ML17117A568

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LaSalle County, Units 1 and 2 - 2016 Annual Radioactive Effluent Release Report, Part 3
ML17117A568
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/27/2017
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17117A559 List:
References
RA17-040
Download: ML17117A568 (55)
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Text

NRC RA17-040 2016 Annual Radioactive Effluent Release Report Part 3 12.1 NOT USED CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls INTENTIONALLY BLANK Page 1-12.1-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation.

REC 12.2.1 The Radioactive Liquid Effluent Instrumentation channels in Table R12.2.1-1 shall be OPERABLE with their alarm/trip setpoints to ensure that the limits of REC 12.3.1 are not exceeded.

APPLICABILITY:

When pump flow is present in the system. For Slowdown, when the Slowdown Flow Control Valve is >0% open and the Slowdown line is not otherwise isolated.

ACTIONS ----------------------------NOTE---------------------------------

1. Separate Condition entry is allowed for each instrument channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend the release of Immediately instrument channels radioactive liquid effluents inoperable due to its monitored by the alarm/trip setpoint less instrument channel. conservative than required.

OR A.2 Enter the Condition referenced Immediately in Table R12.2.1-1 for the instrument channel. B. One or more required B.1 Enter the Condition referenced Immediately instrument channels In Table R12.2.1-1 for the inoperable for reasons instrument channel. other than Condition A. (continued)

Page 1-12.2.1-1 ACTIONS CONDITION

c. As required by Required C.1 Action A.2 or B.1 and referenced in Table R12.2.1-1.

AND C.2 AND C.3 C.4 D. Required Action and D.1 associated Completion Time of Condition C not met. E. As required by Required E.1 Action A.2 or B.1 and referenced in Table R12.2.1-1.

AND E.2 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED ACTION COMPLETION TIME Perform RSR 12.3.1.1 on at Prior to each release least two independent samples of the tanks contents.

Verify the release rate Prior to each release calculations and discharge valve line-up independently with at least two qualified members of the technical staff. Return instrument channel to 30 days OPERABLE status. OR Place Administrative Control 30 days Clearance order to Lock-Closed OWF201, RW DSCH Tank River DSCH Valve, to remove the ability to conduct a Liquid Radwaste Discharge.

Suspend release of radioactive Immediately effluents via this pathway. Analyze affected effluent grab Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> samples for principal gamma emitters and 1-131 at an LLD as specified in Table R12.3.1-2. Restore the instrument channel 30 days to OPERABLE status. Page 1-12.2.1-2 ACTIONS CONDITION F. As required by Required Action A.2 or 8.1 and referenced in Table R12.2.1-1.

G. ------NOTE-------

Required Action G.1 shall be completed if this Condition is entered. --------------------------------

Required Action C.3 or C.4, or E.2 and associated Completion Time not met. REQUIRED ACTION CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls COMPLETION TIME F .1 --------------NOTE---------------

Pump curves for instrument 3.a, or known valve positions for instrument 3.b, may be used to estimate flow. --------------------------------------------

Estimate the flow rate for the Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> release in progress via the affected pathway. F.2 With remote position indication Prior to each release. for OWL005 (BDFCV) not available, verify valve position locally. G.1 Explain why the inoperability In accordance with was not corrected in a timely Technical manner in the next Radioactive Specification

5.6.3. Effluent

Release Report. Page 1-12.2.1-3 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.2.1.1 Perform SOURCE CHECK. Prior to each release RSR 12.2.1.2 Perform CHANNEL FUNCTIONAL TEST. Prior to each Release RSR 12.2.1.3 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RSR 12.2.1.4 Perform SOURCE CHECK. 31 days RSR 12.2.1.5 Perform CHANNEL FUNCTIONAL TEST. Except for 92 days Instrument 3.b, the test shall also demonstrate that the instrument indicates measured levels above the alarm/trip setpoint and that the control room alarm annunciates and the affected pathway automatically isolates, as applicable, under the following conditions:

a. Loss of power, b Downscale failure, or c. Controls not set in Operate or High Voltage mode. RSR 12.2.1 .6 Perform CHANNEL CALIBRATION.

N/A (No longer applicable per E.C. #360580) RSR 12.2.1.7 Perform CHANNEL CALIBRATION 24 months RSR 12.2.1.8 12 months Perform POSITION INDICATION VERIFICATION Page 1-12.2.1-4 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.2.1-1 (page 1of2) Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT

1. Gamma Scintillation Monitor providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluents line 2. Gamma Scintillation Monitors providing Alarm but not providing Automatic Termination of Release a. Service Water Effluent line (Unit 1) b. Service Water Effluent line (Unit 2) c. RHR Service Water (line A) Effluent line (Unit 1) d. RHR Service Water (line B) Effluent Line (Unit 1) e. RHR Service Water (Line A) Effluent Line (Unit 2) f. RHR Service Water (Line B) Effluent Line (Unit 2) REQUIRED CHANNELS PER !INSTRUMENT 1 1 1 1 CONDITION REFERENCED FROM REQUIRED ACTION A.2 AND B.1 c E E E E E E SURVEILLANCE REQUIREMENTS RSR 12.2.1.1 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(8) RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(8) RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(8) RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7<8> RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7<aJ RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7 18) RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7 181 (continued) (a) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used, in order to demonstrate linearity of the original calibration.

This transfer calibration, combined with signal inputs, satisfies channel calibration and functional test requirements as implemented by station procedures.

Page 1-12.2.1-5 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.2.1-1(page2of2)

Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT

3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line b. OWL005 BDFCV Position Indication REQUIRED CHANNELS PER !INSTRUMENT 1 1 Page 1-12.2.1-6 CONDITION REFERENCED FROM REQUIRED ACTION A.2 AND B.1 F F SURVEILLANCE REQUIREMENTS RSR 12.2.1.2 RSR 12.2.1.3 RSR 12.2.1.7 RSR 12.2.1.8 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REC 12.2.2 The Radioactive Gaseous Effluent Instrumentation channels in Table R12.2.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of REC 12.4.1 are not exceeded.

APPLICABILITY:

According to Table R12.2.2-1 ACTIONS ----------------------------------------------------NOTE-----------------------------------------------------

Separate condition entry is allowed for each instrument channel. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend the release of Immediately instrument channels radioactive gaseous inoperable due to its effluents monitored by alarm/trip setpoint less the instrument channel. conservative than required.

OR A.2 Enter the Condition Immediately referenced in Table R12.2.2-1 for the instrument channel. B. One or more required B.1 Enter the Condition Immediately instrument channels referenced in Table R12.2.2-1 inoperable for reasons for the instrument channel. other than Condition A. (continued)

Page 1-12.2.2-1 ACTIONS CONDITION

c. As required by Required C.1 Action A.2 or B.1 and referenced in Table R12.2.2-1.

D. As required by Required D.1 Action A.2 or B.1 and referenced in Table R12.2.2-1.

AND D.2 AND D.3 E. As required by Required E.1 Action A.2 or B.1 and referenced in Table AND R12.2.2-1.

E.2 AND E.3 F. As required by Required F.1 Action A.2 or B.1 and referenced in Table R12.2.2-1.

AND F.2 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED ACTION COMPLETION TIME Place instrument channel in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> trip. Obtain grab samples. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> noble gas emitters.

following each grab sample Restore instrument channel to OPERABLE status. 30 days Obtain grab samples. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> noble gas emitters at an LLD following each grab as specified in Table sample R12.4.1-1.

Restore instrument channel 30 days to OPERABLE status. Establish CONTINUOUS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SAMPLING with auxiliary sampling equipment as required in Table R12.4.1-1.

Restore instrument channel 30 days to OPERABLE status. (continued)

Page 1-12.2.2-2 ACTIONS CONDITION G. As required by Required Action A.2 or B.1 and referenced in Table R12.2.2-1.

H. As required by Required Action A.2 or B.1 and referenced in Table R12.2.2-1.

I.

Required Action 1.1 shall be completed if this Condition is entered. --------------------------------

Required Action and associated Completion Time of Required Action D.3, E.3, F.2, or G.2 or H.4 not met. G.1 AND G.2 H.1 AND REQUIRED ACTION Estimate flow rate. CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls COMPLETION TIME Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Restore instrument channel 30 days to OPERABLE status. Verify offgas treatment Immediately system not bypassed.

H.2.1 Verify at least one Immediately Instrument 1.a channel OPERABLE.

OR H.2.2 Verify Required Actions for Immediately Condition D are met. AND H.3 Obtain and analyze grab Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. samples. AND H.4 Restore instrument channel 30 days to OPERABLE status. 1.1 Explain in the next In accordance with Radioactive Effluent Release Technical Report why the inoperability Specification 5.6.3. was not corrected within the time specified.

Page 1-12.2.2-3 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.2.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RSR 12.2.2.2 Perform SOURCE CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RSR 12.2.2.3 For Instruments 4.b and 4.c, not required to be performed until 7 days after Standby Gas Treatment is placed in operation.

Perform CHANNEL CHECK. 7 days RSR 12.2.2.4 Perform SOURCE CHECK. 31 days RSR 12.2.2.5 Perform CHANNEL FUNCTIONAL TEST. For 92 days Instruments 3.a (log monitor only) and 1.a, the test shall also demonstrate that the control room alarm annunciates and the automatic isolation capability of the affected pathway, as applicable, under the following conditions:

a. Upscale, b. Inoperative, or c. Downscale RSR 12.2.2.6 Perform CHANNEL FUNCTIONAL TEST. The test shall 92 days also demonstrate that the instrument indicates measured levels above the alarm setpoint and that the control room alarm annunciates on a Loss of Counts condition.

RSR 12.2.2.7 Perform CHANNEL CALIBRATION 24 months Page 1-12.2.2-4

1. a. Table R12.2.2-1 (page 1 of 2) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Radioactive Gaseous Effluent Monitoring Instrumentation APPLICABLE MODES OR REQUIRED CONDITION OTHER CHANNELS REFERENCED SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMEN'Pal CONDITIONS INSTRUMENT ACTION A.2 AND B.1 REQUIREMENTS Main Condenser Offgas Treatment System Effluent Monitoring System Noble Gas Activity Monitor -(b) 2 C, if only one required RSR 12.2.2.1 Providing Alarm and Automatic channel Inoperable RSR 12.2.2.2 Termination of Release RSR 12.2.2.5 (Post-Treat)

D, if both required RSR 12.2.2.7<9> channels inoperable

2. Main Stack Monitoring System a. Noble Gas Activity Monitor (Low or Mid Range WRGM) b. Iodine Sampler (Grab Sampler) c. Particulate Sampler (Grab Sampler) d. Effluent System Flow Rate Monitor e. Sampler Flow Rate Monitor (Low/Mid/Hi) (c) (c) (c) (c) (c) 1 1 (a) Equipment Part Numbers (EPN) are provided in Table R12.2.2-2. (b) During effluent releases via this pathway. (c) At all times. E F F G G RSR 12.2.2.1 RSR 12.2.2.4 RSR 12.2.2.6 RSR 12.2.2.7ldl RSR 12.2.2.3 RSR 12.2.2.3 RSR 12.2.2.1 RSR 12.2.2.5 RSR 12.2.2.7 RSR 12.2.2.1 RSR 12.2.2.5 RSR 12.2.2.7 (Continued) (d) The initial CHANNEL CALIBRATION shall be performed using one or more of the referenced radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used. (e) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, the initial calibration shall be used, in order to demonstrate linearity of the original calibration.

This transfer calibration, combined with signal inputs, satisfies channel calibration and functional test requirements as implemented by station procedures.

Page 1-12.2.2-5

3. 4. CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.2.2-1

{page 2 of 2) Radioactive Gaseous Effluent Monitoring Instrumentation APPLICABLE MODES OR REQUIRED CONDITION OTHER CHANNELS REFERENCED SPECIFIED PER FROM REQUIRED SURVEILLANCE CONDITIONS INSTRUMENT ACTION A.2 AND 8.1 REQUIREMENTS Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup System) a. Noble Gas Activity Monitor (f) H RSR 12.2.2.1 RSR 12.2.2.4 RSR 12.2.2.5 RSR 12.2.2.7(dl Standby Gas Treatment (SGT) Monitoring System a. Noble Gas Activity Monitor (Low (g) E RSR 12.2.2.1 or Mid Range WRGM) RSR 12.2.2.4 RSR 12.2.2.6 RSR 12.2.2.?'dl

b. Iodine Sampler (Grab Sampler) (g) F RSR 12.2.2.3 c. Particulate Sampler (Grab (g) F RSR 12.2.2.3 Sampler) d. Effluent System Flow Rate (g) G RSR 12.2.2.1 Monitor RSR 12.2.2.5 RSR 12.2.2.7 e. Sampler Flow Rate Monitor (g) G RSR 12.2.2.1 (Low/Mid/Hi)

RSR 12.2.2.5 RSR 12.2.2.7 (a) Equipment Part Numbers (EPN) are provided in Table R12.2.2-2. (d) The initial CHANNEL CALIBRATION shall be performed using one or more of the referenced radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used. (f) During operation of the main condenser air ejector. (g) During operation of SGT. Page 1-12.2.2-6 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.2.2-2 (page 1 of 2) Radioactive Gaseous Effluent Monitoring Instrumentation Applicability INSTRUMENT A. Unit 1 Applicable Instruments. 1. Main Condenser Offgas Treatment System Effluent Monitoring System a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release 2. Main Stack Monitoring System a. Noble Gas Activity Monitor (Low or Mid Range WRGM) b. Iodine Sampler (Grab Sampler) c. Particulate Sampler (Grab Sampler) d. Effluent System Flow Rate Monitor e. Sampler Flow Rate Monitor (Low/Mid/Hi)

3. Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup System) a. Noble Gas Activity Monitor 4. Standby Gas Treatment (SGT) Monitoring System a. Noble Gas Activity Monitor (Low/Mid Range WRGM) b. Iodine Sampler (Grab Sampler) c. Particulate Sampler (Grab Sampler) d. Effluent System Flow Rate Monitor e. Sampler Flow Rate Monitor (Low/Mid/Hi)

EPNS OF APPLICABLE EQUIPMENT 1D18-N903A, K901A, K601A, R601 1018-N903B,K901B,K601B,R601 OD18-N514, R517, R518 Low Range OD18-N515, R517, R518 Mid Range OFT-VR019, OFY-VR019 AND 019A, OFR-VR019, 0018-K510, OD18-R518 OD18-N527, OD18-N528, OD18-R518 Low OD18-N530, OD18-N531, OB18-R518 Mid/Hi 1D18-N002, K613, R604, or 1018-N012,K600,R605 OD18-N511, R515, R516 Low Range OD18-N512, R515, R516 Mid Range 1FT-VG009, 1FY-VG009, 1FR-VG-009 OD18-N521, OD18-N522, OD18-R516 Low OD18-N524, OD18-N525, OB18-R516 Mid/Hi (Continued)

Page 1-12.2.2-7 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.2.2-2 (page 2 of2) Radioactive Gaseous Effluent Monitoring Instrumentation Applicability INSTRUMENT B. Unit 2 Applicable Instruments

1. Main Condenser Offgas Treatment System Effluent Monitoring System a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release 2. Main Stack Monitoring System a. Noble Gas Activity Monitor (Low or Mid Range WRGM) b. Iodine Sampler (Grab Sampler) c. Particulate Sampler (Grab Sampler) d. Effluent System Flow Rate Monitor e. Sampler Flow Rate Monitor (Low/Mid/Hi)
3. Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup System) a. Noble Gas Activity Monitor 4. Standby Gas Treatment (SGT) Monitoring System a. Noble Gas Activity Monitor (Low/Mid Range WRGM) b. Iodine Sampler (Grab Sampler) c. Particulate Sampler (Grab Sampler) d. Effluent System Flow Rate Monitor e. Sampler Flow Rate Monitor (Low/Mid/Hi)

EPNS OF APPLICABLE EQUIPMENT 2D18-N903A,K901A,K601A,R601 2018-N903B, K901 B, K601 B, R601 OD18-N514, R517, R518 Low Range OD18-N515, R517, R518 Mid Range OFT-VR019, OFY-VR019 AND 019A, OFR-VR019, OD18-K510, OD18-R518 OD18-N527, OD18-N528, OD18-R518 Low OD18-N530, OD18-N531, OB18-R518 Mid/Hi 2D18-N002, K613, R604, or 2D18-N012,K600,R605 OD18-N511, R515, R516 Low Range OD18-N512, R515, R516 Mid Range 2FT-VG009, 2FY-VG009, 2FR-VG-009 OD18-N521, OD18-N522, OD18-R516 Low OD18-N524, OD18-N525, OB18-R516 Mid/Hi Page 1-12.2.2-8 12.3 LIQUID EFFLUENTS 12.3.1 Liquid Effluent Concentration CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REC 12.3.1 The concentration of radioactive material released from the site to areas at or beyond the SITE BOUNDARY shall be limited to: a. 10 times the concentration specified in 10 CFR 20.1001-20.2402 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases; and b. the values listed in Table R12.3.1-1 for total activity concentration for all dissolved or entrained noble gases. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of radioactive A.1 Initiate action to restore the Immediately material released to areas at concentration to within or beyond the SITE limits. BOUNDARY not within limits. B. Requirements of RSR B.1 Enter Condition A of Immediately 12.3.1.4 not met. Technical Requirements Manual Section 3.7.d. SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.3.1.1 Determine radioactivity content of each radioactive liquid waste batch by sampling and analysis in accordance with Table R12.3.1-2.

RSR 12.3.1.2 Perform post-release analysis of samples composited from batch releases in accordance with Table R 12.3.1-2.

RSR 12.3.1.3 Determine radioactivity concentration of liquids discharged from continuous release points by sampling and analysis in accordance with Table R12.3.1-2.

Page 1-12.3.1-1 FREQUENCY In accordance with the Radioactive Liquid Waste Sampling and Analysis Program. In accordance with the Radioactive Liquid Waste Sampling and Analysis Program. In accordance with the Radioactive Liquid Waste Sampling and Analysis Program. (Continued)

SURVEILLANCE REQUIREMENTS RSR 12.3.1.4 Not required to be performed until 7 days after the start of addition if tank(s) is empty at the beginning of the addition.

Verify the quantity of radioactive material of each outside temporary tank is low enough to ensure that in the event of an uncontrolled release of the tanks contents, the resulting concentration would be less than the REC limits. Page 1-12.3.1-2 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 7 days when radioactive material is being added to the tank(s). Once within 7 days after each completion of addition of radioactive material to the tank(s).

  • NUCLIDE Kr-85m Kr-85 Kr-87 Kr-88 Ar-41 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Table R12.3.1-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE ALLOWABLE CONCENTRATION (uCi/ml)* 2 x 10-4 5 x 10 4 4x10-5 9 x 10-5 7x10-5 7 x 10-4 5 x 10-4 6 x 10-4 2 x 10 4 2 x 10-4 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, density = 1.0 glee and Pw/Pt = 1.0. Page 1-12.3.1-3 Table R12.3.1-2(Page1 of4) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY OF DETECTION TYPE FREQUENcy<

9> FREQUENcy<

9> ANALYSIS (LLD)<a> (uCi/ml) A. Batch Waste Prior to each Prior to each release, Principal Gamma 5x10*1 Release Tanks(d) release, Each Each Batch Emitters 1 1l Batch 1-131 1x10-a Prior to each 31 days H-3 1x1Q" 5 release, Each Composite (b) Batch Gross Alpha 1x10*7 Prior to each 92 days Sr-89, Sr-90 5x10-a release, Each Composite (bl Batch Fe-55 1x10-a Prior to each release, One 31 days Dissolved

& Batch per 31 Entrained Gases 1x10" 5 days {Gamma Emitters}

B. Plant Continuous

?days 1-131 1x10-a Releases<a>

CONTINUOUs<c>

Cooling Pond Composite (c) Principal Gamma 5x10*7 Slowdown Emitters 1 1l 31 days 31 days Dissolved

& 1x10*5 Entrained Gases Grab Sample {Gamma Emitters}

CONTINUOUs<c>

31 days H-3 1x10*5 Composite<c>

Gross Alpha 1x10*7 CONTINUOus<c>

92 days Sr-89, Sr-90 5x10-a Composite<c>

Fe-55 1x10-a Page 1-12.3.1-4 Table R12.3.1-2 (Page 2 of 4) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation:

Where: LLD= 4.66Sb E

  • V
  • 2.22xl0 6
  • Y
  • e<-Mz> LLD= the a priori lower limit of detection (microcurie per unit mass or volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), JB B =background sum (counts) t =count time (minutes)

E =the counting efficiency (counts per transformation), V =the sample size (units of mass or volume), 2.22 x 10 6 = the number of transformations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A.= the radioactive decay constant for the particular radionuclide and for composite samples, and At = the elapsed time between the midpoint of sample collection and the time of counting (for plant effluents, not environmental samples).

For batch samples taken and analyzed prior to release, At is taken to be zero. The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y, and At shall be used in the calculation.

Alternate LLD Methodology An alternate methodology for LLD determination follows and is similar to the above LLD equation:

LLD= (2.71+4.65.fii)*Decay E *q *b* Y *t*(2.22xl0

6) Page 1-12.3.1-5 Table R12.3.1-2 (Page 3of4) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where: B =background sum (counts) E = counting efficiency q =sample quantity (mass or volume) b =abundance (if applicable)

Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 10 6 = number of disintegrations per minute per microcurie 2.71 + 4.65-VB = k 2 + (2k -V2 -VB), and k = 1.645 (k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide is present when it is not or that the nuclide is not present when it is.) A.= radioactive decay constant (units consistent with 6t, RT and Td) at = "delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consistent with A.) RT = elapsed real time, or the duration of the sample count (units consistent with A.) T d = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with A.) The LLD may alternately be determined using installed radioanalytical software, if available.

In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis, and during counting), this alternate method will result in a more accurate determination of the LLD. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Page 1-12.3.1-6 Table R12.3.1-2 (Page 4 of 4) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sample employed results in a specimen which is representative of the liquids released.

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release. d. A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
e. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, at the 95% confidence level, together with the above nuclides, shall also be identified and reported.

g. The provisions of RSR 12.0.2 and RSR 12.0.3 are applicable to the Radioactive Liquid Waste Sampling and Analysis Program. Page 1-12.3.1-7 12.3 LIQUID EFFLUENTS 12.3.2 Dose from Liquid Effluents CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REC 12.3.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site shall be limited to: a. 1.5 mrem to the total body and 5.0 mrem to any organ during any calendar quarter; and b. 3.0 mrem to the total body and 10.0 mrem to any organ during any calendar year. APPLICABILITY:

At all times. Page 1-12.3.2-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE----------

A.1 Submit a Report, pursuant to 30 days following the Required Action A.1 shall 1 OCFR50, Appendix I, Section end of the quarter in be completed if this IV.A, to the NRC that identifies which the release Condition is entered. causes for exceeding limits, occurred radiological impact on finished ---------------------------------

drinking water supplies at the Calculated dose not nearest downstream drinking within limits. water source and defines actions to be taken to reduce releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the cumulative dose or dose commitment is within the limits of REC 12.3.2.b.

B. Calculated dose B.1 Enter Condition A of REC 12.4.7. Immediately exceeds two times (2x) the limits. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RS R 12 .3.2.1 ----------------------------NOTE-------------------------

Only required to be performed if liquid releases have occurred since the last performance of this RSR. Calculate cumulative dose contributions from liquid effluents 31 days in accordance with the ODCM. Page 1-12.3.2-2 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Radwaste Treatment Systems REC 12.3.3. The Liquid Radwaste Treatment System shall: a. Be OPERABLE; and b. Be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, from the site would exceed 0.06 mrem to the total body or 0.2 mrem to any organ when averaged over 31 days. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Liquid Radwaste A.1 Restore Liquid Radwaste 31 days Treatment System Treatment System to inoperable.

OPERABLE status. B. ------NOTE--------

B.1 Submit a report to the NRC 30 days Required Action B.1 that includes inoperable shall be completed if this equipment or subsystem Condition is entered. identification and reason, ------------------

action taken to restore the Untreated liquid waste inoperable equipment to release in progress.

OPERABLE status, and a summary description of the action(s) taken to prevent AND recurrence.

Projected dose not within limits. c. --------NOTE-------

C.1 Submit a report to the NRC 30 days Required Action C.1 that includes inoperable shall be completed if this equipment or subsystem Condition is entered. identification and reason, --------------------

action taken to restore the Required Action and inoperable equipment to Associated Completion OPERABLE status, and a time of Condition A not summary description of the met. action(s) taken to prevent recurrence.

Page 1-12.3.3-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.3.3.1 -----------------------NOTE--------------------------

Only required to be performed if liquid releases are planned and RSR has not been performed in the last 38 days 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. FREQUENCY Determine projected doses due to liquid releases in 31 days accordance with the ODCM methods. RSR 12.3.3.2 -----------------------NOTE--------------------

Not required to be performed if Liquid Radwaste Treatment System has been used to process radioactive liquid effluents in the last 115 days. Operate the Liquid Radwaste Treatment System equipment for at least 30 minutes. Page 1-12.3.3-2 92 days if a portable (vendor supplied) waste treatment system is being used. 180 days if a portable supplied) waste treatment system is not being used.

CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.1 Gaseous Effluent Dose Rates REC 12.4.1 The dose rate at or beyond the SITE BOUNDARY due to radioactive materials in gaseous effluents released from the site shall be limited to the following:

a. For noble gases, 500 mrem/year to the total body and 3000 mrem/year to the skin; and b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives

> 8 days, 1500 mrem/year to any organ via the inhalation pathway. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate not within limits. A.1 Initiate action to Immediately decrease release rates to maintain dose rates within limits. SURVEILLANCE REQUIREMENTS RSR 12.4.1.1 SURVEILLANCE Verify the dose rates due to noble gases, iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents is within limits utilizing the methodology and parameters of the ODCM limits by obtaining and analyzing representative samples in accordance with Table R12.4.1-1.

Page 1-12.4.1-1 FREQUENCY In accordance with the Radioactive Gaseous Waste Sampling and Analysis Program GASEOUS RELEASE TYPE A. Containment Vent and Purge System Ii B. Main Vent Stack c. Standby Gas Treatment System D. Main Vent Stack And Standby Gas Treatment Systemc CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.4.1-1(Page1of5)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCy<il FREQUENCy<il ANALYSIS (µCi/ml)8 Prior to each Prior to each Principal Gamma release release Emitters 9 1x10 4 Each Purgeb, k Each Purgeb Grab Sample 31 daysb,k H-3 1x10-a 31 daysb 31 daysb Principal Gamma 1x10 4 Grab Sample Emittersg 7 daysb,a 7 daysb,a H-3 1x10-a Grab Sample 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sc 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sc Principal Gamma 1x10 4 Grab Sample Emitters 9 7 daysd 1-131 1x10-12 CONTINUOUSf Charcoal 1x10-10 Sample 1-133 CONTINUOUSf 7 daysd Principal Gamma 1x10-11 Particulate Emitters 9 (l-131, Sample Others) 31 days CONTINUOUSf Composite Gross Alpha 1x10-11 Particulate Sample 92 days CONTINUOUSf Composite Sr-89,Sr-90 1x10-11 Particulate Sample Noble Gas Noble Gases, CONTINUOUSf Gross Beta or 1x10-a Monitor Gamma Page 1-12.4.1-2 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls TableR12.4.1-1 (Page2of5)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation):

LLD= 4.66Sb E

  • V
  • 2.22xl 0 6
  • Y
  • e<-Mt> Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), t B = background sum (counts) t =count time (minutes)

E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22x10 6 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A. is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y, and At shall be used in the calculation.

Alternate LLD Methodology An alternate methodology for LLD determination follows and is similar to the above LLD equation:

LLD= (2.71+4.65.JB)*Decay E *q*b* Y *t*(2.22xl0

6) Page 1-12.4.1-3 Where: B E q b y t CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.4.1-1(Page3 of 5) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION =background sum (counts} = counting efficiency

=sample quantity (mass or volume} =abundance (if applicable}

=fractional radiochemical yield or collection efficiency (if applicable}

=count time (minutes}

2.22 x 10 6 = number of disintegrations per minute per microcurie 2.71 + 4.65vB = k 2 + (2k v2 vB}, and k = 1.645 Decay At RT (k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide is present when it is not or that the nuclide is not present when it is.} = eM 1 [A.RT/(1-e*ART}][A.

Td /(1-e*Hd}]

if applicable

= radioactive decay constant (units consistent with At, RT and T d} = "delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consistent with A.} = elapsed real time, or the duration of the sample count (units consistent with A.} = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with A.} The LLD may alternately be determined using installed radioanalytical software, if available.

In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis, and during counting}, this alternate method will result in a more accurate determination of the LLD. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

b. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. Page 1-12.4.1-4 Table R12.4.1-1 (Page 4 of 5) CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION c. Whenever there is flow through the SGT. If SGT is run more than 2 hrs in a 24-hour period, ensure a noble gas sample is obtained prior to securing SGT and particulate and iodine samples are taken within 24 hrs after securing SGT. A 2-hour run ensures required sample lower limits of detection are met for particulates and iodine. A SGT run of less than 2 hrs is not a significant contribution to offsite dose and requires no sampling.
d. Samples shall be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following each shutdown, startup, or thermal power level change exceeding 20% of RATED THERMAL POWER in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased by more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. e. Tritium grab samples shall be taken at least once per 7 days from the plant vent to determine tritium releases in the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. If there is no spent fuel in the fuel pool, sampling and analysis of tritium grab samples shall be performed at least once per 31 days. f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with RECs 12.4.1, 12.4.2 and 12.4.3. g. The principal gamma emitters for which the LLD specification applies include the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, at the 95% confidence level, together with the above nuclides, shall also be identified and reported.

h. The drywell tritium and noble gas samples and associated purge calculations are required when the Unit is at power (i.e. critical) and for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of purging activities following shutdown.

The drywall tritium and noble gas sample results are valid for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> from sample time if 1) the drywall radioactivity monitors have not indicated an increase in airborne or gaseous radioactivity, and 2) the drywall equipment and floor drain sump pumps run times have not indicated an increase in leakage in the drywall since the sample was taken, and 3) conditions are such that activity can be calculated for the radionuclide concentration at the time of the release. If there is any reason to suspect that gaseous radioactivity levels have changed in the drywall that would compromise the calculated, or estimated, radionuclide concentrations at the time of the release, since the last sample (30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />), a new sample and analyses should be requested prior to starting a drywall purge to meet the intent of providing current analyses to reflect actual activity released to the environment.

If a known steady state leakage condition exists in the drywall it is possible to calculate a safe and accurate release package. Final release quantification will be based on calculated radionuclide concentrations at the time of the actual release. Page 1-12.4.1-5 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.4.1-1 (Page 5 of 5) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION If the drywall is PURGED in accordance with the ODCM definition, both noble gas and tritium sampling along with the appropriate purge calculations must be completed before the purge begins. If the drywall is simply VENTING in accordance with the ODCM definition, no sample is required before venting. i. The provisions of RSR 12.0.2 and RSR 12.0.3 are applicable to the Radioactive Gaseous Waste Sampling and Analysis Program. j. Not used. k. Drywell tritium results obtained during the previous 31 days may be used in the purge calculations, in lieu of actual results (from most recent purge sample), to allow completion of the purge calculations in an expeditious manner permitting a timely drywall entry, if necessary.

However, the substitute tritium results are valid for use only if the three (3) conditions set forth in Note "h" surrounding sample validity are met. In addition, the substitute results do not change the requirements for tritium sampling frequency (Prior to each release Each Purge) per Table R12.4.1-1.

The most recent purge sample tritium analyses should be completed, and the associated purge calculations should be updated as soon as possible following sampling.

For reporting purposes (i.e. annual reports, etc.), actual results are used, when possible.

Page 1-12.4.1-6 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.2 Dose from Noble Gases REC 12.4.2 The air dose due to noble gases in gaseous effluents released from each reactor unit from the site shall be limited to the following:

a. For gamma radiation, 5 mrad during any calendar quarter and 10 mrad during any calendar year; and b. For beta 10 mrad during any calendar quarter 20 mrad during any calendar year. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION A. ---------NOTE----------

A.1 Submit a report to the NRC, Required Action A.1 shall pursuant to 1 OCFR50 be completed if this Appendix I Section IV.A, that Condition is entered. identifies causes for exceeding limits, defines ------------------------------------

corrective actions to be Calculated air dose not taken to reduce the releases, within limits. and proposed corrective actions to assure that subsequent releases are within limits. 8. Calculated air dose 8.1 Enter Condition A of REC exceeds two times (2x) the 12.4.7. limits. SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.4.2.1 Determine cumulative dose contributions for the current calendar quarter and current calendar year in accordance with the ODCM. Page 1-12.4.2-1 COMPLETION TIME 30 days following the end of the quarter in which the release occurred Immediately FREQUENCY 31 days CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.3 Dose From Iodine -131, Iodine -133, Tritium, and Radioactive Materials in Particulate Form REC 12.4.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form, with half-lives

> 8 days, in gaseous effluents released from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to: a. 7 .5 mrem to any organ during any calendar quarter; and b. 15 mrem to any organ during any calendar year. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------NOTE--------

A.1 Submit a report to the NRC, 30 days following the Required Action A.1 shall be pursuant to 1 OCFR50 end of the quarter in completed if this Condition is Appendix I Section IV.A, which the release entered. that identifies causes for occurred exceeding limits, defines --------------------------------------

corrective actions to be Calculated dose not within taken to reduce the limits. releases, and proposed corrective actions to assure that subsequent releases are within limits. B. Calculated dose exceeds B.1 Enter Condition A of Immediately two times (2x) the limits. REC 12.4.7. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.3.1 Determine cumulative dose contributions for the current 31 days calendar quarter and calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in accordance with the methodology and parameters in the ODCM. Page 1-12.4.3-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.4 GASEOUS RADWASTE TREATMENT SYSTEM REC 12.4.4 The GASEOUS RADWASTE (OFF-GAS)

TREATMENT SYSTEM shall be OPERABLE and in operation.

APPLICABILITY:

During Main Condenser Air Ejector system operation.

ACTIONS CONDITION REQUIRED ACTION A GASEOUS RADWASTE A.1 Restore system to TREATMENT SYSTEM OPERABLE status. inoperable.

AND OR A.2 Place system in operation.

GASEOUS RADWASTE TREATMENT SYSTEM not in operation.

B. ----------NOTE---------

B.1 Submit a report to the NRC Required Action B.1 shall that includes defective be completed if this equipment or subsystem Condition is entered. identification and inoperability cause, actions ------------------------------------

taken to restore the Required action and inoperable equipment to Associated Completion OPERABLE status, and Time not met. summary description of actions taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.4.4.1 Verify the GASEOUS RADWASTE TREATMENT SYSTEM is in operation.

Page 1-12.4.4-1 COMPLETION TIME 7 days 30 days FREQUENCY 7 days CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.5 VENTILATION EXHAUST TREATMENT SYSTEM REC 12.4.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall; a. BE OPERABLE; and b. be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses from each reactor unit from the site would exceed 0.3 mrem to any organ, when average over 31 days. APPLICABILITY:

At all times. ----------------------------------------------------------NOl"E-----------------------------------------------------------

Separate Condition entry is allowed for each VENTILATION EXHAUST TREATMENT system pathway. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore system to 31 days VENTILATION EXHAUST OPERABLE status. TREA l"MENT SYSTEMS inoperable.

B.

B.1 Submit a report to the NRC 30 days Required Action B.1 shall that includes inoperable be completed if this equipment or subsystem condition is entered. identification and reason for inoperability, actions ------------------------------------

taken to restore the Untreated gaseous waste inoperable equipment to release in progress.

OPERABLE status, and summary description of AND actions taken to prevent a recurrence.

Projected dose not within limits. (continued)

Page 1-12.4.5-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE----------

C.1 Required Action C.1 shall Submit a report to the NRC 30 days that includes inoperable be completed if this Condition is entered. Required Action and associated Completion Time of Condition A not met. SURVEILLANCE REQUIREMENTS equipment or subsystem identification and reason for inoperability, actions taken to restore the inoperable equipment to OPERABLE status, and summary description of actions taken to prevent a recurrence.

SURVEILLANCE RSR 12.4.5.1 Project doses due to gaseous releases from the site in accordance with the ODCM. RSR 12.4.5.2 ----------------------NOTE---------------------

Not required to be performed if the VENTILATION EXHAUST TREATMENT SYSTEM has been used to process gaseous effluents in the last 115 days. OPERA TE each required VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes. Page 1-12.4.5-2 FREQUENCY 31 days 92 days CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.6 MARK II Containment REC 12.4.6 VENTING or PURGING of the containment drywall shall be: a. through the Primary Containment Vent and Purge System, or b. through the Standby Gas Treatment (SGT) System. APPLICABILITY:

During drywall VENTING or PURGING. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Above requirements not met. A.1 Suspend all drywall Immediately VENTING and PURGING. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.6.1 Verify containment drywall is aligned for VENTING or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> PURGING through the Primary Containment Vent and Purge System or the SGT System. RSR 12.4.6.2 ---------------------NOTE-------------------

Only required to be met when in MODES 1, 2, or 3. Verify: a. Both SGT trains are OPERABLE, and b. Only one of the SGT System trains to be used for PURGING. Page 1-12.4.6-1 Prior to PURGING through the SGT System.

CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.7 Total Dose REC 12.4.7 The dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from all uranium fuel cycle sources over 12 consecutive months shall be limited to: a. $ 25 mrem to the total body; and b. $ 75 mrem to the thyroid; and c. $ 25 mrem to any other organ. APPLICABILITY:

At all times. ACTIONS CONDITION A. -------NOTE---------

Required Action A.1 and A.2 shall be completed if this Condition is entered. As required by Required Action B.1 of REC 12.3.2, 12.4.2, or 12.4.3. Calculated Total Dose not within limits. REQUIRED ACTION A.1 Submit a report to the NRC (Director, Nuclear Reactor Regulation) that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits to include estimates of radiation exposure to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for a 12 consecutive month period that includes the release(s) covered by this report. Page 1-12.4.7-1 COMPLETION TIME 30 days (continued)

ACTIONS CONDITION A. (continued)

SURVEILLANCE REQUIREMENTS CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED ACTION A.2 ---------NOTE-----------

Only applicable if the release condition resulting in violation of 40 CFR 190 has not been corrected.

COMPLETION TIME Submit a request for a 30 days variance in accordance with 40 CFR 190, including the specified information of 40 CFR 190.11. SURVEILLANCE FREQUENCY RSR 12.4. 7 .1 Determine cumulative dose contributions from direct radiation and liquid and gaseous effluents in accordance with the ODCM. Page 1-12.4.7-2 31 days CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.8 Main Condenser REC 12.4.8 The release rate of the sum of the activities from the noble gases measured prior to the holdup line shall be limited to 3.4 x 10 5 µCi/sec after 30 minutes decay. APPLICABILITY:

MODE 1, MODES 2 and 3 with any steam line not isolated and steam jet air ejectors (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Release rate of the sum of A.1 Restore the release rate to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the activities from noble within limit. gases prior to the holdup line not within the limits. B. Required Action and B.1 Isolate all main steam 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion lines. Time not met. OR B.2 Isolate the SJAE. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR B.3.1 MODE3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND B.3.2 MODE4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Page 1-12.4.8-1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.4.8.1 Monitor the noble gas radioactivity rate prior to the holdup line in accordance with the ODCM and Table R12.2.2-1 RSR 12.4.8.2 -----------------NOTE----------------------

Not required to be performed until 31 days after any Main Steam line not isolated and SJAE in operation.

Verify the release rate of the sum of the activities from noble gases prior to the holdup line is within limits by performing an isotopic analysis of a representative sample of gases taken prior to the holdup line. Page 1-12.4.8-2 FREQUENCY CONTINUOUSLY Once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a increase in the nominal steady state fission gas release from the primary coolant, as indicated by the off gas treatment Noble Gas Activity Monitor, after factoring out increases due to changes in THERMAL POWER level 31 days CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE 12.4.9 Dose Limits for MEMBERS OF THE PUBLIC REC 12.4.9 Operations shall be conducted such that: a. Total Effective Dose Equivalent (TEDE) to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem/year; and b. The dose in any unrestricted area from external sources does not exceed 2 mrem in any one hour. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Submit a report to the NRC 30 days Required Action A.1 shall be in accordance with completed if this Condition is 10 CFR 20.2203. entered. -----------------------------------

Dose limit of REC Item a. exceeded.

B. --------NOTE--------

B.1 Submit a report to the NRC 30 days Required Action B.1 shall be in accordance with completed if this Condition is 10 CFR 20.2203. entered. -----------------------

Dose limit of REC Item b. exceeded.

Page 1-12.4.9-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls FREQUENCY RSR 12.4.9.1 Calculate the TEDE to individual MEMBERS OF THE PUBLIC in accordance with the ODCM. 12 months RSR 12.4.9.2 Determine and/or evaluate direct radiation exposures in unrestricted areas. Page 1-12.4.9-2 12 months CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Radiological Environmental Monitoring Program (REMP) REC 12.5.1 The REMP shall be conducted as specified in Table R12.5.1-1.

APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION A. --------------NOTE--------------

A.1 Required Action A.2 shall Initiate action to identify suitable, alternative sampling media and/or specific locations for obtaining replacement samples for the pathway of interest and add them to the REMP. Delete locations from which samples are unavailable.

be completed if this Condition is entered. Sample type or location(s) required by Table R12.5.1-1 permanently unavailable.

A.2 Prepare and submit a controlled version of the ODCM, in the next Annual Radiological Environmental Operating Report (REOR) including revised figures and tables reflecting the new location(s) with supporting information identifying the sample unavailability cause and justification of the new sampling location(s).

Page 1-12.5.1-1 COMPLETION TIME Immediately In accordance with Technical Specification 5.6.2 (continued)

ACTIONS CONDITION B. -------------NOTE--------------

Required Action B.1 shall be completed if this Condition is entered. ------------------------------------

Level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeds the reporting levels of Table R 12.5.1-2 when averaged over any calendar quarter. C. -------------NOTE--------------

Required Action C.1 shall be completed if this Condition is entered. -------------------

More than one radionuclide in Table R 12.5.1-2 detected in the sampling medium. AND C1 C2 --+--+ ... 1.0 RL1 RL2 where; C = concentration RL = reporting level. B.1 C.1 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED ACTION COMPLETION TIME Submit a report to the NRC 30 days that identifies the cause(s) for exceeding the limits and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of REC 12.3.2, 12.4.2 or 12.4.3. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. Submit a report to the NRC 30 days that identifies the cause(s) for exceeding the limits and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of REC 12.3.2, 12.4.2 or 12.4.3. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. (continued)

Page 1-12.5.1-2 ACTIONS CONDITION D. ------------NOTE-------------

Required Action D.1 and D.2 shall be completed if this Condition is entered. Radionuclides other than those in Table R12.5.1-2 are detected.

AND The potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is greater than or equal to the calendar year limits of REC 12.3.2, 12.4.2, or 12.4.3. CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED ACTION D.1 ----------------NOTE---------------

Only required when the measured levels of radioactivity are the result of plant effluents.

COMPLETION TIME Submit a report to the NRC 30 days that identifies the cause(s) for exceeding the limits and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. D.2 Only required when the radionuclides detected are not the result of plant effluents.

Describe the condition in the next Annual REOR. Page 1-12.5.1-3 In accordance with Technical Specification 5.6.2. (continued)

ACTIONS CONDITION E. ---------NOTE---------

E.1 Required Action E.1 shall be completed if this Condition is entered. RSR 12.5.1.1 not met. CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls REQUIRED COMPENSATORY MEASURE Prepare and submit to the NRC, in the next Annual REOR, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Page 1-12.5.1-4 COMPLETION TIME In accordance with Technical Specification 5.6.2.

CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE RSR 12.5.1.1 ------------------------------NOTES---------------------------

1. Deviations to the sampling schedule for the following reasons may occur and the RSR still be considered met provided the deviations are described in the next Annual REOR: a. specimens are unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of sampling equipment, or b. a person or business who participates in the program goes out of business or can no longer provide samples, or c. a contractor omission which is corrected as soon as discovered.
2. Malfunctioning equipment shall be corrected/replaced and replacement suppliers shall be found, as applicable, as soon as practicable.

Collect and analyze samples in accordance with Table R12.5.1-1 and the ODCM to the detection capabilities required by Table R12.5.1-3.

Page 1-12.5.1-5 FREQUENCY In accordance with the Radiological Environmental Monitoring Program EXPOSURE PATHWAY AND/ OR SAMPLE 1. Airborne Radioiodine and Particulates Table R12.5.1-1(Page1 of6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION SAMPLE LOCATIONsl 1> FREQUENCY 1111 Samples from a total of eight locations:

CONTINUOUS sampler operation with particulate sample a. Indicator-Near Field collection weekly, or more frequently if required due to dust Four samples from locations within 4.0 km {2.5 mi) in loading, and radioiodine canister different sectors. collection weekly. b. Indicator-Far Field Four additional locations within 4.0 to 10 km {2.5 to 6.2 mi) in different sectors. c. Control One sample from a control location within 10 to 30 km (6.2 to 18.6 mi). Page 1-12.5.1-6 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls TYPE AND FREQUENCY OF ANAL YSIS 1111 Radioiodine Canister:

1-131 analysis weekly on near field samples and control 121 samples. Particulate SamE!ler:

Gross beta analysis weekly filter change l and gamma isotopic analysis 141 quarterly on composite filters by location on near field and control 121 samples. {continued)

EXPOSURE PATHWAY AND/ OR SAMPLE 2. Direct Radiation 1" 1 Table R12.5.1-1(Page2of6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION SAMPLE LOCATIONS' 11 FREQUENCY 1111 Forty routine monitoring stations, either with a Field Quarterly Dosimeter or with one instrument for measuring dose rate continuously, placed as follows: a. Indicator-Inner Ring (100 Series) One in each meteorological sector, in the general area of the SITE BOUNDARY (within 0.1 to 2.0 miles; 0.2 to 3.2 km); b. Indicator-Outer Ring (200 Series) One in each meteorological sector, within 4.8 to 10 km (3 to 6.2 mi); c. Other One at each Airborne location given in part 1.a. and 1.b. The balance of the Field Dosimeters to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Exelon Nuclear employees have routine access. d. Control One at each airborne control location given in part 1.c. Page 1-12.5.1-7 CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls TYPE AND FREQUENCY OF ANAL YSIS 1111 Gamma dose on each Field Dosimeter quarterly. (continued)

EXPOSURE PATHWAY AND/ OR SAMPLE 3. Waterborne

a. Ground/Well
b. Drinking 171 c. Surface Water 111 d. Sediment a. a. a. CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.5.1-1(Page3of6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY SAMPLE LOCATIONS' 11 FREQUENCY 1111 OF ANAL YSIS 1111 Indicator Quarterly Gamma isotopic 141 and tritium analysis quarterly.

Samples from two sources only if likely to be affected.

161 Indicator Grab samples weekly. Gross beta and gamma isotopic analyses 14 l on One Sample from each community drinking water monthly composite; tritium supply that could be affected by the station discharge analysis on quaterly within 10 km (6.2 mi) downstream of discharge.

composite.

1-131 on each composite when calculated dose for water consumption

> 1 mrem/year.

If no community water supply (Drinking Water) exists Grab samples weekly. Gross beta and gamma within 10 km downstream of discharge then surface isotopic analyses 14 l on water sampling shall be performed.

monthly composite; tritium lndicator 171 analysis on quarterly composite.

One surface sample downstream of discharge.

b. Control\7J One surface sample upstream of discharge.
a. Indicator Semiannually Gamma isotopic At least one sample from downstream 17> area within 1 O analysis 14 l semiannually.

km (6.2 mi) of discharge. (continued)

Page 1-12.5.1-8 I I I I I I EXPOSURE PATHWAY AND/ OR SAMPLE 4. Ingestion

a. Milk(B) b. Fish c. Food Products CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 4 of 6} RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY SAMPLE LOCATIONs<

1> FREQUENCY 1111 OF ANAL YSIS 1111 a. Indicator Biweekly when animals are on Gamma isotopic'41 and Samples from milking animals from a maximum pasture (May through October), 1-131 191 analysis on each monthly at other times sample. of three locations within 10 km (6.2 mi) distance. (November through April). b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi). a. Indicator Two times annually.

Gamma isotopic Representative samples of commercially and analysis 141 on edible portions recreationally important species in discharge area, and representative samples from the LaSalle Lake. b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.

a. Indicator Annually Gamma isotopic 141 and Two representative samples from the principal 1-131 analysis on each sample. food pathways grown in each of four major quadrants within 10 km (6.2 mi), if available:

At least one root vegetable samp1e<10 l At least one broad leaf vegetable (or vegetation}'

101 b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi). (continued)

I Page 1-12.5.1-9 EXPOSURE PATHWAY AND/ OR SAMPLE 4. Ingestion

d. Vegetation CY-LA-170-301 Revision 7 January 2016 Part I, Radiological Effluent Controls Table R12.5.1-1(Page5 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY SAMPLE LOCATIONsl 1> FREQUENCY 1111 OF ANAL YSIS 1111 ----------------------------NOTE--------

Monthly during the growing Gamma isotopic l 4 l These vegetation samples are only required if milk season (May through October).

analysis and 1-131 sampling is not performed.

analysis on each sample. ----------

a. Indicator Samples of 3 different types of broadleaf vegetation within 10 km (6.2 miles) at 2 different offsite locations in the highest D/Q sector of the station, if available.
b. Control Samples of 3 different types of broadleaf vegetation within 15 to 30 km (9.3 to 18.6 miles) in the lowest D/Q sector of station, if available.

Page 1-12.5.1-10

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