Text

Submittal of 2012 Annual Radioactive Effluent Release Report
	ML13128A058
Person / Time
Site:	LaSalle
Issue date:	04/26/2013
From:	Karaba P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RA13-020
	Download: ML13128A058 (225)
	v • d • e

LaSalle Station Exe!.on Generationm 2601 North 21st Road 61341 Marseilles, IL 815 415 2000 Telephone www.exeloncorp.com RA13-020 10 CFR 50.36a April 26, 2013 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units I and 2 Facility Operating Ucense Nos. NPF-1 I and NPF-1 8 NRC Docket Nos. 50-373 and 50-374 Subject 2012 Annual Radioactive Effluent Release Report Enclosed is the Exelon Generation Company, LLC, 2012 Annual Radioactive Effluent Release Report for LaSalle County Station, submitted in accordance with 10 CFR 50.36a "Technical specifications on effluents from nuclear power reactors,"

paragraph (aX2), and Technical Specification 5.6.3 "Radioactive Effluent Release Report."

Should you have any questions concerning this letter, please contact Mr. Guy V. Ford, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Peter J. Karaba Site Vice President LaSalle County Station Attachment 2012 Effluent and Waste Disposal Annual Report cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SUPPLEMENTAL INFORMATION

1. Regulatory Limits

a. Gaseous Effluents

1) The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:

a) During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and b) During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2) The dose to an individual from radioiodines and radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released, from each reactor unit, from the site shall be limited to the following:

a) During any calendar quarter: Less than or equal to 7.5 mRem to any organ, and b) During any calendar year: Less than or equal to 15 mRem to any organ.

b. Liquid Effluents

1) The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site shall be limited:

a) During any calendar quarter: Less than or equal to 1.5 mRem to the total body and to less than or equal to 5 mRem to any organ, and b) During any calendar year: Less than or equal to 3 mRem to the total body and to less than or equal to 10 mRem to any organ.

c. Total Dose

1) The dose or dose commitment to any member of the public, due to releases or radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mRem to the body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mRem) over 12 consecutive months.

2. Allowable Concentrations

a. Gaseous Effluents

1) The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

a) For noble gases: Less than or equal to 500 mRem/year to the total body and less than or equal to 3000 mRem/year to the skin, and b) For all radioiodines and for all radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days: Less than or equal to 1500 mRem/year to any organ via the inhalation pathway.

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LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SUPPLEMENTAL INFORMATION

b. Liquid Effluents

1) The concentration of radioactive material released from the site shall be limited to ten (10) times the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the following:

Nuclide DWC

_(tCi/nL)

Kr-85m 2.OOE-04 Kr-85 5.00E-04 Kr-87 4.OOE-05 Kr-88 9.OOE-05 Xe-131rm 7.00E-04 Xe-133m 5.OOE-04 Xe-133 6.OOE-04 Xe-135m 2.OOE-04 Xe-135 2.OOE-04 Ar-41 7.OOE-05

3. Average Energy

1) Not applicable - average energy is no longer used to determine dose to the public.

4. Measurements and Approximations of Total Radioactivity

a. Gaseous Effluents

1) Containment Vent and Purge System is sampled by grab sample, which is analyzed for principal gamma emitters and H-3.

2) Main Vent Stack is sampled by grab sample, which is analyzed for principal gamma emitters and H-3.

3) Standby Gas Treatment System is sampled by grab sample, which is analyzed for principal gamma emitters.

4) All release types as listed in I and 2 above are sampled at the vent stack, and those listed in 3 above are sampled at the Standby Gas Treatment System whenever there is flow. These effluents are continuously sampled by charcoal cartridge and particulate filter paper, which are analyzed for iodines and principal gamma emitters. Particulate filter papers are composited and analyzed for gross alpha, Sr-89 and Sr-90. Noble gases, gross beta and gamma are continuously monitored by noble gas monitors for the vent stack and the standby gas treatment system.

5) The LaSalle County Station estimate of 17.01CilUnit/year of C-14 (in the dioxide fraction) is based upon a normalized C-14 production rate of 5.1 Ci/GWt-yr, a gaseous release fraction of 0.99, a C-14 dioxide fraction of 0.95, a reactor power rating of 3546 MWt (per Unit) and equivalent full power operation of 365 days.

b. Liquid Effluents

1) Batch waste release tanks are sampled each batch for principal gamma emitters, 1-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.

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LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SUPPLEMENTAL INFORMATION

2) Continuous releases are sampled continuously in proportion to the rate of flow of the effluent stream and by grab sample. Samples are analyzed for principal gamma enfitters, 1-13 1, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.

5. Batch Releases

a. Gaseous

1) Number of batch releases: None

2) Total time period for batch releases: N/A

3) Maximum time period for a batch release: N/A

4) Average time period for batch releases: N/A

5) Minimum time period for a batch release: N/A

b. Liquid

1) Number of batch releases: None

2) Total time period for batch releases: Min. N/A

3) Maximum time period for a batch release: Min. N/A

4) Average time period for batch releases: Min. N/A

5) Minimum time period for a batch release: Min. N/A

6) Average stream flow during periods of release of effluent into a flowing stream: gpm N/A

6. Abnormal Releases

a. Gaseous

1) Number of releases: None

2) Total activity released: N/A

b. Liquid

1) Number of releases: None

2) Total activity released: N/A

7. Process Control Program On May 2, 2012, the following procedure changes were made to RW-AA-100, Process Control Program for Radioactive Wastes, as described below:

a. Step 4.1.8. was added to allow an Exelon Nuclear plant to store waste from another Exelon Nuclear plant provided formal NRC approval is granted for the transfer of the waste. The addition of this procedural step ensures that a formal NRC review and approval process is Page 3 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SUPPLEMENTAL INFORMATION completed for the storage of waste from another site. The review and approval process will address the site specific effects on the UFSAR and regulatory bases.

b. Step 4.2.8. was modified to further clarify the storage of activated hardware. The additional wording, "...in the pool or loading the processed activated hardware into the Dry Cask storage system...", was added to clarify that the storage of activated hardware is generic and remains consistent with the UFSAR description of the Spent fuel Pool and Dry Cask Storage Systems.

c. Step 4.4.4. was added to the document. The step states that "Shipments sent for offsite storage SHALL meet the storage site's waste acceptance criteria." The addition of this step addresses the transfer of radioactive waste from one Exelon Nuclear plant to another Exelon Nuclear plant. This step also ensures that the formal NRC review and approval process will be completed for the transfer of waste from another site and will address the site specific effects on the UFSAR and regulatory bases.

d. Numerous minor wording and editorial changes were made throughout the document to correct grammatical errors and to improve document's clarity.

A copy of RW-AA-100, Process Control Program for Radioactive Wastes, has been included as Appendix E to this report.

There were no changes to the Process Control Program processing systems or components. There was no use of a solidification agent (e.g, cement, urea formaldehyde) during the processing of solid radioactive waste.

8. Effluent Monitoring Instrumentation timeclocks and sample anomalies.

a. Time clocks:

There were no effluent monitoring time clocks exceeded in 2012.

b. Sample anomalies:

There were no sampling anomalies affecting the measurement of effluents experienced during 2012.

In 2012 during a review of hard-to-detect nuclides in previous Annual Radioactive Effluent Release Reports (ARERR), it was discovered that Fe-55 had been reported as "<LLD" in LaSalle County Station's gaseous effluents. The station's ODCM does not require the Fe-55 analysis in gaseous effluents, and the station had not been performing this analysis. This issue was entered into the station's Corrective Actions Program and historical ARERR's were reviewed. The investigation found that this issue originated with an erroneous change to the report template in 2001, when the Errata Section of that ARERR included changes to the 2000 ARERR. The subsequent ARERRs through 2009 used the same template. In 2010, a fleetwide standardized ARERR template was implemented and the error was removed.

In late 2012. LaSalle Station began remediating the groundwater associated with the Unit I CY Tank leak using extraction well RW-LS-100S. The effluent from the extraction well is being discharged, via the stormwater piping, to the South Storm Water Pond. The South Storm Water Pond interfaces with the Condenser Discharge, which flows to the Cooling Pond, and the Cooling Pond ultimately blows down to the Illinois River. No other nuclides have been detected, and no tritium has been found to have migrated off site.

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LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SUPPLEMENTAL INFORMATION

9. Offsite Dose Calculation Manual Revisions.

There were two revisions made to the ODCM in 2012. Revision 4 included changes related to the retirement of legacy dose calculation software and the implementation of a new dose calculation software. The revision also included changes related to drum evaporator activities and changes related to a potential pathway for low levels of tritium in the Waste Water Treatment Facility. Revision 5 included a revised description for REMP dosimeters, addition of references related to the ODCM revision, and addition of a discussion regarding offsite dose contribution from activities related to Non Fuel Waste storage at LaSalle.

Each change had a determination performed, in accordance with ODCM revision procedures, to ensure the change would not adversely impact accuracy or reliability of effluent, dose or set point calculations and will maintain the level of radiological effluent controls established by regulatory requirements.

The determinations indicated no adverse impacts.

A copy of the ODCM Change Summary Matrix for revision 4 has been included as Appendix A to this report. Also, a copy of revision 4 to the ODCM has been included as Appendix B to this report. All changes in revision 4 to the LaSalle Station ODCM became effective 02/03/2012.

A copy of the ODCM Change Summary Matrix for revision 5 has been included as Appendix C to this report. Also, a copy of revision 5 of the ODCM has been included as Appendix D to this report. All changes in revision 5 to the LaSalle Station ODCM became effective 09/04/2012.

Page 5 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

UNIT 1 AND UNIT 2 DOCKET NUMBERS 50-373 AND 50-374 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES A. Fission & Activation Gases Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Est. Total Error %

1. Total Release Ci 6.91E+02 8.30E+02 1.13E+03 1.03E+03 2.50E+01

2. Average release rate for the period pCi/sec 8.77E+01 1.05E+02 1.43E02 1.31 E+02

3. Percent of ODCM limit % ....

B. Iodine

1. Total Iodine- 131 Ci 9.77E-03 1.03E-02 1.69E-02 2.48E-02 I 1.50E+01

2. Average release rate for the period I.LCi/sec 1.24E-03 1.30E-03 2.14E-03 3.15E-03

3. Percent of ODCM limit % ....

C. Particulates

1. Particulates with half-lives > 8 days Ci 2.47E-03 1.32E-03 4.74E-03 2.37E-03 3.50E+01

2. Average release rate for the period ICi/sec 3.14E-04 1.68E-04 6.03E-04 3.02E-04

3. Percent of ODCM limit % ....

D. Tritium

1. Total Release Ci 1.03E+01 1.79E+00 4.66E-01 1.30E-01 1.50E+01

2. Average release rate for the period gCi/sec 1.30E+00 2.27E-01 5.91 E-02 1.65E-02

3. Percent of ODCM limit % ....

E. Gross Alpha

1. Total Release Ci <1.OOE-11 <1.OOE-11 <1.00E-11 <1.OOE-11 1 3.50E+01

2. Average release rate for the period I Ci/sec <LLD <LLD <LLD <LLD

3. Percent of ODCM limit % ....

F. Carbon-14

1. Total Release Ci 8.45E+00 8.52E+00 8.58E+00 8.57E+00

2. Average release rate for the period pCi/sec 1.07E+00 1.08E+00 1.09E+00 1.09E+00

3. Percent of ODCM limit % ....

This information is contained in the Radiological Impact on Man section of the report.

"<" Indicates activity of sample is less than LLD given in pCi/ml Page 6 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

GASEOUS EFFLUENTS ELEVATED RELEASE UNIT 1 AND UNIT 2 Nuclides Released =

_jUnit IIQuarter

- Continuous Mode Quarter Quarter Quarter f Quarter Batch Mode Quarter Quarter j Quarter A. Fission gases I- - I=

Kr-85m Ci 1.60E+02 1.96E+02 3.17E+02 3.04E+02 N/A N/A N/A N/A Kr-87 Ci 1.40E+01 6.18E+00 2.75E+00 4.36E+00 N/A N/A N/A N/A Kr-88 Ci 1.79E+02 2.61E+02 4.06E+02 3.88E+02 N/A N/A N/A N/A Xe-133m Ci <1.OOE-04 <1.OOE-04 <1.OOE-04 <1.00E-04 N/A N/A N/A N/A Xe-133 Ci 3.27E+02 3.63E+02 3.99E+02 3.30E+02 N/A N/A N/A N/A Xe-135 Ci 1.17E+01 4.01E+00 3.44E+00 4.92E+00 N/A N/A N/A N/A Xe-138 Ci <1.OOE-04 <1.O0E-04 <1.O0E-04 <1.OOE-04 N/A N/A N/A N/A Ar-41 Ci 7.60E-03 <1.OOE-04 <1.OOE-04 <1.OOE-04 N/A N/A N/A N/A Total for Period Ci 6.91 E+02 8.30E+02 1.13E+03 1.03E+03 N/A N/A N/A N/A B. lodines -[1[

1-131 Ci 9.77E-03 1.03E-02 1.69E-02 2.48E-02 N/A N/A N/A N/A 1-132 Ci <1.OE-11 <1.O0E-11 <1.O0E-11 <1.OOE-11 N/A N/A N/A N/A 1-133 Ci 1.88E-02 2.57E-02 5.70E-01 8.87E-02 N/A N/A N/A N/A 1-134 Ci <1.OE- 11 <1.00E-11 <1.OOE-11 <1.OE-11 N/A N/A N/A N/A 1-135 Ci 9.04E-03 2.OOE-02 5.49E-02 8.07E-02 N/A N/A N/A N/A Total for Period Ci 3.76E-02 5.59E-02 1.29E-01 1.94E-01 N/A N/A N/A N/A Tot. 1-131,1-133,1-135 Ci 3.76E-02 5.59E-02 1.29E-01 1.94E-01 N/A N/A N/A N/A C. Particulates I=_ [I Mn-54 Ci <1.O0E-11 2.25E-05 <1.OOE-11 <1.00E-11 N/A N/A N/A N/A Co-58 Ci 5.34E-05 1.07E-05 <1.O0E-11 <1.OOE-11 N/A N/A N/A N/A Fe-59 Ci <1.O0E-11 <1.OE-11 <1.OOE-11 <1.O0E-11 N/A N/A N/A N/A Co-60 Ci 5.61 E-04 4.42E-04 2.22E-04 3.62E-04 N/A N/A N/A N/A Zn-65 Ci 2.17E-04 3.17E-05 <1.O0E-11 <1.OGE-11 N/A N/A N/A N/A Sr-89 Ci 7.06E-04 3.45E-04 2.15E-04 1.06E-03 N/A N/A N/A N/A Sr-90 Ci <1.O0E-11 <1.OE- 1i <1.OE-1I <1.O0E-11 N/A N/A N/A N/A Mo-99 Ci <1.OGE- 11 <1.O0E-11 <1.O0E-11 <1.00E-11 N/A N/A N/A N/A Cs-134 Ci <1 o00E-11 <1.00E-11 <1.O0E-11 <1.OE-11 N/A N/A N/A N/A Cs-136 Ci <1.OE-11 5.28E-05 2.81E-05 <1.00E-11 N/A N/A N/A N/A Cs-137 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.OE-1I N/A N/A N/A N/A Ba-140 Ci 9.29E-04 4.14E-04 2.34E-03 9.50E-04 N/A N/A N/A N/A La-140 Ci <1.O0E-11 <1.O0E-1I <1.00E-11 <1.OE-11 N/A N/A N/A N/A Ce-141 Ci <1.O0E-11 <1.OOE-11 <1.00E-1I <1.OE-1i N/A N/A N/A N/A Ce-144 Ci <1.OE- 1i <1.OE-11 <1.OE-11 <1.OE-11 N/A N/A N/A N/A Total for Period Ci I 2.47E-03 1.32E-03 4.74E-03 2.37E-03 N/A N/A N/A N/A D.Tritium F II H-3 Total for Period Ci [ 1.03E+01 3.34E+00 1.78E+00 8.37E-01 N/A N/A N/A N/A E. Gross Alpha 19 Period <1.00E-11 <1.00E-11 <1.00E-1 1 <1.00E-11 N/A N/A N/A N/A F. Carbon-14 IF C-14 Total for Period Ci I 8.45E+00 8.52E+00 8.58E+00 I8.46E+G00 F N/A N/A N/A N/A Page 7 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

LIQUID RELEASES UNIT 1 AND UNIT 2 SUMMATION OF ALL LIQUID RELEASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Total A. Fission & Activation Products Error %

1. Total Release (not including tritium, gases Ci <LLD <LLD <LLD <LLD N/A

& alpha)

2. Average diluted concentration during gCi/mL <LLD <LLD <LLD <LLD period ____/mL <LD <LLD <L

3. Percent of applicable limit %*....

B. Tritium

1. Total Release Ci <LLD <LLD <LLD <LLD N/A

2. Average diluted concentration during period gCi/mL itim <LLD LD <LLD

<L LD

<LLD <L

<LLD

3. Percent of applicable limit % ....

C. Dissolved & Entrained Gases

1. Total Release Ci <LLD <LLD <LLD <LLD N/A

2. Average diluted concentration during period gCi/mL itim <LLD LD <LLD

<L LD

<LLD <L

<LLD

3. Percent of applicable limit % ....

D. Gross Alpha Activity

1. Total Release Ci <LLD <LLD <LLD <LLD N/A

2. Average release rate for the period gCi/mL <LLD <LLD <LLD <LLD

3. Percent of ODCM limit % ....

E. Volume of Waste Released (prior to Liters OOOEOO OOOE+00 I .OOE+O0 0.OOE+O dilution) .+ . .

F. Volume of Dilution Water Used During iO.OOE+o0 Liters I O.OOE+00 I O.OOE+o0 O.OOE+00o Period I IIII This information is contained in the Radiological Impact on Man section of the report.

"<" Indicates activity of sample is less than LLD given in pCi/ml Page 8 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

LIQUID RELEASES UNIT 1 AND UNIT 2 Nuclides Released _ _ __ Continuous Mode I Batch Mode A. Fission & Un it Quarter Qu a I Quarter Quarter IIQuarter24 Quarter Quarter a4Qrer Activation Products Uni 1 are 2 3 1 4 1 2 3 Qure Mn-54 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Fe-55 Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.O0E-06 N/A N/A N/A N/A Co-58 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Fe-59 Ci <5.00E-07 <5.OOE-07 <5.00E-07 <5.00E-07 N/A N/A N/A N/A Co-60 Ci <5.OOE-07 <5.00E-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Zn-65 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Sr-89 Ci <5.OOE-08 <5.OOE-08 <5.OOE-08 <5.OOE-08 N/A N/A N/A N/A Sr-90 Ci <5.00E-08 <5.OOE-08 <5.OOE-08 <5.OOE-08 N/A N/A N/A N/A Mo-99 Ci <5.00E-07 <5.O0E-07 <5.O0E-07 <5.O0E-07 N/A N/A N/A N/A 1-131 Ci <1.OOE-06 <1.00E-06 <1.OOE-06 <1.00E-06 N/A N/A N/A N/A Cs-134 Ci <5.00E-07 <5.OOE-07 <5.00E-07 <5.OOE-07 N/A N/A N/A N/A Cs-137 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Ce-141 Ci <5.00E-07 <5.00E-07 <5.OOE-07 <5.OOE-07 N/A N/A N/A N/A Ce-144 Ci <5.OOE-07 <5.00E-07 <5.OOE-07 <5.00E-07 N/A N/A N/A N/A Total for Period Ci <LLD <LLD <LLD <LLD N/A N/A N/A N/A B.-3 I[-

H-3 Total for Period Ci][ <1.00E-05 <1.00E-05 <1.00E-05 <1.00E-05][ N/A j N/A N/A N/A C. Dissolved &

Entrained Gasses Kr-85m Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Kr-85 Ci <1.00E-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Kr-87 Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Kr-88 Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Xe-131m Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Xe-133m Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1O0E-05 N/A N/A N/A N/A Xe-133 Ci <1.00E-05 <1.OOE-05 <1.00E-05 <1.00E-05 N/A N/A N/A N/A Xe-135m Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Xe-135 Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 N/A N/A N/A N/A Ar-41 Ci <1.00E-05 <1.00E-05 <1.00E-05 <1.00E-05 N/A N/A N/A N/A Total for Period Ci <LLD <LLD <LLD <LLD N/A N/A N/A N/A D. Gross Alpha ii=

Gross Alpha Total for JCi <1.OOE-07 <1.OOE-07 <1.OOE-07 <1.OOE-07 N/A N/A N/A N/A Period 11< I Page 9 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Quantity Total Est. Total Types of Waste (m) Activity (Ci) Period Error (%)

a. Spent resins, filter sludges, evaporator bottoms, 2.29E+01 2.65E+00 1Q12 +/-25%

etc

b. Dry compressible waste, contaminated equip, etc 9.28E+02 6.60E-01 1Q12 +/-25%

c. Irradiated components, control rods, etc None None 1Q12 N/A

d. Other (water and oil, FW heater) 2.96E+01 6.15E-03 1Q12 +/-25%

2. Estimate of major nuclide composition (by waste type)

Percent Shipment Abundance Type(s)

Major Nuclide Composition (>1%)

a. Spent resins, filter sludges, evaporator bottoms, etc H-3 1.424% LSA C-14 19.309%

Mn-54 1.741%

Fe-55 18.443%

Co-60 45.860%

Zn-65 3.814%

Cs-1 37 7.030%

b. Dry compressible waste, contaminated equip, etc Cr-51 2.240% LSA Mn-54 6.922%

Fe-55 25.544%

Co-60 55.613%

Zn-65 3.897%

1-131 2.648%

c. Irradiated components, control rods, etc None[ N/A N/A

d. Other (water and oil, FW heater)

Cr-51 2.398% LSA Mn-54 6.786%

Fe-55 24.886%

Co-60 54.104%

Zn-65 3.830%

1-131 3.406%

La-140 1.501%

Page 10 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 14 Hittman Transport Energy Solutions - Bear Creek 2 Visionary Solutions Energy Solutions - Bear Creek 3 Hittman Transport Energy Solutions LLC.

B. Irradiated Fuel Shipments (disposition)

Number of Shipments I Mode of Transportation NADestination

-None N/A N/A C. Changes to the Process Control Program There were no changes to the Process Control Program during this period. There was no use of a solidification agent (e.g, cement, urea formaldehyde) during the processing of solid radioactive waste.

Page 11 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Quantity Total Est. Total Types of Waste (MA) Activity (Ci) Period Error (%)

a, Spent resins, filter sludges, evaporator bottoms, 1.52E+01 5.60E+00 2Q12 +/-25%

etc

b. Dry compressible waste, contaminated equip, etc 4.64E+02 5.25E+00 2Q12 +/-25%

c. Irradiated components, control rods, etc None None 2Q12 N/A d, Other (Water and Oil, filters & DAW HIC) 7.92E+01 1.41 E+00 2Q12 +/-25%

2. Estimate of major nuclide composition (by waste type)

Percent Shipment Abundance Type(s)

Major Nuclide Composition 1%)

a, Spent resins, filter sludges, evaporator bottoms, etc C-14 21.860% LSA Fe-55 20.890%

Co-60 51.934%

Cs-137 2.673%

b. Dry compressible waste, contaminated equip, etc C-14 14.008% LSA Mn-54 2.628%

Fe-55 23.154%

Co-60 54.412%

Zn-65 1.483%

1-131 1.293%

c. Irradiated components, control rods, etc None N/A N/A

d. Other (Water and Oil, filters & DAW HIC)

Cr-51 2.413% LSA Mn-54 6.855%

Fe-55 25.144%

Co-60 54.667%

Zn-65 3.869%

1-131 3.393% 1 _1 La-140 1.404%1 Page 12 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 11 Hittman Transport Energy Solutions - Bear Creek 1 Visionary Solutions Energy Solutions - Bear Creek 2 Hittman Transport Energy Solutions LLC.

2 Visionary Solutions Toxco Inc B. Irradiated Fuel Shipments (disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A C. Changes to the Process Control Program On May 2, 2012, the following procedure changes were made to RW-AA-100, Process Control Program for Radioactive Wastes, as described below:

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

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

Step 4.4.4. was added to the document. The step states that "Shipments sent for offsite storage SHALL meet the storage site's waste acceptance criteria." The addition of this step addresses the transfer of radioactive waste from one Exelon Nuclear plant to another Exelon Nuclear plant. This step also ensures that the formal NRC review and approval process will be completed for the transfer of waste from another site and will address the site specific effects on the UFSAR and regulatory bases.

Numerous minor wording and editorial changes were made throughout the document to correct grammatical errors and to improve document's clarity.

A copy of RW-AA-100, Process Control Program for Radioactive Wastes, has been included as Appendix E to this report.

There was no use of a solidification agent (e.g, cement, urea formaldehyde) during the processing of solid radioactive waste.

Page 13 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS THIRD QUARTER A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Quantity Total Est. Total Types of Waste (m) Activity (Ci) Period Error (%)

a. Spent resins, filter sludges, evaporator bottoms, None None 3Q12 N/A etc

b. Dry compressible waste, contaminated equip, etc 7.10E+01 2.02E+01 3Q12 +1-25%

c. Irradiated components, control rods, etc None None 3Q12 N/A

d. Other (water and oil) None None 3Q12 N/A

2. Estimate of major nuclide composition (by waste type)

Percent Shipment Abundance Type(s)

Major Nuclide Composition (1%)

a. Spent resins, filter sludges, evaporator bottoms, etc None[ N/A N/A

b. Dry compressible waste, contaminated equip, etc Mn-54 7.728% LSA Fe-55 31.999%

Co-58 1.776%

Co-60 54.534%

Zn-65 3.025%

c. Irradiated components, control rods, etc None N/A N/A

d. Other (water and oil)

None N/A N/A Page 14 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS THIRD QUARTER

3. Solid Waste Disposition Number of Shipments I Mode of Transportation Destination 5 Hittman Transport Energy Solutions - Bear Creek B. Irradiated Fuel Shipments (disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A C. Changes to the Process Control Program There were no changes to the Process Control Program during this period. There was no use of a solidification agent (e.g, cement, urea formaldehyde) during the processing of solid radioactive waste.

Page 15 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOURTH QUARTER A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Quantity Total Est. Total Types of Waste (M) Activity (Ci) Period Error %

a. Spent resins, filter sludges, evaporator bottoms, 2.79E+01 4.26E+00 4Q12 +/-25%

etc

b. Dry compressible waste, contaminated equip, etc 6.67E+01 2.95E+00 4Q12 +/-25%

c. Irradiated components, control rods, etc None None 4Q12 N/A

d. Other (Water and Oil) 1.21 E+01 3.19E-03 4Q12 +/-25%

2. Estimate of major nuclide composition (by waste type)

Percent Shipment Abundance Type(s)

Major Nuclide Composition 1%)

a. Spent resins, filter sludges, evaporator bottoms, etc H-3 1.039% LSA MAn-54 1.485%

Fe-55 25.841%

Co-60 43.949%

Zn-65 6.160%

Cs- 134 2.015%

Cs-137 17.991%

b. Dry compressible waste, contaminated equip, etc Mn-54 7.728% LSA Fe-55 31.981%

Co-58 1.781%

Co-60 54.498%

Zn-65 3.026%

c. Irradiated components, control rods, etc None[ N/A N/A

d. Other (Water and Oil)

Mn-54 7.737% LSA Fe-55 32.004%

Co-58 1.787%

Co-60 54.531%

Zn-65 3.029%

Page 16 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOURTH QUARTER

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2 Hittman Transport Energy Solutions - Bear Creek 4 Hittman Transport Energy Solutions LLC 1 Visionary Solutions Toxco Inc B. Irradiated Fuel Shipments (disposition)

Number of Shipmentson Mode of Transportation I Destination

-None N/A N/A C. Changes to the Process Control Program There were no changes to the Process Control Program during this period. There was no use of a solidification agent (e.g, cement, urea formaldehyde) during the processing of solid radioactive waste.

Page 17 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

RADIOLOGICAL IMPACT ON MAN MAXIMUM DOSES RESULTING FROM GASEOUS RELEASES AND COMPLIANCE STATUS 1st % of rd Quarterly %of 2nd 3 % of 4th % of Annual % of Units Infant Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit Gamma Air 5.OOE+00 mRad 6.42E-03 0.13 9.OOE-03 0.18 1.39E-02 0.28 1.33E-02 0.27 1.OOE+01 0.85 Beta Air 1.OOE+01 mRad 3.64E-04 0.004 4.30E-04 0.00 6.09E-04 0.01 5.74E-04 0.01 2.OOE+01 0.02 NG Total Body 2.50E+00 mRem 4.28E-03 0.17 6.OOE-03 0.24 9.28E-03 0.37 8.87E-03 0.35 5.OOE+00 1.14 NG Skin 7.50E+00 mRem 7.24E-03 0.10 1.01E-02 0.13 1.56E-02 0.21 1.49E-02 0.20 1.50E+01 0.64 NNG Organ 7.50E+00 mRem 4.84E-02 0.64 5.10E-02 0.68 8.35E-02 1.11 1.22E-01 1.63 1.50E+01 4.07 rd Quarterly 1st % of 2nd % of 3

% of 4th % of Annual % of Units Child Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit Gamma Air 5.OOE+00 mRad 6.42E-03 0.13 9.OOE-03 0.18 1.39E-02 0.28 1.33E-02 0.27 1.OOE+01 0.85 Beta Air 1.OOE+01 mRad 3.64E-04 0.004 4.30E-04 0.00 6.09E-04 0.01 5.74E-04 0.01 2.OOE+01 0.02 NG Total Body 2.50E+00 mRem 4.28E-03 0.17 6.OOE-03 0.24 9.28E-03 0.37 8.87E-03 0.35 5.OOE+00 1.14 NG Skin 7.50E+00 mRem 7.24E-03 0.10 1.01E-02 0.13 1.56E-02 0.21 1.49E-02 0.20 1.50E+01 0.64 NNG Organ 7.50E+00 mRem 2.01E-02 0.27 2.12E-02 0.28 3.46E-02 0.46 5.06E-02 0.67 1.50E+01 1.69 rd Teenager Quarterly 1st % of 2nd % of 3 % of 4th % of Annual % of Units Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit Gamma Air 5.OOE+00 m Rad 6.42E-03 0.13 9.OOE-03 0.18 1.39E-02 0.28 1.33E-02 0.27 1.OOE+01 0.85 Beta Air 1.OOE+01 mRad 3.64E-04 0.004 4.30E-04 0.00 6.09E-04 0.01 5.74E-04 0.01 2.OOE+01 0.02 NG Total Body 2.50E+00 mRem 4.28E-03 0.17 6.OOE-03 0.24 9.28E-03 0.37 8.87E-03 0.35 5.OOE+00 1.14 NG Skin 7.50E+00 mRem 7.24E-03 0.10 1.01E-02 0.13 1.56E-02 0.21 1.49E-02 0.20 1.50E+01 0.64 NNG Organ 7.50E+00 mRem 1.01E-02 0.14 1.07E-02 0.14 1.74E-02 0.23 2.55E-02 0.34 1.50E+01 0.85 Quarterly Units 1s 1st % of 2nd % of 3 rd % of 4th % of Annual % of Quarter Adult Receptor Limit Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit Gamma Air 5.OOE+00 mRad 6.42E-03 0.13 9.OOE-03 0.18 1.39E-02 0.28 1.33E-02 0.27 1.OOE+01 0.85 Beta Air 1.OOE+01 mRad 3.64E-04 0.004 4.30E-04 0.00 6.09E-04 0.01 5.74E-04 0.01 2.OOE+01 0.02 NG Total Body 2.50E+00 mRem 4.28E-03 0.17 6.OOE-03 0.24 9.28E-03 0.37 8.87E-03 0.35 5.OOE+00 1.14 NG Skin 7.50E+00 mRem 7.24E-03 0.10 1.01E-02 0.13 1.56E-02 0.21 1.49E-02 0.20 1.50E+01 0.64 NNG Organ 7.50E+00 mRem 6.41E-03 0.09 6.74E-03 0.09 1.10E-02 0.15 1.61E-02 0.21 1.50E+01 0.54 The LaSalle County Nuclear Power Station maximum expected annual dose from Carbon-14 has been calculated using the maximum gross thermal capacity at full power operation. The resultant bounding doses are based upon site specific assumptions of source term.

Page 18 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

RADIOLOGICAL IMPACT ON MAN MAXIMUM DOSES RESULTING FROM LIQUID RELEASES AND COMPLIANCE STATUS Infant Quarterly Units 1st % of 2nd % of 3rd % of 4th % of Annual % of Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit 10CFR50 Appendix I compliance Total Body 1.50E+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 3.OOE+00 0.00 Organ 5.OOE+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 1.OOE+01 0.00 40CFR141 compliance (nearest public drinking water)

Total Body mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Organ mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Child Quarterly Units 1st % of 2nd % of 3 rd % of 4th % of Annual % of Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit 10CFR50 Appendix I compliance Total Body 1.50E+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 3.OOE+00 0.00 Organ 5.OOE+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 1.OOE+01 0.00 40CFR141 compliance (nearest public drinking water)

Total Body mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Organ mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Teenager Quarterly Units 1st % of 2nd % of 3rd % of 4th % of Annual % of Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit 10CFR50 Appendix I compliance Total Body 1.50E+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 3.OOE+00 0.00 Organ 5.OOE+00 mRem 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 1.OOE+01 0.00 40CFR141 compliance (nearest public drinking water)

Total Body mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Organ mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Adult Quarterly Units 1st % of 2nd % of 3rd % of 4th % of Annual % of Receptor Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Limit Limit 10CFR50 Appendix I compliance Total Body 1.50E+00 mRem 0.00E+00 0.00 O.OOE+00 0.00 O.OOE+00 0.00 O.OOE+00 0.00 3.OOE+00 0.00 Organ 5.OOE+00 mRem 0.OOE+00 0.00 O.OOE+00 0.00 O.OOE+00 0.00 O.OOE+00 0.00 1.OOE+01 0.00 40CFR141 compliance (nearest public drinking water)

Total Body mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.OOE+00 0.00 Organ mRem 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 4.00E+00 0.00 Page 19 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

RADIOLOGICAL IMPACT ON MAN MAXIMUM DOSES RESULTING FROM RELEASES AND COMPLIANCE STATUS 1 OCFR20 / 40CFR1 90 Compliance 1 St nd 3 rd 4 th 2

Quarter Quarter Quarter Quarter Annual Annual Annual Dose Dose Dose Dose Dose Limit Limit (mRem) (mRem) (mRem) (mRem) (mRem) (mRem/yr)

Unit I 40CFR1 90 Compliance Ul D'x 7.69E-02 1.03E-01 1.06E-01 1.08E-01 I3.93E-01 ] 25 LIZ 10CFR20 Compliance UI DTot 1.25E-01 1.54E-01 1.89E-01 2.30E-01 F6.98E-01 100 0.70 40CFR190 Compliance Bone 7.04E-03 7.60E-03 7.28E-03 7.33E-03 2.93E-02 25 0.12 Liver 1.68E-03 1.67E-03 1.76E-03 1.89E-03 7.OOE-03 25 0.03 Thyroid 4.84E-02 5.1 OE-02 8.35E-02 1.22E-01 3.05E-01 75 0.41 Kidney 1.70E-03 1.69E-03 1.80E-03 1.96E-03 7.15E-03 25 0.03 Lung 1.52E-03 1.51 E-03 1.50E-03 1.52E-03 6.05E-03 25 0.02 GI-LLI 1.54E-03 1.52E-03 1.52E-03 1.53E-03 6.11 E-03 25 0.02 Unit 2 40CFR190 Compliance U2 DEx 9.75E-02 9.65E-02 9.60E-02 9.79E-02 F3.88E-01 25 15 10CFR20 Compliance S3.88E-01 D

U2DTot 9.75E-02 9.65E-02 9.60E-02 9.79E-02] 100 0.39 40CFR1 90 Compliance Bone 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 25 0.00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 25 0.00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 75 0.00 Kidney O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 25 0.00 Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 25 0.00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 25 0.00 Page 20 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Extremely Unstable 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 12 NNE 2 0 4 NE 4 9 13 ENE 5 15 22 E 12 2 17 ESE 1 0 6 SE 1 3 9 SSE 0 0 1 S 1 5 7 SSW 2 2 6 SW 8 2 18 WSW 7 1 15 W 12 1 16 WNW 8 7 20 NW 3 2 10 NNW 1 2 10 Variable 0 0 0 Total 7 30 69 51 24 5 186 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili ty class: 0 Hours of missing stability measurements in all stability classes: 4 Page 21 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Moderately Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 1 0 3 NNE 1 1 0 2 NE 0 1 0 4 ENE 0 0 3 E 0 4 ESE 0 4 SE 0 6 SSE 0 5 S 0 6 SSW 0 9 SW 0 5 WSW 0 5 W 1 7 WNW 0 11 NW 0 3 NNW 0 5 Variable 0 0 Total 1 14 24 30 12 1 82 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 22 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Slightly Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 14 NNE 0 3 NE 0 4 ENE 2 8 E 4 5 ESE 4 6 SE 3 7 SSE 1 10 S 11 18 SSW 4 12 SW 1 4 WSW 4 5 W 6 8 WNW 10 21 NW 6 12 NNW 4 8 Variable 0 0 Total 2 19 69 42 9 4 145 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl.asses: 4 Page 23 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Neutral - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 5 15 1 2 1 24 NNE 0 14 12 4 0 0 30 NE 0 8 13 7 3 0 31 ENE 0 4 16 26 1 0 47 E 0 7 11 8 0 0 26 ESE 0 6 9 6 0 0 21 SE 1 5 4 10 6 0 26 SSE 1 2 8 7 5 3 26 S 0 7 13 20 7 3 50 SSW 4 16 9 6 12 48 SW 0 8 14 14 14 4 54 WSW 0 9 24 18 5 2 58 W 0 11 22 50 5 2 90 WNW 1 6 25 37 18 10 97 NW 0 9 14 14 5 1 43 NNW 0 8 33 23 23 0 87 Variable 0 0 0 0 0 0 0 Total 4 113 249 254 100 38 758 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 24 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Slightly Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 14 0 0 0 0 19 NNE 7 0 0 0 0 9 NE 1 3 0 0 0 5 ENE 4 7 1 0 0 12 E 16 7 3 0 0 26 ESE 6 3 11 2 0 22 SE 3 7 9 8 0 28 SSE 7 12 20 6 0 45 S 7 13 22 8 2 52 SSW 3 7 21 10 1 42 SW 2 14 23 4 1 45 WSW 4 15 10 3 2 36 W 7 26 15 38 7 96 WNW 11 16 16 9 18 70 NW 10 3 3 0 0 17 NNW 8 0 0 0 0 9 Variable 0 0 0 0 0 0 Total 17 110 133 154 88 31 533 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 25 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Moderately Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 0 0 0 1 0 0 0 0 NNE 1 2 1 1 0 0 0 NE 2 4 0 0 0 0 ENE 0 3 3 6 0 0 0 E 0 II 17 6 1 0 0 ESE 0 9 16 9 10 1 0 0 SE 0 20 SSE 0 4 9 4 1 0 18 S 0 8 28 14 1 0 51 SSW 2 4 13 7 14 0 40 SW 1 12 10 14 0 0 37 WSW 1 9 17 10 0 0 37 W 0 16 24 7 2 0 49 WNW 1 14 13 0 0 0 28 NW 1 4 0 0 0 0 5 NNW 1 2 0 0 0 0 3 Variable 0 0 0 0 0 0 0 Total 10 107 137 58 18 0 330 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 26 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Extremely Stable - 200Ft-33 Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 0 0 0 0 2 NNE 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 5 2 1 0 0 8 SE 0 12 6 0 0 18 SSE 0 2 10 0 0 12 S 0 6 15 2 0 23 SSW 0 6 19 5 0 30 SW 0 8 6 12 0 26 WSW 0 2 10 2 0 14 W 0 0 5 0 0 5 WNW 0 1 2 0 0 3 NW 0 0 0 0 1 NNW 0 0 0 0 0 0 Variable 0 0 0 0 0 0 Total 1 47 75 22 0 145 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 27 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January March 2012 Stability Class - Extremely Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 NNE 0 0 0 0 0 NE 0 0 0 0 0 ENE 0 0 0 1 E 0 0 0 ESE 0 0 0 SE 0 0 0 SSE 0 0 0 S 0 0 0 SSW 0 0 0 SW 0 0 0 WSW 0 0 0 W 0 0 0 WNW 0 0 2 NW 0 3 3 NNW 0 1 1 Variable 0 0 0 Total 0 1 4 7 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all stability classes: 4 Page 28 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Moderately Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 NNE 0 0 NE 0 0 ENE 0 0 E 0 0 ESE 0 0 SE 0 0 SSE 0 0 S 0 0 SSW 0 0 SW 0 0 WSW 0 0 W 1 0 WNW 0 0 NW 0 0 NNW 0 0 Variable 0 0 Total 1 0 4 7 4 8 24 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stabi lity classes: 4 Page 29 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Slightly Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 3 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 0 0 0 3 1 0 4 ENE 0 0 1 4 10 0 15 E 0 0 0 0 0 3 ESE 0 0 0 0 0 SE 0 0 0 0 0 SSE 0 0 0 0 0 S 0 0 0 2 6 SSW 1 0 1 2 5 SW 2 1 0 2 7 WSW 0 4 0 6 W 0 1 0 5 WNW 0 0 0 2 4 NW 0 0 2 4 8 NNW 2 0 1 0 3 Variable 0 0 0 0 0 Total 0 5 10 25 16 13 69 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 30 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Neutral - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 8 22 17 0 5 52 NNE 2 6 17 16 1 0 42 NE 1 3 14 13 14 8 53 ENE 0 1 19 30 32 3 85 E 0 0 12 9 4 0 25 ESE 0 3 11 8 3 4 29 SE 0 3 5 11 10 11 40 SSE 0 3 3 13 9 9 37 S 0 7 7 28 27 20 89 SSW 0 2 10 23 14 29 78 SW 2 7 7 17 17 17 67 WSW 0 6 12 30 12 6 66 W 0 4 15 39 20 25 103 WNW 0 4 11 40 50 39 144 NW 0 9 25 25 22 26 107 NNW 0 2 13 35 8 18 76 Variable 0 0 0 0 0 0 0 Total 5 68 203 354 243 220 1093 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 31 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Slightly Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 7 4 0 0 11 NNE 0 4 7 2 0 0 13 NE 1 4 4 4 0 0 13 ENE 0 0 5 6 0 0 11 E 0 5 8 12 6 0 31 ESE 0 3 3 8 3 6 23 SE 1 0 4 10 11 11 37 SSE 2 4 3 4 10 32 55 S 1 4 7 20 41 74 SSW 1 0 8 7 14 58 88 SW 1 3 8 6 17 22 57 WSW 1 1 8 2 19 10 41 W 1 8 10 14 21 40 94 WNW 0 5 10 10 33 57 115 NW 1 4 10 12 18 4 49 NNW 1 2 4 0 0 8 Variable 0 0 0 0 0 0 0 Total 11 44 103 109 172 281 720 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 32 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Moderately Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 0 7 NNE 0 0 0 2 NE 0 0 0 3 ENE 0 0 0 3 E 1 0 0 2 ESE 2 2 3 10 SE 8 1 2 13 SSE 1 7 7 17 S 3 12 13 32 SSW 5 10 21 40 SW 2 6 29 WSW 4 1 8 19 W 8 8 4 24 WNW 1 11 4 17 NW 4 2 0 7 NNW 0 0 0 1 Variable 0 0 0 0 Total 3 14 36 49 56 68 226 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 33 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: January - March 2012 Stability Class - Extremely Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 NNE 0 NE 1 ENE 0 E 0 ESE 0 SE 1 SSE 12 S 8 SSW 8 SW 1 WSW 9 W 0 WNW 0 NW 1 NNW 0 Variable 0 Total 0 0 4 5 14 18 41 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 Page 34 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Extremely Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 3 0 0 4 NNE 0 1 0 0 0 2 NE 0 0 0 3 0 0 3 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 1 0 0 0 1 S 0 0 0 3 3 7 13 SSW 0 0 1 11 4 0 16 SW 0 0 0 4 7 1 12 WSW 0 0 0 8 0 0 8 W 0 0 0 4 0 0 4 WNW 0 0 0 0 0 1 NW 0 0 0 3 0 0 3 NNW 0 0 0 1 0 0 1 Variable 0 0 0 0 0 0 0 Total 0 2 3 42 14 8 69 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 35 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April June 2012 Stability Class - Moderately Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 NNE 3 5 NE 11 14 ENE 1 3 E 0 2 ESE 2 4 SE 0 0 SSE 4 6 S 1 6 SSW 20 SW 5 12 WSW 4 5 W 0 1 WNW 2 5 NW 5 5 NNW 3 4 Variable 0 0 Total 0 4 27 53 10 1 95 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 2 Page 36 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Slightly Unstable 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 3 2 0 0 7 NNE 0 3 7 0 0 0 10 NE 0 0 14 8 2 0 24 ENE 0 0 5 1 0 0 6 E 0 0 0 3 2 0 5 ESE 0 0 2 0 0 3 SE 0 0 1 0 0 0 1 SSE 0 0 4 3 0 8 S 0 0 0 3 3 0 6 SSW 0 1 17 7 0 26 SW 0 1 5 9 1 0 16 WSW 0 0 3 9 0 0 12 W 0 1 6 1 0 0 8 WNW 0 0 5 6 0 0 11 NW 0 0 4 4 1 0 9 NNW 0 0 4 8 2 0 14 Variable 0 0 0 0 0 0 0 Total 0 8 80 64 14 0 166 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 4 Hours of missing stability measurements in all stability classes: 2 Page 37 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Neutral - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 20 7 0 41 NNE 19 17 7 0 44 NE 24 32 39 7 104 ENE 11 22 33 10 77 E 7 22 28 12 69 ESE 4 10 11 5 30 SE 7 9 13 2 31 SSE 1 10 8 2 21 S 6 14 14 4 40 SSW 2 23 16 3 45 SW 15 15 19 3 52 WSW 9 16 8 1 36 W 21 19 10 0 51 WNW 12 20 8 1 43 NW 7 17 9 6 41 NNW 9 26 30 4 70 Variable 0 0 0 0 0 Total 8 167 292 260 60 8 795 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 6 Hours of missing stability measurements in all stability classes: 2 Page 38 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Slightly Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 18 16 1 35 NNE 16 16 4 37 NE 6 14 13 34 ENE 3 25 21 50 E 10 35 5 52 ESE 8 9 7 24 SE 4 4 3 11 SSE 6 9 5 20 S 3 20 6 31 SSW 5 31 26 68 SW 3 16 8 31 WSW 9 10 3 24 W 7 13 2 29 WNW 4 24 3 38 NW 11 23 5 40 NNW 13 23 2 38 Variable 0 0 0 0 Total 5 126 288 114 19 10 562 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 3 Hours of missing stability measurements in all stability classes: 2 Page 39 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Moderately Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 1 0 10 NNE 5 0 0 6 NE 0 0 0 0 ENE 4 1 0 5 E 21 23 0 46 ESE 18 12 0 30 SE 9 4 0 14 SSE 5 16 0 22 S 6 21 0 31 SSW 2 21 0 24 SW 6 8 0 15 WSW 11 13 0 24 W 7 10 0 19 WNW 10 8 0 18 NW 4 0 0 5 NNW 4 2 0 7 Variable 0 0 0 0 Total 7 121 140 8 0 0 276 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 4 Hours of missing stability measurements in all stability classes: 2 Page 40 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Extremely Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 4 3 0 0 0 7 ESE 1 17 3 0 21 SE 0 23 13 0 36 SSE 0 18 8 0 26 S 0 12 13 0 25 SSW 0 12 13 0 25 SW 0 10 5 0 15 WSW 2 14 11 0 27 W 0 8 1 0 9 WNW 0 2 1 0 3 NW 0 2 0 0 2 NNW 1 2 0 0 3 Variable 0 0 0 0 0 Total 4 124 71 0 199 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabi lity class: 2 Hours of missing stability measurements in all stability classes: 2 Page 41 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Extremely Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 NNE 0 0 0 NE 0 0 0 ENE 0 0 0 E 0 0 0 ESE 0 0 0 SE 0 0 0 SSE 0 S 0 4 4 SSW 0 0 0 SW 0 0 0 WSW 0 0 0 W 0 0 0 WNW 0 0 0 NW 0 0 0 NNW 0 0 0 Variable 0 0 0 Total 0 4 4 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 42 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Moderately Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 4 10 11 25 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 43 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Slightly Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 3 0 4 NNE 0 0 0 0 1 1 NE 0 0 0 5 0 5 ENE 0 0 1 0 0 E 0 0 0 0 0 0 ESE 0 0 0 0 0 1 SE 0 0 0 0 0 0 SSE 0 0 6 0 0 7 S 0 0 0 2 2 4 SSW 0 0 8 9 4 22 SW 0 0 0 4 5 5 14 WSW 0 0 0 4 2 0 6 W 0 0 0 2 5 0 7 WNW 0 0 1 1 0 0 2 NW 0 0 0 5 0 0 5 NNW 0 0 0 0 3 0 3 Variable 0 0 0 0 0 0 0 Total 0 0 4 32 34 12 82 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 44 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Neutral - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 10 12 26 12 0 60 NNE 10 21 17 10 5 64 NE 7 21 48 62 29 170 ENE 6 19 36 44 10 115 E 5 18 16 21 17 77 ESE 3 7 15 12 9 47 SE 4 5 13 8 2 32 SSE 0 7 11 11 1 30 S 2 8 19 9 16 54 SSW 1 5 39 35 21 101 SW 6 18 21 24 6 76 WSW 6 17 17 9 3 52 W 7 17 20 6 4 54 WNW 8 11 28 11 8 66 NW 7 15 21 14 15 72 NNW 4 18 12 28 1 63 Variable 0 0 0 0 0 0 Total 6 86 219 359 316 147 1133 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 45 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Slightly Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 5 11 8 4 30 NNE 0 1 6 14 3 0 24 NE 0 1 8 22 7 1 39 ENE 0 0 10 29 5 1 45 E 0 2 4 21 16 0 43 ESE 0 3 5 12 9 0 29 SE 0 1 7 9 6 4 27 SSE 0 0 1 9 6 2 18 S 0 0 6 6 22 12 46 SSW 0 0 5 8 26 45 84 SW 0 2 5 9 23 9 48 WSW 0 0 5 7 3 0 15 W 0 1 8 10 7 4 30 WNW 0 4 3 21 12 3 43 NW 0 0 4 8 18 4 34 NNW 0 2 7 12 20 1 42 Variable 0 0 0 0 0 0 0 Total 0 19 89 208 191 90 597 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 46 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Moderately Stable 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 2 2 2 6 NNE 2 0 2 4 0 0 8 NE 1 1 1 1 0 0 4 ENE 0 1 0 0 0 0 1 E 1 0 1 4 2 0 8 ESE 0 4 3 14 3 2 26 SE 1 0 2 24 14 2 43 SSE 0 0 3 7 11 0 21 S 0 0 4 10 14 13 41 SSW 0 4 4 7 20 10 45 SW 0 2 1 7 1 0 11 WSW 0 1 1 6 2 0 10 W 0 1 8 8 10 3 30 WNW 0 0 5 6 0 0 11 NW 2 0 4 2 7 0 15 NNW 1 1 1 0 2 0 5 Variable 0 0 0 0 0 0 0 Total 8 15 40 102 88 32 285 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 47 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: April - June 2012 Stability Class - Extremely Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 2 3 0 5 SSE 0 2 15 0 26 S 0 0 1 4 11 SSW 0 0 0 0 SW 0 3 0 4 WSW 1 0 0 7 W 2 0 0 3 WNW 0 0 0 0 NW 0 0 0 0 NNW 0 0 0 0 Variable 0 0 0 0 Total 5 21 26 4 56 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 2 Page 48 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability C lass - Extremely Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 1 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 0 2 0 0 0 2 SSE 0 0 3 0 0 0 3 S 0 0 0 2 1 0 3 SSW 0 0 1 3 0 0 4 SW 0 0 8 3 0 0 11 WSW 0 0 14 3 0 0 17 W 0 0 4 2 0 0 6 WNW 0 0 0 8 0 0 8 NW 0 0 2 0 0 3 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 0 35 23 1 0 59 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 49 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Moderately Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 4 NNE 4 4 NE 2 3 ENE 0 0 E 0 0 ESE 0 1 SE 8 10 SSE 0 1 S 5 8 SSW 7 15 SW 3 7 WSW 12 18 W 16 20 WNW 2 4 NW 0 1 NNW 3 6 Variable 0 0 Total 0 14 63 24 1 0 102 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 50 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Slightly Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 3 0 0 8 NNE 0 0 0 0 0 5 NE 0 0 2 0 0 6 ENE 0 0 0 0 0 2 E 0 1 0 0 0 1 ESE 0 0 0 0 0 2 SE 0 1 0 0 0 3 SSE 0 4 0 0 0 9 S 0 2 2 0 0 8 SSW 0 9 2 0 0 17 SW 0 7 5 4 0 0 16 WSW 0 3 14 0 0 18 W 0 9 9 3 0 0 21 WNW 0 4 5 2 0 0 11 NW 0 1 6 4 2 0 13 NNW 0 0 7 10 0 0 17 Variable 0 0 0 0 0 0 0 Total 0 42 80 33 2 0 157 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 51 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Neutral - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 15 36 9 62 NNE 13 14 1 31 NE 19 23 14 57 ENE 24 20 17 61 E 10 10 4 26 ESE 11 7 1 19 SE 21 4 1 27 SSE 19 7 2 28 S 24 23 2 52 SSW 15 13 0 29 SW 21 18 6 47 WSW 19 21 6 47 W 25 14 6 46 WNW 17 15 2 37 NW 6 26 3 38 NNW 19 45 32 97 Variable 0 0 0 0 Total 19 278 296 106 5 0 704 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 52 of 76

LASALLE COUNTY NUCLEAR POWER STATION -

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Slightly Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Win .d Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 26 5 1 0 0 32 NNE 2 21 13 0 0 0 36 NE 0 4 29 6 0 0 39 ENE 2 2 21 5 0 0 30 E 1 8 14 0 0 0 23 ESE 0 9 3 0 0 0 12 SE 2 2 2 0 0 0 6 SSE 2 9 4 1 0 0 16 S 1 11 7 4 0 0 23 SSW 2 6 9 3 0 0 20 SW 1 11 9 5 0 0 26 WSW 1 7 11 2 0 0 21 W 3 16 7 1 0 0 27 WNW 1 7 5 1 0 0 14 NW 0 13 16 0 0 0 29 NNW 1 16 3 2 0 0 22 Variable 0 0 0 0 0 0 0 Total 19 168 158 31 0 0 376 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stabil ity classes: 0 Page 53 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Moderately Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 8 0 0 0 0 10 NNE 1 4 0 0 0 0 5 NE 1 2 0 0 0 0 3 ENE 0 2 0 0 0 3 E 2 29 8 0 0 0 39 ESE 4 17 1 0 0 0 22 SE 2 14 4 0 0 0 20 SSE 4 8 2 0 0 0 14 S 5 11 8 0 0 0 24 SSW 2 13 19 0 36 SW 5 11 18 0 34 WSW 3 14 18 0 35 W 4 15 3 0 22 WNW 5 32 1 0 38 NW 2 13 1 0 16 NNW 6 12 3 0 21 Variable 0 0 0 0 0 Total 48 205 87 0 342 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 54 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Cl ass - Extremely Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 1 NNE 1 0 1 NE 0 0 0 ENE 0 0 1 E 13 0 14 ESE 28 1 30 SE 45 4 49 SSE 42 3 45 S 42 23 68 SSW 48 15 63 SW 55 7 65 WSW 48 11 60 W 34 4 41 WNW 25 0 25 NW 1 0 2 NNW 0 0 1 Variable 1 0 1 Total 14 384 68 0 0 467 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 55 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Extremely Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 1 0 0 S 0 0 1 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 Total 0 0 0 1 0 0 1 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 56 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Moderately Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 NNE 0 0 0 1 0 1 NE 0 0 0 1 0 ENE 0 0 0 0 0 0 E 0 0 0 0 0 0 ESE 0 0 0 0 1 SE 0 0 2 4 0 6 SSE 0 0 0 1 0 1 S 0 0 0 0 0 0 SSW 0 0 0 3 4 SW 0 0 4 0 0 4 WSW 0 0 0 3 0 4 W 0 0 0 2 0 2 WNW 0 0 0 2 0 3 NW 0 0 1 0 2 NNW 0 0 0 0 0 0 Variable 0 0 0 0 0 0 Total 0 0 8 16 2 3 29 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl asses: 0 Page 57 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Slightly Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 NNE 0 3 NE 0 4 ENE 0 0 E 0 0 ESE 0 1 SE 0 5 SSE 0 3 S 0 8 SSW 2 9 SW 0 7 WSW 0 13 W 0 1 17 5 0 0 23 WNW 0 0 0 2 2 0 4 NW 0 0 0 2 1 0 3 NNW 0 0 0 3 0 0 3 Variable 0 0 0 0 0 0 0 Total 0 4 38 31 14 2 89 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 58 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Neutral - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 10 19 42 22 95 NNE 6 10 15 2 34 NE 13 22 27 21 89 ENE 17 9 22 18 68 E 8 4 5 4 22 ESE 11 9 2 2 24 SE 10 2 1 24 SSE 16 12 4 0 33 S 21 17 14 2 54 SSW 17 17 15 5 56 SW 18 24 20 5 69 WSW 11 29 16 5 62 W 20 44 18 7 90 WNW 7 24 17 2 50 NW 7 25 31 9 78 NNW 6 20 23 20 72 Variable 0 0 0 0 0 Total 10 199 295 273 125 18 920 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 59 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July September 2012 Stability Class - Slightly Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 5 12 18 7 0 43 NNE 1 5 S 16 0 0 27 NE 0 5 9 25 12 0 51 ENE 0 0 11 20 3 0 34 E 0 5 9 19 8 0 41 ESE 0 5 10 6 3 0 24 SE 0 3 6 3 4 0 16 SSE 1 1 4 1 1 0 8 S 1 5 7 6 3 1 23 SSW 0 2 6 9 7 14 38 SW 0 4 6 9 12 12 43 WSW 1 1 7 12 9 1 31 W 0 4 7 14 3 0 28 WNW 2 5 10 8 2 0 27 NW 1 11 8 19 4 0 43 NNW 0 1 10 6 9 1 27 Variable 0 0 0 0 0 0 0 Total 8 62 127 191 87 29 504 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 60 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Moderately Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 1 6 4 0 13 NNE 1 1 3 2 2 0 9 NE 0 2 0 2 0 5 ENE 1 5 2 0 0 0 8 E 3 6 4 9 3 0 25 ESE 5 1 11 18 2 0 37 SE 1 2 9 21 6 0 39 SSE 0 3 10 14 4 1 32 S 1 5 14 9 16 0 45 SSW 2 4 16 23 16 11 72 SW 0 4 15 23 12 4 58 WSW 2 1 10 28 12 0 53 W 1 0 15 16 7 0 39 WNW 1 3 11 18 1 0 34 NW 3 3 9 7 1 0 23 NNW 0 2 11 6 2 0 21 Variable 0 0 1 0 0 0 1 Total 21 44 142 202 89 16 514 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 61 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: July - September 2012 Stability Class - Extremely Stable- 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 NNE 0 1 NE 0 0 ENE 0 1 E 0 1 ESE 0 1 SE 1 10 SSE 10 19 S 7 19 SSW 13 27 SW 2 23 WSW 0 17 W 0 18 WNW 1 10 NW 0 3 NNW 0 0 Variable 0 0 Total 4 9 34 59 35 10 151 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 62 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class Extremely Unstable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 NNE 0 0 0 0 0 NE 0 0 0 0 0 ENE 0 0 0 0 0 E 0 0 0 0 0 ESE 0 0 0 0 0 SE 0 0 0 0 0 SSE 0 0 0 0 0 S 0 0 0 0 0 SSW 0 0 0 SW 0 0 0 0 0 WSW 0 0 0 0 0 W 0 0 0 0 0 WNW 0 0 0 0 0 NW 0 0 0 0 0 NNW 0 0 0 0 0 Variable 0 0 0 0 0 Total 0 0 0 1 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 63 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Moderately Unstable - 200Ft-33 Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 NNE 0 NE 0 1 ENE 0 0 E 0 0 ESE 0 0 SE 0 0 SSE 0 0 S 0 0 SSW 0 6 SW 0 3 WSW 0 0 W 0 0 WNW 0 0 NW 0 0 NNW 0 0 Variable 0 0 Total 0 0 2 6 3 0 11 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 64 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Slightly Unstable 200Ft-33Ft De lta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 2 NNE 0 0 1 0 0 0 1 NE 0 0 1 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 1 6 3 0 10 SW 0 0 0 3 2 0 5 WSW 0 0 0 0 1 0 1 W 0 0 1 0 1 0 2 WNW 0 0 1 2 0 4 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 0 6 12 8 0 26 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all stability classes: 6 Page 65 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Neutral - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 25 40 11 0 0 77 NNE 0 16 23 6 0 0 45 NE 0 6 10 3 0 0 19 ENE 0 5 19 1 0 0 25 E 1 6 10 6 0 0 23 ESE 0 4 8 1 0 0 13 SE 0 1 9 4 2 0 16 SSE 0 6 18 8 3 2 37 S 0 10 29 12 7 7 65 SSW 0 14 20 27 24 0 85 SW 1 7 11 10 3 1 33 WSW 0 15 10 6 1 1 33 W 3 23 34 25 8 0 93 WNW 0 19 43 42 8 0 112 NW 2 10 37 22 6 3 80 1 24 51 24 12 2 114 Variable 0 0 0 0 0 0 0 Total 9 191 372 208 74 16 870 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all stability classes: 6 Page 66 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Slightly Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 25 43 5 0 0 73 NNE 30 11 1 0 0 43 NE 6 12 1 0 0 19 ENE 4 16 3 0 0 24 E 5 9 10 6 0 30 ESE 4 3 3 1 0 12 SE 7 18 2 3 0 31 SSE 12 14 2 0 0 30 S 5 39 41 12 1 99 SSW 6 37 39 16 0 98 SW 17 15 18 2 0 53 WSW 9 26 13 0 0 51 W 22 34 8 2 1 69 WNW 23 35 5 11 23 97 NW 4 17 1 2 3 27 NNW 9 17 13 6 0 45 Variable 0 0 0 0 0 0 Total 13 188 346 165 61 28 801 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 67 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Cl ass Moderately Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 0 10 NNE 0 0 0 NE 0 0 0 ENE 1 0 3 E 5 5 11 ESE 10 3 13 SE 6 5 11 SSE 6 17 24 S 7 14 30 SSW 7 31 53 SW 8 10 18 WSW 4 6 11 W 11 6 17 WNW 1 7 8 NW 3 3 8 NNW 2 0 2 Variable 0 0 0 Total 10 80 107 21 1 0 219 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 68 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Extremely Stable - 200Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 3 6 0 0 0 9 ESE 0 9 3 0 0 0 12 SE 1 44 6 0 0 0 51 SSE 1 36 21 0 0 0 58 S 0 27 15 0 0 0 42 SSW 0 23 30 3 0 0 56 SW 0 10 8 3 0 0 21 WSW 0 2 0 1 0 0 3 W 1 3 1 0 0 0 5 WNW 1 7 6 0 0 0 14 NW 0 0 2 0 0 0 2 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 5 164 98 7 0 0 274 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabi lity class: 0 Hours of missing stability measurements in all s tability cl asses: 6 Page 69 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Extremely Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 0 0 N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 Total 0 0 0 0 0 0 0 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 70 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Moderately Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 0 0 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 71 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Slightly Unstable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 0 0 0 1 0 0 NNE 0 1 0 1 0 0 1 NE 0 0 0 0 0 ENE 0 0 0 0 0 0 E 0 0 0 0 0 0 ESE 0 0 0 0 0 0 SE 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 1 1 1 SSW 0 3 0 0 1 1 SW 0 2 0 0 0 0 WSW 0 0 0 0 0 0 W 0 0 0 0 1 0 WNW 0 1 0 0 0 0 NW 0 0 0 0 0 0 NNW 0 0 0 0 0 0 Variable 0 0 Total 0 0 3 3 2 8 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 72 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Neutral - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 25 32 14 0 81 NNE 6 28 29 10 0 73 NE 1 19 15 3 0 38 ENE 1 13 20 4 0 38 E 2 7 6 12 7 34 ESE 2 11 2 1 2 19 SE 4 3 10 0 3 20 SSE 4 22 12 3 6 48 S 7 16 24 8 21 76 SSW 7 9 31 19 41 107 SW 6 15 6 15 11 53 WSW 6 18 3 9 4 41 W 10 26 26 21 10 94 WNW 6 26 34 33 37 136 NW 10 30 51 27 23 142 NNW 12 26 27 9 15 90 Variable 0 0 0 0 0 0 Total 7 93 294 328 188 180 1090 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 9 Hours of missing stability measurements in all stability classes: 6 Page 73 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Slightly Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 10 16 23 2 52 NNE 6 22 6 0 36 NE 9 11 3 0 24 ENE 0 12 0 0 12 E 2 9 5 1 17 ESE 5 3 0 2 11 SE 2 6 4 5 18 SSE 6 8 13 0 28 S 3 23 25 45 97 SSW 6 14 32 55 112 SW 14 18 18 13 66 WSW 8 19 12 8 48 W 6 15 10 7 41 WNW 12 19 26 12 72 NW 10 13 13 1 43 NNW 2 3 9 5 21 Variable 0 0 0 0 0 Total 3 28 101 211 199 156 698 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 12 Hours of missing stability measurements in all stability classes: 6 Page 74 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Moderately Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 0 0 5 NNE 2 0 0 0 3 NE 0 0 0 0 0 ENE 0 0 0 0 2 E 1 3 0 0 6 ESE 3 4 3 0 12 SE 9 7 3 0 19 SSE 2 20 9 3 34 S 5 16 17 8 49 SSW 9 13 13 23 58 SW 13 5 19 8 46 WSW 3 1 1 1 8 W 2 0 0 0 2 WNW 2 5 4 0 12 NW 0 1 10 2 13 NNW 0 1 0 0 2 Variable 0 0 0 0 0 Total 4 14 53 76 79 45 271 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 75 of 76

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2012)

METEOROLOGICAL DATA LaSalle County Generating Station Period of Record: October - December 2012 Stability Class - Extremely Stable - 375Ft-33Ft Delta-T (F)

Winds Measured at 375 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 2 0 0 0 0 2 SE 0 0 0 2 3 0 5 SSE 0 0 1 14 2 0 17 S 0 0 4 17 9 5 35 SSW 1 0 4 4 4 12 25 SW 0 3 7 7 1 19 WSW 0 4 3 0 0 8 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 1 1 3 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 2 6 20 47 20 19 114 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 6 Page 76 of 76

Appendix A Offsite Dose Calculation Manual Revision 4 ODCM Change Summary Matrix

ODCM change summary matrix I Page 1 of 2 Item# 3(Old) Rev. I (New) Rev. I Determination Description of change 3 ae# 4page # identifier 7toofcag Editorial and grammatical - Determination EG Removal of legacy methodology related changes - Determination METH Drum evaporator assessment to gaseous effluent pathway assessment - Determination DRUM WWTF potential tritium pathway and associated related changes - Determination WW 1 TOC TOC EG Table of Contents was revised to reflect changes due to added/removed content 2 1.12.2.1-2 1.12.2.1-2 EG Formatted (indented) the REC 12.2.1 table, Condition C, logical connector 'OR' between Required Actions C.3 and C.4, and added '30 days' to the completion time of C.4 to clarify (ref. assignment 1278672-02) 3 1-12.4.1-2 1-12.4.1-2 EG Title of table R12.4.4-1 corrected to indicate the actual number of pages in the table to 1-12.4.1- to 1-12.4.1-6 6 4 N/A 11.2-1 WW Added discussion to section 2.1 detailing the assessment of non significant effluent contribution from WWTF operations (ref. assignment 1301739-07) 5 N/A 11.2-7 DRUM Added discussion to section 2.4 detailing the assessment of effluent contribution from drum evaporation activities (ref. assignment 1262028-04)

6. 11.3-5 N/A METH Removed description of legacy software no longer utilized and dual methodology for dose determination purposes at LaSalle Station in section 3.4.1

7. 11.3-5 to N/A METH Removed legacy methodology no longer utilized for liquid dose determination in 11.3-7 section 3.4.1.1

8. 11.3-8 N/A METH Removed legacy methodology no longer utilized for liquid potable water pathway dose determination in section 3.4.2.1

9. 11.3-9 N/A METH Removed legacy methodology no longer utilized for liquid fish ingestion pathway dose determination in section 3.4.3.1

10. 11.4-1 N/A METH Removed description of legacy software no longer utilized and dual methodology for dose determination purposes at LaSalle Station in section 4.1

11. 11.4-2 to N/A METH Removed legacy methodology no longer utilized for Noble Gas Total Body Dose Rate 11.4-3 determination in section 4,2.1.1

12. 11.4-4 to N/A METH Removed legacy methodology no longer utilized for Noble Gas Skin Dose Rate 11.4-5 determination in section 4.2.1.2

13. 11.4-6 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Organ Dose Rate 11.4-7 determination in section 4.2.1.3

14. 11.4-8 to N/A METH Removed legacy methodology no longer utilized for Noble Gas Gamma Air Dose 11.4-9 determination in section 4.2.2.1

15. 11.4-10 to N/A METH Removed legacy methodology no longer utilized for Noble Gas Beta Air Dose

Item # (Old) Rev. (New) Rev. Determination Description of change

[ODCM change 3 page summary

4matrix page # identifier IPage 2 of 2 11.4-11 determination in section 4.2.2.2

16. 11.4-13 N/A METH Removed legacy methodology no longer utilized for Noble Gas Whole Body Dose determination in section 4.2.2.3

17. 11.4-14 to N/A METH Removed legacy methodology no longer utilized for Noble Gas Skin Dose 11.4-15 determination in section 4.2.2.4

18. 11.4-16 N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Organ Dose determination in section 4.2.3

19. 11.4-18 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Ground Plane 11.4-19 Dose determination in section 4.2.3.1

20. 11.4-20 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Inhalation Dose 11.4-21 determination in section 4.2.3.2

21. 11.4-22 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Vegetation 11.4-25 Ingestion Dose determination in section 4.2.3.3

22. 11.4-26 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Milk Ingestion 11.4-27 Dose determination in section 4.2.3.4

23. 11.4-29 to N/A METH Removed legacy methodology no longer utilized for Non Noble Gas Meat Ingestion 11.4-30 Dose determination in section 4.2.3.5

24. 11.4-38 to 11.4-24 METH Removed legacy methodology data table 4.6 no longer utilized for Noble Gas Dose 11.4-52 determination

25. 11.4-53 to 11.4-25 METH Removed legacy methodology data table 4.7 no longer utilized for Noble Gas Dose 11.4-67 determination

26. 11.6-9 11.6-9 EG Locations on map in figure 6-1 were clarified to more accurately depict the actual locations.

27. 11.6-10 11.6-10 EG Locations on map in figure 6-2 were clarified to more accurately depict the actual locations.

Appendix B Offsite Dose Calculation Manual Part I RECS Part II ODCM LaSalle Station Units 1 and 2 Revision 4

CY-LA-1 70-301 Revision 4 OFFSITE DOSE CALCULATION MANUAL PART I RECS PART II ODCM LaSalle Station Units 1 and 2

CY-LA-170-301 Revision 4 ODCM Parts I and II ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS)

PAGE 1.0 US E A ND A P P LIC A T IO N ....................................................................................... 1-1.1-1 1.1 D E F INITIO NS ......................................................................................................... 1-1 .1-1 1.2 LO G IC A L C O NNEC TO R S ...................................................................................... 1-1.2-1 1.3 C O MP LE T IO N T IME S ............................................................................................ 1-1.3-1 1.4 F R E Q UE NC Y ......................................................................................................... 1-1.4 -1 1.5 R EC & RSR IMPLEM ENTATIO N............................................................................ 1-1.5-1 2.0-11.0 NOT USED 12.0 ODCM RADIOLOGICAL EFFLUENT CONTROL (REC) APPLICABILITY ........... 1-12.0-1 12.0 ODCM RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREM ENT (RSR) APPLICABILITY ............................................................. 1-12.0-3 12.1 NOT USED 12.2 INS T R UME NTA T IO N ........................................................................................ 1-12.2.1-1 12.2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTR UME NTA TIO N.............................................................................. 1-12.2.1-1 12.2.2 Radioactive GASEOUS EFFLUENT MONITORING INSTR UME NTA TIO N.............................................................................. 1-12.2.2-1 12.3 LIQ UID E FFLU E NT S ......................................................................................... 1-12 .3.1-1 12.3.1 Liquid Effl uent Concentration .................................................................. 1-12.3.1-1 12.3.2 Dose from Liquid Effluents ...................................................................... 1-12.3.2-1 12.3.3 Liquid Radwaste Treatment System ....................................................... 1-12.3.3-1 Page 1 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS)

PAGE 12.4 GASEOUS EFFLUENTS AND TOTAL DOSE ................................................... 1-12.4.1-1 12.4.1 G aseous Effluent Dose Rates ................................................................. 1-12.4.1-1 12.4.2 Dose from Noble Gases ......................................................................... 1-12.4.2-1 12.4.3 Dose from Iodine-1 31, Iodine-1 33, Tritium and Radioactive Materials in P a rticulate Fo rm ...................................................................................... 1-12 .4 .3-1 12.4.4 Gaseous Radwaste Treatment System ................................................... 1-12.4.4-1 12.4.5 Ventilation Exhaust Treatment System ....................... I 1-12.4.5-1 12 .4.6 Mark IIC ontainm ent ................................................................................ 1-12 .4 .6-1 12 .4 .7 Tota l Do se ............................................................................................... 1-12 .4 .7-1 12 .4 .8 Main C ondense r ...................................................................................... 1-12 .4 .8-1 12.4.9 Dose Limits For Members Of The Public ................................................ 1-12.4.9-1 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................... 1-12.5.1-1 12.5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1-12.5.1-1 12.5.2 LA ND US E C E NS US .............................................................................. 1-12.5.2-1 12.5.3 Interlaboratory COMPARISON PROGRAM ............................................ 1-12.5.3-1 12.5.4 METEOROLOGICAL MONITORING PROGRAM ................................... 1-12.5.4-1 12.6 REPO RTING REQ UIREM ENTS ........................................................................ 1-12.6.1-1 12.6.1 Annual Radiological Environmental Operating Report .......................... 1-12.6.1-1 12.6.2 Annual Radioactive Effluent Release Report ........................................ 1-12.6.2-1 12.6.3 Off-site Dose Calculation Manual (ODCM) ........................................... 1-12.6.3-1 12.6.4 Major Changes to Radioactive Waste Treatment Systems (Liquid a nd Gaseo us) ....................................................................................... I-12 .6 .4-1 Page 2 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS)

B BASES .................................................... I-B-1 B.12.0 REC & RSR APPLICABILITY BASES ................................................... I-B12.0-1 B.12.1 NOT USED B.12.2 INSTR UMENTATIO N ......................................................................... 1-B 12.2.1-1 B.12.2.1 Radioactive Liquid Effluent Monitoring Instrum entation ................................................................ I-B 12 .2 .1-1 B.12.2.2 Radioactive Gaseous Effluent Monitoring Instrum entation .............................................. 1-B12.2.2-1 B 12.3 LIQ UID EFFLU ENTS .......................................................................... I-B 12.3.1-1 B.12.3.1 Liquid Effluent Concentration ........................................... 1-B12.3.1-1 B.12.3.2 Dose from Liquid Effluents ............................................... I-B12.3.2-1 B.12.3.3 Liquid Radwaste Treatment Systems .............................. i-B12.3.3-1 B.12.4 GASEOUS EFFLUENTS & TOTAL DOSE ......................................... 1-B12.4.1-1 B.12.4.1 Gaseous Effluent Dose Rates .......................................... 1-B12.4.1-1 B.12.4.2 Dose From Noble Gases ................................................. 1-B12.4.2-1 B.12.4.3 Dose From Iodine-1 31, Iodine-1 33Tritium And Radioactive Materials In Particulate Form ....................... I-B12.4.3-1 B.12.4.4 Gaseous Radwaste Treatment (O ffgas) System ............................................................... 1-1 12.4.4-1 B.12.4.5 Ventilation Exhaust Treatment System ............................ !-B12.4.5-1 B.12.4.6 Mark II Containm ent ........................................................ 1-B12.4.6-1 B.12.4 .7 Total D ose ....................................................................... 1-B 12.4 .7-1 B.12.4.8 Main C ondenser .............................................................. I-B 12.4.8-1 B.12.4.9 Dose Limits for Members of the Public ............................ 1-112.4.9-1 B.12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .... 1-B12.5.1-1 B.12 .5.1 R E MP .............................................................................. 1-B 12 .5 .1-1 8.12.5.2 Land Use Census ............................................................ 1-B 12.5.2-1 B.12.5.3 Interlaboratory Comparison Program ............................... I-B12.5.3-1 B.12.5.4 Meteorological Monitoring Program ................................. I-B12.5.4-1 Page 3 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 0DCM Parts I and II TABLE OF CONTENTS PART II - ODCM PAGE

1.0 INTRODUCTION

- ODCM GENERAL INFORMATION ........................................... 11.1-1 1.1 STRUCTURE OF THE ODCM ............................... 11.1-1 1.2 REGULATIONS ......................................... 11.1-2 1.2.1 C ode of Federal R egulations ............................................................... 11.1-2 1.2.2 Radiological Effluent Technical Specifications .................................... 11.1-4 1.2.3 O ffsite Dose Calculation Manual ......................................................... 11.1-5 1.2.4 O verlapping R equirem ents .................................................................. 11.1-5 1.2.5 Dose Receiver Methodology ............................................................... 11.1-6 1.3 OFFSITE DOSE CALCULATION PARAMETERS ....................................... 11.1-10 1.4 R E F E R E NC E S ............................................................................................. 11.1-10 2.0 INSTRUM ENTATIO N AND SYSTEM S ..................................................................... 11.2-1 2 .1 LIQ UID R E LE A S E S ....................................................................................... 11.2 -1 2.1.1 Radw aste Discharge tanks ........................................................... 11.2-1 2.1.2 C ooling Pond Blow dow n ............................................................... 11.2-1 2.2 RA D IAT IO N MO NITO R S ............................................................................... 11.2-2 2.2.1 Liquid Radwaste Effluent Monitor ................................................. 11.2-2 2.2.2 Service Water Effl uent Monitor ..................................................... 11.2-2 2.2.3 RHR Heat Exchange Cooling Water Effluent Monitors ................. 11.2-2 2.3 LIQUID RADIATION EFFLUENT MONITORS ALARM AND TR IP S E T P O INT S .......................................................................................... 11.2-2 2.3.1 Liquid Radwaste Effluent Monitor ................................................. 11.2-3 2.3.2 Service Water Effluent Monitor ..................................................... 11.2-3 2.3.3 RHR Heat Exchanger Cooling Water Effluent Monitors ................ 11.2-3 2.3.4 Discharge Flow R ates ................................................................... 11.2-4 2.3.5 Allocation of Effluents from Common Release Points ................... 11.2-5 2.3.6 Projected Doses from Releases .................................................... 11.2-6 2.3.7 Solidification of Waste/Process Control Program .......................... 11.2-6 2.4 A IR BO R NE R E LEA S ES ................................................................................. 11.2-6 2.4.1 Condenser Offgas Treatment System ........................................... 11.2-7 2.4.2 Ventilation Exhaust Treatment System ......................................... 11.2-8 2.5 GASEOUS EFFLUENT RADIATION MONITORS ......................................... 11.2-8 2.5.1 Station Vent Stack Effluent Monitor .............................................. 11.2-8 2.5.2 Standby Gas Treatment System Effluent Monitor ......................... 11.2-8 2.5.3 Reactor Building Ventilation Monitors ........................................... 11.2-9 2.5.4 Condensor Air Ejector Monitors .................................................... 11.2-9 2.5.5 Turbine Building Trackway and North Service Building ............... 11.2-10 Page 4 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II TABLE OF CONTENTS PART II - ODCM PAGE 2.6 GASEOUS RADIATION EFFLUENT ALARM AND TRIP SETPOINTS. 11.2-10 2.6.1 Reactor Building Vent Effluent Monitor ....................................... 11.2-10 2.6.2 Condenser Air Ejector Monitors .................................................. 11.2-10 2.6.3 Station Vent Stack Effluent Monitor ............................................ 11.2-11 2.6.4 Standby Gas Treatment Stack Monitor ....................................... 11.2-11 2 .6 .5 Release Lim its ............................................................................ 11.2-1 1 2 .6 .6 Re lease Mixture .......................................................................... 11.2-12 2 .6 .7 C onversio n Factors ..................................................................... 11.2-12 2.6.8 HV A C Flow R ates ....................................................................... 11.2-13 2.6.9 Allocation of Effluents from Common Release Points ................. 11.2-13 2.6.10 Dose P rojections ......................................................................... 11.2-13 3.0 LIQ UID E F F LU E NT S .......................................................................................... 11.3-1 3.1 LIQUID EFFLUENT RELEASES - GENERAL INFORMATION .............. 11.3-1 3.2 LIQUID EFFLUENT CONCENTRATIONS ............................................... 11.3-2 3.3 LIQUID EFFLUENT DOSE CALCULATION REQUIREMENTS .............. 11.3-4 3.4 DOSE METHODOLOGY ......................................................................... 11.3-5 3.4.1 Liquid Effluent Dose Method: General .......................................... 11.3-5 3.4.2 Potable Water Pathway ................................................................. 11.3-6 3.4.3 Fish Ingestion Pathw ay ................................................................. 11.3-7 3 .4 .4 Offsite Doses ................................................................................ 11.3-7 3 .4 .5 D rinking Wate r .............................................................................. 11.3-7 3.5 BIOACCUMULATION FACTORS ............................................................ 11.3-7 4.0 G AS EO US E FFLU E NTS .................................................................................... 11.4-1 4.1 GASEOUS EFFLUENTS- GENERAL INFORMATION .......................... 11.4-1 4.2 GASEOUS EFFLUENTS - DOSE AND DOSE RATE CALCULATION R E Q UIR E ME NT S .................................................................................... 11.4-2 4.2.1 Instantaneous Dose Rates ............................................................ 11.4-2 4.2.2 Time Averaged Dose from Noble Gas .......................................... 11.4-5 4.2.3 Time Averaged Dose from Non-Noble Gas Radionuclides ........... 11.4-9 Page 5 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II TABLE OF CONTENTS PART 11- ODCM PAGE 5 .0 T O TAL DO S E ..................................................................................................... 11.5-1 5.1 TOTAL DOSE CALCULATION REQUIREMENTS .................................. 11.5-1 5.1.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40 C FR190 ..................................................................................... 11.5 -1 5.1.2 Total Dose Calculation Methodology ............................................ 11.5-2 5 .1.3 BW R S kyshine .............................................................................. 11.5-2 5.2 BWR SKYSHINE CALCULATION ............................................................ 11.5-3 5.3 ONSITE RADWASTE AND RAD MATERIAL STORAGE FACILITIES ..... 11.5-6 5.3.1 Process Waste Storage Facilities ................................................ 11.5-6 5.3.2 DAW Storage Facilities ................................................................ 11.5-6 5 .3.3 ISFS I Facilitie s ............................................................................ 11.5-6 5.4 ME T HO DO LO G Y...................................................................................... 11.5-6 5.5 T OTAL DO S E ........................................................................................... 11.5-7 5.6 COMPLIANCE TO TOTAL DOSE LIMITS ................................................ 11.5-8 5.6.1 Total Effective Dose Equivalent Limit- 10CFR20 Compliance ..... 11.5-8 5.6.2 Dose to a MEMBER OF THE PUBLIC in the Unrestricted Area .............................................................................................. 11.5 -8 5.6.3 Dose to a MEMBER OF THE PUBLIC in the Restricted Area ....... 11.5-8 5.6.4 Total Dose Due to the Uranium Fuel Cycle (40CFR190) .............. 11.5-9 5.7 WHEN COMPLIANCE ASSESSMENT IS REQUIRED ........................... 11.5-10 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................... 11.6-1 Page 6 of 11 LaSalle ODCM Table of Contents

CY-LA-1 70-301 Revision 4 ODCM Parts I and II ODCM TABLE OF CONTENTS LIST OF TABLES PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS)

PAGE Table 1-1 C o m plia nce Matrix ............................................................................. 1-1.1-6 Table R12.2.1-1 Radioactive Liquid Effluent Monitoring Instrumentation ................ 1-12.2.1-5 Table R12.2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation ........... 1-12.2.2-5 Table R12.2.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation A p p lica b ility .................................................................................. 1-12 .2 .2 -7 Table R12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liq u id Wa ste ................................................................................. 1-12 .3 .1-3 Table R12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program ......... 1-12.3.1-4 Table R12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program .... 1-12.4.1-2 Table R12.5.1-1 Radiological Environmental Monitoring Program .......................... 1-12.5.1-6 Table R12.5.1-2 Reporting Levels for Radioactivity Concentrations in Environm ental Sam ples .............................................................. 1-12.5.1-11 Table R12.5.1-3 Detection Capabilities for Environmental Sample Analysis Low er Lim it of Detection ............................................................. 1-12.5.1-12 PART II - ODCM Table 1-1 R egulatory Dose Lim it Matrix ......................................................................... 11.1-7 Table 1-2 Dose Assessment Receivers ......................................................................... 11.1-8 Table 1-3 Miscellaneous Dose Assessment Factors: Environmental Parameters ....... 11.1-17 Table 1-4 Stable Elem ent Transfer Data ...................................................................... 11.1-19 Table 2-1 Assumed Composition Of the LaSalle Station Noble Gas Effluent ............... 11.2-14 Page 7 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II ODCM TABLE OF CONTENTS LIST OF TABLES PART II - ODCM PAGE Table 3-1 Bioaccumulation Factors (Bfi) to be Used in the Absence of Site-S p e c ifi c Da ta .................................................................................................. 11.3 -8 Table 4-1 C ritica l R a n g e s ............................................................................................. 11.4 -18 Table 4-2 Average Wind Speeds ................................................................................. 11.4-19 Table 4-3 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary ........... 11.4-20 Table 4-4 X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary .............. 11.4-21 Table 4-5 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles ..... 11.4-22 Table 4-6 De le te d .......................................................................................................... 11.4 .2 4 Table 4-7 D e le ted ......................................................................................................... 11.4 -2 5 Table 4-8 Parameters for Calculations of N-16 Skyshine Radiation From La S a lle ......................................................................................................... 11.4 -2 6 Table 4-9 Elevated Level Joint Frequency Distribution Table Summary ...................... 11.4-27 Table 4-10 Mid Elevation Joint Frequency Distribution Table Summaries ...................... 11.4-29 Table 4-11 Ground Level Joint Frequency Distribution Table Summary ......................... 11.4-31 Table 4-12 Station Characteristics ...................................................................................... 11.4-33 Table 4-13 Dose Factors for Noble Gases ..................................................................... 11.4-34 Table 4-14 External Dose Factors for Standing on Contaminated Ground DFGIj (mrem/hr per pCi/ 2

)................................................................................... 11.4-35 Table 4-15 Maximum Bi and Vi at or Beyond the Unrestricted Area Boundary ....... 11.4-38 Table 4-16 Infant Drinking Water AiT .............................................................................. 11.4-53 Table 4-17 Child Drinking W ater AiT ............................................................................... 11.4-57 Table 4-18 Teen Drinking W ater AiT ............................................................................... 11.4-61 Table 4-19 Adult Drinking W ater AiT ............................................................................... 11.4-65 Page 8 of 11 LaSalle ODCM Table of Contents

CY-LA-1 70-301 Revision 4 ODCM Parts I and II Table 4-20 Infa nt F is h A T ............................................................................................... 11.4 -6 9 Table 4-21 C h ild F is h AiT................................................................................................ 11.4 -7 3 Table 4-22 T e e n Fis h A r ................................................................................................ 11.4 -7 7 Table 4-23 A d ult F is h A T................................................................................................ 11.4 -8 1 Table 4-24 Infa n t Inh a latio n P i........................................................................................ 11.4 -8 5 Table 4-25 Child Inhalation Pi ........................................................................................ 11.4-89 Table 4-26 Teen Inhalation Pi ................................................. .. .... .... ..... .... ...... ... .. .... .... . 11.4-93 Table 4-27 Adult Inhalation Pi ................................................. .. .... .... ..... .... .... ..... ...... .... . 11.4-97 Table 4-28 All Age Groups Ground Plane Ri ................................................................ 11.4-101 Table 4-29 Infant Inhalation R ...................... I............................................................... 11.4-105 Table 4-30 Child Inhalation Ri ...................................................................................... 11.4-109 Table 4-31 Teen Inhalation R1 ................................................ ..... .... ..... .... .... ..... .... .... .. . 11.4-113 Table 4-32 Adult Inhalation R, ...................................................................................... 11.4-117 Table 4-33 Infant Vegetation Ri .................................................................................... 11.4-121 Table 4-34 Child Vegetation R1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.4-125 Table 4-35 Teen Vegetation R1 ................................................ .. .... .. .... ... .... .. ... .... .. .... ... 11.4-129 Table 4-36 Adult Vegetation R, ..................................................................................... 11.4-133 Table 4-37 Infa n t Milk Ri..................................................... ... .... ..... .... ..... ... ...... ... ...... ... 11.4 -1 3 7 Table 4-38 C h ild Milk R i ............................................................................................... 11.4 -14 1 Table 4-39 T e e n Milk R, ............................................................................................... 11.4 -14 5 Table 4-40 A d u lt Milk R i ............................................................................................... 11.4 -14 9 Table 4-41 Infa n t Me a t R1 .................................................... .... .... ... .. .... ... ..... .... ..... .... ... 11.4 -15 3 Page 9 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 ODCM Parts I and II Table 4-42 Child Meat R1 ..................................................... ... ..... ... .... .. ... .... ..... ..... .... ... 11.4-157 Table 4-43 Teen Meat Ri .............................................................................................. 11.4-161 Table 4-44 Adult Meat R1 ..................................................... .. .... .... .... ... .. .... ... ...... .... ..... 11.4-165 Table 6-1 Radiological Environmental Monitoring Program ........................................... 11.6-2 Page 10 of 11 LaSalle ODCM Table of Contents

CY-LA-1 70-301 Revision 4 00CM Parts I and II ODCM TABLE OF CONTENTS LIST OF FIGURES PART I - RADIOLOGICAL EFFLUENT CONTROLS PAGE None PART II - ODCM Figure 1-1 Radiation Exposure Pathways to Humans ....... ........................................ 11.1 -9 Figure 1-2 Unrestricted Area Boundary ............................. ...................................... 11.1 -2 1 Figure 1-3 Restricted Area Boundary ................................ ...................................... 11.1 -2 2 Figure 2-1 Simplified Gaseous Radwaste and Gaseous E-ffluent Flow Diagram ..... 11.2-15 Figure 2-2 Simplified Liquid Radwaste Processing Diagra m ................................... 11.2 -17 Figure 2-3 Simplified Liquid Effluent Flow Diagram ......... ....................................... 11.2 -18 Figure 2-4 Simplified Solid Radwaste Processing Diagrar n .................................... 11.2 -19 Figure 6-1 Fixed Air Sampling Sites and Outer Ring TLD Locations ........................ 11.6-9 Figure 6-2 Inner Ring TLD Locations ............................... ....................................... 11.6 -10 Figure 6-3 Ingestion and Waterborne Exposure Pathway Sample Locations ......... 11.6-11 Page 11 of 11 LaSalle ODCM Table of Contents

CY-LA-170-301 Revision 4 OFFSITE DOSE CALCULATION MANUAL PART I RECS PART II ODCM LaSalle Station Units 1 and 2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls RADIOLOGICAL EFFLUENT CONTROLS LASALLE STATION Units 1 and 2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.1 DEFINITIONS

NOTE --------------

The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual (ODCM) Controls and Bases.

Term Definition ACTION ACTION shall be that part of a control that prescribes remedial measures required under designated conditions.

CHANNEL A CHANNEL CALIBRATION shall be the adjustment, as CALIBRATION necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in-place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

For specific calibration requirements refer to surveillance requirements section for the applicable instrumentation.

CHANNEL CHECK A CHANNEL CHECK shall be a qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL A CHANNEL FUNCTIONAL TEST shall be the injection of a FUNCTIONAL TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

CONTINUOUS Uninterrupted sampling with the exception of sampling SAMPLING interruptions of short duration for required surveillances.

DOSE EQUIVALENT That concentration of 1-131 (microcuries/gram) that alone would 1-131 produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID -14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites"; Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

GASEOUS Any system designed and installed to reduce radioactive RADWASTE gaseous effluents by collecting primary coolant system TREATMENT offgases from the primary system and providing for delay or SYSTEM holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBERS OF THE Any individual, except when that individual is receiving an PUBLIC occupational dose.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications with fuel in the reactor vessel.

OCCUPATIONAL The dose received by an individual in the course of DOSE employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

OFFSITE DOSE The ODCM shall contain the methodology and parameters used in CALCULATION the calculation of offsite doses resulting from radioactive gaseous MANUAL (ODCM) and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Program and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports.

OPERABLE - A system, subsystem, division, component, or device shall be OPERABILITY OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified function(s) are also capable of performing their related support function(s).

PROCESS CONTROL The PCP shall contain the current formulas, sampling, analyses, PROGRAM (PCP) test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes shall be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

PURGE - PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL The applicable unit's RTP shall be a total reactor core heat POWER (RTP) transfer rate to the reactor coolant as defined in Technical Specifications.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

RADIOLOGICAL A compilation of the various regulatory requirements, EFFLUENT CONTROL surveillance and bases, commitments and/or components of STANDARDS (RECS) the radiological effluent and environmental monitoring programs for LaSalle Station. To assist in the understanding of the relationship between effluent regulations, ODCM equations, RECS and related Technical Specification requirements, Table 1-1 provides a matrix that relates these various components, as well as the Radiological Environmental Monitoring Program fundamental requirements.

SITE BOUNDARY That line beyond which the land is not owned, leased, or otherwise controlled by licensee as defined in ODCM Part II Figure 1-3.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed),

monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source (This could be an external source or known radioactive process stream).

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNRESTRICTED AREA UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

VENTILATION A VENTILATION EXHAUST TREATMENT SYSTEM shall be EXHAUST TREAT- any system designed and installed to reduce gaseous MENT SYSTEM radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.1 DEFINITIONS (continued)

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

DEFINITIONS PECULIAR TO ESTIMATING DOSE TO MEMBERS OF THE PUBLIC USING THE ODCM COMPUTER PROGRAM:

a. ACTUAL Refers to using known release data to project the dose to the public for the previous time period. These data are stored in the database and used to demonstrate compliance with the reporting requirements of RECS.

b. PROJECTED Refers to using known release data from the previous time period or estimated release data to forecast a future dose to the public. This data is NOT incorporated into the database.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table 1-1 (Page 1 of 2)

COMPLIANCE MATRIX ODCM Technical Regulation Dose Component Limit Equation RECS Specification 10 CFR 50 1. Gamma air dose and beta air dose due to airborne 4-4 12.4.2 5.5.4.h Appendix I radioactivity in effluent plume. 4-5

a. Whole body and skin dose due to airborne 4-2 N/A N/A radioactivity in effluent plume are reported only if 4-8 certain gamma and beta air dose criteria are exceeded.

b Projected doses due to gaseous release, when N/A 12.4.5 5.5.4.f averaged over 31 days, exceed 0.3 mrem to any organ.

c Projected doses due to liquid release, when N/A 12.3.3 5.5.4.f averaged over 31 days, exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

2. CDE for all organs and all four age groups due to 4-14 12.4.3 5.5.4.i iodines and particulates in effluent plume. All pathways are considered.

3. CDE for all organs and all four age groups due to 3-3 12.3.2 5.5.4.d radioactivity in liquid effluents.

10 CFR 20 1. TEDE, totaling all deep dose equivalent components 5-3 12.4.9 5.5.4.c (direct, ground and plume shine) and CDE (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 database.

40 CFR 190 1. Whole body dose (DDE) due to direct dose, ground and 5-2 12.4.7 5.5.4.j (now by plume shine from all sources at a station.

reference, also part of 2. Organ doses (CDE) to an adult due to all pathways. 3-3 10 CFR 20) 4-8 Technical 1. "Instantaneous" whole body (DDE), skin (SDE), and 4-9 12.4.1 5.5.4.g Specifications thyroid (CDE) dose rates due to radioactivity in airborne 4-10 effluents. For the thyroid dose, only inhalation is 4-6 considered.

2. "Instantaneous" concentration limits for liquid effluents. 3-5 12.3.1 5.5.4.b

3. Radioactive Effluent Release Report N/A 12.6.2 5.6.3 (continued)

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table 1-1 (Page 2 of 2)

COMPLIANCE MATRIX ODCM Technical Regulation Dose Component Limit Equation RECS Specification 10CFR50 Appendix I 1. Implement environmental monitoring program. N/A 12.5.1 N/A Section IV.B.2 10CFR50 Appendix I 1. Land Use Census N/A 12.5.2 N/A Section IV.B.3 10CFR50 Appendix I 1. Interlaboratory Comparison Program N/A 12.5.3 N/A Section IV.B.2 10CFR50 Appendix I Section IV.B.2 1. Annual Radiological Environmental Operating Report N/A 12.6.1 5.6.2 and Technical Specifications I Page V-1.1-7

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in ODCM to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in ODCM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.2 Logical Connectors EXAMPLES (continued) EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control not met. A.1 Verify ...

AND A.2 Restore...

In this example, the logical connector AND is used to indicate that, when in Condition A, both Required Actions A.1 and A.2 must be completed.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.2 Logical Connectors EXAMPLES (continued) EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control not met. A.1 Trip...

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Align This example represents a more complicated use of logical connectors. Required Actions A. 1, A.2 and A.3 are alternate choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Action may be chosen. If A.2 is chose, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND ODCM Radiological Effluent Controls (RECs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a REC state Conditions that typically describe the ways in which the requirements of the REC can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times.

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the REC. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the REC Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single REC (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystem, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times DESCRIPTION However, when a subseauent division, subsystem, component, or variable (continued) expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those RECs that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual RECs.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery. . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

(continued)

Page I-1.3-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE 4.

Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are in to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching Mode 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Page 1-1.3-3

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One monitor A. 1 Restore monitor to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a monitor is declared inoperable, Condition A is entered. If the monitor is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Action B.1 and B.2 start. If the inoperable monitor is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a monitor pump is declared inoperable while the first monitor is still inoperable, Condition A is not re-entered for the second monitor. REC 12.0.3 is entered, since the ACTIONS do not include a Condition from more than one inoperable monitor.

The Completion Time clock for Condition A does not stop after REC 12.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has not expired, REC 12.0.3 may be exited and operation continued in accordance with Condition A.

(continued)

Page 1-1.3-4

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has expired, REC 12.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

On restoring one of the monitors to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first monitor was declared inoperable. This Completion Time may be extended if the monitor restored to OPERABLE status was the first inoperable monitor. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second monitor being inoperable for > 7 days.

(continued)

Page I-1.3-5

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore Function X 7 days subsystem inoperable, subsystem to OPERABLE status.

AND 10 days from discovery of failure to meet the Control B. One Function Y B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable, subsystem to OPERABLE status.

AND 10 days from discovery to meet Control C. One Function X C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable, subsystem to OPERABLE status.

AND One Function Y OR subsystem inoperable. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C.2 Restore Function Y subsystem to OPERABLE status.

(continued)

Page 1-1.3-6

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the REC was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the REC.

The separate Completion Time modified by the phrase "from discovery of failure to meet the Control" is designed to prevent indefinite continued operation while not meeting the REC. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock." In this instance, the Completion Time "time zero" is specified as commencing at the time the associated Condition was entered.

(continued)

Page I-1.3-7

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months instruments inoperable, instruments(s) to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE 4.

A single Completion Time is used for any number of instruments inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per instrument basis. Declaring subsequent instruments inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the instruments has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first instrument was declared inoperable. The Completion Time may be extended if the instrument restored to OPERABLE status was the first inoperable instrument. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent instrument being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more instruments are still inoperable, Condition B is entered.

(continued)

Page 1-1.3-8

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

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

Separate Condition entry is allowed for each inoperable instrument.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more instruments A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable, instrument(s) to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE 4.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable instrument, and Completion Times tracked on a per instrument basis. When an instrument is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent instruments are declared inoperable, Condition A is entered for each instrument and separate Completion Times start and are tracked for each instrument.

If the Completion Time associated with an instrument in Condition A expires, Condition B is entered for that instrument. If the Completion Times associated with subsequent instruments in Condition A expire, Condition B is entered separately for each instrument and separate Completion Times start and are tracked for each instrument. If a instrument that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that instrument.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

(continued)

Page 1-1.3-9

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel Perform RSR 12.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR Reduce THERMAL POWER to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

50% RTP.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per RSR 12.0.2 to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A. 1 begins when Condition A is entered and the initial performance of Required Action A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by RSR 12.0.2), Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

(continued)

Page 1-1.3-10

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.3 Completion Times EXAMPLES (continued) EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, subsystem isolated.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A. 1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by RSR 12.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action should be COMPLETION pursued without delay and in a controlled manner.

TIME Page I-1.3-11

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each ODCM Radiological Effluent Surveillance Requirement (RSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated ODCM REC. An understanding of the correct application of the specified Frequency is necessary for compliance with the RSR.

The "specified Frequency" is referred to throughout this section and each of the Requirements of Section 12.0, ODCM Surveillance Requirement (RSR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each RSR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by RSR 12.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated REC is within its Applicability, represent potential RSR 12.0.4 conflicts. To avoid these conflicts, the RSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a RSR satisfied, RSR 12.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specified meanings.

A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met."

"Performance" refers only to the requirement to (continued)

Page 1-1.4-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.4 Frequency DESCRIPTION specifically determine the ability to meet the acceptance criteria.

(continued) RSR 12.0.4 restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the REC (REC not shown) is MODES 1, 2, and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of RSR most often encountered in the ODCM.

The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by RSR 12.0.2 for operational flexibility. The measurement of this interval continues at all times, event when the RSR is not required to be met per RSR 12.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the REC). If the interval specified by RSR 12.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the REC, (continued)

Page 1-1.4-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued) and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then RSR 12.0.3 becomes applicable.

If the interval as specified by RSR 12.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the REC for which performance of the RSR is required, the Surveillance must be performed within the Frequency requirements of RSR 12.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of RSR 12.0.4.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after > 25%

RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to > 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(continued)

Page 1-1.4-3

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by RSR 12.0.2.

"Thereafter" indicates future performances must be established per RSR 12.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). Ifreactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE ---------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after > 25% RTP.

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches

> 25% RTP to perform the Surveillance. The Surveillance is still considered to be within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by RSR 12.0.2),

but operation was < 25% RTP, (continued)

Page I-1.4-4

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued) it would not constitute a failure of the RSR or failure to meet the REC. Also, no violation of RSR 12.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power

> 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of RSR 12.0.3 would apply.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE-------------

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1.

However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, ifthe Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by RSR 12.0.2), but the unit was not in MODE 1, there would be no failure of the RSR nor failure to meet the REC.

Therefore, no violation of RSR 12.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), RSR 12.0.4 would require satisfying the RSR.

Page 1-1.4-5

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 1.0 USE AND APPLICATION 1.5 REC and RSR Implementation The ODCM provides those limitations upon plant operations which are part of the licensing basis for the station but do not meet the criteria for continued inclusion in the Technical Specifications.

It also provides information which supplements the Technical Specifications by implementing the requirements of Technical Specification Sections 5.5.1, 5.5.4, 5.6.2, and 5.6.3.

RECs and RSRs are implemented the same as Technical Specifications (see 12.0 Applicability).

However, RECs and RSRs are treated as plant procedures and are not part of the Technical Specifications. Therefore the following exceptions apply:

a. Violations of the Action or Surveillance requirements in a REC are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72 or 10 CFR 50.73.

b. Power reduction or plant shutdowns required to comply with the Actions of a REC are not reportable per 10 CFR 50.72 or 10 CFR 50.73.

Page 1-1.5-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 2.0 through 11.0 NOT USED INTENTIONALLY BLANK Sections 2.0 through 11.0 are not used in the ODCM in order to maintain the Original ODCM numbering convention Page 1-2.0-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.0 ODCM RADIOLOGICAL EFFLUENT CONTROL (REC) APPLICABILITY REC 12.0.1 RECs shall be met during the MODES or other specified conditions in the Applicability, except as provided in REC 12.0.2.

REC 12.0.2 Upon discovery of a failure to meet a REC, the Required Actions of the associated Conditions shall be met, except as provided in REC 12.0.5.

If the REC is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

REC 12.0.3 When a REC is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to:

a. Implement appropriate compensatory actions as needed;

b. Verify that the plant is not in an unanalyzed condition or that a required safety function is not compromised by the inoperabilities; and

c. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , obtain Shift Operations Superintendent or designee approval of the compensatory actions and the plan for exiting REC 12.0.3.

Exceptions to this REC are stated in the individual RECs.

Where corrective measures are completed that permit operation in accordance with the REC or ACTIONS, completion of the actions required by REC 12.0.3 is not required.

REC 12.0.3 is only applicable in MODES 1, 2, and 3.

REC 12.0.4 When a REC is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified (continued)

Page 1-12.0-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.0 REC APPLICABILITY REC 12.0.4 condition in the Applicability for an unlimited period of time. This REC shall (continued) not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Exceptions to this REC are stated in the individual RECs.

REC 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.

REC 12.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to REC 12.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

REC 12.0.6 RECs, including associated ACTIONS, shall apply to each unit individually, unless otherwise indicated. Whenever the REC refers to a system or component that is shared by both units, the ACTIONS will apply to both units simultaneously.

Page 1-12.0-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.0 ODCM RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY RSR 12.0.1 RSRs shall be met during the MODES or other specified conditions in the Applicability for individual RECs, unless otherwise stated in the RSR.

Failure to meet a RSR, whether such failure is experienced during the performance of the RSR or between performances of the RSR, shall be failure to meet the REC. Failure to perform a RSR within the specified Frequency shall be failure to meet the REC except as provided in RSR 12.0.3. RSRs do not have to be performed on inoperable equipment or variables outside specified limits.

RSR 12.0.2 The specified Frequency for each RSR is met if the RSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per..

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this RSR are stated in the individual RSRs.

RSR 12.0.3 If it is discovered that a RSR was not performed within its specified Frequency, then compliance with the requirement to declare the REC not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the RSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the RSR is not performed within the delay period, the REC must immediately be declared not met, and the applicable Condition(s) must be entered.

When the RSR is performed within the delay period and the RSR is not met, the REC must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

Page 1-12.0-3

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.0 RSR APPLICABILITY (continued)

RSR 12.0.4 Entry into a MODE or other specified condition in the Applicability of a REC shall not be made unless the REC's RSRs have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

RSR 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.

RSR 12.0.5 RSRs shall apply to each unit individually, unless otherwise indicated.

Page 1-12.0-4

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.1 NOT USED INTENTIONALLY BLANK Page 1-12.1-1

CY-LA-170-301 Revision 4 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 Blowdown, when the Blowdown Flow Control Valve is >0% open and the Blowdown line is not otherwise isolated.

ACTIONS

NOTE-----------

1. Separate Ccondition 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

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION I REQUIRED ACTION ICOMPLETION TIME C. As required by Required C.1 Perform RSR 12.3.1.1 on at Prior to each release Action A.2 or B.1 and least two independent referenced in Table samples of the tanks R12.2.1-1. contents.

AND C.2 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.

AND C.3 Return instrument channel to 30 days OPERABLE status.

OR C.4 Place Administrative Control 30 days I Clearance order to Lock-Closed OWF201, RW DSCH Tank River DSCH Valve, to remove the ability to conduct a Liquid Radwaste Discharqe.

D. Required Action and D.1 Suspend release of radioactive Immediately associated Completion effluents via this pathway.

Time of Condition C not met.

E. As required by Required E.1 Analyze affected effluent grab Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action A.2 or B.1 and samples for principal gamma referenced in Table emitters and 1-131 at an LLD as R12.2.1-1. specified in Table R12.3.1-2.

AND E.2 Restore the instrument channel 30 days to OPERABLE status.

(continued)

Page 1-12.2.1-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 --------- NOTE ----- ----------

Action A.2 or B.1 and Pump curves for instrument 3.a, referenced in or known valve positions for Table R12.2.1-1. instrument 3.b, may be used to estimate flow.

Estimate the flow rate for the Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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. ------- NOTE ------------- G.1 Explain why the inoperability In accordance with Required Action G.1 was not corrected in a timely Technical shall be completed if this manner in the next Radioactive Specification 5.6.3.

Condition is entered. Effluent Release Report.

Required Action C.3 or C.4, or E.2 and associated Completion Time not met.

Page 1-12.2.1-3

CY-LA-1 70-301 Revision 4 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.2.1-1 (page 1 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation CONDITION REQUIRED REFERENCED CHANNELS PER FROM REQUIRED SURVEILLANCE INSTRUMENT IINSTRUMENT ACTION A.2 AND B.1 REQUIREMENTS

1. Gamma Scintillation Monitor providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluents Line I C RSR 12.2.1.1 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(a)

2. Gamma Scintillation Monitors providing Alarm but not providing Automatic Termination of Release

a. Service Water Effluent Line (Unit 1) 1 E RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(a)

b. Service Water Effluent Line (Unit 2) 1 E RSR 12.2.1.4 RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(o)

c. RHR Service Water (Line A) Effluent Line 1 E RSR 12.2.1.4 (Unit 1) RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(e)

d. RHR Service Water (Line B) Effluent Line 1 E RSR 12.2.1.4 (Unit 1) RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(a)

e. RHR Service Water (Line A) Effluent Line 1 E RSR 12.2.1.4 (Unit 2) RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(a)

f. RHR Service Water (Line B) Effluent Line 1 E RSR 12.2.1.4 (Unit 2) RSR 12.2.1.3 RSR 12.2.1.5 RSR 12.2.1.7(a)

(continued)

(")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-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.2.1-1 (page 2 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation CONDITION REQUIRED REFERENCED CHANNELS PER FROM REQUIRED SURVEILLANCE INSTRUMENT IINSTRUMENT ACTION A.2 AND B.1 REQUIREMENTS

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line F RSR 12.2.1.2 RSR 12.2.1.3 RSR 12.2.1.7

b. OWL005 BDFCV Position Indication F RSR 12.2.1.8 Page 1-12.2.1-6

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation 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

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Place instrument channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action A.2 or B.1 and trip.

referenced in Table R12.2.2-1.

D. As required by Required D.1 Obtain grab samples. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action A.2 or B.1 and referenced in Table R12.2.2-1. AND D.2 Analyze grab samples for Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months noble gas emitters. following each grab sample AND D.3 Restore instrument channel to OPERABLE status. 30 days E. As required by Required E.1 Obtain grab samples. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Action A.2 or B.1 and referenced in Table AND R12.2.2-1.

E.2 Analyze grab samples for Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months noble gas emitters at an LLD following each grab as specified in Table sample R12.4.1-1.

AND E.3 Restore instrument channel 30 days to OPERABLE status.

F. As required by Required F.1 Establish CONTINUOUS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action A.2 or B.1 and SAMPLING with auxiliary referenced in Table sampling equipment as R12.2.2-1. required in Table R12.4.1-1.

AND F.2 Restore instrument channel 30 days to OPERABLE status.

(continued)

Page 1-12.2.2-2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Estimate flow rate. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action A.2 or B. I and AND referenced in Table R12.2.2-1. G.2 Restore instrument channel 30 days to OPERABLE status.

H. As required by Required H.1 Verify offgas treatment Immediately Action A.2 or B.1 and system not bypassed.

referenced in Table AND R12.2.2-1.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

samples.

AND H.4 Restore instrument channel 30 days to OPERABLE status.

NOTE ------------ 1.1 Explain in the next In accordance with Required Action 1.1 shall be Radioactive Effluent Release Technical completed if this Condition Report why the inoperability Specification 5.6.3.

is entered. was not corrected within the time specified.

Required Action and associated Completion Time of Required Action D.3, E.3, F.2, or G.2 or H.4 not met.

Page 1-12.2.2-3

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.2.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RSR 12.2.2.2 Perform SOURCE CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RSR 12.2.2.3 ---------------- NOTE ------------------

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

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.2.2-1 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation APPLICABLE MODES OR REQUIRED CONDITION OTHER CHANNELS REFERENCED SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMENT(e) CONDITIONS INSTRUMENT ACTION A.2 AND B.1 REQUIREMENTS

1. Main Condenser Offgas Treatment System Effluent Monitoring System

a. 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(e) channels inoperable

2. Main Stack Monitoring System

a. Noble Gas Activity Monitor (Low (c) 1 E RSR 12.2.2.1 or Mid Range WRGM) RSR 12.2.2.4 RSR 12.2.2.6 RSR 12.2.2.7(d)

b. Iodine Sampler (Grab Sampler) (c) 1 F RSR 12.2.2.3

c. Particulate Sampler (Grab (c) 1 F RSR 12.2.2.3 Sampler)

d. Effluent System Flow Rate (c) 1 G RSR 12.2.2.1 Monitor RSR 12.2.2.5 RSR 12.2.2.7

e. Sampler Flow Rate Monitor (c) 1 G RSR 12.2.2.1 (Low/Mid/Hi) RSR 12.2.2.5 RSR 12.2.2.7 (Continued)

(a) Equipment Part Numbers (EPN) are provided in Table R12.2.2-2.

(b) During effluent releases via this pathway.

(c) At all times.

(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

CY-LA-1 70-301 Revision 4 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 INSTRUMENT(B) CONDITIONS INSTRUMENT ACTION A.2 AND B.1 REQUIREMENTS

3. 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(d)

4. Standby Gas Treatment (SGT)

Monitoring System

a. Noble Gas Activity Monitor (Low (g) 1 E RSR 12.2.2.1 or Mid Range WRGM) RSR 12.2.2.4 RSR 12.2.2.6 RSR 12.2.2.7(d)

b. Iodine Sampler (Grab Sampler) (g) I F RSR 12.2.2.3

c. Particulate Sampler (Grab (g) 1 F RSR 12.2.2.3 Sampler)

d. Effluent System Flow Rate (g) 1 G RSR 12.2.2.1 Monitor RSR 12.2.2.5 RSR 12.2.2.7

e. Sampler Flow Rate Monitor (g) 1 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-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.2.2-2 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation Applicability INSTRUMENT EPNS OF APPLICABLE EQUIPMENT A. Unit 1 Applicable Instruments I. Main Condenser Offgas Treatment System Effluent Monitoring System

a. Noble Gas Activity Monitor - Providing Alarm 1D18-N903A, K901A, K601A, R601 and Automatic Termination of Release 1018-N903B, K901B, K601B, R601

2. Main Stack Monitoring System

a. Noble Gas Activity Monitor (Low or Mid Range 0D18-N514, R517, R518 Low Range WRGM) 0D18-N515, R517, R518 Mid Range

b. Iodine Sampler (Grab Sampler)

c. Particulate Sampler (Grab Sampler)

d. Effluent System Flow Rate Monitor OFT-VR019, OFY-VR019 AND 019A, OFR-VRO19, 0D18-K510, 0D18-R518

e. Sampler Flow Rate Monitor (Low/Mid/Hi) 0D18-N527, 0D18-N528, 0D18-R518 Low OD18-N530, OD18-N531, OB18-R518 Mid/Hi

3. Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup System)

a. Noble Gas Activity Monitor 1D18-N002, K613, R604, or 1D18-N012, K600, R605

4. Standby Gas Treatment (SGT) Monitoring System

a. Noble Gas Activity Monitor (Low/Mid Range 0D18-N511, R515, R516 Low Range WRGM) 0D18-N512, R515, R516 Mid Range

b. Iodine Sampler (Grab Sampler)

c. Particulate Sampler (Grab Sampler)

d. Effluent System Flow Rate Monitor 1FT-VG009, 1FY-VG009, 1FR-VG-009

e. Sampler Flow Rate Monitor (Low/Mid/Hi) 0D18-N521, 0D18-N522, 0D18-R516 Low 0D18-N524, 0D18-N525, 0B18-R516 Mid/Hi (Continued)

Page I-12.2.2-7

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.2.2-2 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation Applicability INSTRUMENT EPNS OF APPLICABLE EQUIPMENT B. Unit 2 Applicable Instruments

1. Main Condenser Offgas Treatment System Effluent Monitoring System

a. Noble Gas Activity Monitor - Providing Alarm 2D18-N903A, K901A, K601A, R601 and Automatic Termination of Release 2D18-N903B, K901B, K601B, R601

2. Main Stack Monitoring System

a. Noble Gas Activity Monitor (Low or Mid Range 0D18-N514, R517, R518 Low Range WRGM) 0D18-N515, R517, R518 Mid Range

b. Iodine Sampler (Grab Sampler)

c. Particulate Sampler (Grab Sampler)

d. Effluent System Flow Rate Monitor OFT-VRO19, OFY-VRO19 AND 019A, OFR-VRO19, 0D18-K510, 0D18-R518

e. Sampler Flow Rate Monitor (Low/Mid/Hi) 0D18-N527, 0D18-N528, 0D18-R518 Low OD18-N530, OD18-N531, OB18-R518 Mid/Hi

3. Condenser Air Ejector Radioactivity Monitor (Prior to Input to Holdup System)

a. Noble Gas Activity Monitor 2D18-N002, K613, R604, or 2D18-N012, K600, R605

4. Standby Gas Treatment (SGT) Monitoring System

a. Noble Gas Activity Monitor (Low/Mid Range 0D18-N511, R515, R516 Low Range WRGM) 0D18-N512, R515, R516 Mid Range

b. Iodine Sampler (Grab Sampler)

c. Particulate Sampler (Grab Sampler)

d. Effluent System Flow Rate Monitor 2FT-VG009, 2FY-VG009, 2FR-VG-009

e. Sampler Flow Rate Monitor (Low/Mid/Hi) 0D18-N521, 0D18-N522, 0D18-R516 Low OD18-N524, OD18-N525, 0B138-R516 Mid/Hi Page I-12.2.2-8

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.3 LIQUID EFFLUENTS 12.3.1 Liquid Effluent Concentration 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 FREQUENCY RSR 12.3.1.1 Determine radioactivity content of each In accordance with the radioactive liquid waste batch by sampling Radioactive Liquid and analysis in accordance with Table Waste Sampling and R12.3.1-2. Analysis Program.

RSR 12.3.1.2 Perform post-release analysis of samples In accordance with the composited from batch releases in Radioactive Liquid accordance with Table R12.3.1-2. Waste Sampling and Analysis Program.

RSR 12.3.1.3 Determine radioactivity concentration of In accordance with the liquids discharged from continuous release Radioactive Liquid points by sampling and analysis in Waste Sampling and accordance with Table R12.3.1-2. Analysis Program.

(Continued)

Page 1-12.3.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS RSR 12.3.1.4 NOTE------------

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 7 days when radioactive ensure that in the event of an uncontrolled material is being added release of the tanks contents, the resulting to the tank(s).

concentration would be less than the REC limits. AND Once within 7 days after each completion of addition of radioactive material to the tank(s).

Page 1-12.3.1-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.3.1-1 ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE ALLOWABLE CONCENTRATION (lJCi/ml)*

Kr-85m 2 x 10-4 Kr-85 5 x 10.4 Kr-87 4 x 10-5 Kr-88 9 x 10.5 Ar-41 7 x 10s Xe-131m 7 x 10,4 Xe-1 33m 5 x 104 Xe-133 6 x 10-4 Xe-1 35m 2 x 10-4 Xe-135 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 g/cc and Pw/Pt = 1.0.

Page 1-12.3.1-3

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.3.1-2 (Page 1 of 4)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY OF DETECTION TYPE FREQUENCY(g) FREQUENCY(g) ANALYSIS (LLD)(a) (jCi/ml)

A. Batch Waste Prior to each Prior to each release, Principal Gamma Erelease,_____Each__ 5xtte release, Each Each Batch Release Tanks(d) Batch 1-131 lx10.6 5

Prior to each 31 days H-3 1X10 release, Each Composite (b)

Batch Gross Alpha lx10.7 Prior to each 92 days Sr-89, Sr-90 5x10-8 release, Each Composite (b)

Batch Fe-55 1x10"6 Prior to each release, One 31 days Dissolved &

Batch per 31 Entrained Gases 1x10s days (Gamma Emitters)

B. Plant Continuous 7 days 1-131 Ix10 6 Releases(e) CONTINUOUS(C) Composite (c)

Cooling Pond Principal Gamma 5x10" Blowdown Emitters(O 31 days 31 days Dissolved & lx10 5 Grab Sample Entrained Gases GrabSample_ (Gamma Emitters)

CONTINUOUS(c) 31 days H-3 1x10.5 Composite(c) Gross Alpha 1x10.7 92 days Sr-89, Sr-90 5x10.8 CONTINUOUS(c)

Composite(c) Fe-55 lx10.6 Page 1-12.3.1-4

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.3.1-2 (Page 2 of 4)

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:

LLD = 4.66Sh E. V 2.22x] 06 -.Y e(-A)

Where:

LLD =the a oriori 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),

t 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 106 = the number of transformations per minute per microcurie, Y =the fractional radiochemical yield, when applicable, X= 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 inthe calculation.

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

LLD = (2.71 + 4.65VrB-). Decay E . q . b. Y .1 (2.22xl 06)

Page 1-12.3.1-5

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.3.1-2 (Page 3 of 4)

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 (ifapplicable)

Y= fractional radiochemical yield or collection efficiency (ifapplicable) t= count time (minutes) 2.22 x 106 = number of disintegrations per minute per microcurie 2.71 + 4.654/B = k2 + (2k 42 4B), 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 itis.)

Decay = eIE[XRT/(1-e-'RT)][XTd/(1-e )'Td)l if applicable

, = radioactive decay constant (units consistent with At, 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 X)

RT = elapsed real time, or the duration of the sample count (units consistent with .)

Td = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with X)

The LLD may alternately be determined using installed radioanalytical software, ifavailable. 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.

Itshould 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

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.3.1-2 (Page 4 of 4)

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 inwhich 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 inproportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed inorder for the composite sample to be representative of the effluent release.

d. Abatch 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. Acontinuous 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

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.3 LIQUID EFFLUENTS 12.3.2 Dose from Liquid Effluents 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-1 70-301 Revision 4 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 10CFR50, 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 RSR 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 4 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 -------- .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-1 70-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

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 92 days if a portable equipment for at least 30 minutes. (vendor supplied) waste treatment system is being used.

AND 180 days if a portable (vendor-supplied) waste treatment system is not being used.

Page 1-12.3.3-2

CY-LA-1 70-301 Revision 4 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 SURVEILLANCE FREQUENCY RSR 12.4.1.1 Verify the dose rates due to noble gases, iodine-131, In accordance with iodine-133, tritium, and all radionuclides in the Radioactive particulate form with half lives > 8 days in gaseous Gaseous Waste effluents is within limits utilizing the methodology and Sampling and parameters of the ODCM limits by obtaining and Analysis Program analyzing representative samples in accordance with Table R12.4.1-1.

Page 1-12.4.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.4.1-1 (Page 1 of 5)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD)

TYPE FREQUENCY(') FREQUENCYi) ANALYSIS (pCi/ml)a A. Containment Vent Prior to each release Prior to each Emitters9 Gamma Principal lx1i04 and Purge breease_______ release Systemr Each Purgeb Each Purgeb Grab Sample H-3 lx108 31 daysb 31 daysb Principal Gamma 1x10.4 B. Main Vent Stack Grab Sample _ _ _ _ _ _ _ _ _

7 daysb'e 7 days,'e H-3 1x10 8 Grab Sample C. Standby Gas Treatment 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sc 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Principal9 Gamma lx10. 4 System Grab Sample Emitters 2

D. Main Vent Stack 7 dayS, 1-131 ,1x1 And Standby Gas CONTINUOUS'r Charcoal Treatment System' Sample 1-133 1x10°1 7 daysd Principal Gamma CONTINUOUS' Particulate Emitters9 (1-131, lx1011 Sample Others) 31 days CONTINUOUS' Composite Gross Alpha 11 Particulate 1x10 Sample 92 days CONTINUOUS' Composite Particulate Sr-89,Sr-90 lxi.1" Sample Noble Gas Noble Gases, CONTINUOUS' Montobe Monitor Gross Beta or Gamma 1x10s Page 1-12.4.1-2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.4.1-1 (Page 2 of 5)

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 06. Y. e.-"w)

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 (counds) t = count time (minutes)

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22x106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

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 inthe 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.B). Decay E q b. Y .1. (2.22x1 06)

Page 1-12.4.1-3

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.4.1-1 (Page 3 of 5)

RADIOACTIVE GASEOUS 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 106 = number of disintegrations per minute per microcurie 2.71 + 4.6541B = k2 + (2k 4/2 41B), 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.)

Decay = e""' [XRT/(1l-e')RT)][XTd /(1-e Td)] if applicable X = radioactive decay constant (units consistent with At, 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 X)

RT = elapsed real time, or the duration of the sample count (units consistent with 4)

Td = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with X)

The LLD may alternately be determined using installed radioanalytical software, ifavailable. 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.

Itshould 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1)analysis shows that the dose equivalent 1-131 concentration inthe 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

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls Table R12.4.1-1 (Page 4 of 5)

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. ASGT 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following each shutdown, startup, or thermal power level change exceeding 20% of RATED THERMAL POWER in one hour. This requirement does not apply if1) 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. Ifthere 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-1 33, Xe-1 33m, Xe-1 35, and Xe-1 38 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of purging activities following shutdown. The drywell tritium and noble gas sample results are valid for 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months from sample time if 1)the drywell radioactivity monitors have not indicated an increase inairborne or gaseous radioactivity, and 2) the drywell equipment and floor drain sump pumps run times have not indicated an increase in leakage in the drywell 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.

Ifthere is any reason to suspect that gaseous radioactivity levels have changed inthe drywell that would compromise the calculated, or estimated, radionuclide concentrations at the time of the release, since the last sample (30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ), a new sample and analyses should be requested prior to starting a drywell purge to meet the intent of providing current analyses to reflect actual activity released to the environment. Ifa known steady state leakage condition exists in the drywell itis 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 I-12.4.1-5

CY-LA-1 70-301 Revision 4 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 drywell is PURGED in accordance with the ODCM definition, both noble gas and tritium analyses must be completed before the purge begins. If the drywell is simply VENTING in accordance with the ODCM definition, no sample is required before venting.

The provisions of RSR 12.0.2 and RSR 12.0.3 are applicable to the Radioactive Gaseous Waste Sampling and Analysis Program.

Page 1-12.4.1-6

CY-LA-1 70-301 Revision 4 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 radiation, < 10 mrad during any calendar quarter and < 20 mrad 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 pursuant to 10CFR50 end of the quarter in be completed if this Appendix I Section IV.A, that which the release Condition is entered. identifies causes for occurred 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.

B. Calculated air dose B.1 Enter Condition A of REC Immediately exceeds two times (2x) the 12.4.7.

limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year in accordance with the ODCM.

Page 1-12.4.2-1

CY-LA-170-301 Revision 4 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 10CFR50 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-1 31, 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 4 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 COMPLETION TIME A. GASEOUS RADWASTE A.1 Restore system to 7 days 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 30 days 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 FREQUENCY RSR 12.4.4.1 Verify the GASEOUS RADWASTE TREATMENT 7 days SYSTEM is in operation.

Page 1-12.4.4-1

CY-LA-170-301 Revision 4 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.

NOTE --------------------------------------- -------------------

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.

TREATMENT SYSTEMS inoperable.

B. --------- NOTE--------- 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. I (continued)

Page 1-12.4.5-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. -------- NOTE -------- C.1 Submit a report to the NRC 30 days Required Action C. 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 Required Action and inoperable equipment to associated Completion OPERABLE status, and Time of Condition A not summary description of met. actions taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.5.1 Project doses due to gaseous releases from the 31 days 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.

OPERATE each required VENTILATION 92 days EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes.

Page 1-12.4.5-2

CY-LA-170-301 Revision 4 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 drywell shall be:

a. through the Primary Containment Vent and Purge System, or

b. through the Standby Gas Treatment (SGT) System.

APPLICABILITY: During drywell VENTING or PURGING.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Above requirements not A.1 Suspend all drywell Immediately met. VENTING and PURGING.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.6.1 Verify containment drywell is aligned for VENTING or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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: Prior to PURGING

a. Both SGT trains are OPERABLE, and through the SGT System.

b. Only one of the SGT System trains to be used for PURGING.

Page I-12.4.6-1

CY-LA-170-301 Revision 4 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 REQUIRED ACTION COMPLETION TIME A. --------- NOTE ---------..... A.1 Submit a report to the NRC 30 days Required Action A.1 and A.2 (Director, Nuclear Reactor shall be completed if this Regulation) that defines the Condition is entered. corrective action to be taken to reduce subsequent releases to prevent As required by Required recurrence of exceeding the Action B.1 of REC 12.3.2, limits to include estimates of 12.4.2, or 12.4.3. radiation exposure to a MEMBER OF THE PUBLIC from uranium fuel cycle OR sources, including all effluent pathways and direct radiation, Calculated Total Dose not for a 12 consecutive month within limits, period that includes the release(s) covered by this report.

AND (continued)

Page 1-12.4.7-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --------- NOTE--------

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

Submit a request for a 30 days variance in accordance with 40 CFR 190, including the specified information of 40 CFR 190.11.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.7.1Determine cumulative dose contributions from direct 31 days radiation and liquid and gaseous effluents in accordance with the ODCM.

Page 1-12.4.7-2

CY-LA-1 70-301 Revision 4 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 105 pCi/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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion lines.

Time not met.

OR B.2 Isolate the SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.3.1 MODE 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 MODE 4 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Page 1-12.4.8-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.8.1 Monitor the noble gas radioactivity rate prior to the CONTINUOUSLY 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 Once within 4 noble gases prior to the holdup line is within limits by hours after a performing an isotopic analysis of a representative >50% increase in sample of gases taken prior to the holdup line. the nominal steady state fission gas release from the primary coolant, as indicated by the off gas pre-treatment Noble Gas Activity Monitor, after factoring out increases due to changes in THERMAL POWER level AND 31 days Page 1-12.4.8-2

CY-LA-170-301 Revision 4 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 I-12.4.9-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.4.9.1 Calculate the TEDE to individual MEMBERS OF 12 months THE PUBLIC in accordance with the ODCM.

RSR 12.4.9.2 Determine and/or evaluate direct radiation 12 months exposures in unrestricted areas.

Page 1-12.4.9-2

CY-LA-1 70-301 Revision 4 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 I COMPLETION TIME A. ----- NOTE ------------- I A.1 Initiate action to identify Immediately Required Action A.2 shall suitable, alternative be completed if this sampling media and/or Condition is entered. specific locations for obtaining replacement samples for the pathway of Sample type or location(s) interest and add them to the required by Table REMP. Delete locations R12.5.1-1 permanently from which samples are unavailable. unavailable.

AND A.2 Prepare and submit a In accordance with controlled version of the Technical Specification ODCM, in the next Annual 5.6.2 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).

(continued)

Page 1-12.5.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. -------- NOTE --------- B.1 Submit a report to the NRC 30 days Required Action B.1 shall that identifies the cause(s) for be completed if this exceeding the limits and Condition is entered. defines the corrective actions to be taken to reduce radioactive effluents so that Level of radioactivity as the the potential annual dose to a result of plant effluents in MEMBER OF THE PUBLIC an environmental sampling is less than the calendar year medium at a specified reporting level of REC 12.3.2, location exceeds the 12.4.2 or 12.4.3. The reporting levels of Table methodology and parameters R12.5.1-2 when averaged used to estimate the potential over any calendar quarter. annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

C. -------- NOTE -------------- C.1 Submit a report to the NRC 30 days Required Action C. 1 shall that identifies the cause(s) for be completed if this exceeding the limits and Condition is entered. defines the corrective actions to be taken to reduce radioactive effluents so that More than one the potential annual dose to a radionuclide in Table MEMBER OF THE PUBLIC is R12.5.1-2 detected in the less than the calendar year sampling medium, reporting level of REC 12.3.2, 12.4.2 or 12.4.3. The AND methodology and parameters used to estimate the potential C1 C2 annual dose to a MEMBER

- + + ... > 1.0 OF THE PUBLIC shall be RL1 RL2 indicated in this report.

where; C = concentration RL = reporting level.

(continued)

Page 1-12.5.1-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION I REQUIRED ACTION I COMPLETION TIME D. -------- NOTE --...-------- D. 1 --------- NOTE ---------------

Required Action D.1 and Only required when the D.2 shall be completed if measured levels of this Condition is entered. radioactivity are the result of plant effluents.

Radionuclides other than those in Table R12.5.1-2 are detected. Submit a report to the NRC 30 days AND that identifies the cause(s) for exceeding the limits and defines the corrective actions The potential annual dose to be taken to reduce to a MEMBER OF THE radioactive effluents so that PUBLIC from all the potential annual dose to a radionuclides is greater MEMBER OF THE PUBLIC is than or equal to the less than the calendar year calendar year limits of reporting level. The REC 12.3.2, 12.4.2, or methodology and parameters 12.4.3. used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

AND D.2 --------- NOTE-------

Only required when the radionuclides detected are not the result of plant effluents.

Describe the condition in the In accordance with next Annual REOR. Technical Specification 5.6.2.

(continued)

Page 1-12.5.1-3

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED COMPENSATORY COMPLETION TIME MEASURE E. ------- NOTE--------- E.1 Prepare and submit to the NRC, In accordance with Required Action E.1 in the next Annual REOR, a Technical shall be completed if description of the reasons for not Specification 5.6.2.

this Condition is conducting the program as entered. required and the plans for preventing a recurrence.

RSR 12.5.1.1 not met.

Page 1-12.5.1-4

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.5.1.1 TES------

-IV%,

j -------

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 In accordance with R12.5.1-1 and the ODCM to the detection capabilities the Radiological required by Table R12.5.1-3. Environmental Monitoring Program Page 1-12.5.1-5

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 1 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS(') FREQUENCY"" OF ANALYSIS"t 1 "

1. Airborne Radioiodine Samples from a total of eight locations: CONTINUOUS sampler Radioiodine Canister:

and Particulates operation with particulate sample 1-131 analysis once per

a. Indicator- Near Field collection once per 7 days, or 14 days on near field more frequently if required due samples and control(2)

Four samples from locations within 4.0 km (2.5 mi) in to dust loading, and radioiodine samples.

different sectors. canister collection once per 14 days. Particulate Sampler:

b. Indicator- Far Field Gross beta analysis following once per 7 day Four additional locations within 4.0 to 10 km (2.5 to 6.2 filter change(3) and gamma mi) in different sectors. isotopic analysis(4) once per 92 days on composite

c. Control filters by location on near field and control(2) samples.

One sample from a control location within 10 to 30 km (6.2 to 18.6 mi).

(continued)

Page 1-12.5.1-6

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 2 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS") FREQUENCY"1 ") OF ANALYSISI1 1 )

2. Direct Radiation[b) Forty routine monitoring stations, either with a 92 days Gamma dose on each TLD thermoluminescent dosimeter (TLD) or with one once per 92 days.

instrument for measuring dose rate continuously, placed as follows:

a. Indicator- Inner Ring (100 Series TLD)

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 kin);

b. Indicator- Outer Ring (200 Series TLD)

One in each meteorological sector, within 4.8 to 10 km (3 to 6.2 mi);

c. Other (300 Series TLD)

One at each Airborne location given in part 1.a. and 1.b.

The balance of the TLDs 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. I (continued)

Page 1-12.5.1-7

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 3 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS(" FREQUENCY"11 ) OF ANALYSIS"11"

3. Waterbome a. Indicator 92 days Gamma isotopice4) and tritium analysis once per 92

a. Ground/ Well Samples from two sources only if likely to be days.

affected .6)

b. Drinking(') a. Indicator Grab samples once per 7 days. Gross beta and gamma isotopic analyses(4) on once One Sample from each community drinking water per 31 day composite; supply that could be affected by the station discharge tritium analysis on once per within 10 km (6.2 mi) downstream of discharge. 92 day composite.

1-131 on each composite when calculated dose for water consumption > 1 mrem/year.

c. Surface Waterl: If no community water supply (Drinking Water) exists Grab samples once per 7 days. Gross beta and gamma within 10 km downstream of discharge then surface isotopic analyses(4) on once water sampling shall be performed. per 31 day composite; tritium analysis on once per

a. Indicator 92 day composite.

One sample downstream

d. Control Sample () a. Control Grab samples once per 7 days. Gross beta and gamma isotopic analyses(4) on once One surface sample upstream of discharge. per 31 day composite; tritium analysis on once per 92 day composite.

e. Sediment a. Indicator 184 days Gamma isotopic analysis'4 once per 184 days.

within 10 At least one sample from downstream(7) area km (6.2 mi).

(continued)

Page 1-12.5.1-8

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 4 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY 1

AND/ OR SAMPLE SAMPLE LOCATIONS(1 ) FREQUENCY"t"I OF ANALYSIS(" )

4. Ingestion a. Indicator Once per 14 days when animals Gamma isotopicd4) and are on pasture (May through 1-131(9) analysis on each

a. Milk(8) Samples from milking animals from a maximum of October), once per 31 days at sample.

three locations within 10 km (6.2 mi) distance. other times (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).

b. Fish a. Indicator Twice per 12 months. Gamma isotopic analysis14) on edible portions commercially and Representative samples of 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.

c. Food Products a. Indicator 12 months Gamma isotopic"4 ' and 1-131 analysis on each Two representative samples from the principal food sample.

pathways grown in each of four major quadrants within 10 km (6.2 mi), if available:

0 At least one root vegetable sample(1 )

At least one broad leaf vegetable (or vegetation)(1 °)

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

Page 1-12.5.1-9

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-1 (Page 5 of 5)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table R12.5.1-1, except for vegetation. For vegetation, due to location variability year to year, the parameters of distance and direction shall be provided inthe Annual Environmental Operating Report.

(2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the ODCM Specialist.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. Ifgross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., ifa station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters that could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) The "downstream" sample shall be taken inan area beyond but near the mixing zone. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence.

(8) Ifmilking animals are not found in the designated indicator locations, or ifthe owners decline to participate in the REMP, all milk sampling may be discontinued.

(9) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.

(10) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container.

(11) The provisions of RSR 12.0.2 and RSR 12.0.3 are not applicable to the REMP.

Page 1-12.5.1-10

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE FOOD PRODUCTS ANALYSIS WATER (pCi/I) OR GASES (pCi/m 3) FISH (pCi/kg, wet) MILK (pCi/I) (pCi/kg, wet)

H-3 20,000(1)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2(2) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-La-1 40 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

(2) If no drinking water pathway exists, a value of 20 pCi/I may be used.

Page 1-12.5.1-11

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls Table R12.5.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(a)

LOWER LIMIT OF DETECTION (LLD)(b)

AIRBORNE PARTICULATE FISH FOOD PRODUCTS SEDIMENT/SOIL 3

ANALYSIS WATER (pCi/I) OR GASES (pCi/m ) (pCi/kg, wet) MILK (pCi/I) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1(c) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) All peaks identified at the 95% confidence level, shall also be analyzed and reported.

(b) Most restrictive ODCM LLD requirement or technical requirement. The reported minimum detectable concentration (MDC) shall be < these values.

(c) If no drinking water pathway exists, a value of 15 pCi/I may be used (NUREG 1301/1302)

Page 1-12.5.1-12

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.2 Land Use Census REC 12.5.2 A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.

.-------------- NOTES----------------

1. The 16 meteorological sectors requirement may be reduced according to geographical limitations; e.g. at a lake site where some sectors will be over water.

2. The nearest industrial facility shall also be documented if closer than the nearest residence.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.--------- NOTE --------- A.1 Add the new location to the 30 days Required Action A. 1 and Radiological Environmental A.2 shall be completed if Monitoring Program this Condition is entered. (REMP).

Land use census identifies AND a location which yields a calculated dose or dose commitment, via the same exposure pathway, that is at least 20% greater than at a location from which samples are currently being obtained in accordance with REC 12.5.1.

(continued)

Page 1-12.5.2-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------ NOTE-- --

The sampling location(s),

excluding the control location, having the lowest calculated dose or dose commitment(s),

via the same exposure pathway, may be deleted from the REMP after October 31 of the year in which Land Use Census was conducted.

Submit the documentation for In accordance with a change in the ODCM in the Technical next Annual Radiological Specification 5.6.2.

Environmental Operating Report and include the revised figures and tables for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.5.2.1 Conduct a land use census during the growing -------- NOTE --------

season, between June 1 and October 1, using RSR 12.0.2 and 12.0.3 information that will provide the best results, such as are not applicable.

by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results 12 months of the census shall be included in the Annual Radiological Environmental Operating Report.

Page 1-12.5.2-2

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.3 Interlaboratory Comparison Program REC 12.5.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that is traceable to NIST.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------- NOTE -------- A. 1 Report corrective actions to In accordance with Required Action A.1 shall prevent recurrence to the NRC Technical be completed if this in the next Annual Radiological Specification 5.6.2 Condition is entered. Environmental Operating Report.

Requirements of the REC not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY RSR 12.5.3 Include a summary of the results of the Interlaboratory In accordance with Comparison Program in the Annual Radiological Technical Environmental Operating Report. Specification 5.6.2 Page 1-12.5.3-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.4 Meteorological Monitoring Program (NOT APPLICABLE)

Page 1-12.5.4-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating Report 12.6.1.1 Routine Annual Radiological Environmental Operating Report covering the operation of the Units during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring program for the report period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual, and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.c. It should include, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

12.6.1.2 The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Part II, Section 6 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

12.6.1.3 The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by REC 12.5.1, and discussion of all deviations from the sampling schedule of Table R12.5.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of ODCM Part II, Table 6.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table R12.5.1-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table R12.5.1-3 was not achievable; results of the Land Use Census required by REC 12.5.2; and the results of licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by REC 12.5.3.

(continued)

Page 1-12.6.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating Report (continued) 12.6.1.4 The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining the summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

12.6.1.5 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Page 1-12.6.1-2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12.6.2 Annual Radioactive Effluent Release Report 12.6.2.1 The radioactive effluent release reports covering the operation of the unit during the previous calendar year of operation shall be submitted in accordance with 10 CFR 50.36a prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the PROCESS CONTROL PROGRAM and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1. A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

12.6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

12.6.2.3 The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

1. Container volume,

2. Total curie quantity (specify whether determined by measurement or estimate),

3. Principal radionuclides (specify whether determined by measurement or estimate),

4. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

6. Solidification agent (e.g., cement, urea formaldehyde).

(continued)

Page 1-12.6.2-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12.6.2 Radioactive Effluent Release Report (continued) 12.6.2.4 The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

12.6.2.5 The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

12.6.2.6 The radioactive effluent release reports shall include a description of licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous and solid), as described in Section 12.6.3.)

Page I-12.6.2-2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12,6.3Offsite Dose Calculation Manual (ODCM) 12.6.3.1 The ODCM is common to LaSalle Unit 1 and LaSalle Unit 2. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and 12.6.3.2 The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

12.6.3.3 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance (QA) Manual. This documentation:

1. Shall contain sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s); and

2. Shall contain a determination that the change(s) maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Shall become effective after approval of the Plant Manager.

4. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

Page 1-12.6.3-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls 12.6 REPORTING REQUIREMENTS 12.6.4 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12.6.4.1 Licensee initiated major changes to the radioactive waste treatment systems (liquid and gaseous):

a. Shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operations Review Committee (PORC). The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit or additional or supplemental information;

3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period to when the changes are to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

Page 1-12.6.4-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.1302 of 10 CFR, Part 20. At the same time, the licensee is permitted the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in Section 20.1302 of 10 CFR, Part 20. It is expected that in using this operational flexibility under unusual operating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.

I-B-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.0 OFFSITE DOSE CALCULATION MANUAL (ODCM) RADIOLOGICAL EFFLUENT CONTROL (REC) APPLICABILITY BASES RECs REC 12.0.1 through REC 12.0.6 establish the general requirements applicable to all RECs in Sections 12.1 through 12.5 and apply at all times, unless otherwise stated.

REC 12.0.1 REC 12.0.1 establishes the Applicability statement within each individual REC as the requirement for when the REC is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Requirement).

REC 12.0.2 REC 12.0.2 establishes that upon discovery of a failure to meet a REC, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a REC are not met. This Requirement establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a REC; and

b. Completion of the Required Actions is not required when a REC is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the REC must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the REC is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.) The second type of Required (continued)

I-B12.0-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls BASES REC 12.0.2 Action specifies the remedial measures that permit continued operation of (continued) the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.

Completing the Required Actions is not required when a REC is met or is no longer applicable, unless otherwise stated in the individual RECs.

The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Condition no longer exists. The individual REC's ACTIONS specify the Required Actions where this is the case. An example of this is in REC 12.4.2, "Dose from Noble Gases."

The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead. Doing so limits the time both subsystems/divisions of a function are inoperable and limits the time conditions exist which may result in REC 12.0.3 being entered. Individual RECs may specify a time limit for performing a RSR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another REC becomes applicable. In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new REC becomes applicable and the ACTIONS Condition(s) are entered.

(continued) 1-112.0-2

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls BASES (continued)

REC 12.0.3 REC 12.0.3 establishes the actions that must be implemented when a REC is not met and:

a. An associated Required Action and Completion Time is not met and no other Condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of Conditions are such that entering REC 12.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that REC 12.0.3 be entered immediately.

Upon entering REC 12.0.3, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is allowed to implement appropriate compensatory actions and verify the plant is not in an unanalyzed condition or that a required safety function is not compromised. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , Shift Operations Superintendent or designee approval of the compensatory actions and the plan for exiting REC 12.0.3 must be obtained. The use and interpretation of specified times to complete the actions of REC 12.0.3 are consistent with the discussion of Section 1.3, Completion Times.

The actions required in accordance with REC 12.0.3 may be terminated and REC 12.0.3 exited if any of the following occurs:

a. The REC is now met.

b. A Condition exists for which the Required Actions have now been performed.

c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time REC 12.0.3 is exited.

(continued)

I-B12.0-3

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls BASES REC 12.0.3 In MODES 1, 2, and 3, REC 12.0.3 provides actions for Conditions not (continued) covered in other Requirements. The requirements of REC 12.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive Condition. The requirements of REC 12.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual RECs sufficiently define the remedial measures to be taken.

REC 12.0.4 REC 12.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an REC is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:

a. Unit conditions are such that the requirements of the REC would not be met in the Applicability desired to be entered; and

b. Continued noncompliance with the REC requirements, ifthe Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the Required Actions.

Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change.

Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions. The provisions of this REC should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of REC 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of REC 12.0.4 shall not prevent (continued) 1-B132.0-4

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES REC 12.0.4 changes in MODES or other specified conditions in the Applicability that (continued) result from any unit shutdown.

Exceptions to REC 12.0.4 are stated in the individual RECs. The exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time. Exceptions may apply to all the ACTIONS or to a specific Required Action of a REC.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by RSR 12.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS Condition, either in compliance with REC 12.0.4, or where an exception to REC 12.0.4 is stated, is not a violation of RSR 12.0.1 or RSR 12.0.4 for those Surveillances that do not have to be performed due to the associated inoperable equipment. However, RSRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected REC.

REC 12.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, REC 12.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of REC 12.0.4 do not apply in MODES 4 and 5, or in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Requirements sufficiently define the remedial measures to be taken.

REC 12.0.5 REC 12.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Requirement is to provide an exception to REC 12.0.2 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of required testing to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or (continued) 1-B132.0-5

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES REC 12.0.5 b. The OPERABILITY of other equipment.

(continued)

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Requirement does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

REC 12.0.6 REC 12.0.6 establishes the applicability of each REC to both Unit 1 and Unit 2 operation. Whenever a requirement applies to only one unit, or is different for each unit, this will be identified in the appropriate section of the REC (e.g., Applicability, RSR, etc.) with parenthetical reference, Notes, or other appropriate presentation within the body of the requirement.

1-812.0-6

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.0 ODCM RADIOLOGICAL SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY BASES RSRs RSR 12.0.1 through RSR 12.0.5 establish the general requirements applicable to all Requirements in 12.1 through 12.5 and apply at all times, unless otherwise stated.

RSR 12.0.1 RSR 12.0.1 establishes the requirement that RSRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the REC apply, unless otherwise specified in the individual RSRs. This REC is to ensure that RSRs are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a RSR within the specified Frequency, in accordance with RSR 12.0.2, constitutes a failure to meet a REC.

Systems and components are assumed to be OPERABLE when the associated RSRs have been met. Nothing in this RSR, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the RSRs; or

b. The requirements of the RSR(s) are known to be not met between required RSR performances.

RSR do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated REC are not applicable, unless otherwise specified.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given RSR. In this case, the unplanned event may be credited as fulfilling the performance of the RSR.

(continued)

I-B12.0-7

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES RSR 12.0.1 RSRs, including RSRs invoked by Required Actions, do not have to be (continued) performed on inoperable equipment because the ACTIONS define the remedial measures that apply. RSRs have to be met and performed in accordance with RSR 12.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable RSRs are not failed and their most recent performance is in accordance with RSR 12.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

RSR 12.0.2 RSR 12.0.2 establishes the requirements for meeting the specified Frequency for RSRs and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..."

interval.

RSR 12.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates RSR scheduling and considers plant operating conditions that may not be suitable for conducting the RSR (e.g.,

transient conditions or other ongoing RSR or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the RSR at its specified Frequency. This is based on the recognition that the most probable result of any particular RSR being performed is the verification of conformance with the RSRs.

As stated in RSR 12.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action, (continued) 1-B132.0-8

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES RSR 12.0.2 whether it is a particular RSR or some other remedial action, is considered a (continued) single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

The provisions of RSR 12.0.2 are not intended to be used repeatedly merely as an operational convenience to extend RSR intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

RSR 12.0.3 RSR 12.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a RSR has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater, applies from the point in time it is discovered that the RSR has not been performed in accordance with RSR 12.0.2, and not at the time that the specified Frequency was not met. This delay period provides adequate time to complete RSRs that have been missed. This delay period permits the completion of a RSR before complying with Required Actions or other remedial measures that might preclude completion of the RSR.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the RSR, the safety significance of the delay in completing the required RSR, and the recognition that the most probable result of any particular RSR being performed is the verification of conformance with the requirements.

When a RSR with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to each release, or in accordance with the Radioactive Liquid Waste Sampling and Analysis Program, etc.) is discovered to not have been (continued)

I-B12.0-9

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES RSR 12.0.3 performed when specified, RSR 12.0.3 allows for the full delay period of up (continued) to the specified Frequency to perform the RSR. However, since there is not a time interval specified, the missed RSR should be performed at the first reasonable opportunity.

RSR 12.0.3 provides a time limit for, and allowances for the performance of, RSRs that become applicable as a consequence of MODE changes imposed by Required Actions.

Failure to comply with specified Frequencies for RSRs is expected to be an infrequent occurrence. Use of the delay period established by RSR 12.0.3 is a flexibility which is not intended to be used as an operational convenience to extend RSR intervals. While up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the limit of the specified Frequency is provided to perform the missed RSR, it is expected that the missed RSR will be performed at the first reasonable opportunity. The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the RSR as well as any plant configuration changes required or shutting the plant down to perform the RSR) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the RSR. This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed RSR should be treated as an emergent condition as discussed in the Regulatory Guide.

The risk evaluation may use quantitative, qualitative, or blended methods.

The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed RSRs for important components should be analyzed quantitatively. Ifthe results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed RSRs will be placed in the station's Corrective Action Program.

(continued) 1-B132.0-10

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls BASES RSR 12.0.3 If a RSR is not completed within the allowed delay period, then the (continued) equipment is considered inoperable or the variable then is considered outside the specified limits and the Completion Times of the Required Actions for the applicable REC Conditions begin immediately upon expiration of the delay period. If a RSR is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable REC Conditions begin immediately upon the failure of the RSR.

Completion of the RSR within the delay period allowed by this RSR, or within the Completion Time of the ACTIONS, restores compliance with RSR 12.0.1.

RSR 12.0.4 RSR 12.0.4 establishes the requirement that all applicable RSRs must be met before entry into a MODE or other specified condition in the Applicability.

This RSR ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.

The provisions of this RSR should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

However, in certain circumstances, failing to meet a RSR will not result in RSR 12.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated RSR(s) are not required to be performed per RSR 12.0.1 which states that RSRs do not have to be performed on inoperable equipment. When equipment is inoperable, RSR 12.0.4 does not apply to the associated RSR(s) since the requirement for the RSR(s) to be performed is removed. Therefore, failing to perform the RSRs within the specified Frequency, on equipment that is inoperable, does not result in a RSR 12.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the REC is not met in this instance, REC 12.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.

(continued) 1-812.0-11

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls BASES RSR 12.0.4 The provisions of RSR 12.0.4 shall not prevent changes in MODES or (continued) other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of RSR 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

The precise requirements for performance of RSRs are specified such that exceptions to RSR 12.0.4 are not necessary. The specific time frames and conditions necessary for meeting the RSRs are specified in the Frequency, in the RSR, or both. This allows performance of RSRs when the prerequisite condition(s) specified in a RSR procedure require entry into the MODE or other specified condition in the Applicability of the associated REC prior to the performance or completion of a RSR. A RSR that could not be performed until after entering the REC Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the RSR may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of RSRs' annotation is found in Section 1.4, Frequency.

RSR 12.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, RSR 12.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of RSR 12.0.4 do not apply in MODES 4 and 5, or in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.

RSR 12.0.5 RSR 12.0.5 establishes the applicability of each RSR to both Unit 1 and Unit 2 operation. Whenever a requirement applies to only one unit, or is different for each unit, this will be identified with parenthetical reference, Notes, or other appropriate presentation within the RSR.

1-812.0-12

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.1 NOT USED INTENTIONALLY BLANK 1-B132.1-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.2 INSTRUMENTATION B 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RECS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

I-B12.2.1-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.2 INSTRUMENTATION B 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RECS.

1-B132.2.2-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.3LIQUID EFFLUENTS B 12.3.1 Liquid Effluent Concentration BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section II.A design objectives of Appendix 1,10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.1301 to the population. In addition, this limit is associated with 40 CFR 141 which states concentration limits at the nearest downstream potable water supply. The results of the analyses of RSR 12.3.1.1, 12.3.1.2, and 12.3.1.3 shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of this REC. Refer to Technical Specification 5.5.9.b for the definition of an outside temporary tank.

I-B1 2.3.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B.12.3LIQUID EFFLUENTS B 12.3.2 Dose From Liquid Effluents BASES This control is provided to implement the requirements of Sections ILA, III.A and IV.A of Appendix 1,10 CFR Part 50. The REC implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This control applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing that system.

1-B132.3.2-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.3LIQUID EFFLUENTS B 12.3.3 Liquid Radwaste Treatment Systems BASES The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." A system bypass allows connection to portable waste treatment equipment. This enables the efficient processing of liquid radwaste through the use of state-of-the-art radwaste processing technology. The portable radwaste treatment system may be used in lieu of various portions of the liquid radwaste treatment system. When a portable waste treatment is not used, RSR 12.3.3.2 may be extended to 180 days. This control implements the requirements of 10 CFR Part 50.36a. General Design Criterion 50 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents. This specification implements Technical Specification Section 5.5.4.f for liquid effluents.

Page 1-812.3.3-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.1 Gaseous Effluent Dose Rates BASES This control is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of RECS for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary exceeding the limits specified in 10 CFR 20.1301. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to a dose rate of 500 mrem/year to the total body or to less than or equal to a dose rate of 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrem/year.

This control applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. For units within shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

Page I-B12.4.1-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.2 Dose from Noble Gases BASES This control is provided to implement the requirements of Sections 11.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section 11.8 of Appendix I. The ACTION statements provide the required operating flexibilit, and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man fror Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equation-,

provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

Page I-B12.4.2-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.3 Dose from Iodine-1 31, Iodine-1 33, Tritium and Radioactive Materials in Particulate Form BASES The control is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1,10 CFR Part 50. The operability requirements are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive materials in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.4 GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM BASES The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.8 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES The OPERABILITY of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents. This control implements Technical Specification 5.5.4.f for gaseous effluents.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.6 MARK II CONTAINMENT BASES This control provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10 CFR 20 for unrestricted areas.

Based on definition, VENTING would not release a volume resulting in significant contribution to gaseous plant effluents, nor resultant offsite dose. As such, there is no ODCM requirement for sampling. Sampling is required for PURGING, however, since the entire drywell volume is potentially released. Sampling prior to conducting a drywell PURGE provides a pre-release check to ensure release limits will not be exceeded, and allows for the subsequent calculation of offsite dose as a result of the drywell purge.

Once the Unit is sub-critical following shutdown, the initial 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months purge will exchange multiple volumes of the drywell removing the pre-existing noble gas concentration, and the lack of any source term will yield no new concentration. Likewise, there will be no source term until criticality has been achieved following startup.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.7 Total Dose BASES This control is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The report will describe a course of action that should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purpose of the report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of the RECS. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.8 Main Condenser BASES This control provides reasonable assurance that the releases from the main condenser will not exceed the requirements of the LaSalle Technical Specifications 3.7.6. In addition, a sample is required within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months if the increase is not due to thermal power changes. If the cause is known and not fuel related and less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration, then no sample is required. [This is based on a letter from W. R. Huntington to Operating Engineers, Shift Engineers and F.R. Lawless, dated May 24, 1984.]

Page I-B12.4.8-1

CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.4GASEOUS EFFLUENTS AND TOTAL DOSE B 12.4.9 Dose Limits for MEMBERS OF THE PUBLIC BASES This control applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents. 10 CFR 20.1301 sets forth the 100 mrem/year dose limit to members of the public; 2 mrem in any one-hour limit in the unrestricted area; and reiterates that the licensee is also required to meet the 40 CFR 190 standards. 10 CFR 20.1302 provides options to determine compliance to 10 CFR 20.1301. Compliance to the above operability requirement is based on 10 CFR 20, 40 CFR 190 and LaSalle Station Technical Specification 5.5.4.g. The Effluents Program shall implement monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters of the ODCM.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B 12.5.1 Radiological Environmental Monitoring Program BASES The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table R 12.5.1-3 are considered optimum for routine environmental measurements in industrial laboratories. 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.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Table R12.5.1-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) that is used for drinking.

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CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B 12.5.2 Land Use Census BASES This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

Page 1-B12.5.2-1

CY-LA-170-301 Revision 4 Part I, Radiological Effluent Controls B 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B 12.5.3 Interlaboratory Comparison Program BASES The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

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CY-LA-1 70-301 Revision 4 Part I, Radiological Effluent Controls B 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B 12.5.4 Meteorological Monitoring Program (NOT APPLICABLE)

Page 1-B12.5.4-1

RA13-020, Submittal of 2012 Annual Radioactive Effluent Release Report

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1.0 INTRODUCTION

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RA13-020, Submittal of 2012 Annual Radioactive Effluent Release Report

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1.0 INTRODUCTION

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