ML17083A260

Annual Radioactive Effluent Release Report for 2016

ML17083A260
Person / Time
Site:	Rancho Seco
Issue date:	03/14/2017
From:	Tallman D Sacramento Municipal Utility District (SMUD)
To:	Cruz Z Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
DPG 17-045
Download: ML17083A260 (20)

Text

I' I

.r. Powering forward. Together.

March 14, 2017 DPG 17-045 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2016 Attention: Zahira Cruz In accordance with 10 CFR 50.36a(a)(2) and Rancho Seco Quality Manual (RSLBD-010), Appendix A, Section 1.5.2.4, we are submitting the Rancho Seco 2016 Annual Radioactive Effluent Release Report for the period of January 1 through December 31, 2016.

If you or members of your staff have questions requiring additional information or clarification, please contact me at (916) 732-4893.

Sincerely, i

Dan A. Tallman Manager, Rancho Seco Assets Enclosures (

Attachment:

Rancho Seco Annual Radioactive Effluent Release Report for 2016) '

Cc:

• NRC, Jack Parrot, Region IV w/Attachment DPG Chron w/ Attachment RIC 1F.099 wAttachment RIC 1L,320 (Report only)

Rancho Seco Nuclear Generating Station I 14440 Twin Cities Road I Herald, CA 95638-9799 I 1.209.333.2935 I smud.org

RANCHO, SECO NUCLEAR 'GENERATING STATION Ll¢eNSE NUMBERS D,PR*S4cand SNM-25.10 ANNUAL RADIOACTIV,E EFFLUENT RELEASE RE,PORT JANUARY - DECEMBER 2016

RSNGS ANNUAL RADIOAOTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2016

_TABLE-OF CONTENTS INTRODUCTfON ................._................................... : ................,. ... _ ..., ........................................... ,................... 1 I. SUPPLEMENTAL INFORMATION ............... ,.................................................., ................................ 2 A. Regulatory Limits.& Guidelines forEffluentReleases: ....... ;.c ................. , .............. ;;.; ........... 2 B. Maximum Effluent Concentrations ........................................., ........................... ;... :.* ~ ......... 3 c, Measurement Me.thodsfor Total Radioa9tlvity ............... :.................... :... :.................. :........ a D; B.atch Releases (via mon'itored pathways} ...... ,, ......................... ,......................... ,..... ,.......:4 E. Unplanned Relea_ses .. .*. _ ,_,., ................,........... ,.......... _

.._...... ,...*.... ,..............,..................... ,............. 4 i=. Radioacitlve Effluent Monitoring lnstrumenti:ltion Inoperable for Greater Than 30 Days *............................., ...............................-............................-....................................................4 IL ESTIMATION OF.ERROR .......-........................... :.................. :............ , ... , ............ ,................. -........... 5 Ill. GASEQUS. EFFLUENTS ............_.::*********:**** .............. '.:_:****:***.****** ....... : .. :**** .. **:****** .. ***************** ......... 6 TABLE Ill-A: GASE()US _EFFLUENTS *'SUMMATION QF ALL RELEASES ........... ,. ..................... 7 TABLE 111-B: GASEOUS EFFLUENTS -'GROUND LEVEL RELEASES ....................... ,................. 7 TABLE 111.-c: GASEOUS EFFLUENTS-TYPICAL LOWER LIMITS OF DETECTION ................ , ... 8 TABLE 111-D: RADIOLOGICAL IMPACT ON.MAN DUE TO GASEOUS EFFLUENT RELEASES,., .................... , ....... ,..... .-, ........... , .................... : ...........-., .......................,.-.............. 9 IV. pOUID EFFLUENTS ............ :***: .. *:.********** ... :*:*******::**********,.. t**: .................. ,. ................ ,................... 10 TA.BLE_IV-A: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES .......,. ............................. 11 TABLE IV~!3: LIQIJID- EFFLUENTS .........................: ..................... , .. ,.. , ..................... , ..................... 12 TABLE 1.V~C: LIQUID EFFLUENTS - TYPICAL LOWER LIMITS-OF DETECTION ...................... , 13.

TABLE IV-D: RADIOLOGICAL IMPACTON MAN DUE TO LIQUID EFFLUENT RELEASES .... ~ ......... , ....................... , ... .-............................ ;......................*............................ 14 V. SOLID_ WASTE .... , ...................................... ,.................................................................. ,...........: ...... 15 TABLE V-A: Low-Level Radioactive Wa$te, Resins, Filters, and Evaporator Bottoms , .. ,, ... '" ....... 15 TABLE V-A: Low-Level Radioactive Waste, Ory ActiveWaste ............... , ...................................... 15 TABLE V~A: Low-Level Radioactive Waste, Irradiated Components .. , ................ ,............. ,........... 16 TABLE V~A:. Low-Level Radioactive Waste, Other Waste ...................................... , ...................... 16 TABLE V*A: Low-Level Radioactive Waste, Sum of All Low-*Level Waste Shipped from Site .......................................................................................;: ....... , ...... ,._ *...* ,.. ,.................. 17 ATTACHMENTS None

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER2016.

INTRODUCTION Rancho Seco Nuclear Generating Station (RSNGS) Unit No. 1 is located in Sacramento County, California approximately 25 miles southeast of Sacramento and26 miles nprth~northeast of Stockton.

Rancho Seco Unit No. 1 began commercial operation on April 17, 197;5. The single unit on the Rancho Seco site was a pressurized W<;lter reactor supplied by Babcock and Wilcox. The rated capacity was 913 megawatts electrlcaL Because of a public vote on June 6, 1989, Sacramento Municlpal Utility District (SMUD)shutdowrithe Rancho Seco Nuclear Generating Station and completed defueling operations on December 8, 1989. Transfer of the spentluel rod assemblies from the Spent Fuel Pooljnto dry storage at the Independent Spent Fuel $torage Installation (ISFSI) was completed on August 21, 2002.

Radiological dismantleh1eht oftne nuclear facility was completed ln December 2068 and the release of the Rancho Seco property, ex.ceptfor the area associated with the lnterirn,Onsite Storage Building (IOSB), from NRC license DPR~54 was i;ipprovedon September2!5, 2009. With.the completion of Phase I of decommissioning, the facility was placed in a SAFSTOR-type condition awaiting a suitable disposal option for the low~levelradioactive waste in storage in the IOSB. In 2014, the. Class B & c radioactive waste. stored in the IOSB was shipped to a suitable disposal-facility in Texas. Phase II of decommissioning {the IOSB and surrounding area) began in 20.15 and is expected to be completed in the first quarter of201'7. * * *

• This-Annual Radioactive Effluent Releas~ Report (AR ERR) provides ,a summary ofgaseous anc;l liquid effluent releases made from Rancho Seco during the period of January 1 through December 3,1, 2016.

This report also:provides a summary of solid radioactili'e waste shipments during the.reporting period.

In the currentcondition, there are nb radioactive liquids or liquid systems atthe facility. Radioactive material handing during limited remediation activities associated with the Phase II decommissioning effort, as well as subsequer:itwaste packaging activities were monitored with local air sampling as was the exhaust ventilation system. None of these portable air samples returned activity levels above. Ml)A,.

elimillatlng th~ potential of rc:idiocictive material being released from the facility in gaseous effluents.

Accordingly, there were no radioactive liquid or gaseous effluent releases made from Rancho *seco during the reporting period.

One shipment of solid radioactive waste was made during. the reporting period utilizing contract brokerage services This repOrt ha.s been prepared by SMUD to meet the requirements of Rancho seco Quality M<,mual (RSQM), Appendix A, Section 1.5.2:4 and Offsite Dose Calculation Manual (O[)CM) Revision 23, Step 6.10.1. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. Radiation doses associated with radioactive effluents in liquids and gasses would be calc1,1lated for a hypothetical individual who receives the maximum possible exposure at or beyond the applicable Site Boundary, had any releases occurred. *

• Since there were no releases of radioactivity in gaseous and liquid effluents during this report period, the limits' of 10 CFR20 were riot exceeded, nor were the numerical guidelines of 10 CFR 50, Appendix I ex.ceeded .. A 40 CFR 190 dose evaluation is not required be.cause radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix L 1

RSNGS ANNUAL RAPIOACTIVE EFFLU.ENT RELEASE REPORT JANUARY- DECEMBER 2016 L SUPPLEMENTAL INFORMATION A. *Regulatory Limits & Guidelines for !Effluent Releases

1. Gaseous Effluents.

a. Dose rate limit at or b~yond the Site Boundary for Gaseous Effluents for Tritium and raqioactive material in particulate form with half*lives greater than 8 days (OD'CM Technical Requirement fr~.3):

1500 rnrem/year to any organ

p. Do$e commitment to a*member of the public at or beyond .the Site Boundary for Gaseous.

Effluents from Tritium ahd raqio9ctive material in particulate form with half.:.Jives greater than 8 days (ODCM Technical Requirement6.9.4, numerical guidelines of 10 CFR50,

,A.pp~n.dix I):

7.5 mrem per calendarquarter to any organ 15 mrem per calendar year to any organ

2. Liquid Effluents

a. Th~ concentration ofradipactlve material in liquid effluents released beyond the Site Boundary for Liquid Effluents sh?ll not exceed the lirnits of to CFR20, Appen(fix B, Table 2,Column2. * *

b. Dose commitment to a member pf the p1.1blic at.or beyond th.e Site Boundary for Liquid.

Effluents from radipactive materials in liquid effluents shall be* limited to (numerical gµidelines of 10 CFR 50, Appendix I):

• 1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter fo any organ 3 mrem per calendar year to the total body 10 mrem per cale.ndar year to any organ NOTE: The noble gas source term was removed when spent fuel transfer to the ISFSI was completed in August 2002. Reference to noble gases was completely removed from the QDCM.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORi JANUARY- DECEMBER2016 B. Maximum Effluent Concentrations

1. Gaseous l;ffl uents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 {air) are not directly used in calculations for determining p*ermissible gaseous effluentrelease rates.

The annual dose limits of 10 CFR 20 for unrestricted areas are the doses assCitiated with the concentrations of 10CFR 20, Appendix B, Ti:ible 2, Column 1. QDCM Technical R.eqµirement dose rate lirriitS (mrem/yr) for gaseous effluents are pr()Vided to ensure that thELdose rate from g~seous effluents at any time at the. s*ite f?oundary for G;;:iseous Effluents will be within the annual dose limits of 10 CFR 20 forunrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release-rates.

2. liqU,id Efflue11ts The concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2 are used in calculations to determine permissible liquid discharge flow rates. The most conservative Maximum Effluent Coneentration (MEC) value for each radionµclide detected in the liquid effluent sample is used in the calcu_lations. * * *

c. Mee1$uremen_t M.etho~s* fQr To~ai Radioa~tivify The methodslisted below are-examples should radioactive effluents be discharged.

1. Gas_e.ous *Effluents LiquidSCintillation (H-3)

Gamma Spectroscopy (HPGe)

[3eta Proportional (Sr-.96, gross beta)

Alpha Proportional (gross alpha)

2. Liquid EffiuentS Gamma Spectroscc>py (HPGe)

Liquid Scintillation (H-3)

Beta Proportional (Sr~90, gross beta)

Alpha Proportional (gross alpha)

NOTE: HPGe refers to Hyper-Pure Germanium 3

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

.. JANUARY - DECEMBER 2016 D. Batch Releases (via monitored pathways}

Quarter 1 Quarter 2 Quarter.3 Quarter4 Liquid Discharges Number of batch releases 0 0 0 0 Total time period for batch releases (hours) :N/A NIA NIA NIA Maximum time period for a batch release (hours) NIA NIA N/A N/A Average time period for' a batch release (hours) N/A N/A N/A NIA Minimum time period for a batch release (hours) N/A NIA NIA NIA Average Plant Effluent Flow (cfs) N/A N/A NIA NIA None E. Unplanned ~elecises This sectic:m describes unplanned releases of radioactivity in liquid arid gaseous effluent Gaseous None None F. Radioactive Effluent Monitoring Instrumentation Inoperable for Gr~ater Than 30 Days None 4

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 II. ESTIMATION OF ERROR The methods for establishing error estimates included review ofapplicable station procedures, inspection of sampling equipment. engineering estimates, statistical applications, review of calibration setpoint data, and communication with plantpersonneL The various sources of error (s) in reported values of gaseous effluents, liquid effluents, and solid waste. are assumed to be Independent, and thus the total error is calculated according to the formula:

where: cri = relative error associated with component i Sources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficiency, counting, and calibration.

Sources of error for liquid effluents include collection container volume, dilution water flow ratt:l. grab sampling, counting, and calibration, Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, .dose rate meter reading; computer program dose-to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination.

5

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - .DECEMBER 2016

-Ill. GASEOUS EFFLUENTS Table Ill-A, Gaseous Effluents - Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of tritium and particulates with half-lives greater'than 8 days. The methodology used to calculate the Percent of ODCM Technical Requirement limitis as follows:

L[(Fi)( Avg Rel Ratc){X I Q)(Dose Factor)]

% Tech Req Limit = -=-----------.,-----

(Dose Rate Limit)

>< 100%

where:

Fi = The fraction of the total number of Curies of nuclide i out of the total curies in that category for that quarter (unitless).

NOTE: Fi always equals 1.0 for H-3 because it is the only nuclide in the category.

_ ., (.Tota1C* unes

. per category per quarter (1 E+06.UCi)Ci '

Avg Rel Rate=-------------._.,,.-_ _ _ __._

(#seconds in the quarter)

X/Q. = A default dispersion factor determined to be conser.iative when compared to the use of actual data (sec/m3).

Dose Factor = The values derived for each nuclide i from NRG Regulatory Guide* 1.109 (Ki, Li+t1Mi, or Raij). [Units in {mrern/yr)/(µCi/m3)]

Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed in Section I of this report (mrem/yr).

NOTE: Particulates with half-lives Jess than 8days are not includec;I in this calculation.

The methodology used to calculate the Estimated Total Error(%) in Table Ill-A is presented in Section II of this report Table 111-B, Gaseous Effluents - Ground Level Releases, *provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batch releases are provided for particulates and tritium. Data reported for batch releases results only from unplanned releases.

Table 111-C, Gaseous Effluents - Typical Lower Limits of Detection, provides a listing of the typical- lower limit of detection (LLD) concentrations in µCi/cc for various radionuclides.

Table 111-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 2015 Annual REMP Report). The maximum calculated organ dose is listed for each quarter along with an annual total. The direct radiation dose results, based on monitoring badge dosimetry, are also listed. Presented in this table for each category is a comparison versus ODCMTechnical Requirement dose limits with the exception of direct radiation measurements.

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RSNGS ANNUAL RAD.IOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 TABLE 111-A: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Error,%

A. Particulates

1. Particulates with half-lives>8 days Ci O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO NIA

2. Average Release Rate for period µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Percent of Tech Req limit O/o NIA NIA NIA NIA

4. Gross Alpha radioactivity Ci O.OOE+OO O.OOEt-00 O.OOE+OO O.OOE+OO B. Tritium

1. Total Release Ci 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO NIA

2. Average Release Rate. for petiod µCi/sec 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OQ

3. Percent of Tech Req limit  % NIA NIA N/A N/A TABLE 111-B: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Nuclides Released

1. Particulates None

2. Tritium None 7

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 TABLE 111-C: GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDE$ LLD {µCi/cc)

1.

• Tritium (H-3) 2.27 E-10

2. Particulates:

Manganese-54 2.08 E~12 Cobalt-58 2.29 E-12 lron-59 5.89 E-12 Cobalt-60 3.11 E-12 Strontium-89 2.00 E-15 Strontium-90 5.00 E-15 Cesium-134 1.52 E-1*2 Cesium-137 1.88 E-12 Barium-140 3.06 E~12 Cerium-141 1.15 E-12 Cerium-144 3.69 E-12 8

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 2016 TABLE 111-D: RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOi,JS EFFLUENTS:

2016 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Tritium, Particulate

1. Maximum Organ Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO

2. Percent Tech Req limit  % N/A NIA NIA N/A N/A B.. Direct Radiation

1. Dose (M<mitoring Badges)1 mrern 0.00 E+OO 0.00 E:+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO

2. Percent of Tech Req limit  % NIA N/A NfA NIA NIA NOTE: No releases of gaseous radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2016.

1 None of the Indicator stations indicate significant radiation attributable to facility operations.

9

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUA.RY- DECEMBER 2016 . .

IV. LIQUID EFFLUENTS Table IV-A, Liquid Effluents - Summation of All Releases; provides a detailed summary of liquid effluent releases per quarter. This table summarizes releases of fission and .

activation products, tritium, dissolved and entrained gases, and gross alpha radioactivity.

Also listed is the volume of waste released prior to dilution and the volume of dilution water used during each quarter.

The following methodology is used to calculate the Average Diluted Concentration and the Percent of ODCM Technical Requirement Limit in Table IV-A:

% Tech Req Limit = f [ Ci i MECi

].

where: n = The total number of radionuclides identified Ci = The average diluted concentration of radionuclide i (Total Release per Category per Quar:ter in µCi)

= (Total Release Volume (part Fin Table IV -A) in ml)

MECi= The MECof the i1h radionuclide, from 10 CFR 20, Appendix B, Tc:1ble 2, Column 2 The methodology used to calculate the estimated total. error in Table IV-A is presented in Section II of this report.

Table 1v~s, Liquid Effluents, provides a complete quarterly sumrnary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed in Table IV-A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data is provided only for batch releases.

Table IV-C, Liquid Effluents - Typical Lower Limits of Detection, provides'a listing of the typical lower limit of detection (LLD) concentrations in µCi/ml for various radionuclides.

Table IV-D, Radiological Impact on Man Due Tq Liquid Efflqent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Liquid Effluents (actual doses will be assessed iii the 2015 Annual REMP Report). The maximum calculated total body dose and organ dose are listed for each quarter along with an annual total. A comparison versus ODCM Technical Requirement dose limits is also presented.

10

R.SNGS ANNUAL RAOIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2016 TABLE IV-A: LIQUID EFFLUENTS- SUMMATIONOF ALL RELEASES Est. Total Unit Quarter 1 Quarter2 Quarter 3 Quarter4 Error.%

A Fission & Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO NIA

2. Average diluted concentration during period µCi/ml 0.00.E+OO 0.00 E+OO o:oo E+OO 0.00 E+OO

3. Percent of Tech Req limit  % NIA N/A NIA NIA B: Tritium

1. Total Release Ci 0.00 E+OO. 0.00 E+OO 0.00 E+OO 0.00 E+OO N/A

2. Average .diluted concentration during period µCi/ml 0.00 E+OO 0.00 E+OO 0.00 E+O.O 0.00 E+OO

3. Percent of Tech Req limit  % NJA NIA NIA NIA C. Dissolved and Entrained Gases

1. Total Release Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO NIA

2. Average diluted concentration during period µCi/ml 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO D. Gross Alpha radioactivity

1. Total Rele<:1se Ci 0.00 E+OO 0.00 E+OO 0.00 E+OO O.OQE+OQ NIA E. Volume of Waste Released (priorto dilution) Liters 0.00 E+OO O~OOE+OO 0.00 E+OO a.ob E+OO NIA F. Volurne of dilution water used during period Liters N/A N/A NIA NIA N/A 11

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 TABLE IV-B: LIQUID EFFLUENTS Nuclides Released

1. Fission and activation products (excluding tritium. gross alpha)

None

2. Dissolved ahd entrained gases None NOTE: No releases of liquid radioactive effluent were made from Rancho Seco Nuclear Generating Station in 2016.

12

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 TABLE IV-C: LIQUID EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTiON RADIONUCLIDES BATCH MODE: LLD (µCi/ml)

1. Tritium (H-3) 2.60 E-06

2. Particulates:

Manganese-54 2.11 E-09 lron-59 3.71 E-09 Cobalt-57 2.12 E-09 Cobalt-58 1.93 E-09

• Cobalt-60 1.98 E-09 Zinc"65 4.34 E-09 Strontium-90 5.00 E-10.

Ruthenium-106 1.79 E-08 Silver-110m1.94 E-09 Antimony-125 5.78 E-09 Cesiu.m-1341.93 E-09 Cesium-1362.23. E-09 Cesium-1372.30 E-09 Barium~140 7.75 E*09 Cerii.Jm-1413.60 E-09 Cerium-1441.*59 E-08 13

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 2016 TABLE IV-0: RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:

2016 Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Annual A. Maximum Total Body Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO 0.00 E+OO Percent Tech Req limit  % N/A N/A NIA NIA NIA B. Maximum Organ Dose mrem 0.00 E+OO 0.00 E+OO 0.00 E+OO O.OOE+OO 0.00 E+OO Percent Tech Req limit  % NIA NIA NIA NIA NIA 14

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 2016 V. SOLIPWASTE:

A. SOLID WASTE Si:UPPED OFFSITE FOR BURIAL OR DISPOSAL (Not:irradiated fuel)

... ' -~-"'.>~*

. *~'~~~~.ijipp~~~>e*.

.. * ./..:.:~

A Q,OOE+OO Q;OOE+OO O;OOJ~:+oo B 0,()0£+00 o.oo E+OO O:OOE+OO c Q.00 E+OO 0.00 E+OO O;OOE+OO All O.OOE+OO O:OOE+OO b.bo E'*QO

• Major*Nuclides for the Above Table: None A 1.05 E+03 2.97E+01 2*.22:E"."04*

B O.OOE+OO O.OOE+OO 0.00.E+OO c o:.oo E+oo o.oo E+oo 0:00.E+OO All 1.05 E+03 2.97 E+01 2~22 E.:04 Major Nuclid~sfor the Abov~ Table:. Cs"'..131; Co-$0 15

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016

' ,n3* !\ .,

A 0.00 E+OO 0.00 E+OO 0.00' E+OO B 0.00 E+OO o~oo E+oo 0.00 E+OO c 0.00 Ef-00 0.QO E+OO O.Ob E+OO All o~oo E+oo O,OO E+OO 0.00 E+OO Major Nuclides for the Above Table: Npne

~::::;~ *:

'

qurie~.sh.ippec,t,,C::':

J*.:* - . ,,, ,- '.',*

A O.OOE+OO 0.00 E+OO B O.OOE+OO o.oo E+oo O.OOE+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 0.00 E+OO 0.00 E+OO O.OOE+OO Major Nuclides for the Above Table: Nolie 16

RSNGS ANNUAL .RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 Table V-A: Low-Level Waste (continued

<$'4m of All Lo~i~~vel ,

• . Waste Shippetrfrom ,":

,~ ... ,) *':;:-.:~~ite

'/; -.,

A 1.05 E+03 2.97 E+01 2.22 E-04 B 0.00 E+OO 0.00 E+OO 0.00 E+OO c 0.00 E+OO 0.00 E+OO 0.00 E+OO All 1.05 E+03 2.97 E+01 222 e.;04 Major Nuclides for the Above Table: Cs-137; Co-60 17