02 CFWFSp 1.01E-02 3.83E-02 3.57E-02 3.62E-02 3.58E-02 5.07E-02 0.OOE+00 3.74E-02 IPWtr 5.07E-05 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 0.OOE+00 2.88E-02 TOTALS--------------------------------------------

ADULT 7.51E-03 8.08E-02 7.78E-02 7.96E-02 7.79E-02 1.38E-01 0.OOE+00 8.03E-02 TEEN 7.78E-03 6.14E-02 5.84E-02 5.91E-02 5.85E-02 1.01E-01 0.OOE+00 6.04E-02 CHILD 1.01E-02 6.77E-02 6.51E-02 6.56E-02 6.51E-02 8.01E-02 0.OOE+00 6.68E-02 INFANT 5.07E-05 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 0.OOE+00 2.88E-02 AGE GROUP /

PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway APWtr ADULT Potable Water (PWtr)

AFWFSp ADULT Fresh Water Fish -

Sport (FFSP)

TPWtr TEEN Potable Water (PWtr)

TFWFSp TEEN Fresh Water Fish -

Sport (FFSP)

CPWtr CHILD Potable Water (PWtr)

CFWFSp CHILD Fresh Water Fish -

Sport (FFSP)

IPWtr INFANT Potable Water (PWtr)

Page 75 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

.01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

2 Receptor.................

0 Liquid Receptor PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT H-3 0.OOE+00 7.77E-02 7.77E-02 7.77E-02 7.77E-02 7.77E-02 0.OOE+00 7.77E-02 CR-51 0.OOE+00 0.OOE+00 1.57E-07 5.80E-08 3.49E-07 6.62E-05 0.OOE+00 2.63E-07 MN-54 0.OOE+00 2.47E-04 0.OOE+00 7.35E-05 0.OOE+00 7.57E-04 0.OOE+00 4.72E-05 FE-59 1.40E-05 3.30E-05 0.OOE+00 0.OOE+00 9.21E-06 1.10E-04 0.OOE+00 1.26E-05 CO-58 0.OOE+00 1.37E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.78E-03 0.OOE+00 3.08E-04 CO-60 0.OOE+00 2.52E-04 0.OOE+00 0.OOE+00 0.OOE+00 4.74E-03 0.OOE+00 5.57E-04 NI-63 6.44E-03 4.47E-04 0.OOE+00 0.OOE+00 0.OOE+00 9.32E-05 0.OOE+00 2.16E-04 ZN-65 9.22E-05 2.93E-04 0.OOE+00 1.96E-04 0.OOE+00 1.85E-04 0.OOE+00 1.33E-04 ZR-95 1.35E-09 4.34E-10 0.OOE+00 6.82E-10 0.OOE+00 1.38E-06 0.OOE+00 2.94E-10 NB-95 1.48E-05 8.25E-06 0.OOE+00 8.16E-06 0.OOE+00 5.01E-02 0.OOE+00 4.44E-06 TE-125M 2.78E-04 1.01E-04 8.37E-05 1.13E-03 0.OOE+00 1.lIE-03 0.OOE+00 3.73E-05 1-132 6.29E-09 1.68E-08 5.88E-07 2.68E-08 0.OOE+00 3.16E-09 0.OOE+00 5.88E-09 1-133 2.59E-08 4.51E-08 6.63E-06 7.87E-08 0.OOE+00 4.05E-08 0.OOE+00 1.37E-08 CS-134 6.63E-04 1.58E-03 0.OOE+00 5.10E-04 1.69E-04 2.76E-05 0.OOE+00 1.29E-03 TEEN H-3 0.OOE+00 5.83E-02 5.83E-02 5.83E-02 5.83E-02 5.83E-02 0.OOE+00 5.83E-02 CR-51 0.OOE+00 0.OOE+00 1.51E-07 5.95E-08 3.87E-07 4.56E-05 0.OOE+00 2.71E-07 MN-54 0.OOE+00 2.43E-04 0.OOE+00 7.25E-05 0.OOE+00 4.98E-04 0.OOE+00 4.82E-05 FE-59 1.45E-05 3.37E-05 0.OOE+00 0.OOE+00 1.06E-05 7.98E-05 0.OOE+00 1.30E-05 CO-58 0.OOE+00 1.36E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.88E-03 0.OOE+00 3.14E-04 CO-60 0.OOE+00 2.52E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.29E-03 0.OOE+00 5.69E-04 NI-63 6.68E-03 4.72E-04 0.OOE÷00 0.OOE+00 0.OOE+00 7.51E-05 0.OOE+00 2.26E-04 ZN-65 8.36E-05 2.90E-04 0.OOE+00 1.86E-04 0.OOE+00 1.23E-04 0.OOE+00 1.35E-04 ZR-95 1.39E-09 4.38E-10 0.OOE+00 6.43E-10 0.OOE+00 1.01E-06 0.OOE+00 3.01E-10 NB-95 1.49E-05 8.29E-06 0.OOE+00 8.03E-06 0.OOE+00 3.54E-02 0.OOE+00 4.56E-06 TE-125M 3.03E-04 1.09E-04 8.47E-05 0.OOE+00 0.OOE+00 8.94E-04 0.OOE+00 4.05E-05 1-132 6.57E-09 1.72E-08 5.79E-07 2.71E-08 0.OOE+00 7.49E-09 0.OOE+00 6.17E-09 1-133 2.79E-08 4.73E-08 6.61E-06 8.30E-08 0.OOE+00 3.58E-08 0.OOE+00 1.44E-08 CS-134 6.79E-04 1.60E-03 0.OOE+00 5.08E-04 1.94E-04 1.99E-05 0.OOE+00 7.42E-04 CHILD H-3 0.OOE+00 6.50E-02 6.50E-02 6.50E-02 6.50E-02 6.50E-02 0.OOE+00 6.50E-02 CR-51 0.OOE+00 0.OOE+00 1.61E-07 4.40E-08 2.94E-07 1.54E-05 0.OOE+00 2.90E-07 MN-54 0.OOE+00 1.90E-04 0.OOE+00 5.34E-05 0.OOE+00 1.60E-04 0.OOE+00 5.07E-05 FE-59 1.76E-05 2.85E-05 0.OOE+00 0.OOE+00 8.25E-06 2.96E-05 0.OOE+00 1.42E-05 CO-58 0.OOE+00 1.10E-04 0.OOE+00 0.OOE+00 0.OOE+00 6.41E-04 0.OOE+00 3.36E-04 CO-60 0.OOE+00 2.07E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.14E-03 0.OOE+00 6.09E-04 NI-63 8.80E-03 4.71E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.17E-05 0.OOE+00 2.99E-04 Page 76 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date.......

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ZN-65 8.57E-05 2.28E-04 0.OOE+00 1.44E-04 0.OOE+00 4.01E-05 0.00E+00 1.42E-04 ZR-95 1.88E-09 4.13E-10 0.OOE+00 5.91E-10 0.OOE+00 4.31E-07 0.OOE+00 3.68E-10 NB-95 1.76E-05 6.86E-06 0.OOE+00 6.45E-06 0.00E+00 1.27E-02 0.00E+00 4.90E-06 TE-125M 3.90E-04 1.06E-04 1.09E-04 0.OOE+00 0.OOE+00 3.76E-04 0.OOE+00 5.19E-05 1-132 8.35E-09 1.53E-08 7.12E-07 2.35E-08 0.OOE+00 1.81E-08 0.OOE+00 7.05E-09 1-133 3.64E-08 4.50E-08 8.37E-06 7.50E-08 0.OOE+00 1.82E-08 0.OOE+00 1.70E-08 CS-134 8.19E-04 1.34E-03 0.OOE+00 4.17E-04 1.50E-04 7.25E-06 0.OOE+00 2.84E-04 INFANT H-3 0.OOE+00 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 0.OOE+00 2.88E-02 CR-51 0.OOE+00 0.OOE+00 7.14E-10 1.56E-10 1.39E-09 3.19E-08 0.OOE+00 1.09E-09 MN-54 0.OOE+00 4.22E-07 0.OOE+00 9.36E-08 0.OOE+00 1.55E-07 0.OOE+00 9.57E-08 FE-59 1.56E-07 2.72E-07 0.OOE+00 0.OOE+00 8.05E-08 1.30E-07 0.OOE+00 1.07E-07 CO-58 0.OOE+00 2.07E-06 0.OOE+00 0.OOE+00 0.OOE+00 5.16E-06 0.OOE+00 5.16E-06 CO-60 0.OOE+00 3.98E-06 0.OOE+00 0.OOE+00 0.OOE+00 9.46E-06 0.OOE+00 9.39E-06 NI-63 4.92E-05 3.04E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.51E-07 0.OOE+00 1.71E-06 ZN-65 2.75E-08 9.44E-08 0.OOE+00 4.58E-08 0.OOE+00 7.97E-08 0.OOE+00 4.35E-08 ZR-95 3.95E-10 9.63E-11 0.OOE+00 1.04E-10 0.OOE+00 4.80E-08 0.OOE+00 6.83E-11 NB-95 5.25E-10 2.16E-10 0.OOE+00 1.55E-10 0.OOE+00 1.82E-07 0.OOE+00 1.25E-10 TE-125M 9.50E-07 3.18E-07 3.20E-07 0.OOE+00 0.OOE+00 4.53E-07 0.OOE+00 1.28E-07 1-132 5.26E-10 1.07E-09 5.01E-08 1.19E-09 0.OOE+00 8.66E-10 0.OOE+00 3.80E-10 1-133 2.34E-09 3.40E-09 6.19E-07 4.OOE-09 0.OOE+00 5.76E-10 0.OOE+00 9.96E-10 CS-134 3.16E-07 5.89E-07 0.OOE+00 1.52E-07 6.21E-08 1.60E-09 0.OOE+00 5.94E-08 Page 77 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date..... :.01/01/2012 00:00 Period End Date.......

.01/01/2013 00:00 Period Duration (mins): 5.270E+05 Unit..................

2 Receptor.................

0 Liquid Receptor

==MAXIMUM DOSE FOR PERIOD Limit Type Organ Type Admin Any Organ Admin Tot Body T.Spec Any Organ Age Dose Limit Group Organ (mrem)

Period ADULT GILLI 1.38E-01 31-day Quarter Annual ADULT TBODY 8.03E-02 31-day Quarter Annual ADULT GILLI 1.38E-01 31-day Quarter Annual Limit (mrem)

1. 50E-01

3. 75E+00 7.50E+00 4.50E-02

1. 13E+00

2. 25E+00

2. OOE-01 5. OOE+00

1. OOE+01 Percent of Limit 9.18E+01 3.67E+00 1.84E+00 1.78E+02 7.14E+00 3.57E+00 6.88E+01 2.75E+00 1.38E+00 Critical Pathway........

.1 Fresh Water Fish -

Sport (FFSP)

Major Contributors.......

.0.0 % or greater to total Nuclide Percentage H-3 5.64E+01 CR-51 4.81E-02 MN-54 5.50E-01 FE-59 7.99E-02 CO-58 2.02E+00 CO-60 3.45E+00 NI-63 6.77E-02 ZN-65 1.34E-01 ZR-95 1.00E-03 NB-95 3.64E+01 TE-125M 8.08E-01 1-132 2.29E-06 1-133 2.94E-05 CS-134 2.00E-02 T.Spec Tot Body ADULT TBODY 8.03E-02 31-day Quarter Annual 6.00E-02

1. 50E+00 3. 00E+00 1.34E+02

5. 35E+00 2. 68E+00 Page 78 of 79

LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS -

BY UNIT)------

Release ID..............

1 All Liquid Releases Period Start Date.....

01/01/2012 00:00 Period End Date.......

01/01/2013 00:00 Period Duration (mins): 5.270E+05 Critical Pathway..........

1 Fresh Water Fish -

Sport (FFSP)

Major Contributors......

.0.0

% or greater to total Nuclide Percentage H-3 CR-51 MN-54 FE-59 CO-58 CO-60 NI-63 ZN-65 ZR-95 NB-95 TE-125M 1-132 1-133 CS-134

9. 68E+01

3. 28E-04

5. 87E-02

1. 57E-02

3. 83E-01

6. 93E-01 2.69E-01 1 65E-01 3.66E-07

5. 53E-03

4. 65E-02

7. 33E-06

1. 71E-05

1. 61E+00 Page 79 of 79

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D Item (old)

(new)

Determination Description of Change No.

Rev.

Rev.

Identifier page page No.

No.

1.

ODC ODC A

Added month/year of revision M

M Title Title Page Page

2.

TOC TOC A

Changed Radiological Effluent Controls to Radiological Effluents Page Page to align with TRM 1 of 7 1 of 7

3.

TOC TOC A

Changed Radiological Effluent Controls to Radiological Effluents Page Page to align with TRM 4 of 7 4 of 7

4.

TOC TOC A

Changed Table 1-1 to Table 1-a to eliminate duplicate tables in Page Page document 4 of 7 4 of 7

5.

TOC TOC A

Changed Table 1-2 to Table 1 -b to eliminate duplicate tables in Page Page document 4 of 7 4 of 7

6.

TOC TOC A

Fixed typo - Removed "Milk" from Table 4-6 title "X/Q and D/Q at Page Page the Nearest Cow Milk Meat Locations within 5 miles" 5of7 5of7

7.

TOC TOC A

Changed Radiological Effluent Controls to Radiological Effluents Page Page to align with TRM 6 of 7 6 of 7

8.

TOC TOC A

Changed Figure 6-1 Title from "Onsite Air Sampling Locations Page Page and Site Boundary" to "Onsite Air Sampling Locations and 6 of 7 6 of 7 Unrestricted Area Boundary" for nomenclature consistency.

9.

TOC TOC A

Changed Figure 6-3, "Inner & Outer Ring TLD Locations" to Page Page "Inner & Outer Ring Dosimeter Locations" based on recent 6 of 7 6 of 7 dosimeter type change.

10.

TOC TOC A

Removed Figure 6-5, Site Layout and Exclusion Area. The Page Page associated figure had been previously removed from the ODCM.

6 of 7 6 of 7

11.

TOC TOC A

Added "Page intentionally left blank" Page 1 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D Page Page 7 of 7 7 of 7

12.

RECS RE A

Changed Radiological Effluent Controls to Radiological Effluents Title Title to align with TRM Page Page Added month/year of revision

13.

Page Page A

Changed Table 1-2 to Table 1-b to eliminate duplicate tables in 1.1-1 1.1-1 document and changed reference from Improved Technical Sect Sect Specification 3.0.2 to Surveillance Requirement 3.0.2 for 1.6 1.6 accuracy.

14.

Page Page D

Changed rated thermal power definition from "shall be a total 1.1-2 1.1-2 core heat transfer rate to the reactor coolant of 3586.6 MWT" to Sect Sect "shall be a total core heat transfer rate to the reactor coolant of 1.14 1.14 3586.6 MWT. (3645 MWT following NRC approval of license amendment request submitted under Exelon letter RS-1 1-099 and implementation of power uprate per Byron Unit 1 EC 378382 and Unit 2 EC 378383)."

15.

Page Page A

Changed Radiological Effluent Controls and Surveillances 1.1-2 1.1-2 (RECS) to Radiological Effluents (RE) to align with the TRM -

Sect Sect this is a hold over from original tech specs that is no longer used 1.15 1.15

16.

Page Page A

Changed Radiological Effluent Controls and Surveillances 1.1-2 1.1-2 (RECS) to Radiological Effluents (RE) to align with the TRM -

Sect Sect this is a hold over from original tech specs that is no longer used 1.22 1.22

17.

Page Page A

Changed Table 1-1 to Table 1-a to eliminate duplicate tables in 1.1-4 1.1-4 the document.

Table Table 1-1 1Fixed incorrect reference in the following sentence:

'The bases to ITS 3.0.2 provide clarifications to this requirement' to 'The bases to TSR 3.0.b provide clarifications to this requirement."

18.

Page Page A

Changed Table 1-2 to Table 1-b to eliminate duplicate tables in 1.1-5 1.1-5 the document.

Table Table 1-2 1-2 Fixed typos - Changed REC column heading to TRM, added N/A to blank space under 10CFR20 REC reference, changed Technical Specifications Radioactive Effluent Release Report Page 2 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D REC reference from 5.2 to N/A and Technical Specification reference from 5.6.2 to N/A.

19.

Page Page A

Changed Table 1-2 to Table 1-b to eliminate duplicate tables in 1.1-6 1.1-6 the document.

Table Table Fixed typo - Changed 10CFR50 Appendix I Section IV.B.2 and 1-2 1-2 Technical Specifications, Annual Radiological Environmental Operating Report, TRM reference from 5.1 to N/A.

20.

Page Page A

Changed note from "3.0.5 through 3.10 not used" to "2.0 through 1.3-1 1.3-1 3.10 not used" based on inaccuracy of current note

21.

Page Page A

Changed Radiological Effluent Controls and Surveillances 1.3-1 1.3-1 (RECS) to Radiological Effluents (RE) to align with the TRM -

this is a hold over from original tech specs that is no longer used

22.

Page Page A

Removed the last sentence: 'These data are used to calculate 1.3-2 1.3-2 optional isopleths of radiation dose and radioactivity Sect Sect concentration" to align with current practice.

3.13.1 3.13.1

23.

Page Page A

Removed from last sentence : "and also computes and plots 1.3-2 1.3-2 isopleths included in the AREOR" to align with current practice.

Sect Sect 3.13.2 3.13.2

24.

Page Page A

Changed title of section from Liquid Effluent Concentration (TRM 1.4-1 1.4-1 3.11.c) to Concentration Limits for Effluents to align with the Sect Sect TRM.

4.3 4.3

25.

Page Page A

Changed title of section from Gaseous Effluents Dose Rates 1.4-3 1.4-3 (TRM 3.11.f) to Dose Rate for Gaseous Effluent to align with the Sect Sect TRM.

4.6 4.6

26.

Page Page A

Changed title of section from Dose From Noble Gases (TRM 1.4-3 1.4-3 3.11.g) to Dose - Noble Gases to align with the TRM.

Sect Sect 4.7 4.7

27.

Page Page A

Changed title of section from Dose From Iodine-131, Tritium, 1.4-4 1.4-3 and Radioactive Material in Particulate Form (TRM 3.11.h) to Sect Sect Dose - Iodine - 131, Tritium, and Radioactive Material in 4.8 4.8 Particulate Form to align with the TRM.

Page 3 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D

28.

Page Page A

Added "Page intentionally left blank" 1.5-5 1.5-5

29.

Page Page A

Changed Radiological Effluent Controls and Surveillances 11.1-1 11.1-1 (RECS) to Radiological Effluents (RE) to align with the TRM Sect Sect 1.0 &

1.0 &

1.1 1.1

30.

Page Page A

Fixed incorrect reference - Changed the sentence: 'The 11.1-2 11.1-2 10CFR20 dose limits are summarized in Table 1-1 to "The Sect Sect 10CFR20 dose limit references are summarized in Table 1-2" 1.21 1.21

31.

Page Page A

Changed Radiological Effluent Controls and Surveillances 11.1-5 11.1-5 (RECS) to Radiological Effluents (RE) to align with the TRM Sect Sect 1.2.2 1.2.2

32.

Page Page A

Added reference #109: "Exelon Letter RS-1 1-099, Request for 11.1-16 11.1-16 License Amendment Regarding Measurement Uncertainty Refer Refer Recapture (MUR) Power Uprate, June 23,2011."

ences ences

33.

N/A Page A

Added, Figure 1-3, Restricted Area Boundary, which was 11.1-20 mistakenly omitted from Revision 7.

34.

Page Page A

Fixed typo - removed 0 from the term Frma and changed RECS 11.2-5 11.2-5 to RE to align with TRM Sect Sect 2.3.2.

2.3.2.

4 4

35.

Page Page C

Adds the following information, which allows vent stack rad 11.2-8 11.2-8 monitor setpoints to be adjusted without necessitating an ODCM Sect Sect change:

2.6.1 2.6.1 The setpoint methodology must ensure simultaneous releases do not exceed the off-site dose rate limits set forth in TRM 3.11.

Setpoints can be adjusted based upon operational requirements with the restriction that the sum of the percentages between the Ul and U2 noble gas channels does not exceed 90% of the maximum permissible release rate."

36.

Page Page B

Adds additional information to indicate that containment purge 11.2-9 11.2-9 effluent rad monitor setpoints are established at 1.25 times the I

,_ containment noble gas activity under normal conditions based on Page 4 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D Sect Sect a grab sample obtained from the rad monitor and 1.5 times the 2.6.2 2.6.2 noble gas activity to prevent a spurious alarm based on a grab sample that may not be as representative of the containment atmosphere as monitored by the containment purge rad monitor during non-release periods when the containment atmosphere monitor gas detector is not operational. This change is made to align with current procedural guidance.

37.

Page Page A

Fixed typo - Changed reference from TRM Section 3.11.b to 11.2-9 11.2-9 3.11.f Sect Sect 2.6.4 2.6.4

38.

Page Page A

Changed RECS to RE to align with TRM 11.2-10 11.2-10 Sect Sect 2.6.4 2.6.4

39.

Page Page A

Changed RECS to RE to align with TRM 11.3-1 11.3-1 Sect Sect 3.1 3.1

40.

Page Page A

Changed RECS to RE to align with TRM 11.3-2 11.3-2 Sect Sect 3.2.1 3.2.1

41.

Page Page A

Removed duplicate definition of term Ci and changed RECS 11.3-3 11.3-3 reference to RE to align with TRM Sect Sect 3.2.3 3.2.3

42.

Page Page A

Changed RECS to RE to align with TRM 11.3-4 11.3-4 Sect Sect 3.3.1 3.3.1

43.

Page Page A

Changed RECS to RE to align with TRM 11.3-4 11.3-4 Sect Sect 3.3.2 3.3.2

44.

Page Page A

Added C-14 to the exception (H-3) for vegetation ingestion dose 11.4-13 11.4-13 factor, which uses D/Q for H-3 and C-14 instead of X/Q. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

Page 5 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D

45.

Page Page A

Added C-14 to the exception (H-3) for milk ingestion dose factor, 11.4-15 11.4-15 which uses D/Q for H-3 and C-14 instead of X/Q. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

46.

Page Page A

Added C-14 to the exception (H-3) for meat ingestion dose 11.4-17 11.4-17 factor, which uses D/Q for H-3 and C-14 instead of X/Q. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

47.

Page Page A

Added C-14 to Note 2 of Table 4-13, stating that C-14 and H-3 11.4-40 11.4-40 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

48.

Page Page A

Added C-14 to Note 2 of Table 4-14, stating that C-14 and H-3 11.4-42 11.4-42 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

49.

Page Page A

Added C-14 to Note 2 of Table 4-15, stating that C-14 and H-3 11.4-44 11.4-44 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

50.

Page Page A

Added C-14 to Note 2 of Table 4-16, stating that C-14 and H-3 11.4-46 11.4-46 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

51.

Page Page A

Added C-14 to Note 2 of Table 4-17, stating that C-14 and H-3 11.4-48 11.4-48 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

52.

Page Page A

Added C-14 to Note 2 of Table 4-18, stating that C-14 and H-3 11.4-50 11.4-50 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

53.

Page Page A

Added C-14 to Note 2 of Table 4-19, stating that C-14 and H-3 11.4-52 11.4-52 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

54.

Page Page A

Added C-14 to Note 2 of Table 4-20, stating that C-14 and H-3 11.4-54 11.4-54 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted Page 6 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D when C-14 was added to the gaseous effluents during Revision 7.

55.

Page Page A

Added C-14 to Note 2 of Table 4-21, stating that 0-14 and H-3 11.4-56 11.4-56 are in units of mrem/yr per u(i/m3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

56.

Page Page A

Added C-14 to Note 2 of Table 4-22, stating that 0-14 and H-3 11.4-58 11.4-58 are in units of mrem/yr per u(i/m3. This was mistakenly omitted when 0-14 was added to the gaseous effluents during Revision 7.

57.

Page Page A

Added C-14 to Note 2 of Table 4-23, stating that 0-14 and H-3 11.4-60 11.4-60 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when C-14 was added to the gaseous effluents during Revision 7.

58.

Page Page A

Added C-14 to Note 2 of Table 4-24, stating that 0-14 and H-3 11.4-62 11.4-62 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when 0-14 was added to the gaseous effluents during Revision 7.

59.

Page Page A

Added 0-14 to Note 2 of Table 4-25, stating that 0-14 and H-3 11.4-64 11.4-64 are in units of mrem/yr per uCi/m 3. This was mistakenly omitted when 0-14 was added to the gaseous effluents during Revision 7.

60.

Page Page A

Added 0-14 to Note 2 of Table 4-26, stating that C-14 and H-3 11.4-66 11.4-66 are in units of mrem/yr per u(i/m3. This was mistakenly omitted when 0-14 was added to the gaseous effluents during Revision 7.

61.

Page Page Changed RECS to RE to align with TRM 11.5-4 11.5-4 A

Sect Sect 5.5.1 5.5.1

62.

Page Page Changed RECS to RE to align with TRM 11.5-5 11.5-5 A

Sect Sect 5.5.4 5.5.4

63.

Page Page Changed Figure title from "Onsite Air Sampling Locations" to 11.6-11 11.6-11 A

"Onsite Air Sampling Locations and Unrestricted Area Boundary" Figure Figure for nomenclature consistency.

Page 7 of 8

Byron Station ODCM Revision 8 Change Summary Matrix Administrative Changes - Determination A Technical Changes (containment purge monitor setpoints) - Determination B Technical Changes (auxiliary building vent effluent monitor setpoints) - Determination C Technical Changes (rated thermal power change from 3586.6 MWT to 3645 MWT following MUR power uprate) - Determination D 6-1 6-1

64.

Page Page Figure 6-3 Changed TLD references to Dosimeter based on 11.6-13 11.6-13 A

recent dosimeter type change.

65.

Page Page Typo correction - changed BY-04 latitude coordinate in Table 6-2 11.6-15 11.6-15 A

from 42.88167 to 42.01867

66.

Page Page Table 6-2 Changed TLD references to Dosimeter based on 11.6-16 11.6-16 A

recent dosimeter type change To To 11.6-19 11.6-19 Page 8 of 8

Byron Station ODCM Revision 9 Change Summary Matrix Administrative Changes - Determination A Technical Changes (REMP milk location) - Determination B Technical Changes (Meteorological Programs Reference) - Determination C Item (old)

(new)

Determination Description of Change No.

Rev.

Rev.

Identifier page page No.

No.

1.

Page Page C

Changed Reference #5 from "U.S. Nuclear Regulatory I1.1-11 I1.1-11 Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17, 1972" to "U.S. Nuclear Regulatory Commission, Meteorological Monitoring Programs For Nuclear Power Plants, Regulatory Guide 1.23, Rev 1, March 2007" UFSAR commitment is being updated from RG 1.23 Rev 0 to RG 1.23 Rev 1 to align with current Met Tower calibration criteria for dew point sensors.

2.

Table Table B

Removed milk indicator sampling location BY-30-1 as dairy 6-1 6-1 farmer went out of business Page Page 116-8 116-8

3.

Figure Figure A

Changed milk sample location 26 to 26-1 and removed milk 6-4 6-4 sample locations 30 and 38 due to existing error.

Page Page II 6-14 116-14

4.

Table Table B

Removed milk sampling location BY-30-1 as dairy farmer went 6-2 6-2 out of business Page Page 116-15 116-15 Page 1 of 1