ML12229A529

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Byron Nuclear Power Station Annual Radiological Effluent Release Report for 2011, Pages 1 - 40
ML12229A529
Person / Time
Site: Byron  Constellation icon.png
Issue date: 12/31/2011
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
References
BYRON 2012-0038
Download: ML12229A529 (40)
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Text

BYRON NUCLEAR POWER STATION ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT (ARERR) 2011 Page lof81 BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKET NUMBER STN-50-454I455 RADIOACTIVE EFFLUENT RELEASE REPORT January 2011 -December 2011 Supplemental Information

1. Regulatory Umits a. Fission and activation products:

Tech Spec Whole Body = 500 mrernlyear Skin = 3000 mremlyear 1OCFRSO Gamma = 5 mradlquarter; 10 mradlyear Beta = 10 mradlquarter; 20 mradlyear

b. Iodine: (summed with particulate, see below) c. Particulates with half-lives>

8 days: Tech Spec Organ = 1OCFRSO Organ = d. liquid Effluents:

1OCFRSO Whole Body = Organ = 2. Maximum Permissible Concentration 1500 mremlyear 7.5 mremlquarter; 15 mrem/year 1.5 mremlquarter; 3 mremJyear 5 mremlquarter; 10 mremlyear

a. FISSion and Activation Products:

1OCFR20 Appendix B Table 2 b. Iodine: 1OCFR20 Appendix B Table 2 c. Particulates:

1OCFR20 Appendix B Table 2 d. Liquid Effluents:

10 X 1OCFR20 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. Rssion and activation products:

Prior to release, the isotopic content is determined.

Released activity is calculated using volume of release, which is detennined by the change in tank 01 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. Page 2 of81
c. Liquid effluents:

Isotopic analysis is perfonned 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 bIowdown composite activity or a sum of the input composite activities.

d. Analysis results that are less than the lower limit of detection

<<LLO) are reported in units of uCVcc or uCVml unless otherwise noted. AU LLD values are listed in Attachment A. 5. Batch Releases:

a. Uquid: 1. Number of batch releases = 105 2. Total time period for batch releases = 15,083 minutes 3. MaxImum time period for a batch release = 673 minutes 4. Average time period for a batch release = 144 minutes 5. Minimum time period for a batch release = 47 minutes 6. Average stream flow during periods of release of effluent into a flowing stream = 222 m 3/sec, based on information from the U.S. Geological Survey Byron Gauging Station. b. Gaseous: 1. Number of batch releases = 361 2. Total time period for batch releases = 57.225 minutes 3. Maximum time period for a batch release = 4,080 minutes 4. Average time period for batch releases = 159 minutes 5. Minimum time period for a batch release = 8 minutes 6. Abnormal Releases:
a. Liquid* None b. Gaseous -None 7. 2011 Radiological Groundwater Protection Program (RGPP) Results Summary: In 2011. thirteen (13) Radiological Groundwater Protection Program (RGPP) monitoring wells were sampled. The samples were obtained In March. May. July. and November and analyzed for tritium. In addition.

a study of gamma. beta. alpha. and hard-to-detect 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 radlonuclldes above what Is considered background levels. Three weUs contained levels of tritium above the lower limit of detection (LLD) of 200 pCVl.. They were: AR-4 (875 pCiIL in March. 818 pClIl.ln May. 777 pCiIl in July. 912 pCiIl. in November).

AR*11 (827 pCiIL. in March. 919 pCiIL. In May. 1,150 pCiIl in July. 894 pCiIl. in November).

and AR*7 <<LLO in March, <LLD in May. 291 pCVL in July. 269 pCiIl. in August. 314 pCiIL in September.

318 pCilLln November).

Wefls AR-4 and AR-11 are near the Circulating Water BIowdown 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. WeH AR-7, located just west of the plant structures.

last showed tritium above the LLO (228 pCiIl) in 2008. The tritium In this well is believed to be from precipitation recapture of pennitted gaseous release of tritium from the plant that has entered the well during rainfall events as a result of Improperly compacted soil Page 3 of81 around the well during original installation.

The dose consequence from tritium present in these sample welts is negligible.

8. 2010 Addendum The Solid Radioactive Waste for Burial table. which estimates the radioactive solid waste composition of materials that were sent off site for burial. was mistakenly omitted from the 2010 ARERR. The table is included below: 80UD MDlCMC'nVI WAIITI PO" 8UNAL "'1'I'1oIId w_ Com, a Iron IOtO Page 4 of81 IrrMIatIcI 2010* No v_ ptgJ o.ooI!..oo 0.. NlA _CUrtM 2010* No* :-Cm3) NlA .... AIIund ::a.-UCI/mI UCIhftI

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 (OOCM) limits. The Total Effective Dose Equivalent (TEOE) due to licensed activities at Byron Station calculated for the maximum exposed Individual for the period Is 2.62E-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 1OCFRSO Appendix I, 1OCFR20 and 4OCFR190.

There were no additional operational controls Implemented in 2011 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 1.40E+OO curies of fission and activation gases were released with a maximum average quarterly release rate of 1 .36E-01 IJCVsec. A total of 7.47E-05 curies of 1-131 were released during the year with a maximum average quarterly release rate of 5.36E-06 IJCVsec. A total of 1.37E-06 curies were released as airborne particulate matter with a maximum average quarterly release rate of 1.32E-07 JJCVsec. A total of 8.23E+OO curies of other (C-14, Br-82) radioisotopes were released with a maximum average quarterly release rate of 2.86E-01 JJCVsec. A total of 5.95E+01 curies of tritium were released with a maximum average quarterly release rate of 2.51 E+OO JJCVsec. Gross alpha-emittlng radlonuclldes were below detectable limits. liquids Released to Rock Atyer A total of 2.66E+10 liters of radioactive liquid wastes containing 2.52E-02 curies of Page 5 of81 fission and activation products were discharged with a maximum quarterly average concentration of 2.46E-09 IJCVml. A total of 2.58E+03 curies of tritium were discharged with a maximum quarterly average concentration of 4.26E-04 uCVml. A total of 1.23E-03 curies of dissolved and entrained gases were discharged with a maximum quarterly average concentration of 2.90E-10 uCVml. 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 5.02E-QS mrad based on measured effluents and average meteorological data, and 8.68E-06 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 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 sensitive tissues. For purposes of this report the skin Is taken to have a thickness of 7.0 mglcm 2 and an occupancy factor of 1.0 is used. The skin dose based on measured effluents and concurrent meteorological data was 1.23E-05 mrem. The maximum offsite beta air dose for the year based on measured effluents and average meteorological data was 2.2SE-QS mrad, and 1.60E-05 mracl 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.

C-14 exhibits a capacity to concentrate in bone. C-14 is released in gaseous form and is absorbed into vegetation through photosynthesis.

The principal pathways of Interest for C-14 are the consumption of vegetation by humans and milk from which animals have ingested C-14 through the consumption of vegetation.

With the requirement to report C-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 C-14 from the plant. Page60fSl 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 from May through October. The maximum organ dose from radioactive iodine and particulate (including C-14) to any organ was 6.71 E-01 mrem (childlbone) based on measured effluents and average meteorological data. and 6.11 E-Q1 mrem (childlbone) based on measured effluents concurrent meteorological data. The maximum dose from radioactive iodine and particulate (including C-14) to the whole body was 1.37E-Q1 mrem (child) based on measured effluents and average meteorological data. and 1.26E-Q1 mrem (child) based on measured effluents and concurrent meteorological data. Gaseous Total Dose The maximum total dose from gaseous releases to any organ was 6.71 E-01 mrem (childlbone) based on measured effluents and average meteorological data. and 6.11 E-Q1 mrem (childlbone) based on measured effluents and concurrent meteorological data. The maximum total dose from gaseous releases to the whole body was 1.37E-Q1 mrem (child) based on measured effluents and average meteorological data. and 1.26E-Q1 mrem (chId) based on measured effluents and concurrent meteorological data . UQUID 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. Uquid 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 2.15E-Q1 mrem (adult/gilli).

The maximum dose from liquid releases to the whole body was 1.49E-01 mrem (adult). GASEOUS + LIQUID TOTAL DOSE The maximum total dose to any organ via both gaseous and liquid effluents is 6.72E-01 mrem (childlbone).

The maximum dose to the whole body via both gaseous and liquid effluents is 2.62E-Q1 mrem (child). Dose Umits 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.

  • 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 Page 7 of81 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.
  • The RETS limits on dose to a member of the public due to radioactive iodine & particulate with haH-llves 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.
  • The 1OCFR20 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 99.80/0 during 2011. Page 80f81 SOLID RADIOACTIVE WASTE FOR BURIAL 1 ST QUARTER 2011 DISPOSITION OF MATERIAL MODE OF DESTINATION CURIES* DATE (DESCRIPTION, CLASS, TYPE AND TRANSPORT PER PER SOliDIFYING AGENT) SHIPMENT SHIPMENT AAOICW:TIVE MATEAW., EXCEPTED PACKAGE
  • tt LIMITED QUANT1TY OF MATERIAL.
7. UN2ItO
  • EXCLUSlVEoUSE FISSILE EXCEPTeD.

CLASS A. GENEAAI. DESIGN KIngIIoI'I.

TN t.54E.ot Ute.03 PACKAGE (oop). 2(f METAL. BOX(2). NONE RADICW:'TIVE MATERIAL.

LOW SPECIFIC ACTMTY :w1Of11 (lSAoI1).

7. UN332t. FIS8U EXCEPTED.

CLASS A. EXCLUSIVE-WE GENEIW. DESIGN PACKAGE (OOP). 'JI1 METAL. BOX OakAldp, TN 3.08E+01 UIIE-ot (1), NONE AAOOAC11YE MATEAlAL.I.OW SPECIFIC ACTIVITY 3I2It1t (lSAoI1).

7. UN332t. FISSILE EXCEPTED.

CLASS A. ElClCUJSIVI!oU8E 0ENEfW. DESIGN PAQ(AQE (OOP), 'JI1 METAl. BOX 0Ik RIdge, TN e.73E+01 l.ttEoOZ (2),NONE Quarterly Totals Number of 3 1.13E+02 8. 13E-02 Shipments:

  • Calculaled using measured ratios CUBlCM CURIES Page90fSl SOLID RADIOACTIVE WASTE FOR BURIAL tj40 QUARTER 2011 DISPOSITION OF MATERiAl MODE OF VOLUME CURIES* DATE (DESCRIPTION.

CLASS. TYPE DESTINATION PER PER AND SOLIDIFYING AGENT) TRANSPORT SHIPMENT SHIPMENT AADIOACT1VE MATERIAL.

LOW SPECIFIC <WI11 ACTIVITY (lSMI). 7. UN3321. FlSSa.E EXlCLUSNE-usE 08k FUdge. TN 8.78E.o1 A.

PACKAGE 20' METAl. &OX AADIOACTMl MATERIAL.

EXCEPTED PACUOI! LIMJ1'ED QUANT1TV OF MAnNAL. EXlCLUSlVI-usE 0aII RIdge. TN 1 ** .01 8.04E.05 7. WGlto. FI88a.E EXCEPTED.

CLASS A.

DESIGN PACKAGE (OOP). 20' METAl. 80)((1). NONE AADIOACTIYE MATERIAL.

LOW SPEaFIC 411211 1 ACTIVITY (lSMI). 7. UN3321. FISSILE! EXClUSIVE-usE 0aII RIdge. TN 8.7tE.o1 AADIOACT1VE MATERIAL, LOW SPEClPlC 411411 1 N:fNrrY (L8A-II).

7. UN3321. FISSILE EXlCLUSNE-usE 0IIII RIdp. TN 3.41E+01 2.13&+00 MATERIAL.

LOW SPECIFIC 4121111 AC1MTY (lSMI). 7. UN3321. FISSILE EXCLUSIVE-usE Oak RIdge, TN 8.8OE+01 I!)CCEP i ED. ClASS A. OENEFW. DESIGN PAaCAGliIODPt 20' METAl. &OX m. NONE AADIOACTIVE MATERIAL, LOW SPECIFIC 111M 1 AC'TMTY (LSA-II), 7. UN332t. CLASS A. EXa.U8NE.usE Che.UT 4.52+00 3.84E+OO I DESICIN PAQCAGfi (ODP). CASl(1). MATEAfAI., LOW SPECIFIC 1118111 AC1MTY (LSA-II), 7. UN332t. ClASS A. EXCLUSIYE-USE QIwe.UT 4.en:+oo 3.71E+OO I:::W-DE8IQN PAaCAOI (ODP). CASl(1). AADIOACTIYE MATERIAL.

LOW SPECIFIC M4It1 N:fNrrY(lSMI).

7. UN3321. F1S8&.2 EXCLUSIVEoUSl!

Oak RIdge. TN 8.13E.o1 A.

PACKAGE METAl. NONE AAD1OACT1VE MATERIAL.

LOW SPECIFIC M4I11 AC'TMTY (LSIrU). 7. UN3321. FI88IU! EXa.U8IVI!.usE Oak RIdge. TN 3.47&.01 0uar1811y Totals Number of 9 3.6OE+02 1.06E+01 Shipments:

  • Calculated using measured ratios CUBlCM c::uAIES Page 10 of 81 SOLID RADIOACTIVE WASTE FOR BURIAL 3 RD QUARTER 2011 DISPOSITION OF MATERIAL MODE OF VOLUME CURIES* DATE (DESCRIPTION, CLASS, TYPE DESTINATION (m') PER PER AND SOLIDIFYING AGENT) TRANSPORT SHIPMENT SHIPMENT AADIOACTIYE MATaUAL.l0ll8PECtFIC 711 11" ACTMTY (l.SA-II).

7, UN3321, CLASS A. EXCWSIVE.us&

QIve,UT 4.87&+00 1.25E+01 GENERAL DE8ION PAQ<AOE (GOP), CASK(1" NaN! RADIOACTIVE MATaUAL. EXCEPTED 71215111 PAO<AOE LMYm 0UNmTV OF MATERIAL.

E)CCLUSIYE.usE 1.88E+Ot 7, UNa1O, FIS8LE EXCEP i eo, ClASS A. GENERAL DESIGN PACICAQE (GOP), 'ltI MeTAlsoxm.

NONE AADIOACTIYE MATaAL.lJ:NISPECIFIC 8122111 ACTMTY (1..SAofI).

7, UN332'I, ClASS A. EXCWSIYE..usE CiNe,UT 4.531:+00 1.00E+OO 0ENERAl DE8ION PACKAGE (GOP), CA8K(1" NONE MATEIUAL.

LOW SPEQFIC l1l24I1 t ACTMTY (lSAof1).

7, UN332'I, CLASS A. E)CCLUSiYE.uaE CiNe,UT 4.531:+00 UtE+Ot PACKAGE (GOP), CA8K(1" Quarterty Totals Number of 4 Shipments:

3.35E+01 6.46E+01

  • Calculated using measured ratios CUBIC .. CURIES Page 11 of81 SOLID RADIOACTIVE WASTE FOR BURIAL 4 TH QUARTER 2011 DISPOSITION OF MATERIAL MODE OF CURIES* DATE (DESCRIPTION.

ClASS. TYPE TRANSPORT DESTINATION PER PER AND SOlIDIFYING AGENT) SHIPMENT SHIPMENT RADIOACTM!

MATERIAL, LOW SPECIFIC 1018111 /ICfMfY (LSA-I). 7. UN3321. FISSILE EXCUJSIVE.usE 0Ik RIdge. 1M 4.11E+Ol EXCEPfED.

Q.A88 A, GENERAL DESIGN PAQ(AOE (GOP). 2(f METAlIlOX(2).

NONE AADIOACT1VE MATERIAL.

LOW SPECIFIC 1018111 ACrMTY(LSA-I).

7. CM3321. FISSLE OIl! RIdge. 1M 7.1eE+Ol EXCEPrED.

Q.A88 A, GENERAL DESIGN PAQ(AOE (GOP). 2(f METAlIlOX(2).

NONE AAOIOACTIVE MATEAIAL.

EXCEPTED PAQ(AOE LMrED QUNmTY OF MATERIAl.

11M" 7. U'GI1O, FISSILE EXCEPTED.

Q.A88 A, EXCLUSIVE.us&

KIngItan.

TN 2,88£+01 GENEJW. DESIGN PACKAO! (ClOP). 2(f METAl BOX(2). NONE Quarterly Totals 3 1.40E+02 7.58E-02 Shipments:

  • Calculated using measured ratios CUSIC .. CURIES Page 12 of81 2011 (m3J 2.--:.0, 4, .I2E-.15E* lnadiated 2011* No VOUne (m3) O.CIOE+oo Cia. NlA CuriII DrY Adlva Wall8 2011 jIIoIume (1113) c iC1aa A UCIIda r", AlliN f 1-3 1.311 ,ol 1.8281 =e-li * :0-::I :0-1 H .18 JoE 1.11 .,. n* .,.. I :. :e-u.2311 I.IIDOI ,,*Z41 1.014. Page 13 of81 uam 1.88E-

!.7IIIi. IJME. If. 1.28E* tJME* i foo_ IA7E-< ,7ftI:.. O.OIl process CQntrol program (PCP) for Radioactive Wastes There were no changes made to RW*AA*100, Process Control Program (PCP) for Radioactive Waste, In 2011. Page 140f81 Error AnalvsiS The followtng Is an estimate of the errors associated with effluent monitoring and analysis.

The estimate is caJculated using the square root of the sum of the squares methodology.

1. Gaseous Effluents Qme-3.33%

RMaNlA ECe--5% StdcselSmplcse=5%

gme=NIA Total error = 7.8% 2. Uquid Effluents Qme--3.33%

RM=NlA Eee-NlA StdcseISmplcse=:5%

qme-2.22%

Total error = 6.4% 3. Waste Resin Ome=10.0%

RM-NIA ECe=5% ." StdcselSmplcse=5%

gme=1.0% Total error ="12.3% ." 4. DAW, Mechanical Filters, and Contaminated MetaJ ame-10.0%

RM=NIA ECe=NlA StdcselSmplcse=5%

qme:NIA Instrument calibration error = 10% Total error = 11.2% Om. = 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 COCM"Itlng Instrument of Interest Smplcse = on.s!gma 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 IS of81 Miscellaneous Information A. As required by Technical SpecifIcation 5.6.2, meteorological and environmentallmpad information is reported in the 2011 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 2011 reporting period. C. There were no irradiated fuel shipments during the 2011 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 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. Data from the dosimeters, when compared to the existing environmental dosimeters, showed no statistical difference.

As a result, there Is currentty no off site 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 2011 reporting period. REMP composite surface water samples from point BY -12, Rock River downstream of the plant liquid effluent discharge, detected tritium results of 225 pCVL (2"" Quarter), 584 pCUl (3"' Quarter), and 352 pClIL (4'" Quarter), against a lower detection Hmlt of 200 pCiIl. These positive sample results can be attributed to one or more weekly samples being obtained shortty after a permitted liquid discharge.

and are not unexpected.

The results are well below the TAM reportable limit of 30,000 pClIL. There are no communities using the Rock River for drinking water within 10 km downstream of the station. E. There were no elevated releases during the 2011 reporting period. All gaseous releases were via vent stacks and are considered mixed mode reteases.

F. There was one liquid effluent radiation release monitor that exceeded its inoperabillty time limit as stated In TRM TlCO 3.11.L The ORE-PROO1.

Radwaste Release Tank Monitor. was declared inoperable on 12128110 and retumed to service on 2123111. The reason the ORE*PROO1 monitor was extended beyond the 14 day reporting requirement was due to an obsolete part on the monitor. Flow indicating switch. 0FI5-PR173, failed and Byron did not have a replacement.

Radio frequency interference (RFI) considerations Increased the duration of the search for a new part. Additional time was required because a modification was needed. as a like-for-Ike part was not available.

Shortly after the modification was completed the work package was created and the Instrument Maintenance Department instaUed a new switch that has been functioning property since the installation.

G. Each week. particulate sample filters are obtained from vent stack effluent rad monitors, Isotopically analyzed in accordance with the ODCM and TRM 3.11, and saved. Each quarter, the saved filters are composited and sent to an off-site vendor laboratory for to-detect analyses (gross alpha. Sr-89, Sr-90) In accordance with TRM 3.11. When preparing the filter composites for 2011 Second Quarter, vent stack effluent filters PR028. 1I2RE-PR029) for the week of 3127/11 -413111 were obtained and anatyzed for gamma activity, but the filters could not be located in preparation for shipment to the off-site vendor. As a result, the 2011 Second Quarter U11U2 Vent Stack particulate filter composites did not include filters from 3127/11 -413111. These filters contained no detectable gamma activity and as typical, vendor lab results indicated there was no Page 16 of81 detectable gross alpha, Sr-89, Sr-90 activity for this set of composite filters. Corrective actions were put in place to help prevent recurrence.

H. In August of 2010, liquid process radiation monitors were found with non-conservative high and alert setpoints.

Methodology for the calculations performed in 1997 were found to be in error as they did not correctly account for the individual isotopic release criteria set forth In 10 CFR 20 Appendix a, Table 2, Column 2. The error affected the following liquid rad monitors:

ORE-PROO1.

Liquid Radwaste Efftuent ORE-PROO5, Turbine Building Fire and Oil Sump ORE-PROO9, U-O Component Cooling Heat Exchanger Water Outlet OAE-PR010.

Station alowdown ORE-PR041, Condensate Polisher High and Low Sumps 1 RE*PROO2, RCFC 1 A & 1 C EssentIal Service Water Outlet 1 RE-PR003, RCFC 18 & 1 D Essential Service Water Outlet 1 AE*PR009, U*1 Component Cooling Heat Exchanger Water Outlet 2RE*PROO2, RCFC 2A & 2C Essential Service Water Outlet 2RE*PR003, RCFC 2B & 20 EssentIal Service Water Outlet 2RE-PROO9.

U-2 Component Cooling Heat Exchanger Water Outlet In 2011, an extent of condition review was performed on gaseous effluent rad monitors.

where the following monitors were found to have non-conservative alarm setpoints:

1 RE*PROO1, U1 Containment Purge effluent particulate channel 2RE*PROO1.

U2 Containment Purge effluent particulate channel 1 RE*PR028.

U1 Auxiliary Building Vent Effluent noble gas channel 2RE*PR028, U2 Auxiliary Building Vent Effluent noble gas channel The se1points for 1I2RE*PROO1 particulate channels were non-conservatlve based on assumptions regarding detector response and the setpoints for 1I2RE-PR028 noble gas channels were non-conservative based on a difference In the percentage of the maximum permissible release rate as described In the ODCM. Although the setpoint calculation discrepancies were in the non-conservative direction, there was no impact to 1OCFR20 compliance for liquid releases or 1OCRF50 Appendix I compliance for gaseous releases.

Permits generated subsequent to each release based on analyzed effluent stream activity verify that no release concentration or off*site dose limits are exceeded.

Engineering changes were Initiated, and the Uquld effluent setpoints were revised in December 2010. The gaseous efftuent setpoints were revised In December 2011. I. There were no unplanned or abnormal releases of radioactivity from the site to unrestricted areas during the 2011 reporting period. J. On March 11. 2011, an earthquake off the east coast of Japan triggered a massive tsunami that ultimately caused nuclear accidents to four of the six Fukushima Daiichi reactors.

The radioactive plume reached the United States, where low levels of radioactivity were measured at nearly all nuclear reactor sites. Low levels of lodine-131, IOOine*132, and IOOine-133 were measured on U1 and U2 vent stack effluent samples obtained between March 14 and April 17, 2011. One of the release paths through the plant vent stacks is from the auxiliary building, which draws outside air as a makeup source. While iodine is not usually present in vent stack samples under normal conditions, it is not uncommon for small amounts to be released through the plant vent stacks during outages as a result of primary Page 17 of 81 system draining activities.

Byron Unit 1 happened to be in an outage during the same time the post-Fukushima iodine measurements were observed at Byron and at other nuclear sites. These measurements were observed on samples taken between 3114111 and 4117/11. Although it is believed the vent stack iodine measurements obtained during this time were due to the Fukushima accident, all vent stack iodine measurements were conservatively included in the Byron 2011 effluent program and resultant dose calculations.

The low levels d iodine measured in these samples did not result in a significant increase to calculated off-site dose for 2011. K. There was one revision made to the Off Site Dose calculation Manual (OOCM) in 2011. OOCM Rev 7 was issued on 2110111. The revision incorporated NRC requirements to include C8rb0n-14 (C-14) in nuclear plant gaseous effluents.

changed several outer ring TlD locations, reflected newly-measured GPS sample locations.

changed milk and groundwater sample locations, and included other administrative changes and corrections.

L Attached are offsite dose calculation reports for January through December of 2011. Page 18 of81 The following are the maximum annual calculated cumulative offsite doses resulting from Byron airbome releases in 2011 based on concurrent meteorological data: Unit 1: I2Ra gamma air (1) beta air (2) whole body (3) skin (4) organ (I) (child-bone)

Maximum Value 3.610 x mrad 3.690 x 1 mrad 6.222 x 10-2 mrem 4.440 x mrem 3.065 x 10" mrem Unit 1 CompIIaoct Status 10 CFA 50 Appendix I gamma air beta air whole body skin organ Unit 2: I2sB gamma air (1, beta air (2) whole body skin (4) .. organ (I) (child-bone)

Yearly Objective 10.0 mrad 20.0 mrad 5.0 mrem 15.0 mrem 15.0 mrem Maximum Val", 5.070 x 1 mrad 1.230 x 10-5 mrad 6.351 x 10.2 mrem 7.820 x mrem 3.043 x 10" mrem Un" 2 Compliance sw-10 CFR 50 Appendix I gamma air beta air whole body skin organ Y ..... y Objective 10.0 20.0 5.0 15.0 15.0 mrad mrad mrem mrem mrem Gamma Air Dose -GASPAR II, NUREG-0597 Beta Air Dose -GASPAR II, NUREG-0597 Whole Body Dose -GASPAR II, NUREG-0597 Skin Dose -GASPAR II, NUREG-0597 SflCto cA ffec1ed North-Northwest North-Northwest North-Northwest North-Northwest North-Northwest

% of Appendix I 0.00 0.00 1.24 0.00 2.04 Sector Affectfld North-Northwest North-Northwest North-Northwest North-Northwest North-Northwest

% of Appendix I 0.00 0.00 1.27 0.00 2.03 (1, (2) (3) (4) (I) Inhalation and Food Pathways Dose -GASPAR II, NUREG-0597 Data recovery:

99.8% Page 19 of 81 AIlac:hment A. 2011 Racioactlve Effluent Release Report 2011 Lower Linlts of Oetecticrt (UD's) LLD -" :I . H3 c, H3 Ar41 !4 Cr51 Fe .35£-1: :0 :0 1.2 E-1: :"15 1.4 12 Fe IrE 2 6.c.e-13 Co Kr8i5m 1. ",,1:"'" Zn K,U7 3.71 1:.()7 $r1 01EO( 3.361:.0 5 .. 19 1.78IE-13 Sr-1 3.01E-08 Sr-9O 4.59E-14 Sr92 4 Mo99 Nb95 3.14E-08 11:Jt 7.18E-13 Zr95 5.19E-08 )(u13 1m ! :.0 Mo 9

)&1 3 ,n' st 2 .02 ;.,. 1. :.()8 Tit' 1m 11:-4 ca1 a4 b.. :-13 ib' 14 r7 113 '.1 !E-12 ib1lS Xet 15 .* IE.()7 .Te125m i.81E-13 Sb1 B ____

____ __

__ ____

____ __ __ l4140 2.76E-13 Te' 12 Ce141 3.8HE-13 113 Ce144 1.SUE-12 Gross Alpha 5.01£-14 Cs134. Page20of81 1Ce1 15 0s1 17 681 4 0 La140 Ce141 Ce144 Gross Alpha Grass Beta *. , 2.31E.()7 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS

-BATCH MODE Unit 1 REPORT FOR 2011 Units QTR 1 QTR2 QTR 3 QTR4 YEAR ---------------------

Number of releases 58 61 44 45 214 Total release time minutes 1.41E+04 2.09E+04 2.79E+03 4.51E+03 4.23E+04 Maximum release time minutes 4.08E+03 3.19E+03 1.82E+02 8.83E+02 4.08E+03 Average release time minutes 2.43E+02 3.12E+02 6.33E+01 1.00E+02 1.98E+02 Minimum release time minutes 2.30E+01 3.20E+01 1.60E+01 3.40E+01 1.60E+01 Note: Waste Gas Decay Tank releases are included with Unit 1 data EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS

-BATCH MODE Unit 2 REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR4 YEAR ---------------------

Number of releases 37 33 42 35 147 Total release time minutes 2.53E+03 2.65E+03 5.51E+03 4.23E+03 1.49E+04 Maximum release time minutes 1.15E+02 1.55E+02 2.25E+03 2.18E+03 2.25E+03 Average release time minutes 6.82E+01 8.03E+01 1.31E+02 1.21E+02 1.01E+02 Minimum release time minutes 1.80E+01 3.30E+01 8.00E+00 1. 70E+01 8.00E+00 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS

-BATCH MODE Unit 1 " Unit 2 REPORT FOR 2011 Units QTR 1 QTR 2 QTR3 QTR 4 YEAR ---------------------

Number of releases 28 31 32 14 105 Total release time minutes 6.54E+03 4.14E+03 3.45E+03 9.61E+02 1.51E+04 Maximum release time minutes 6.73E+02 4.50E+02 2.23E+02 2.02E+02 6.73E+02 Average release time minutes 2.33E+02 1.348+02 1.08E+02 6.86E+01 1.44E+02 Minimum release time minutes 6.10E+01 4.60E+01 5.60E+01 4.70E+01 4.60E+01 Avg. dil. water flow gpm O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Note: Liquid releases are divided evenly between units Page 21 of81 8FFLUENT AND WAST8 DISPOSAL REPORT TABLE 1A GAS80US EFFLUENTS

-SUMMATION OF ALL RELEASES unit 1 REPORT FOR 2011 Units QTR1 QTR2 QTR3 QTR 4 ---------------------

Fission and Activation Gases 1. Total Release Ci 1.10E-01 1.20E-01 4.058-02 8.208-03 2. Avg. Release Rate uCi/sec 1.41E-02 1.538-02 5.108-03 1.038-03 Iodine-131

1. Total Release Ci 1.158-05 1.608-06 (1 ) (1) 2. Avg. Release Rate uCi/sec 2.258-06 2.048-01 (1) (1) Particulates Half Life >= 8 days 1. Total Release Ci (1) (1) (1) (1) 2. Avg. Release Rate uCi/sec (1) (1) (1) (1) Others 1. Total Release Ci 9.558-01 1.998-01 1.188+00 1.208+00 2. Avg. Release Rate uCi/sec 1. 238-01 1.028-01 1.488-01 1. 518-01 Tritium 1. Total Release Ci 3.958+00 3.018+00 3.148+00 5.318+00 2. Avg. Release Rate uCi/sec 5.018-01 3.828-01 3.958-01 6.688-01 Gross Alpha Radioactivity
1. Total Release Ci (1) (1) (1) (1) 2. Avg. Release Rate uCi/sec (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 22 of81 YEAR --------2.80E-01 8.888-03 1. 918-05 6.058-01 (1) (1) 4.138+00 1.318-01 1.548+01 4.898-01 (1) (1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS

-MIXED MODE -CONTINUOUS RELEASES Unit 1 REPORT FOR 2011 Units QTR1 QTR 2 QTR 3 QTR 4 ---------------------

Fission and Activation Gases XE-133 Ci 6.41E-02 8.42E-02 2.93E-02 (1) XE-135 Ci 6.32E-06 (1) (1) (1) --------------------------------Totals for Period .** Ci 6.41E-02 8.42E-02 2.93E-02 (1) Iodines I-131 Ci 1.75E-05 1.60E-06 (1) (1) I-132 Ci 3.48E-04 (1) (1) (1)

.---Totals for Period ... Ci 3.668-04 1.60E-06 (1) (1) Particulates Half Life >-8 days No Nuclide Activities (1) (1) (1) (1)

Totals for Period ... Ci (1) (1) (1) (1) Others C-14 Ci 9.55E-01 7.99E-01 1.18E+00 1.20E+00 --------------------.-----------Totals for Period ... Ci 9.55E-01 7.99E-01 1.18E+00 1.20E+00 Tritium H-3 Ci 3.768+00 2.80E+00 3.028+00 4.04E+00 --------------------------------Totals for period *** Ci 3.76E+00 2.80E+00 3.02E+00 4.04E+00 Gross Alpha Radioactivity No Nuclide Activities (1) (1) (1) (1) --------------------------------Totals for Period ... Ci (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 23 of81 YEAR --------1.78E-01 6.32E-06 --------1. 78E-01 1.91E-05 3.48E-04 --------3.67E-04 (1) --------(1) 4.13E+00 --------4.13E+00 1. 36E+01 --------1.36E+01 (1) --------(1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS

-MIXED MODE -BATCH RELEASES Unit 1 REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci KR-85M Ci KR-87 Ci KR-88 Ci XE-131M Ci XE-133 Ci XE-133M Ci XE-135 C! Totals for Period ... Ci Iodines No Nuclide Activities Ci Totals for Period ... C! Particulates Half Life >-8 days 1.21E-02 (1) (1) (1) 4.91£-05 3.14£-02 4.98E-04 1. 91E-03 2.78E-03 1.25£-04 6.89£-06 8.40E-05 (1) 2.90E-02 5.52E-04 3.58E-03 7.65£-03 (1) (1) (1) (1) 3.32£-03 8.11£-05 1.93E-04 5.99£-03 (1) (1) (1) (1) 2.21E-03 (1) (1) 2.85£-02 1.25£-04 6.89£-06 8.40£-05 4.91£-05 6.60£-02 1.13£-03 5.68E-03 4.60E-02 3.61E-02 1.12£-02 8.20E-03 1.02£-01 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) No Nuclide Activities Ci (1) (1) ( 1) (1) (1) Totals for Period ... C! (1) (1) (1) (1) (1) Others No Nuclide Activities Ci (1) (1) (1) (1) (1) Totals for Period...

Ci (1) (1) (1) (1) (1) Tritium H-3 Ci 1.87£-01 2.05E-01 1.26£-01 1.27E+00 1.79£+00 Totals for Period ... Ci 1.87£-01 2.05£-01 1.26£-01 1.27E+00 1.79E+00 Gross Alpha Radioactivity No Nuclide Activities Ci Totals for Period ... Ci (1) (1) (1) (1) (1) (1) (1) (1) Note: Waste Gas Decay Tank curies are split evenly between Unit 1 & Unit 2 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page24of81 (1) (1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Unit 2 REPORT FOR 2011 Units QTR 1 QTR2 QTR3 QTR4 ---------------------

Fission and Activation Gases 1. Total Release Ci 9.49E-01 1.28E-01 4.48E-02 1. 48E-03 2. Avg. Release Rate uCi/sec 1.22E-01 1. 63E-02 5.64E-03 1.86E-04 Iodine-131

1. Total Release Ci 2.42E-05 3.14E-05 (1) (1 ) 2. Avg. Release Rate uCi/sec 3.11E-06 4.00E-06 (1) (1) Particulates Half Life >-8 days 1. Total Release Ci (1) 1.04E-06 3.35E-07 (1) 2. Avg. Release Rate uCi/sec (1) 1.32E-07 4.22E-08 (1 ) Others 1. Total Release Ci 1.13E+00 1.02E+00 8.80E-01 1.08E+00 2. Avg. Release Rate uCi/sec 1.45E-01 1.30E-01 1.11E-01 1. 35E-01 Tritium 1. Total Release Ci 1.56E+01 1.02E+01 1.10E+01 7.26E+00 2. Avg. Release Rate uCi/sec 2.00E+00 1.30E+00 1.38E+00 9.13E-01 Gross Alpha Radioactivity
1. Total Release Ci (1) (1) (1) (1) 2. Avg. Release Rate uCi/sec (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 25 of81 YEAR --------1.12E+00 3.55E-02 5.56E-05 1. 76E-06 1. 37E-06 4.35E-08 4.10E+00 1.30E-01 4.41E+01 1.40E+00 (1) (1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS

-MIXED MODE -CONTINUOUS RELEASES Unit 2 REPORT FOR 2011 Units QTR 1 QTR2 QTR 3 QTR 4 ---------------------

Fission and Activation Gases XE-133 Ci 8.98E-01 8.42E-02 2.93E-02 (1) --------------------------------Totals for Period ..* Ci 8.98E-01 8.42E-02 2.93E-02 (1) 10dines 1-131 Ci 2.42E-05 3.14E-05 (1) (1) 1-132 Ci 6.07E-04 (1) (1) (1) 1-133 Ci 1. 69E-05 (1) (1) (1 ) --------------------------------Totals for Period .*. Ci 6.48E-04 3.14E-05 (1) (1) Particulates Half Life >-8 days CO-58 Ci (1) 1.04E-06 3.35E-07 (1) --------------------------------Totals for Period ... Ci (1) 1.04E-06 3.35E-07 (1) Others BR-82 Ci 6.08£-06 (1) (1) (1) C-14 Ci 1.13£+00 1.02£+00 8.80£-01 1.08E+00 --------------------------------Totals for Period *** Ci 1.13E+00 1.02£+00 8.80E-01 1.08E+00 Tritium H-3 Ci 1.54£+01 1.01£+01 1.09E+01 7.19E+00 --------------------------------Totals for Period ..* Ci 1.54E+01 1.01E+01 1.09E+01 7.19E+00 Gross Alpha Radioactivity No Nuclide Activities (1) (1) (1) (1) --------------------------------Totals for Period .*. Ci (1) (1) (1) (1) (1) Less than minLmum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 26of81 YEAR --------1.01E+00 --------1.01E+00 5.56E-05 6.07E-04 1.69E-05 --------6.80E-04 1. 37E-06 --------1. 37E-06 6.08£-06 4.10E+00 --------4.10£+00 4.35£+01 --------4.35E+01 (1) --------(1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE Ie GASEOOS EFFLUENTS

-MIXED MODE -BATCH RELEASES Unit 2 REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 ei KR-85M ei KR-87 ei KR-88 ei XE-131M ei XE-133 ei XE-133M ei XE-135 ei Totals for Period ... ei Iodines No Nuclide Activities ei Totals for Period ... ei Particulates Half Life >a 8 days 4.11E-03 (1) (1) (1) 1. 07E-02 3.35E-02 4.98E-04 2.09E-03 3.93E-03 1.26E-04 6.91E-06 8.40E-05 (1) 3.49E-02 5.48E-04 3.80E-03 1.73E-03 (1) (1) (1) (1) 1. 35E-02 8.09E-05 1.942-04 9.99E-04 (1) (1) (1) (1) 4.77E-04 (1) (1) 1.08E-02 1.26E-04 6.91E-06 8.40E-05 1.07E-02 8.24E-02 1.13E-03 6.08E-03 5.09E-02 4.34E-02 1.55E-02 1.48E-03 1.11E-01 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) No Nuclide Activities ei (1) (1) (1) (1) (1) Totals for Period ... ei Others No Nuclide Activities ei Totals for Period ... ei Tritium H-3 ei Totals for Period ... Ci Gross Alpha Radioactivity No Nuclide Activities ei Totals for Period ... ei (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) 1.89E-01 1.52E-01 1.39E-01 6.83E-02 5.48E-01 1.89E-01 1.52E-01 1.39E-01 6.83E-02 5.48E-01 (1) (1) (1) (1) (1) ( 1) (1 ) (1 ) (1) (1) Note: Waste Gas Decay Tank curies are split evenly between Unit 1 & Unit 2 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 27 of81 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Unit 1 REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1. Total Release Ci 3.63E-03 3.69E-03 3.83£-03 1.49B-03 1.26£-02 2. Avg. Diluted Conc. uCi/ml 1.23£-09 1.09£-09 1.03£-09 4.63£-10 9.53£-10 Tritium 1. Total Release Ci 6.298+02 3.30£+02 2.75£+02 5.708+01 1.29£+03 2. Avg. Diluted Conc. uCi/ml 2.138-04 9.78£-05 7.38£-05 1.778-05 9.73£-05 Dissolved and Entrained Gases 1. Total Release Ci 4.278-04 2.67£-05 1.61£-04 2. Avg. Diluted Conc. uCi/ml 1.45£-10 7.92£-12 4.33£-11 Gross Alpha Radioactivity

1. Total Release Ci 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) 6.15£-04 4.64£-11 (1) (1) Volume of liquid waste liters 2.95£+09 3.38£+09 3.72£+09 3.228+09 1.338+10 (1) Less than minLmum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 28 of81

£FFLUENT AND WAST£ DISPOSAL R£PORT TABL£ 2A -Release Tank LIQUID £FFLUENTS

-SUMMATION BY RELEAS£ POINT Unit 1 R£PORT FOR 2011 Units OTR 1 OTR2 OTR3 OTR4 ---------------------

Fission and Activation Products 1. Total Release Ci 3.63£-03 3.69£-03 3.83£-03 1. 49£-03 2. Avg. Diluted Conc. uCi/ml 3.14£-06 2.81£-06 2.80£-06 2.58£-06 Tritium 1. Total Release Ci 5.47£+02 3.15£+02 2.35£+02 5.29£+01 2. Avg. Diluted Conc. uCi/ml 4.73£-01 2.40£-01 1.72£-01 9.16E-02 Dissolved and Entrained Gases 1. Total Release Ci 4.27£-04 2.67£-05 1.61E-04 (1) 2. Avg. Diluted Conc. uCi/ml 3.70£-07 2.04£-08 1.18£-07 (1) Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1)

(1) Volume of liquid waste liters 1.16£+06 1.31B+06 1.37£+06 5.78E+05 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 290f81 YEAR --------1.26£-02 2.86£-06 1.15£+03 2.61£-01 6.15£-04 1.39£-07 (1) (1) 4.41£+06 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A -Circulating Water Blowdown LIQUID EFFLUENTS

-SUMMATION BY RELEASE POINT Unit 1 REPORT FOR 2011 Units QTR1 QTR 2 QTR3 QTR 4 ---------------------

Fission and Activation Products 1. Total Release Ci (1) (1) (1)

(1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Tritium 1. Total Release Ci 8.12£+01 1.52E+01 4.01E+01 4.11E+00 2. Avg. Diluted Conc. uCi/ml 2.76£-05 4.51£-06 1.08£-05 1.28£-06 Dissolved and Entrained Gases 1. Total Release Ci (1) (1) (1) (1 ) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Volume of liquid waste liters 2.95E+09 3.38£+09 3.72E+09 3.22£+09 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 300f81 YEAR --------(1) (1) 1.41E+02 1.06E-05 (1)

(1) (1) (1) 1.33E+10 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS

-CONTINUOUS MODE Unit 1 REPORT FOR 2011 Units QTR1 QTR 2 QTR 3 QTR4 ---------------------

Fission and Activation Products No Nuclide Activities Ci (1) (1) (1) (1) ------------------------

Totals for Period ... Ci (1 ) (1) (1) (1) Tritium H-3 Ci 8.12E+01 1.S2E+01 4.01E+01 4.11E+OO --------------------------------Totals for Period ... Ci 8.12E+01 1.S2E+01 4.01E+01 4.11E+OO Dissolved and Entrained Gases No Nuclide Activities Ci (1) (1) (1) (1) ------------------------

Totals for Period ... Ci (1) (1) (1) (1) Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) --------------------------------Totals for Period ... Ci (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 81 YEAR --------(1) --------(1) 1.41E+02 --------1.41E+02 (1) --------(1) (1) --------(1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 28 LIQUID EFFLUENTS

-BATCH MODE Unit 1 REPORT FOR 2011 Units OTRl QTR 2 QTR 3 OTR 4 ---------------------

.--.------------Fission and Activation Products CO-57 Ci 4.57E-06 1.23£-06 4.41£-06 4.35E-06 CO-58 Ci 1.81E-03 2.72B-03 3.398-03 1.158-03 CO-60 Ci 6.21E-04 5.698-04 3.20E-04 1.06E-04 CR-Sl Ci (1) 2.11£-04 (1) 1.37E-04 CS-137 Ci (1) 1. 288-06 (1) (1) F8-55 Ci 1.10E-03 (1) (1) (1) F8-59 Ci 1.02E-05 4.308-05 1.768-05 5.18E-05 I-132 Ci (1) 4.498-06 (1) (1) MN-54 Ci 3.228-05 1.448-05 1.408-05 2.488-05 NB-95 Ci 3.468-06 1.178-05 2.36E-05 7.318-06 S8-125 Ci 4.788-05 7.50E-05 5.768-05 1.14£-05 S8-126 Ci 1.428-06 (1) (1) (1)

SN-113 Ci (1) 2.218-05 (1) (1) T8-123M Ci (1) 1.448-05 (1) (1) ZR-95 Ci (1) 7.188-06 5.48E-06 (1) --------------------------------Totals for Period ... Ci 3.638-03 3.698-03 3.838-03 1. 498-03 Tritium H-3 Ci 5.47E+02 3.158+02 2.35E+02 5.298+01 --------------------------------Totals for Period ... Ci 5.478+02 3.15£+02 2.35E+02 5.29E+01 Dissolved and Entrained Gases X8-133 Ci 4.278-04 2.67E-05 1.618-04 (1) --------------------------------Totals for Period ... Ci 4.278-04 2.678-05 1.6lE-04 (1) Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) ------------------------

Totals for Period ... Ci (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 32 of81 YEAR --------1.468-05 9.078-03 1.62E-03 3.48B-04 1.288-06 1.10B-03 1.238-04 4.498-06 8.558-05 4.61B-05 1.92B-04 1.42B-06 2.218-05 1.44E-05 1.278-05 --------1.268-02 1.15E+03 --------1.158+03 6.158-04 --------6.158-04 (1) --------(1)

£FFLUENT AND WAST£ DISPOSAL REPORT TABL£ 2A LIQUID EFFLUENTS

-SUMMATION OF ALL R£LEASES Unit 2 R£PORT FOR 2011 Units QTR 1 QTR 2 OTR 3 OTR4 ---------------------

. ----------------

Fission and Activation Products 1. Total Release Ci 3.63£-03 3.69£-03 3.83£-03 1.49£-03 2. Avg. Diluted Cone. uCi/ml 1. 23£-09 1.09£-09 1.03£-09 4.63£-10 Tritium 1. Total Release ci 6.29£+02 3.30£+02 2.75£+02 5.70£+01 2. Avg. Diluted Cone. uCi/ml 2.13E-04 9.78£-05 7.38£-05 1.77£-05 Dissolved and Entrained Gases 1. Total Release Ci 4.27£-04 2.67£-05 1.61£-04 (1) 2. Avg. Diluted Cone. uCi/ml 1. 45£-10 7.92£-12 4.33£-11 (1 ) Gross Alpha Radioactivity

1. Total Release ci (1) (1) (1) (1) 2. Avg. Diluted Cone. uCi/ml (1) (1) (1) (1) volume of liquid waste liters 2.95£+09 3.38£+09 3.72£+09 3.22£+09 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 33 of 81 YEAR --------1. 26B-02 9.53£-10 1.29£+03 9.73£-05 6.15£-04 4.64£-11 (1) (1) 1.33E+10 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A -Release Tank LIQUID EFFLUENTS

-SUMMATION BY RELEAS£ POINT Unit 2 REPORT FOR 2011 units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1. Total Release Ci 3.63E-03 3.69E-03 3.83E-03 1.49£-03 1.26£-02 2. Avg. Diluted Conc. uCi/ml 3.14£-06 2.81E-06 2.80E-06 2.58E-06 2.86£-06 Tritium 1. Total Release Ci 5.47£+02 3.15£+02 2.35E+02 5.29£+01 1.15£+03 2. Avg. Diluted Conc. uCi/ml 4.73£-01 2.40£-01 1.72£-01 9.16£-02 2.61£-01 Dissolved and Entrained Gases 1. Total Release Ci 4.27£-04 2.67E-05 1.61£-04 2. Avg. Diluted Conc. uCi/ml 3.70£-07 2.04£-08 1.18E-07 Gross Alpha Radioactivity

1. Total Release Ci 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) 6.15£-04 1.39£-07 (1) (1) Volume of liquid waste liters 1.16£+06 1.31£+06 1.37£+06 5.78£+05 4.41£+06 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 34of81 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A -Circulating Water Blowdown LIQUID EFFLUENTS

-SUMMATION BY RELEASE POINT Unit 2 REPORT FOR 2011 Units OTR 1 QTR 2 on 3 OTR4 ---------------------

Fission and Activation Products 1. Total Release Ci (1) (1) (1) (1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Tritiwn 1. Total Release Ci 8.12£+01 1.52E+Ol 4.01E+Ol 4. 11E+OO 2. Avg. Diluted Conc. uCi/ml 2.76E-05 4.51E-06 1.08£-05 1.288-06 Dissolved and Entrained Gases 1. Total Release Ci (1) (1) ( 1) (1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Gross Alpha Radioactivity

1. Total Release Ci (1) (1) (1) (1) 2. Avg. Diluted Conc. uCi/ml (1) (1) (1) (1) Volume of liquid waste liters 2.95£+09 3.388+09 3.72E+09 3.22E+09 (1) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of TRM Section 3.11 Page 3S of81 YEAR --------(1) (1) 1.41E+02 1.06E-05 (1) (1) (1) (1) 1. 33E+10 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS

-CONTINUOUS MOD2 Unit 2 R2PORT FOR 2011 Units OTR 1 OTR 2 OTR3 OTR4 ---------------------

Fission and Activation Products No Nuclide Activities Ci (1) (1) (1) (1) --------------------------------Totals for Period *.. Ci (1) (1) (1) (1) Tritium H-3 Ci 8.12E+01 1.522+01 4.01E+Ol 4.11E+00 --------------------------------Totals for Period *.. Ci 8.122+01 1.522+01 4.01E+01 4.112+00 Dissolved and Entrained Gases No Nuclide Activities Ci (1) (1) (1) (1) --------------------------------Totals for Period ... Ci (1) (1) (1) (1) Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) --------------------------------Totals for Period .*. Ci (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 360f81 YEAR --------(1) --------( 1) 1.41E+02 --------1.412+02 (1) --------(1) (1) --------(1)

EFFLUENT AND WASTE DISPOSAL REPORT TABLE 28 LIQUID EFFLUENTS

-BATCH MODE Unit 2 REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 ---------------------

Fission and Activation Products CO-57 Ci 4.57E-06 1. 23E-06 4.41E-06 4.35E-06 CO-58 Ci 1.81E-03 2.72E-03 3.39E-03 1. 15E-03 CO-60 Ci 6.21E-04 5.69E-04 3.20E-04 1.06E-04 CR-51 Ci (1 ) 2. 11E-04 (1) 1.37E-04 CS-137 Ci (1) 1.28E-06 (1) ( 1) FE-55 Ci 1.10E-03 (1) (1) (1) FE-59 Ci 1.02E-05 4.30E-05 1.76E-05 5.18E-05 1-132 Ci (1) 4.49E-06 (1) (1) MN-54 Ci 3.22E-05 1.44E-05 1.40E-05 2.48E-05 NB-95 Ci 3.46E-06 1.17E-05 2.36E-05 7.31E-06 S8-125 Ci 4.78E-05 7.50E-05 5.76E-05 1. 14E-05 S8-126 Ci 1.42E-06 (1) (1) (1) SN-113 Ci (1) 2.21E-05 (1) (1) TE-123M Ci (1) 1.44E-05 (1) (1) ZR-95 Ci (1 ) 7.18E-06 5.48E-06 (1) --------------------------------

Totals for Period ... Ci 3.63E-03 3.69E-03 3.83E-03 1. 49E-03 Tritium H-3 Ci 5.47E+02 3.15£+02 2.35£+02 5.29E+01 --------------------------------Totals for Period ... Ci 5.47E+02 3.15£+02 2.35E+02 5.29£+01 Dissolved and Entrained Gases x£-133 Ci 4.27£-04 2.67£-05 1.61£-04 (1) --------------------------------Totals for Period ... Ci 4.27S-04 2.67£-05 1.61E-04 (1) Gross Alpha Radioactivity No Nuclide Activities Ci (1) (1) (1) (1) ----------------

Totals for Period ... Ci (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 37 of81 YEAR --------1.46E-05 9.07E-03 1. 62E-03 3.48E-04 1.28E-06 1.10E-03 1.23E-04 4.49E-06 8.55E-05 4.61E-05 1. 92E-04 1.42E-06 2.21E-05 1. 44E-05 1.27E-05 --------1.26E-02 1.15£+03 --------1.15£+03 6.15E-04 --------6.15E-04 (1 ) --------(1) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 " 2 Report for: 2011 Unit Range -From: 1 To: 2 Liquid Receptor ==-PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) _ *** a *** =.=. QUARTER 1 aa.a.a=====

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB --------------------------------------. --------------------------------ADULT 3.32E-04 4.48E-02 4.43E-02 4.43£-02 4.44E-02 4.99E-02 0.00£+00 4.47E-02 TEEN 3.48E-04 3.37E-02 3.32£-02 3.33E-02 3.34£-02 3.71E-02 0.00£+00 3.36E-02 CHILD 4.57E-0' 3.75E-02 3.71E-02 3.71E-02 3.72E-02 3.84E-02 O.OOE+OO 3.75E-02 INFANT 2.64E-06 1. 65E-02 1.65E-02 1.65E-02 1.65E-02 1.65£-02 0.008+00 1.65E-02 *** SIT£ DOS£ LIMIT ANALYSIS **********

= ***** ==a== *** === ** QUARTER 1 Limit (mrem) * **** =.= ** :. Quartr -Limit Qtr 1 Qtr 1 -Admin. Any Organ -Admin. Total Body Age Group ADULT ADULT Organ GILLI T80DY 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 MN-54 F£-55 FE-59 CO-58 CO-60 NB-95 8.88£+01 3.91E-Ol 2.60£-01 7.56E-02 2.98£+00 2.72E+00 4.73E+00 Qtr 1 -T.Spc. Total Body ADULT T80DY Critical Pathway: Fresh Water Fish -Sport (FFSP) Major Contributors ( 0' or greater to total) Nuclide Percentage H-3 MN-54 F£-55 FE-59 CO-58 CO-60 NB-95 9.91E+01 2.72£-02 1. 18E-01 9.708-03 3.68£-01 3.57£-01 4.67£-04 Page 380f81 Dose (mrem) 4.99E-02 4.47£-02 3.75E+OO 1.13£+00 Max , of Limit 1.33£+00 3.97£+00 4.99£-02 5.00£+00 9.97£-01 4.47£-02 1.50£+00 2.98E+00 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 1 & 2 Report for: 2011 Unit Range -From: 1 To: 2 Liquid Receptor asa PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ============

QUARTER 2 =a=========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB -----------------------------------------------ADULT 3.40E-04 3.64E-02 3.57E-02 3.58E-02 3.57E-02 TEEN 3.63E-04 2.75E-02 2.68E-02 2.69B-02 2.68E-02 CHILD 4.55B-04 3.05E-02 2.98B-02 2.99E-02 2.99B-02 INFANT 4.76E-07 1. 32B-02 1.32E-02 1.32B-02 1.32B-02 =aa SITB DOSE LIMIT ANALYSIS Quartr -Limit Age Group Organ Qtr 2 -Admin. Any Organ Qtr 2 -Admin. Total Body ADULT ADULT GILLI TBODY Qtr 2 -T. Spc. Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish -Sport (PFSP) Major Contributors 0' or greater to total) Nuclide Percentage H-3 CR-51 MN-54 FB-59 CO-58 CO-60 ZR-95 NB-95 1-132 CS-137 6.85B+01 8.21E-02 2.35E-01 4.268-01 6.00E+00 3.35B+00 2.35B-03 2. 14E+01 2.04B-05 1.578-02 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 CR-51 MN-54 FB-59 CO-58 CO-60 ZR-95 NB-95 9.76B+01 4.66B-04 2.09B-02 6.98B-02 9.468-01 5.618-01 7.168-07 2.71E-03 Page 390f81 ------------------------

5.21E-02 O.OOE+OO 3.65E-02 3.83E-02 O.OOE+OO 2.75E-02 3.39E-02 O.OOE+OO 3.05B-02 1. 32B-02 O.OOE+OO 1. 32E-02 Dose (mrem) QUARTER 2 Limit (mrem) .81 *********

Max , of Limit 5.21E-02 3.75E+00 1.39E+00 3.65E-02 1.13E+00 3.25E+00 5.21E-02 5.00E+00 1.04E+00 3.65E-02 1.50B+00 2.43B+00 Nuclide 1-132 CS-137 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Percentage S.42E-OS 7.S7E-Ol Page400fSl

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