Text

Transmittal of Year 2009 Radioactive Effluent Release Report
	ML101250615
Person / Time
Site:	Comanche Peak
Issue date:	04/29/2010
From:	Madden F; Luminant Power
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CP-201000647, TXX-10068
	Download: ML101250615 (174)
	v • d • e

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002

& Chief Nuclear Officer 6322 North FM 56 Rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201000647 Ref. # Tech. Spec. 5.6.3 Log # TXX-10068 April 29, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF YEAR 2009 RADIOACTIVE EFFLUENT RELEASE REPORT

Dear Sir or Madam:

In accordance with Comanche Peak Nuclear Power Plant Unit 1 and 2 Technical specifications (TS) 5.6.3 and Section 6.9.1.4 of the Comanche Peak Offsite Dose Calculation Manual (ODCM), enclosed is the Radioactive Effluent Release Report which covers the reporting period from January 1, 2009 through December 31, 2009.

The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21, Rev. 1, dated June, 1974.

During this reporting period there were two revisions to the ODCM. These revisions are discussed in the report and are denoted by change bars in the copy of the ODCM provided in Enclosure 2.

If there are any questions regarding this report, please contact Steve Dixon at (254) 897-5482 or Bill Moore at (254) 897-8222.

Sincerely, Luminant Generation Company LLC Rafael Flores By: /*A",I W- )n ý,..

4

red W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance ,4- *0 Callaway

Comanche Peak - Diablo Canyon

Palo Verde

San Onofre- South Texas Project

Wolf Creek /"-4 I'

U. S. Nuclear Regulatory Commission TXX-10068 Page 2 04/29/2010 Enclosures 1. 2009 Radiological Effluent Release Report

2. Comanche Peak Nuclear Power Plant Offsite Dose Calculation Manual (ODCM)

Unit 1 and 2, Revision 29 and Revision 30 c- E. E. Collins, Region IV L. K. Gibson, NRR Resident Inspectors, Comanche Peak (w/o Encl 2)

2009 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2009 - December 31, 2009 Prepared By: David Valentine Date: 3/25/2010 Reviewed By: Randy Walsh Date: 3/30/2010 Approved By: Bill Moore Date: 4/4/2010 Page 1 of 45

TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS

1.0 INTRODUCTION

1.1 Executive Summary 1.2 Historical Trend Graphs 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total Radioactivity 2.4 Batch Releases 2.5 Abnormal or Unplanned Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RADIOLOGICAL IMPACT ON MAN 6.1 Dose Due to Liquid Effluents 6.2 Dose Due to Gaseous Effluents 6.3 Dose Due to Radioiodines, Tritium and Particulates 6.4 40CFR190 Dose Evaluation 6.5 Dose to a MEMBER OF THE PUBLIC From Activities Inside the Site Boundary 7.0 METEROLOGICAL DATA 7.1 Meteorological Monitoring Program 8.0 RELATED INFORMATION 8.1 Operability of Liquid and Gaseous Monitoring Instrumentation 8.2 Changes to the Offsite Dose Calculation Manual Page 2 of 45

8.3 New Locations for Dose Calculations or Environmental Monitoring 8.4 Liquid Holdup and Gas Storage Tanks 8.5 Noncompliance with Radiological Effluent Control Requirements 8.6 Resin Releases to the LVW Pond 8.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems 8.8 Groundwater Tritium Monitoring Program 9.0 TABLES 9.1 Site Liquid and Gaseous Batch Release Summary 9.2 Site Abnormal Batch Liquid and Gaseous Release Summary 9.3 Site Gaseous Effluents-Summation of All Releases 9.4 Site Gaseous Effluents-Ground Level Releases 9.5 Site Liquid Effluents Summation of All Releases 9.6 Site Liquid Effluents 9.7 Dose Due to Liquid Releases-Site 9.8 Dose Due to Gaseous Releases-Site 9.9 Dose Due to Radioiodines, Tritium, and Particulates in Gaseous Releases-Site 9.10 Solid Waste and Irradiated Fuel Shipments 9.11 Meteorological Joint Frequency Tables 10.0 ATTACHMENTS 10.1 Meteorological Joint Frequency Distribution Tables Page 3 of 45

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPNPP Comanche Peak Nuclear Power Plant ECL Effluent Concentration Limit LDCR Licensing Document Change Request LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks pCi Picocurie REC Radiological Effluent Control SORC Station Operations Review Committee uCi Microcurie WMT Waste Monitor Tanks WWHT Waste Water Holdup Tanks Page 4 of 45

1.0 Introduction This Radioactive Effluent Release Report, for Comanche Peak Nuclear Power Plant Unit 1 and Unit 2, is submitted as required by Technical Specification 5.6.3 and Offsite Dose Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 2009, through December 31, 2009.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2009 was conducted as described in the following report. The results of the monitoring program indicate the continued effort to maintain the release of radioactive effluents to the environment as low as reasonably achievable (ALARA).

Gaseous Effluents:

A summary of all the radioactive gaseous releases to the environment during 2009 Gaseous Waste 2009 2008 Comments Tritium Activity 56.2 Ci 61.27 Ci 1 Total Fission and Activation Activity 5.08 Ci 996.9 Ci 2,5 Total Particulate Activity 0 Ci 8.44E-05 Ci 2,3,5 Gross Alpha Activity 0 Ci 0 Ci 3 Iodine Activity 0 Ci 1.41E-04 Ci 2,3,5 Calculated Gamma Air Dose 4.79e-4 mRad 3.93E-02 mRad 2,5.

Calculated Beta Air Dose 1.1Oe-3 mRad 0.112 mRad 2,5 Total Whole body dose 0.0789 mRem 0.0868 mRem 4,5 Comments:

1. The major contributor to gaseous tritium activity is evaporation from the spent fuel pools.

Factors contributing to the tritium activity in the pools is related to the type of fuel used (i.e., 18-month fuel) the core life and power output and number of core cycles.

2. Because CPNPP had no fuel defects during 2009 (whereas 2008 did), most of the total activities and dose decreased significantly in 2009.

3. No alpha, iodine or particulate activity was released.

4. Total whole body dose is very low (0.31% of Technical Specification).

5. There was only one refueling outage in 2009 versus two in 2008.

Overall the gaseous radioactivity releases from CPNPP are well controlled and maintained ALARA.

CPNPP is well below all applicable limits for gaseous releases. Because neither unit had fuel defects during 2009, most of the released activity and associated dose was significantly lower than those during 2008.

Page 5 of 45

Liquid Effluents:

A summary of all the radioactive liquid releases to the environment during 2009:

Liquid Waste 2009 2008 Comments Total Activity (excluding tritium) 3.75mCi 15.2 mCi 1,2 Tritium Activity 1623 Ci 2426 Ci 1,2 Total Whole Body Dose 0.129 mRem 0.127 mRem Comments

1. There was only one refueling outage in 2009 versus two in 2008.

1. Because CPNPP had no fuel defects during 2009 (whereas 2008 did), most of the total activities and dose decreased significantly in 2009.

Meteorological Data The CPNPP meteorological system achieved a greater than 90% recoverable data rate for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed, wind direction and delta temperature. The individual percent recoveries are listed below:

Meteorological Data Recovery Channel % Recovery Wind Speed 97.6 Wind Direction 97.9 Delta Temperature A 99 Delta Temperature B 98.7 Monitors OOS > 30 Days During 2009 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

ODCM Changes There were two revisions to the ODCM submitted in 2009.

Page 6 of 45

Solid Waste Summary of the solid waste production Total Waste 2009 2008 % Error Comments Shipped (m3) 168 362 25%

Shipped (Ci) *175 383 25% 1 Buried (m3) 28.5 40.6 25%

Buried (Ci) 2.34 559 25% 1 Comments

1. The large decrease in Ci shipped was due to clearing our backlog of B & C Class (high activity) waste last year prior to Barnwell closing.

Overall, the radioactive effluent monitoring program has been conducted in an appropriate manner to ensure the activity released and associated dose to the public has been maintained as low as reasonably achievable (ALARA).

Groundwater Tritium CR-2009-001351-00 documented some positive indications of tritium in the seepage sump near the water plant and in the A and C Waste Monitoring Basins. All of these samples were well below the state reportable criteria of 20,000 pCi/L. None of these positive tritium values were released to the environment.

See section 8.8 for details.

Page 7 of 45

1.2 Historical Trend Graphs Total Gaseous Fission and Activation Activity Released from CPNPP 845.00 996.9 1000.00 228.00 148.00 100.00 25.20 0 13.90 0

10.00- F7L 5.62 5.08 2.60 0

I.-

1.00 -H F- fi 1.60 1.60 1.00 1.30

,F_

1.48 0.10 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Total Gaseous Tritium Released from CPNPP 90.00 80.00 70.00 60.00 6

0 50.00

'~40.00 0

'U o30.00 20.00 10.00 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Page 8 of 45

Total Whole Body Dose due to Gaseous Activity released from CPNPP 0.12 0.10 0.08 0.06 0

0.04 0.02 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 - 2007 2008 2009 Year Total Volume Liquid Effluents Released from CPNPP 1400000 1200000 CD 1000000 E

.2 800000 0

600000 400000 200000 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Page 9 of 45

Total Activity (Excluding H3) Released in Liquid Effluents from CPNPP 400.00 358.00 350.00 "

300.00 200 -227.90 232.10 150.00 1.

200.00

<* 150.00 -144.00, ;

I 124.80 110.00 I - 111.90 108.70 100,00 ---- -

50.00-17.60 21.60 15.00 0.00 * * -156 .0r-I *.. *37 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Total Curies of Tritium Released in Liquid Effluents from CPNPP U

'C 0i 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Page 10 of 45

Total Whole Body Dose Due to Liquid Effluents Released from CPNPP 0.16 0.14 0 ,14 0.12 0.10 0 0.09 01 0.09 _

0.009 0.080

.0 0

0.06 0.04--

0.02 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Total Volume of Solid Radwaste Buried from CPNPP 200.00 180.00 160.00 140.00 ------

120.00 E

O= 100.00 90.20

.2 80.00 0

60.00 - 22 40.00 34.00 27.10 27.90 20.00 19.20 1 8.70 19.30 UE 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 Year Page 11 of 45

Total Curies of Solid Radwaste Buried from CPNPP C.)

1996 1997 1998 1999 2000 2001- 2002 2003 2004 2005 2006 2007 2008 2009 Year Page 12 of 45

2.0 SUPPLEMENTAL INFORMATION 2.1 Re2ulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.2 Iodine-131. Iodine-133, Tritium and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem/yr to any organ.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

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2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 pCi/ml total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

2.1.4 LVW Pond Resin Inventory The quantity of radioactive material contained in resins transferred to the LVW pond shall be limited by the following expression:

(264/V)

Ij Aj/Cj < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

Aj = pond inventory limit for a single radionuclide j (Curies),

Ci = IOCFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (jiCi/ml),

V = volume of resins in the pond (gallons), and 264 = conversion factor (pCi/Ci per ml/gal) 2.1.5 Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Page 14 of 45

2.2 Effluent Concentration Limits 2.2.1 Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.

2.2.2 Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.OE-04 gCilml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

2.3 Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPNPP ODCM.

2.3.1 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT), Laundry Holdup and Monitor Tanks (LHMT) and Waste Water Holdup Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.

For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly, for Sr-89 and Sr-90, by a contract laboratory.

For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge. These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques. Composite samples were also analyzed for tritium and gross alpha radioactivity using liquid scintillation and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory.

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2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For releases from Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.

For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for 1-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode.

Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the gas flow proportional counting technique. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.

2.4 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 9.1.

2.5 Abnormal or Unplanned Releases Abnormal releases are defined as the unintended discharge of a volume of liquid or airborne radioactivity to the environment. No abnormal or unplanned liquid or gaseous effluent releases occurred during 2009. Table 9.2 summarizes the abnormal and unplanned releases.

3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 9.3 and 9.4. All releases of radioactive material in gaseous form are considered to be ground level releases.

4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 9.5 and 9.6.

5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Table 9.10.

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6.0 RADIOLOGICAL IMPACT ON MAN 6.1 Dose Due to Liquid Effluents The dose to an adult from the fish and cow-meat consumption pathways from Squaw Creek Reservoir were calculated in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in table 9.7.

6.2 Dose Due to Gaseous Effluents The air dose due to gamma emissions and the air dose due to beta emissions were calculated using the highest annual average atmospheric dispersion factor at the Site Boundary location, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 9.8.

6.3 Dose Due to Radioiodines. Tritium and Particulates The dose to an adult, teen, child, and infant from radioiodines and particulates, for the pathways listed in Part II, Table 2.4 of the ODCM, were calculated using the highest dispersion and deposition factors, as appropriate, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 9.9.

Page 17 of 45

6.4 40CFR190 Dose Evaluation ODCM Radiological Effluent Control 3.11.4 requires dose evaluations to demonstrate compliance with 40 CFR Part 190 only if the calculated quarterly or yearly dose exceed two times the applicable quarterly or annual dose limits. At no time during 2009 were any of these limits exceeded, therefore no evaluations are required.

6.5 Dose to a MEMBER OF THE PUBLIC From Activities Inside the Site Boundary Three activities are considered in this evaluation: fishing on Squaw Creek Reservoir, recreation activities at the CPNPP employee recreational area and site tours through the CPNPP Visitors Center.

The highest dose occurred in the evaluation for fishing, resulting in a dose of 1.27E-4 mRem/yr.

The dose to a MEMBER OF THE PUBLIC (fisherman) on Squaw Creek Reservoir was calculated based on fishing twice a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation and submersion. Liquid pathways are not considered since all dose is calculated at the point of circ water discharge into the reservoir.

The dose to a MEMBER OF THE PUBLIC engaged in recreational activities at the CPNPP employee recreational park was calculated based on one visit a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation, submersion and ground plane.

The dose to a MEMBER OF THE PUBLIC during site tours through the CPNPP Visitors Center was calculated based on two visits per year, thirty minutes each visit. Pathways included in the calculation were gaseous inhalation and submersion.

Due to increased security, routine fishing on Squaw Creek Reservoir and visitation by the public on-site has been significantly restricted. The calculations are still valid and included in the event security access restrictions are ever returned to previous conditions and controls.

All calculations were performed in accordance with the methodology and parameters in the ODCM.

7.0 METEROLOGICAL DATA 7.1 Meteorological Monitorin2 Program In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 2009, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 10. During 2009, the goal of >90%

joint data recovery was met. The individual percent recoveries are listed below:

Meteorological Data Recovery Channel % Recovery Wind Speed 97.6 Wind Direction 97.9 Delta Temperature A 99 Delta Temperature B 98.7 Page 18 of 45

8.0 RELATED INFORMATION 8.1 Operability of Liquid and Gaseous Monitoring Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require an explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to operable status within thirty days.

During the period covered by this report, there were no instances where these instruments were inoperable for more than thirty days.

8.2 Changes to the Offsite Dose Calculation Manual During the period covered by this report, there were two revisions to the ODCM approved and/or implemented.

REVISION 29 LDCR-OD-2007-2 (EVAL-2007-002019-01):

Table 3.3-8 action and associated statements were revised to clarify necessary actions in the event of a loss of heat tracing or sample lines to the WRGM sampling skid. These particulate and iodine channels are USNRC Regulatory Guide, 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways.

This 7 day period for entry into the CPNPP Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.

REVISION 30 LDCR-OD-2009-1 (EVAL-2008-002039-03):

Note 2 of Table 3.12-1 and Note 2 of Table 4.12-1 were changed from thermo luminescent dosimeters (TLDs) to Optically Stimulated Luminescence (OSL) Badges. Also "thermoluminescent dosimeter" was replaced with "optically stimulated luminescence (OSL) badge" in section 2.5. This change acknowledges the recent switch from TLDs to OSLs.

8.3 New Locations for Dose Calculations or Environmental Monitorin2 ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental monitoring, identified by the Land Use Census, to be included in the Radioactive Effluent Release Report. Based on the 2009 Land Use Census, no new receptor locations were identified which resulted in changes requiring a revision in current environmental sample locations. Values for the current nearest resident, milk animal, garden, X/Q and D/Q values in all sectors surrounding CPNPP were included in the 2009 Land Use Census.

Page 19 of 45

8.4 Liquid Holdup and Gas Storage Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the limits required to be established by Technical Specification 5.5.12. Technical Requirements Manual 13.10.3.3 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten curies, excluding tritium and dissolved or entrained noble gases. Technical Requirements Manual 13.10.32 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered as Xe-133 equivalent). These limits were not exceeded during the period covered by this report.

8.5 Noncompliance with Radiological Effluent Control Requirements This section provides a listing and description of Abnormal Releases, issues that did not comply with the applicable requirements of the Radiological Effluents Controls given in Part I of the CPNPP ODCM and/or issues that did not comply with associated Administrative Controls and that failed to meet CPNPP expectations regarding Station Radioactive Effluent Controls. Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite.

8.5.1 Normal, Unplanned Gaseous Release No normal, unplanned gaseous effluent releases occurred during 2009.

8.5.2 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2009.

8.5.3 Abnormal, Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2009.

8.6 Resin Releases to the LVW Pond A total of 158 ft3 of powdex resin was transferred to the LVW pond during the period covered by this report. The cumulative activity deposited in the LVW pond since operations began through the end of 2009 is 1.15E-3 Curies, consisting of Co-58, Co-60, Cs-134, Cs-137, 1-131 and Sb-125.

8.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems In accordance with the CPNPP Process Control Program, Section 6.2.6.2, changes to the Radwaste Treatment Systems (liquid, gaseous and solid) should be summarized and reported to the Commission in the Radioactive Effluent Release Report if the changes implemented required a 10CFR50.59 safety evaluation.

For the reporting period of this report, no changes to the Radwaste Treatment Systems occurred that meet the reporting criteria of the Process Control Program.

Page 20 of 45

8.8 Groundwater Tritium monitorin2 Pro2ram Samples of perched groundwater are taken quarterly in accordance with the site groundwater tritium monitoring program. During the first quarter of 2009, a sample from the Water Production Plant seepage sump (storm drain) had positive values for tritium as listed in the table below. This value was well below state reportable limit of 20,000 pCi/L. The source of the tritium is from a small leak of reservoir water that feeds the water plant clarifier. Because CPNPP discharges its effluents into Squaw Creek Reservoir, there is always a low level background concentration of tritium in the reservoir water. Essentially the seepage sump is discharging diluted Squaw Creek Reservoir water back to Squaw Creek Reservoir.

The other positive samples were in waste monitoring basin A and C were from efforts made to repair the outer liner (CR 2008-3781). Water was intentionally transferred from the ponds to the space between the inner and outer liner in order to perform ultrasonic leak testing of the outer liner. Pond water was used because it had a lower concentration of tritium than the reservoir.

Repairs to the liners were completed and the sample results of the Pond Leachate sample points are listed below.

Tritium Results in pCi/L Date Seepage Pond A Pond C Sump Leachate Leachate Feb-09 6200 No Sample 1365 Apr-09 3500 607 337 Aug-09 3000 164 <mda Nov-09 2760 <mda <mda 6.11 Nonroutine planned release There were no unplanned releases during 2009.

Page 21 of 45

SECTION 9.0 TABLES Page 22 of 45

Table 9.1 Site Liquid and Gaseous Batch Release Summary (2009)

A. Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals

1. Number of batch releases 3 8 12 25 48

2. Total time period for Batch releases ( Minutes ) 9.950E+02 2.641E+03 3.750E+03 5.801E+03 1.319E+04

3. Maximum time period for a batch release ( Minutes ) 3.550E+02 3.540E+02 3.350E+02 3.640E+02 3.640E+02

4. Average time period for a batch release ( Minutes ) 3.317E+02 3.301E+02 3.125E+02 2.320E+02 2.747E+02

5. Minimum time period for a batch release ( Minutes ) 3.1 OOE+02 3.030E+02 2.970E+02 6.700E+01 6.700E+01

6. Average stream flow during periods of release of liquid Effluent into a flowing stream (GPM) 1.194E+04 3.665E+04 5.230E+04 7.695E+04 1.778E+05 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals

1. Number of batch releases 36 36 36 32 140

2. Total time period for batch releases ( Minutes ) 1.369E+04 1.406E+04 1.292E+04 1.319E+04 5.386E+04

3. Maximum time period for a batch release (Minutes) 4.850E+02 1.840E+03 4.190E+02 1.200E+03 1.840E+03

4. Average time period for a batch release (Minutes) 3.803E+02 3.907E+02 3.588E+02 4.121E+02 3.847E+02

5. Minimum time period for a batch release (Minutes) 3.090E+02 1.760E+02 2.460E+02 2.120E+02 1.760E+02 Page 23 of 45

Table 9.2 Site Abnormal Liquid and Gaseous Batch Release Summary (2009)

A. Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals.

1. Number of batch releases : 0 0 0 0 0

2. Total time period for Batch releases (Minutes) 0.OOOE+00 O.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00

3. Maximum time period for a batch release (Minutes) 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 O.000E+00

4. Average time period for a batch release (Minutes) 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00

5. Minimum time period for a batch release (Minutes) 0.OOOE+00 O.000E+00 0.000E+00 0.OOOE+00 O.000E+00

6. Total Activity for all releases (Curies) 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals

1. Number of batch releases : 0 0 0 0 0

2. Total time period for batch releases (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

3. Maximum time period for a batch release (Minutes) 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00

4. Average time period for a batch release (Minutes) 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 O.000E+00

.5. Minimum time period for a batch release (Minutes) 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

6. Total Activity for all releases (Curies) 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Page 24 of 45

Table 9.3 Site Gaseous Effluents - Summation of All Releases (2009) 1ST 2ND 3RD 4TH Year Type of Effluent Units Quarter Quarter Quarter Quarter Totals A. Fission And Activation Gases

1. Total Release Curies: 2.224E+00 1.228E-01 2.388E+00 3.495E-01 5.084E+00

2. Average Release rate for period uCi/sec: 2.821E-01 1.557E-02 3.028E-01 4.433E-02 6.449E-01

3. Percent of Applicable Limit %* * *

B. Radioiodines

1. Total Iodine-131 Curies: O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00

2. Average Release rate for period uCi/sec: O.OOOE+00 O.OOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

3. Percent of Applicable Limit %* * *

C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies: O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

2. Average Release rate for period uCi/sec: O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

3. Percent of Applicable Limit %* * *

D. Tritium

1. Total Release Curies: 1.370E+01 1.762E+01 1.535E+01 9.574E+00 5.624E+01

2. Average Release rate for period uCi/sec: 1.738E+00 2.235E+00 1.947E+00 1.214E+00 7.134E+00

3. Percent of Applicable Limit %* * *

E. Gross Alpha

1. Total Release Curies: O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

2. Average Release rate for period uCi/sec: O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

Applicable limits are expressed in terms of dose. Estimated total error for all values is <1.0%

Page 25 of 45

2009 Table 9.4 Site Gaseous Effluents - Ground Level Releases (2009)

Reactor Unit: Site ContinuousMode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases No Nuclides Found N/A N/A N/A N/A Iodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies 1.366E+01 1.759E+01 1.533E+01 9.547E+00 5.613E+01 Gross Alpha No Nuclides Found N/A N/A N/A N/A Page 26 of 45

.2009 Table 9.4 (cont.)

qitc, ('-aepal Effluents - Ground Level Releases (2009*

Effluents - Ground Level Releases (2009)

LJIL*

J *L*IJ Uk*

Batch Mode Nuclides Released .Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Ar-41 Curies 1.212E-01 1.209E-01 1.315E-01 1.005E-01 4.741E-01 Kr-85m Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 6.847E-05 6.847E-05 Kr-85 Curies 2.102E+00 O.OOOE+00 2.244E+00 1.437E-01 4.490E+00 Kr-87 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 6.242E-06 6.242E-06 Kr-88 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 1.699E-07 1.699E-07 Xe-131m Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 1.927E-05 1.927E-05 Xe-133m Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 2.759E-03 2.759E-03 Xe-133 Curies 5.911E-04 1.894E-03 1.218E-02 7.420E-02 8.886E-02 Xe-135m Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 2.098E-03 2.098E-03 Xe-135 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 2.614E-02 2.614E-02 Total For Period Curies 2.224E+00 1.228E-01 2.388E+00 3.495E-01 5.084E+00 lodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies 3.665E-02 3.609E-02 1.813E-02 2.622E-02 1.17E-01 Gross Alpha No Nuclides Found N/A N/A N/A N/A

Zeroes or N/A in this table indicate that no radioactivity was present at detectable levels.

Page 27 of 45

Table 9.5 Site Liquid Effluents - Summation Of All Releases (2009)

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 5.805E-05 1.127E-04 3.918E-04 3.188E-03 3.750E-03

2. Average diluted concentration during period uCi/ml 1.869E-11 1.161E-11 2.787E-11 1.530E-10 2.112E-10

3. Percent of Applicable Limit % 0.000006 0.000009 0.000002 0.000061 B. Tritium

1. Total Release Curies 8.025E+01 3.278E+02 6.005E+02 6.143E+02 1.623E+03

2. Average diluted Concentration during period uCi/ml 2.584E-05 3.378E-05 4.273E-05 2.948E-05 1.318E-04 3.'Percent of Applicable Limit % 2.584 3.378 4.273 2.948 C. Dissolved and Entrained Gases

1. Total Release Curies 4.530E-04 2.793E-03 3.559E-03 1.705E-03 8.511E-03

2. Average diluted Concentration during period uCi/ml 1.459E-10 2.879E-10 2.532E-10 8.184E-1I 7.688E-10

3. Percent of Applicable Limit % 0.000 0.000 0.000 0.000 D: Gross Alpha Radioactivity

1. Total Release Curies 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 2.332E+05 6.146E+05 8.838E+05 1.885E+06 3.616E+06 F. Volume of Dilution Water Used Liters 3.106E+09 9.702E+09 1.405E+10 2.084E+10 4.770E+10 Applicable limits are expressed in terms of dose.

Estimated Total Error For All Values Reported Is < 1.0%

Page 28 of 45

Table 9.6 Site Liquid Effluents (2009)

ContinuousMode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Fission & Activation Products No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A Gross Alpha Radioactivity Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Fission & Activation Products Cr-51 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 7.777E-04 7.777E-04 Mn-54 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 5.747E-05 5.747E-05 Fe-59 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 1.725E-05 1.725E-05 Co-57 Curies O.OOOE+00 O.OOOE+00 7.319E-06 O.OOOE+00 7.319E-06 Co-58 Curies 4.463E-05 6.738E-05 2.512E-04 1.846E-03 2.210E-03 Co-60 Curies 1.342E-05 4.531E-05 1.332E-04 2.230E-04 4.149E-04 Zr-95 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 6.522E-05 6.522E-05 Nb-95 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 1.051E-04 1.051E-04 Sb-125 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 9.554E-05 9.554E-05 Total For Period Curies 5.805E-05 1. 127E-04 3.918E-04 3.188E-03 3.750E-03 Page 29 of 45

Table 9.6 (cont.)

Site Liquid Effluents (2009)

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Tritium H-3 Curies 8.025E+01 3.278E+02 6.005E+02 6.143E+02 1.623E+03 Dissolved And Entrained Gases Kr-85 Curies 4.530E-04 2.766E-03 3.279E-03 1.215E-03 7.713E-03 Xe-133 Curies O.OOOE+00 2.740E-05 2.802E-04 4.647E-04 7.722E-04 Xe-135 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 2.562E-05 2.562E-05 Total For Period Curies 4.530E-04 2.793E-03 3.559E-03 1.705E-03 8.51 1E-03 Gross Alpha Radioactivity 0 0 0 0 0

Zeroes or N/A in this table indicate that no radioactivity was present at detectable levels Page 30 of 45

Table 9.7 Dose to a member of the public due to Liquid Releases (2009)

Cumulative Dose Per Quarter

% of % of % of % of Tech Tech Tech Tech Tech Spec Spec Spec Spec Spec Organ Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit Total Body 1.500E+00 mRem 3.306E-02 2.204E+00 3.211 E-02 2.141E+00 3.094E-02 2.063E+00 3.281E-02 2.187E+00 Bone 5.OOOE+00 mRern 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 3.124E-07 6.249E-06 Thyroid 5.OOOE+00 mRem 3.306E-02 6.612E-01 3.211 E-02 6.423E-01 3.094E-02 6.188E-01 3.280E-02 6.561E-01 Kidney 5.OOOE+00 mRem 3.306E-02 6.612E-01 3.211 E-02 6.423E-01 3.094E-02 6.188E-01 3.280E-02 6.561E-01 Lung 5.OOOE+00 mRem 3.306E-02 6.612E-01 3.21 1E-02 6.423E-01 3.094E-02 6.188E-01 3.281E-02 6.561E-01 Liver 5.OOOE+00 mRem 3.306E-02 6.612E-01 3.211E-02 6.423E-01 3.094E-02 6.188E-01 3.281E-02 6.561E-01 GI-Lli 5.OOOE+00 mRem 3.306E-02 6.612E-01 3.212E-02 6.423E-01 3.094E-02 6.189E-01 3.354E-02 6.707E-01 Cumulative Dose per Year

% of Tech Year to Tech Spec Ending Spec Organ Limit Units Date Limit Receptor Limit Total Body 2.500E+01 mRem 1.289E-01 5.157E-01 Liquid Receptor - Adult 40CFR190.10 (a) TB Thyroid 7.500E+01 mRem 1.289E-01 1.719E-01 Liquid Receptor - Adult 40CFRI 90.10 (a) Thyroid Bone 2.500E+01 mRem 3.124E-07 1.250E-06 Liquid Receptor - Adult 40CFRI90.10 (a) Organ Liver 2.500E+01 mRem 1.289E-01 5.157E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Kidney 2.500E+01 mRem 1.289E-01 5.157E-01 Liquid Receptor - Adult 40CFRI 90.10 (a) Organ Lung 2.500E+01 mRem 1.289E-01 5.157E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ GI-Lli 2.500E+01 mRem 1.297E-01 5.186E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Bone 1.000E+01 mRem 3.124E-07 3.124E-06 Liquid Receptor - Adult Liq Annual Organ Dose Liver 1.000E+01 mRem 1.289E-01 1.289E+00 Liquid Receptor - Adult Liq Annual Organ Dose Thyroid 1.000E+01 mRem 1.289E-01 1.289E+00 Liquid Receptor - Adult Liq Annual Organ Dose Kidney 1.000E+01 mRem 1.289E-01 1.289E+00 Liquid Receptor - Adult Liq Annual Organ Dose Lung 1.000E+01 mRem 1.289E-01 1.289E+00 Liquid Receptor - Adult Liq Annual Organ Dose GI-Lli 1.000E+01 mRem 1.297E-01 1.297E+00 Liquid Receptor - Adult Liq Annual Organ Dose Total Body 3.OOOE+00 mRem 1.289E-01 4.297E+00 Liquid Receptor - Adult Liq Annual TB Dose Total Dilution Volume for 1st Quarter: 3.106E+09 Total Dilution Volume for 2nd Quarter: 9.702E+09 Total Dilution Volume for 3rd Quarter: 1.405E+10 Total Dilution Volume for 4th Quarter: 2.084E+10 Page 31 of 45

Table 9.8 Air Dose Due To Gaseous Releases - Site (2009)

Cumulative Dose Per' Quarter Type of Tech Spec % Tech Spec % Tech Spec % Tech Spec % Tech Spec Radiation Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit Gamma 5.OOOE+00 mRad 1.218E-04 2.436E-03 1.177E-04 2.354E-03 1.324E-04 2.648E-03 1.069E-04 2.139E-03 Beta 1.000E+01 mRad 4.707E-04 4.707E-03 4.169E-05 4.169E-04 5.043E-04 5.043E-03 7.932E-05 7.932E-04 Cumulative Dose Per Year Type of Tech Spec Year to % Tech Spec Radiation Limit Units End Date Limit Receptor Limit Gamma 1.OOOE+01 mRad 4.789E-04 4.789E-03 Gas Receptor SB - Adult NG Annual Gamma Air Dose Gamma 1.000E+01 mRad 4.789E-04 4.789E-03 Gas Receptor SB - Teen NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 4.789E-04 4.789E-03 Gas Receptor SB - Child NG Annual Gamma Air Dose Gamma 1.000E+01 mRad 4.789E-04 4.789E-03 Gas Receptor SB - Infant NG Annual Gamma Air Dose Gamma I.OOOE+01 mRad 4.789E-04 4.789E-03 Gas Receptor MI - Adult NG Annual Gamma Air Dose Gamma 1.0003E+01 mRad 4.789E-04 4.789E-03 Gas Receptor MI - Teen NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 4.789E-04 4.789E-03 Gas Receptor MI - Child NG Annual. Gamma Air Dose Gamma 1.OOOE+01 mRad 4.789E-04 4.789E-03 Gas Receptor MI - Infant NG Annual Gamma Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor SB - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor SB - Teen NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor SB - Child NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor SB - Infant NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor MI - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor MI - Teen NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor MI - Child NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.096E-03 5.480E-03 Gas Receptor MI - Infant NG Annual Beta Air Dose Page 32 of 45

Table 9.9 Dose to A Member Of The Public Due To Radioiodines. Tritium. and Particulates in Gaseous Releases (2009)

Cumulative Dose Per Quarter

% of % of % of % of Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec Organ Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit GI-Lli 7.500E+00 mRem 1.921E-02 2.562E-01 2.471 E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Kidney 7.500E+00 mRem 1.921E-02 2.562E-01 2.471E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Liver 7.500E+00 mRem 1.921E-02 2.562E-01 2.471E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Lung 7.500E+00 mRem 1.921E-02 2.562E-01 2.471E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Thyroid 7.500E+00 mRem 1.921E-02 2.562E-01 2.471E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Total Body 7.500E+00 mRem 1.921E-02 2.562E-01 2.4711E-02 3.295E-01 2.152E-02 2.870E-01 1.343E-02 1.790E-01 Cumulative Dose per Year Tech Year to % of Tech Spec Ending Tech Spec Organ Limit Units Date Limit Receptor Limit Total Body 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor SB - Child 40CFR1 90.10 (a) TB Total Body 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor MI - Child 40CFR1 90.10 (a) TB Thyroid 7.500E+01 mRem 7.888E-02 1.052E-01 Gas Receptor SB - Child 40CFRI 90.10 (a) Thyroid Thyroid 7.500E+01 mRem 7.888E-02 1.052E-01 Gas Receptor MI - Child 40CFRI 90.10 (a) Thyroid Liver 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ Kidney 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor SB - Child 40CFR1 90.10 (a) Organ Lung 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor SB - Child 40CFR1 90.10 (a) Organ GI-Lli 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor SB - Child 40CFR1 90.10 (a) Organ Liver 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor MI - Child 40CFR1 90.10 (a) Organ Kidney 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ Lung 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ GI-Lli 2.500E+01 mRem 7.888E-02 3.155E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ Page 33 of 45

Table 9.9 (cont)

Dose to A Member Of The Public Due To Radioiodines. Tritium. and Particulates in Gaseous Releases (2009)

Cumulative Dose per Year (cont.)

Tech Year to % of Tech Spec Ending Tech Spec Organ Limit Units Date Limit. Receptor Limit Liver 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose Thyroid 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose Lung 1.500E+01 rnRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose GI-Lli 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor SB - Child Gas Annual Organ Dose Liver 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose Thyroid 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose Lung 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose GI-Lli 1.500E+01 mRem 7.888E-02 5.259E-01 Gas Receptor MI - Child Gas Annual Organ Dose Page 34 of 45

TABLE 9.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2009 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Shipled Shipped Buried Buried Percent M Ci m3 Ci Error

a. Spent resins/filters 7.02E-01 2.08E+00 +/- 25%

b. Dry active waste 1.68E+02 1.75E-01 2.78E+01 2.57E+01 +/-25%

c. Irradiated components N/A

d. Other (oil/miscellaneous liquids sent to processor for volume N/A reduction)

TOTAL 1.68E+02 1.75E-01 2.85E+01 2.34E+00 +/- 25%

Note:Shipped volumes and curies are not always equal to the buried volumes and curies since some disposal occurs outside the twelve month time period in which shipments occurred.

Dry active waste also includes some low-level radioactive resins tank sediments and filters that are handled and processed in a manner that is consistent with this waste stream.

2. Estimate of Major Nuclide Composition (by type of Nuclide % Abund. Activity waste) (Ci)

a. Spent resins/filters NA Fe-55 53.35 9.36E-02 Ni-63 22.65 3.97E-02 Co-60 16.70 2.93E-02 Co-58 4.76 8.35E-03

b. Dry active waste H-3 0.21 3.75E-04 C- 14 LLD Tc-99 LLD 1-129 LLD Other* 2.33 4.08E-03 Total 100.00 1.75E-01

d. Other (oil/miscellaneous liquids sent to processor for volume reduction) NA Nuclides representing <1% of total shipped activity: Cr-51,Mn-54,Co-57,Nb-95,ZR-95,Sb-125,Cs-134,Cs-137,Ce-144,Pu-238,Pu-239/240,Am-241,Cm-242,Cm-243/244.

Page 35 of 45

TABLE 9.10 (cont.)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2009

3. Solid Waste Disposition (Mode of Transportation: Truck)

Waste Type Waste Number of Destination Class Container Type Shipments

a. Resin/filters NA NA 0 NA

b. Dry active waste A General Design 3 Energy Solutions

. DOak Ridge, TN B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 36 of 45

Attachment 10.1 2009 Meteorological Joint Frequency Table Page 37 of 45

14-JAN10 1.0:08 R;.1. 21 .ON FEUEC TA BLE Ti U. ELECTRIC C'OMPAN'Y HOUiRS. AT EACH WIND SPEED AND.DIRECTION.

.PERIOD 0FERECOHI): . -01JAN-09 00:00 Td 31"-DEC-09 23:t9

.STABILITY CLA*SS: A ELEVATION: 10 M, VWind Spewed '(mph) alt Wm;O'. leyve Wind D'i recti.on 1-3 4-7 8-12 13-18 "19-24 '24 TTAL N 0 5 19. 1$ 0 0 40 NNE 0 5 22 1 0 0 -26 E .2 I2 o 0 .42 EkE 1 14 0 Q 0 20 S 0 1t 4 0 o 15 SE E, 7. 10 0 0 29 S1 .8

.8 0 0 32Z sS 1 14 52 :29, 90 0 104 i-4 10 8o 18 0 3 63.

SW 1 3' 14. 4: 0 0 22 WSW -0 10002 W or, 0h0 0 a 00 WOW 0 0 " 060 0d2 W0007 05 .22 NNW~~~ 52097 1,08 Totul t.2 137 ý260 173 45 16 643

peri,0d'3of calrn(hpurs):

flours Ore missing: di"6a: I'0 Page 38 of 45

R.G.1.21JOINT FREQUENCY TABLE T. U. ELECTRICJCOMPANY PHOURS. ATl EACH, WINI Sp-EED ;ANVDIRECTION.

PERIOD 'OF RECORD" -01*-*-JAN-09 00:00 TO 31-'DEC-09 23i*j59 SSPTABIL-ITY CLASS: B ELEVATION: "1 Mi.

WidSpeied (mphj) at. 10, i. level Wind Mi rectj on, 'i-'3 =7 ,24 TOTAL

S-l'2. 13-18 19-24 7 1-7 8 0

,NN

]I. 8 0 28 2 0 0 1:5.

NE 3 I 0 29'.

ENE 0 0 .2, 0 36 2'4 13 14 4 7 38 1.7 4 66 59 4,6 .17 WSE 17 0 4,3 22 7 0 40

,to 3 0 -20

-Sw '6 2 1 3 10

.5 0 0 0 0 WNW 0 5 .8 32, 12 22 8 56

-NNW

'VARTIABLE. 7 .2 0 0 ":0 0: 9.

Total 22 172 .226 147 39 5s .611.

perlods or calm*(houra): 0 90ourA f .misriiaa Page 39 of 45

IL. 41JOIT-FREQUENCY, TABLE T. U. ELECTRi.C CO.PARY HOURS AT EACH WIND SPEED AND DIRECTTON PERIOb OF REC(lD: 01.JAN-O9 00:00 TO 31j-DEC-09 23:59 ELEVATION:: I 0 m, Wind Speed (Mph) aýt 10 M. Ieve:1 W -kind D i rýecti:on 1-3. a8,2 13-6 I9-Z 1,24 TOTUL 2 i3 10 ý0 0 35" ENE 3, 14 13 4 0 "4 0

8 .4 28

1I ENE 0, 0 0 E 1' 37§:

24 0

ý0 39' 21

-13 13 r6 4 13 Li 35 rSSE ,,I 70)

S 4 24: 0- 122.

s~w 13 '14 W

15 0, sW 6%

-14 2 2f 4

1'

2. 2

.4

'6 17' NW0 I!

i .0 0 Totai 128 -~ .180 ..I159 156.;1.D'2

'Prio d 1 c'c '(ho*urlýea 0

7 Page 40 of 45

14-JA~-10 10:08 R,., -..- 1;.21 JO0INT FAtobvNdY TAblIE, OUh S AT -EAdH WIND SPEED. AND 6Di 6rCT

'fi PER IOD OF RECO RD: '01--JAN-099 00:00 TO 31-DktC-0 3:5 ELE!VATI!ON. I 0m.

Wk~ind'Spee~d (mpbO at 1-0,m,. le*V e~l

Wi hd A- ~ 0-e4in.13 2 .13-18a 1'-24. i24 TOTAL

s. ý. -

87 192 86 t 2. ,388-

.NN 72 53 3 .2 161 lt4N 0 20b 118 2 206

,2, S5.1 4 0 Et 49 4, 0 2'

'E E- 4'3 '7 0 ST 1,81 3A 4,00 3.7 '17

,SSE 290 .239 ,3 720 236 35 .2 2.8 57 2ý3 12

816 143 27

,42 2,

59 8

!I 3*- 28

'5 161

'47 ,3 408 V,AtiABLE '3 `3 8, 8 0 ý0 0 ,109 Total 2o765 1,033

!927 16t5 168 27 4096 P.6-r-iodii of' chlinfhourR) 5 Hors o4 mpis.Ing 00t! 4137 Page 41 of 45

14-7JANý-1:o 0 0o9 R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPAWY 46OURS AT EACH NIND WI 'SPEED AND -DIRECrION kki&OD OF RECiD*: 0=-JAN-09 0000 TO6,." DEC-9. 23:59 Wind Spe.ed. (mphi). at 10 m. level wind 6 Ii .- A Direction 1-3 4-.+/-- -.1 - 3-,78 19 -24 )24. OT'AL N .22 33 0 1 56 "NE 5 22 26 '1 0 0 54 NE 4 98 4 0 00 0.6

,ENE 5 61 60 1 1.L2.

E 9 31 30 0 0 43.

ESE 20 89. 10 0 0 01,9:

0.

SE -2j 263 182 1 0 4069

.5SF.= 18 156 .257 12 1 0 444:!

sSti5 66 13 0 0 ý146ý SSW .20 37 38 112 0 0' 107 SW .5 i's 16 7 010 .56.

`vWSW 14. 0i2 7 6 0 0 49 aW 0 !0 0 30-wnw 6.. 26 23 2 'P 0 57 Na S54. 21 5 1.86

ýNN .5. '27 4 3 044 VAO)ABLE -61'3 5 00 7S Totai 237 857 702 64 1_1 ..2- 1865 Perlods. of calm(hours): 1-2.

HOu61ra, of missing d-ta 347 Page 42 of 45

14-4. io 10:09 RG.1.21 JOITNT FRE.QUENCY TA3BLE TO I, ELECTRIC COMPA~NY 9OURSý 0 EACHWtINDO ADDIETON !-E

.PERIýOD OF RECORD: 01-*JAN-09 00:.00 TO DEC-09 23:59 STil:,LITY CLkSS': F ELEVATION: 10 m.

Wio" Speed (**l)m)jevel a 10 in.

WiFnd.

Direot ion 1-3 8-:1,2 13-1f8, M-24 ) 24 TOTAL N 0 0- 0 0 0

I

.0 iNE 0 '0 0 ENE 0 '0

.0 E 0 I ,2.

2 8 I0 10

,SE 3 46

.S.E 19 7

'S 19 SS.W 1!7 1"3

sw 32 10.

16 43.

1:2 3.

W WNW 13 14 3 NW B: 34 0 NNW I 4.

VAkIAI4I.E 26 1 0 0 0 0 .27-

-Total 154 1:98 52. .2 0 0 '406, eri'ods.0f p- lm'.i(hourf,) f: 3 Ho'urs ofr-iaai'ng data: 0 Page 43 of 45

- ~~'~ 111:09 R.G 1.21 JOINT FREQUEjNCY TABLE T. U. ELECTRIC COMPANy HOURS AT EACH WIND SPEEDANbD DIRi§ECTIbN PERIOD O,.F JRECORD: 61-JAN-0. 60:40 TO 131-DEC-09 231:59

'STABILITT tILA_9SS,:G EýLEVATION: 10 m .

0i~nd Spoed ýMph,) at 1C in-.I leleV.

Wi nd

,I~irect ion .4-7 *1.9-4 TOTA7L B-2 05 16 0:

N 0 D

'NNE 0 10 O' 0

NE 0 a, A

FERJ "0 0, 0 0 '0 0; O..

a 60

'ESE 0 0a *0 0 sE D '6 0.- +0 0

-SSE 0 0

4 0

a 0 0 0 6, SW 18 WSW. 35 0 I.

8:

.0 w

o-

.0 WNW .4 17,

'NW 1

VAilkABE 10 3 0 a 0 13 Toti, lag 1120 22 z C) 0, 3'.

Ifo'ti of i'i~n d'at: 0 Page 44 of 45

14-JAN-10 10:09 R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-09 00:00 TO 31-DEC-09 23:59 STABILITY CLASS: ALL ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 18 132 264 122 12 3 551 NNE 21 110 235 67 3 2 438 NE 35 101 139 19 3 0 297 ENE 34 125 63 5 0 1 228 E 38 173 51 4 0 0 266 ESE 62 306 85 9 0 0 462 SE 52 503 420 52 6 1 1034 SSE 45 294 665 322 59 4 1389 S 48 171 443 388 82 3 1135 SSW 63 131 177 79 1 1 452 SW 73 107 108 27 2 0 317 WSW 51 95 57 16 0 1 220 W 50 49 21 10 1 1 132 WNW 35 69 63 34 13 15 230 NW 30 146 89 101 35 10 411 NNW 17 101 212 220 92 18 660 VARIABLE 179 62 15 1 0 0 257 Total 852 2675 3107 1476 309 60 8479 Periods of calm(hours): 20 Hours of missing data: 261 Page 45 of 45

SECTIONS 3.0 AND 4.OCONTROLS AND SURVEILLANCE REQUIREMENTS CPSES - UNITS I AND 2 - ODCM PARTL134-0 Rev. 29

3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY The guidance provided for the use and application of LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY in Section 3.0, "LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY" of the Technical Specifications is applicable to the Controls contained in this manual, except as noted below.

The guidance provided for the use and application of SURVEILLANCE REQUIREMENT (SR)

APPLICABILITY in Section 3.0, "SURVEILLANCE REQUIREMENT (SR) APPLICABILITY" of the Technical Specifications is applicable to the Surveillance Requirements contained in this manual.

For the purpose of the ODCM, the ODCM terms specified below should be considered synonymous with the listed Technical Specification term:

ODCM Technical Specification Control LCO ACTION Required Action A cross reference between Section 3/4.0 of the Offsite Dose Calculation Manual (ODCM) and the applicable Section 3.0 of the Technical Specifications is as follows:

ODCM Control: Technical Specification Section 3.0.1 LCO 3.0.1 3.0.2 LCO 3.0.2 N/A (see Note 1) LCO 3.0.3 N/A (see Note 1) LCO 3.0.4 N/A (see Note 1) LCO 3.0.5 N/A (see Note 1) LCO 3.0.6 N/A (see Note 1) LCO 3.0.7 ODCM Surveillance Reauirement: Technical Specification Section 4.0.1 SR 3.0.1 4.0.2 SR 3.0.2 4.0.3 SR 3.0.3 N/A (see Note 1) SR 3.0.4

- NOTE 1 -

The provisions of the cross referenced Technical Specification LCO/SR are not pertinent for use in the ODCM; therefore, the Technical Specification LCO/SR is not applicable (N/A).

CPSES - UNITS I AND 2 - ODCM PART 1 3/4-1 Rev. 29 I

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordance with CPSES TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-7.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-2 Rev. 29

TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (XRE-5253) 30

b. Turbine Building (Floor Drains) Sumps Effluent Lines I/sump 31 (1RE-5100 & 2RE-5100)

c. Auxiliary Building to LVW Pond Liquid Effluent Line I 31A (XRE-5251A)

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Service Water System Effluent Lines 1/train 32 (1 RE-4269, 1RE-4270, 2RE-4269 & 2RE-4270)

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (XFT-5288) 1 33 CPSES - UNITS 1 AND 2 - ODCM PART I13/4-3 Rev. 29

TABLE 3.3-7 (Continued)

ACTIONS STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1; and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 31- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10- 7 microCurie/ml:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131; or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)

ACTION 31A- With number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower-limit of detection of no more than 5 x 10-7 microCurie/ml at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue provided that:

a. With the component cooling water monitors (uRE-4509, uRE-4510,

&uRE-451 1)* OPERABLE and indicating an activity of less than IX10"4 micro Curie/mI, a grab sample is collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml at least every 31 days; or "u" designates monitor for the applicable unit, e.g., 1 or 2.

CPSES - UNITS I AND 2 - ODCM PARTI13/4 Rev. 29

TABLE 3.3-7 (Continued)

ACTIONS STATEMENTS (Continued)

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)

NOTE: Collection of grab samples is not required when there is no process flow at the monitor.-

ACTION 33- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

CPSES - UNITS 1 AND 2 - ODCM PART13/4-5 Rev. 29

TABLE 4.3-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL CHANNEL CHANNEL:.

CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. Q(1)

b. Turbine Building (Floor Drains) Sumps Effluent Lines (1RE-5100 & 2RE-5100) D M R(4) N.A. Q(2)

c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251A) D M R(4) N.A. Q(2)

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Service Water System Effluent Lines (1 RE-4269, I RE-4270, 2RE-4269 &

2RE-4270) D M R(4) N.A. Q(3)

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (XFT-5288) D(5) N.A. R Q N.A.

CPSES - UNITS 1 AND 2 - ODCM PART13/4-6 Rev. 29

TABLE 4.3-3 (Continued)

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if any of the following conditions exist:

a. Instrument indicates measured levels above the AlarmfTrip Setpoint; or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic flow diversion of this pathway (from the Low Volume Waste Treatment System to the Co-Current Waste Treatment System) and Control Room alarm annunciation occur if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm/Trip Setpoint; or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, or Check Source Failure).

(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm Setpoint; or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(4) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference 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, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.

(5) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

CPSES - UNITS 1 AND 2 - ODCM PARTL134-7 Rev. 29

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3,5 In accordance with CPSES TS 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the ODCM.

APPLICABILITY: As shown in Table 3.3-8.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm/

Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-8 Rev. 29

TABLE 3.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Release Rate Monitor - Providing Alarm and Automatic Termination of Release

[XRE-5570A & XRE-5570B (effluent release rate channel)] 1/stack 34

2. PRIMARY PLANT VENTILATION

a. Noble Gas Release Rate Monitor

[XRE-5570A & XRE-5570B (effluent release rate channel)] 1/stack 36

b. Iodine Sampler (WRGM sample skid) 1/stack 37

c. Particulate Sampler (WRGM sample skid) 1/stack 37

d. Sampler Flow Rate Monitor SMPL Flow I (X-RFT-5570A-1, X-RFT-5570B-1) 1/stack 35 CPSES - UNITS I AND 2 - ODCM PART13/4-9 Rev. 29

TABLE 3.3-8 (Continued)

TABLE NOTATIONS

At all times.

- During Batch Radioactive Releases via this pathway.

ACTION 34- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. The auxiliary building vent duct monitor (XRE-5701) is confirmed OPERABLE; or

b. At least two independent samples of the tank's contents are analyzed; and

c. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 35- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 36- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that:

a. A Plant Vent Noble Gas Activity Monitor (XRE-5570A, XRE-5570B (low range activity) or XRE-5567A, XRE-5567B) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or

b. The Plant Vent Flow Monitor, PROC FLOW N (X-FT-5570A-1, X-FT-5570B-1), is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERABLE (XRE-5567A, XRE-5567B) or grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

c. The plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

d. if the number of channels OPERABLE is less than required by the "Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via this pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.

CPSES - UNITS I AND 2 - ODCM PART I13/4-10 Rev. 29 I

TABLE 3.3-8 (Continued)

TABLE NOTATIONS ACTION 37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that:

a. samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2, or

b. if the number of channels OPERABLE is less than required by the "minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine & Particulate samplers INOPERABLE. Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical; or

c. if the number of channels OPERABLE is less than required by the "Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via the affected pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-11 Rev. 29 I

TABLE 4.3-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Release Rate Monitor - P P R(3) N.A. Q(1)

Providing Alarm and Automatic Termination of Release

[XRE-5570A, XRE-5570B (effluent release rate channel)]

2. PRIMARY PLANT VENTILATION

a. Noble Gas Release Rate Monitor D R(3) N.A. Q(2)

[XRE-5570A, XRE-5570B (effluent release rate channel)]

b. Iodine Sampler W(4) N.A. N.A. N.A. N.A.

(WRGM sample skid)

c. Particulate Sampler W(4) N.A. N.A. N.A. N.A.

(WRGM Sample Skid)

d. Sampler Flow Rate Monitor D N.A. R Q N.A.

SMPL Flow I (X-RFT-5570A-1, X-RFT-5570B-1)

CPSES - UNITS 1 AND 2 - ODCM PART13/4-12 Rev. 29

TABLE 4.3-4 (Continued)

TABLE NOTATIONS

Prior to any release fromthe WASTE GAS HOLDUP SYSTEM or containment PURGING or VENTING, not to exceed 31 days.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm/Trip Setpoint; or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm Setpoint; or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference 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, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.

(4) The CHANNEL CHECK shall consist of visually verifying that the collection element (i.e.,

filter or cartridge. etc.) is in place for sampling.

CPSES - UNITS I AND 2 - ODCM PART 13/4-13 Rev. 29

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With less than the minimum number of meteorological monitoring instrumentation channels OPERABLE for more than 7 days, initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by performance of a CHANNEL CHECK; and

b. At least once per 184 days by performance of a CHANNEL CALIBRATION except the wind speed and wind direction sensors which are replaced with calibrated sensors at least once per 12 months.

CPSES.- UNITS 1 AND 2 - ODCM PART 13/4-14 Rev. 29

TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNEL LOCATION OPERABLE

1. WIND SPEED 1 of 3

a. X-S-4117 Nominal Elev. 60 m.

b. X-S-4118 Nominal Elev. 10 m.

c. X-S-4128* Nominal Elev. 10 m.

2. WIND DIRECTION 1 of 3

a. X-Z-4115 Nominal Elev. 60 m

b. X-Z-4116 Nominal Elev. 10m.

c. X-Z-4126* Nominal Elev. 10m.

3. AIR TEMPERATURE - AT 1 of 2

a. X-T-4119 Nominal Elev. 60 m. and Nominal Elev. 10m.

b. X-T-4120 Nominal Elev. 60 m. and Nominal Elev. 10m.

Mounted on backup tower.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-15 Rev. 29

INSTRUMENTATION SEALED SOURCE CONTAMINATION CONTROLS 3.7.15 Each sealed source containing radioactive material either in excess of 100 microCuries of beta and/or gamma emitting material or 5 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microCurie of removable contamination.

APPLICABILITY: At all times.

ACTION:

With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source; or

2. Dispose of the sealed source in accordance with Commission Regulations.

SURVEILLANCE REQUIREMENTS 4.7.15.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee; or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microCurie per test sample.

4.7.15.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.

a. Sources in use - At least once per 6 months for all sealed sources containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogen 3), and

2) In any form other than gas.

b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and CPSES - UNITS 1 AND 2 - ODCM PART 13/4-16 Rev. 29 I

SURVEILLANCE REQUIREMENTS (Continued)

c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.

4.7.15.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microCurie of removable contamination.

CPSES - UNITS I AND 2 - ODCM PART13/4-17 Rev. 29

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 5.5.4.b and 5.5.4.c the concentration of radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microCurie/ml total activity.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11. 1.1.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-18 Rev. 29 I

TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF 1

LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION( )

TYPE FREQUENCY FREQUENCY ANALYSIS (P.Ci/ml)

IA. Batch Waste Release (2) P P Principal Gamma 5.0E-07 Tanks to the Circulating Each Batch Each Batch Emitters (3)

Water Discharge 1-131 1.0E-06

a. Waste Monitor Tanks Dissolved & Entrained(3) 1.0E-05 Laundry Holdup & (Gamma Emitters)

b. _Gases Monitor Tanks M H-3 1.OE-05

c. Waste Water Composite (4) Gross Alpha 1.OE-07 Holdup Tanks (8) a Sr-89, Sr-90 5.OE-08

d. Plant Effluent Composite (4) Fe-55 1.OE-06 Tanks lB. Batch Waste Release (2) P P Principal Gamma 5.OE-07 Tanks to the Waste Water Each Batch Each Batch Emitters (3)

Management System

a. Condensate Polisher 1-131 1.OE-06 Backwash Recovery Tanks (6,7)

b. Waste Water H-3 1.OE-05 Holdup Tanks (6.8)

c. Temporary holdup tanks (10) 2A. Continuous Release(5) to Monthly Monthly Dissolved & Entrained (3) (11) the Circulating Water Grab (11) Grab (11) Gases (Gamma Emitters) 11 Discharge Daily Grab Composite over Principal Gamma 5.0E-070 )

Waste Pond Sample (9) pond discharge Emitters (3)

Effluents period (4)

Efuns1-131 1.0E-06 H-3 1.OE-05 Gross Alpha 1.OE-07 Q Sr-89, Sr-90 5.0E-08 Composite (4) Fe-55 1.OE-06 2B. Continuous Releases (5) to W W Principal Gamma 5.OE-07 the Waste Water Grab Sample Emitters (3)

Management System

a. Turbine Bldg.

Sump No. 2 1-131 1.0E-.06 Effluents (6,7)

b. Turbine Bldg.

Sump No. 4 Effluents (6,7)I.OE-05

c. Auxiliary Bldg.

Secondary Effluents (6,7)

CPSES - UNITS 1 AND 2 - ODCM PART13/4-19 Rev. 29

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, 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"66Sb E*V*2.22x 106 Y e exp(-?,At)

Where:

LLD = "A priori" lower limit of detection (microCurie per unit mass or volume),

sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = Counting efficiency (counts per disintegration),

V = Sample size (units of mass or volume),

2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable,

= Radioactive decay constant for the particular radionuclide (sec 1 ), and At = Elapsed time between the midpoint of sample collection and the time of counting(s).

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

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Part II of the ODCM to assure representative sampling.

(3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-137, and Ce-141 for fission and corrosion products, and Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases. Ce-144 shall also be measured, but with an LLD of 5 x 10-6. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall CPSES - UNITS.1 AND 2 - ODCM PART I 3/4-20 Rev. 29 I

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued) also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Control 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) These waste streams shall be sampled and analyzed, in accordance with this table, if radioactive material is detected in the LVW Pond composite samples in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2. This sampling shall continue until 2 consecutive samples from the waste stream show that the concentration of radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2.

(7) All flow from these waste streams shall be diverted to the Waste Water Holdup Tanks if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Sampling and analysis of the respective Tanks or sumps are not required when flow is diverted to the Waste Water Holdup Tanks.

(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Otherwise, WWHTs may be discharged to the Low Volume Waste Pond. WWHT discharges to the Circulating Water Discharge Tunnel shall be sampled and analyzed per Item 1A.c of this table. WWHT discharges to the LVW Pond shall be sampled and analyzed per Item I B.b of this table.

(9) Samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while the release is occurring. To be representative of the liquid effluent, the sample volume shall be-proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.

(10) Temporary holdup tanks used to support special plant activities (e.g., Steam Generator Secondary Cleaning) involving potentially radioactive systems may be transferred to the Waste Water Management System when sampled in accordance with this table and the special plant activity has been evaluated in accordance with the 50.59 process. This waste stream shall not be discharged to the Waste Water Management System if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10CFR20, Appendix B, Table 2, Column 2.

(11) Dissolved and entrained gases should be included in the analysis (including Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138). There are no LLD requirements for these gases in the LVW samples since the half life of the isotopes are relatively short with respect to the sample counting frequency. Gases are also not expected to be found in the LVW due CPSES - UNITS 1 AND 2 - ODCM PART I13/4-21 Rev. 29

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued) to delay times associated with water being transported to the LVW and the open exposure of the ponds which would aid in the degasification of the liquids. One sample should be obtained monthly from the Low Volume Waste in addition to the composite sample to analyze for these noble gases. The count time for the sample should be equal to the time required to establish LLD values for the noble gas isotopes (e.g., 2000 seconds or the same count time used for effluent liquid batch releases).

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-22 Rev. 29

RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with CPSES TS 5.5.4.d and 5.5.4.e the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ; and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.

CPSES - UNITS 1 AND 2 - ODCM PART 13/4-23 Rev. 29 I

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with CPSEýS TS 5.5.4.f, the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, that includes the following information:

1) Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS and UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-24 Rev. 29

RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins transferred to the LVW Pond shall be limited by the following expression:

264 1A1,10 V jC excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life, where:

A, = Pond inventory limit for single radionuclide "j" (Curies),

Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (microCuries/ml),

V = Volume of resins in the pond (gallons), and 264 = Unit conversion factor (microCuries/Curie per milliliter/gallon).

APPLICABILITY: Atall times.

ACTION:

a. With the quantity of radioactive material contained in resins in the LVW Pond exceeding the above limit, immediately suspend all additions of resins to the pond.

SURVEILLANCE REQUIREMENTS 4.11.1.4 Prior to transferring any batch of used powdex resin to the pond, the total inventory of radioactive materials in resins contained in the pond, including the batch to be transferred, shall be determined to be within the above limit. The inventory shall be determined based on analysis of a representative sample of the resin batch. Decay of radionuclides in previously discharged resins may be taken into account in determining inventory levels.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-25 Rev. 29

RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY SURVEILLANCE REQUIREMENTS (Continued)

Additionally, each batch of resins transferred to the pond shall be limited by the expression:

T. Q.

J C Cj <0.1 where:

Qi =Concentration of radioactive materials (microCuries/ml) in wet, drained slurry (used powdex resin) for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life. The analysis shall include at least Ce-144, Cs-1 34, Cs-137, Co-58 and Co-60.

Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent quarterly composite analysis, Cj 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j"(microCuries/milliliter).

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-26 Rev.. 29 I

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE 3.11.2.1 In accordance with CPSES TS 5.5.4.c and 5.5.4.g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin; and

b. For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limits(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-2.

4.11.2.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the dose rates at or beyond the SITE BOUNDARY are maintained within the limits of Control 3.11.2.1.

CPSES - UNITS 1 AND 2 - ODCM PART 13/4-27 Rev. 29

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD) (1)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (liCi/ml)

1. Waste Gas Storage P P Tank Each Tank Each Tank Grab Sample Principal Gamma Emitters(2) lx10"4

2. Containment Purge P P or Vent Each Release(3) Each Release(3) Principal Gamma Emitters(2) lx10 4 Grab Sample M H-3 (oxide) lx1O-6

3. Plant Vent M(3), (4), (5) M(3) Principal Gamma Emitters(2) 1x10-4 Grab Sample H-3 (oxide) 1x10-6 Continuous(6) W(7)

Radioiodine Adsorber 1-131 lxl0-12 Continuous(6) W(7)

Particulate Sample Principal Gamma Emitters(2) 1x10- 1 1 Continuous(6) M Composite Par-ticulate Sample Gross Alpha lx 0-11 Continuous(6) Q Composite Par-ticulate Sample Sr-89, Sr-90 lx10 11 Continuous(6) Noble Gas **

Beta or Gamma Noble Gas IX10-6 Outside Buildings Grab sample W(8) Principle Gamma Emitters(2) 1x10-11

Table notations next page

- This sample is continuously analyzed by a radiation monitor CPSES - UNITS 1 AND 2 - ODCM PART I 3/4-28 Rev. 29

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, 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:

4 66 LLD = . sb E*V*2.22 x 106 Y exp(-XAt)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

Sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = Counting efficiency (counts per disintegration),

V = Sample size (units of mass or volume),

2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, X = Radioactive decay constant for the particular radionuclide (sec-1 ), and At = Elapsed time between the midpoint of sample collection and the time of counting(s).

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

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, 1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. In the case of release type 4, Outside Buildings, noble gases and iodine may not be sampled based on an evaluation of the source term. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report, pursuant to Control 6.9.1.4, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-29 Rev. 29

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change Ž 15% of RATED THERMAL POWER within a 1-hour period.

This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical Specification 3.4.16 shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) noble gas monitoring shows that effluent activity has not increased more than a factor of 3.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) 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 Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from the sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change __15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. 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. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) noble gas monitoring shows that effluent activity has not increased more than a factor of 3.

(8) Samples shall be changed at least once per seven (7) days and analysis shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from the sampler. This requirement does not apply, if no activities are being conducted in the Outside Building that would generate radioactive effluent.

CPSES - UNITS 1 AND 2 - ODCM PART I 3/4-30 Rev. 29 I

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with CPSES TS 5.5.4.e and 5.5.4.h, the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-31 Rev. 29

RADIOACTIVE EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with CPSES TS 5.5.4.e and 5.5.4.i, the dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ; and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-1 31, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.

CPSES - UNITS 1 AND 2 - ODCM PART13/4-32 Rev. 29

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 5.5.4.f, the PRIMARY PLANT VENTILATION SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that includes the following information:

1) Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3) Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-33 Rev. 29

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with CPSES TS 5.5.4.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources. shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a., 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a., or 3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 20.1301(d) and 10 CFR 20.2203(a)(4) that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This report, as defined in 10 CFR 20.2203(b),

shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in Part II of the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Part II of the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.

CPSES - UNITS 1 AND 2 - ODCM PART I 3/4-34 Rev. 29 I

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 314.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the NRC, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reason(s) for not conducting the program as required and the plan for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) +... > 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*

to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-35 Rev. 29

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program. The specific locations from which samples were unavailable may then be deleted from the monitoring program. New sampling locations shall be listed in the results of the annual Land Use Census.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. The specific sample locations for the Radiological Environmental Monitoring Program shall be listed and maintained current in the results of the annual Land Use Census.

CPSES - UNITS I AND 2 - ODCM PART 13/4-36 Rev. 29 I

TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS( 1 ) COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation(2) Forty routine monitoring stations either with Quarterly Gamma dose quarterly two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

2. Airborne Radioiodine Samples from five locations: Continuous sampler operation Radioiodine Canister:

and Particulates with sample collection weekly, 1-131 analysis weekly Three samples from close to the three SITE or more frequently if required by BOUNDARY locations, in different dust loading.

sectors, of the highest calculated annual Particulate Sampler:

average ground-level D/Q; Gross beta radioactivity analysis following filter change;(4) and gamma isotopic analysis(5) of composite (by location quarterly).

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-37 Rev. 29

TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least 3

prevalent wind direction.( )

3. Waterborne

a. Surface Squaw Creek Reservoir(6) Monthly composite of weekly Gamma isotopic analysis(5) grab samples. monthly.

Composite for tritium analysis quarterly.

Lake Granbury Monthly composite of weekly Gamma isotopic analysis(5) grab samples when Lake monthly.

Granbury is receiving letdown Composite for tritium analysis from SCR. Otherwise, monthly quarterly.

grab sample.(7)

Control-Brazos River upstream of Lake Monthly Gamma isotopic analysis(5)

Granbury monthly.

Composite for tritium analysis quarterly.

b. Ground Samples from two sources if likely to be Quarterly Gamma isotopic(5) and tritium affected.(s) analysis quarterly.

CPSES - UNITS 1 AND 2 - ODCM PART 13/4-38 Rev. 29

TABLE 3.12-1 (Continued)

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

3. Waterbome (Continued)

c. Drinking One sample from Squaw Creek Reservoir. Composite of weekly grab 1-131 analysis of each composite samples over 2-week period sample when the dose calculated when 1-131 analysis is for the consumption of the water performed; monthly composite is greater than 1 mrem per of weekly grab samples year(9 ). Gross beta and gamma otherwise.

isotopic analyses(5) monthly.

Composite for tritium analysis quarterly.

d. Sediment from One sample from downstream area with Semiannually. Gamma isotopic analysis(s)

Shoreline existing or potential recreational value. semiannually.

4. Ingestion

a. Milk Samples from milking animals in three Semimonthly when animals are Gamma isotopic(5) and 1-131 locations within 5 km distance having the on pasture; monthly at other analysis semimonthly when highest dose potential. If there are times. animals are on pasture; monthly none, sample from milking animals in each of at other times.

three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.(9) One sample from milking animals at a control location, 15 to 30 km distant and in the least prevalent wind direction.(3 )

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-39 Rev. 29

TABLE 3.12-1 (Continued)

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

4. Ingestion (Continued)

b. Fish and One sample of at least two recreationally Sample semiannually. Gamma isotopic analysis(5) on Invertebrates important species in vicinity of plant discharge edible portions semiannually area.

One sample of same species in areas not influenced by plant discharge.

c. Food Products* One sample of each principal class of food At time of harvest(10 ) Gamma isotopic analysis(5)on products from any area that is irrigated by edible portion following sample water in which liquid plant wastes have been collection.

discharged.

A sample of broad leaf vegetation grown Monthly, when available. Gamma isotopic(5) and 1-131 nearest each of two different offsite locations of analyses, monthly, when samples highest predicted annual average ground level are collected D/Q if milk sampling is not performed at all required locations.

One sample of each of the similar broad leaf Monthly, when available. Gamma isotopic(5) and 1-131 vegetation grown 15 to 30 km distant in the analyses, monthly, when least prevalent'wind direction(3) ifmilk samples are collected sampling is not performed at all required locations.

Reports from 3 additional airborne radioiodine sample locations may be supplemented for broad leaf vegetation samples.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-40 Rev. 29

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (1) For each sample location required by Table 3.12-1, specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided in information maintained current in the results of the annual Land Use Census. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program.

New sampling locations shall be listed in the results of the annual Land Use Census.

(2) 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. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(3) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. The control sample location at 12.3 miles in the southwest sector has been evaluated and found to be an acceptable substitute sampling location.

(4) 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. If gross 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.

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

(6) The Reservoir shall be sampled in an area at or beyond but near the mixing zone. Also, the Reservoir shall be sampled at a distance beyond significant influence of the discharge.

(7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge.

(8) 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.

CPSES - UNITS I AND 2 - ODCM PART13/4I4 Rev. 29

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

(9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in Part II of the ODCM.

(10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

CPSES - UNITS I AND 2 - ODCM PART13/442 Rev. 29

TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS ANALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet)

H-3 20,000*

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** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

(*) 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.

(**) If no drinking water pathway exists, a value of 20 pCi/I may be used.

CPSES - UNITS 1 AND 2 - ODCM PART13/4-3 Rev_ 29

TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 3

Lower Limit of Detection (LLD)( )

AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/1) (pCi/m 3 ) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co -58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/I may be used.

- If no drinking water pathway exists, a value of 15 pCi/I may be used.

CPSES - UNITS 1 AND 2 - ODCM PART13/4-44 Rev. 29

TABLE 4.12-1 (Continued)

TABLE NOTATIONS (1) The list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

LLD = 4"66Sb E V

Y 9 exp (-XAt) 2.22 Where:

LLD = the "a priori" lower limit of detection (picoCurie per unit mass or volume),

sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = Counting efficiency (counts per disintegration),

V = Sample size (units of mass or volume),

2.22 = Number of disintegrations per minute per picoCurie, Y = Fractional radiochemical yield, when applicable,

= Radioactive decay constant for the particular radionuclide (sec-1), and At = Elapsed time between the midpoint of sample collection and the time of counting(s).

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

It should be recognized that the LLD is defined as an P orion (before the fact) limit representing the capability of a measurement system and not as an a gosteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-45 Rev. 29

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50m 2 (500 ft 2 ) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4, identify the new location(s) in the next Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location(s) within 30 days, to the Radiological Environmental Monitoring Program. The sampling locations having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. New sampling locations shall be listed in the results of the annual Land Use Census.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1, Item 4.c. shall be followed, including analysis of control samples.

CPSES - UNITS I AND 2 - ODCM PARTI13/446 Rev. 29

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times..

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in Part II of the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

CPSES - UNITS 1 AND 2 - ODCM PART 1 3/4-47 Rev. 29

CPSES/ODCM COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL (ODCM)

EFFECTIVE LISTING FOR SECTIONS, TABLES, AND FIGURES BELOW IS A LEGEND FOR THE EFFECTIVE LISTING OF SECTIONS, TABLES, AND FIGURES:

Revision 0 (TXX-89118) Submitted to the NRC March 2, 1989 Revision 1 (TXX-89595) Submitted to the NRC August 25,1989 Revision 2 (TXX-8971 1) Submitted to the NRC November 27, 1989 Revision 3 April 10, 1990 Revision 4 October 9, 1990 Revision 5 December 20, 1990 Revision 6 July 3, 1991 Revision 7 December 4, 1991 Revision 7A August 6, 1992 Revision 8 (Unit 2 Operations) January 1, 1993 Revision 9 September 28, 1994 Revision 10 April 22, 1994 Revision 11 November 7, 1994 Revision 12 December 8, 1995 Revision 13 February 14, 1996 Revision 14 October 1, 1996 Revision 15 March 3, 1999 Revision 16 July 27, 1999 Revision 17 October 7, 1999 Revision 18 December 20, 1999 Revision 19 October 16, 2001 Revision 20 July 8, 2002 Revision 21 March 23, 2004 Revision 22 December 8, 2004 Revision 23 January 31, 2006 Revision 24 March 13, 2006 Revision 25 June 1, 2006 Revision '26 December 12, 2006 Revision 27 July 24, 2007 Revision 28 September 11, 2008 Revision 29 February 26, 2009 CPSES/ODCM EL-1 Revision 29

CPSES/ODCM PART I Section 1 Revision 28 Table 1.1 Revision 27 Table 1.2 Revision 27 Section 2 Revision 23 Section 3/4 Revision 29 Bases 3/4 Revision 23 Section 5 Revision 23 Figure 5.1-3 Revision 23 Section 6 Revision 23 PART II Section 1 Revision 23 Table 1.1 Revision 23 Table 1.2 Revision 23 Figure 1.1 Revision 23 Figure 1.2 Revision 23 Figure 1.3 Revision 23 Section 2 Revision 26 Table 2.1 Revision 26 Table 2.2 Revision 23 Table 2.3 Revision 23 Table 2.4 Revision 23 Table 2.5 Revision 23 Figure 2.1 Revision 23 Figure 2.2 Revision 23 Figure 2.3 Revision 23 Figure 2.4 Revision 23 Figure 2.5 Revision 23 Section 3 Revision 23 Table 3.1 Revision 23 Figure 3.1 Revision 23 Appendix A Revision 23 Appendix B Revision 23 Appendix C Revision 23 Appendix D Revision 23 Appendix E Revision 23 Appendix F Revision 23 Appendix G Revision 23 CPSES/ODCM EL-2 Revision 29

CPSESIODCM EL-1 Revision 29 EL-2 Revision 29 EL-3 Revision 29 CPSES/ODCM EL-3 Revision 29

"OFFSITE DOSE CALCULATION MANUAL - Description of Changes LDCR-OD-2006-2 (CPSES-200600206) (RJK):

Revision 23 updates the entire ODCM to reflect the following changes:

The electronic files have been converted from Microsoft Word to Adobe Framemaker and published in Adobe Portable Document Format (PDF).

The type of changes include changes such as:

- Correction of spelling errors

- Correction of inadvertent word processing errors from previous changes

- Style guide changes (e.g., changing from a numbered bullet list to an alphabetized bullet list and vice versa, change numbering of footnote naming scheme)

- Administrative change only and contain no technical changes.

This change maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

The entire ODCM will be reissued as Revision 23. For the text and tables there will be no change bars in the page margins for editorial changes. The list of effective pages is being replaced with a list of effective section, tables, and figure Sections Revised: All Tables Revised: All Figures Revised: All BEVII _.24 LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM):

Revision 24 updates ODCM Section 3/4 to reflect the following changes:

Delete the requirement to submit a special report outlining the cause of the malfunction and the plans for restoring the channel(s) to operable status.

Adds the requirement to initiate actions in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.

CPSES/ODCM DOC-1 I

OFFSITE DOSE CALCULATION MANUAL - Description of Changes REVISION 24 (continued)

LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM) (continued):

The CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance. The minimum set of conditions required by law to be reported to the NRC are contained in the Code Of Federal Regulations (10CFR50.73, 10CFR50.72, 10CFR73, etc.). This ODCM special report is not required by the CFRs, and there is no regulatory basis for this special report. There is no Technical Specification action, regulation, license condition, order, or commitment that requires this ODCM special report. The meteorological monitoring system is governed by Regulatory Guide 1.23, "Onsite Meteorological Programs", and this Regulatory Guide contains no requirement for a special report to the NRC. Based on the above, this ODCM special report is only an administrative requirement and therefore it can be deleted.

Sections Revised: 3/4 Tables Revised: None Figures Revised: None REVYISIONZ2 LDCR-OD-2006-3 (EVAL-2006-000932-01) (RJK):

Revision 25 updates ODCM Section 3/4 to reflect the following changes:

The 7 day allowance for planned and/or scheduled channel maintenance (similar to the TS COMPLETION TIME) was removed in error by Revision 24 of the ODCM (LDCR-OD-2005-01). That revision intended only to remove the requirement to issue a Special Report to the NRC if the 7 days allowance was exceeded.

This LDCR restores an acceptable outage duration for planned and/or scheduled work commensurate with the safety significance of this item.

This change also maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Sections Revised: 3/4 Tables Revised: None Figures Revised: None CPSES/ODCM DOC-2 I

OFFSITE DOSE CALCULATION MANUAL - Description of Changes LDCR-OD-2006-5 (EVAL-2006-002463-01) (RJK):

Engineering evaluation ME-CA-0000-5326 assessed the potential gaseous effluent release from a planned decontamination facility on site. The evaluation also provides for operational controls on any similar facility to limit the source term and assess the effluents. The proposed changes to the ODCM provide the framework to identify, control, and monitor any gaseous effluent pathway. The results of the monitoring are reported in the Radioactive Effluent Release Report, pursuant to ODCM Control 6.9.1.4.

LDCR-OD-2006-6 (EVAL-2006-001766-01) (RJK):

Revise Action Statement 37 (applicable to WRGM skid iodine and particulate channels) to add "If the number of channels OPERABLE is less than required by the "minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine &

Particulate samplers INOPERABLE. Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical."

These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways. This 7 day period for entry into the CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.

LDCR-OD-2006-1 (EVAL-2005-001822-07) (GLM):

Revise definition of DOSE EQUIVALENT IODINE 131 and add new definition for DOSE EQUIVALENT XENON 133.

LAR 06-001 revises TS 3.4.16 to eliminate E-bar and adopt DOSE EQUIVALENT XE-133 for monitoring RCS gross specific activity. This change makes the ODCM definition consistent with the revised TS definition.

LDCR-OD-2007-1 (EVAL-2006-003080-05) (JDS):

Revise Definition of Rated Thermal Power to reflect 4.5% increase on Units 1 and 2 as issued by the NRC in Amendment 146 to the Operating Licenses and Technical Specifications.

CPSES/ODCM DOC-3

OFFSITE DOSE CALCULATION MANUAL - Description of Changes LDCR-OD-2007-2 (EVAL-2007-002019-01) (SCD):

Revise Table 3.3-8 ACTION and associated statements to clarify necessary actions in the event of a loss of heat tracing or sample lines to the WRGM sampling skid. These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/

Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways. This 7 day period for entry into the CPNPP Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.

CPSES/ODCM DOC-4

SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS CPSES - UNITS 1 AND 2- ODCM PART I13/4-0 Rev. 30

3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY The guidance provided for the use and application of LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY in Section 3.0, "LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY" of the Technical Specifications is applicable to the Controls contained in this manual, except as noted below.

The guidance provided for the use and application of SURVEILLANCE REQUIREMENT (SR)

APPLICABILITY in Section 3.0, "SURVEILLANCE REQUIREMENT (SR) APPLICABILITY" of the Technical Specifications is applicable to the Surveillance Requirements contained in this manual.

For the purpose of the ODCM, the ODCM terms specified below should be considered synonymous with the listed Technical Specification term:

ODCM Technical Specification Control LCO ACTION Required Action A cross reference between Section 3/4.0 of the Offsite Dose Calculation Manual (ODCM) and the applicable Section 3.0 of the Technical Specifications is as follows:

ODCM Control: Technical Specification Section 3.0.1 LCO 3.0.1 3.0.2 LCO 3.0.2 N/A (see Note 1) LCO 3.0.3 N/A (see Note 1) LCO 3.0.4 N/A (see Note 1) LCO 3.0.5 N/A (see Note 1) LCO 3.0.6 N/A (see Note 1) LCO 3.0.7 ODCM Surveillance Requirement: Technical Specification Section 4.0.1 SR 3.0.1 4.0.2 SR 3.0.2 4.0.3 SR 3.0.3 N/A (see Note 1) SR 3.0.4

- NOTE 1 -

The provisions of the cross referenced Technical Specification LCO/SR are not pertinent for use in the ODCM; therefore, the Technical Specification LCO/SR is not applicable (N/A).

CPSES - UNITS I AND 2 --ODCM PART I13/4-1 Rev. 30

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordance with CPSES TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-7.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3.

CPSES - UNITS I AND 2- ODCM PART I13/4-2 Rev. 30

TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (XRE-5253) 1 30

b. Turbine Building (Floor Drains) Sumps Effluent Lines 1/sump 31 (1RE-5100 & 2RE-5100)

c. Auxiliary Building to LVW Pond Liquid Effluent Line 1 31A (XRE-5251 A)

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Service Water System Effluent Lines 1/train 32 (1RE-4269, 1RE-4270, 2RE-4269 & 2RE-4270)

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (XFT-5288) 1 33 CPSES- UNITS 1 AND 2- ODCM PART I13/4-3 Rev. 30

TABLE 3.3-7 (Continued)

ACTIONS STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1; and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 31- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131; or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)

ACTION 31A- With number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower-limit of detection of no more than 5 x 10-7 microCurie/ml at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue provided that:

a. With the component cooling water monitors (uRE-4509, uRE-4510,

&uRE-4511)* OPERABLE and indicating an activity of less than lX10-4 micro Curie/ml, a grab sample is collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml at least every 31 days; or

"u" designates monitor for the applicable unit, e.g., 1 or 2.

CPSES - UNITS 1 AND 2- ODCM PART13/4-4 Rev. 30

TABLE 3.3-7 (Continued)

ACTIONS STATEMENTS (Continued)

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)

NOTE: Collection of grab samples is not required when there is no process flow at the monitor.

ACTION 33- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

CPSES - UNITS 1 AND 2 - ODCM PART I13/4-5 Rev. 30

TABLE 4.3-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST

1. Radioactivity Monitors Providing.Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. Q(1)

b. Turbine Building (Floor Drains) Sumps Effluent Lines (1 RE-51 00 & 2RE-51 00) D M R(4) N.A. Q(2)

c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251A) D M R(4) N.A. Q(2)

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Service Water System Effluent Lines (1 RE-4269, 1 RE-4270, 2RE-4269 &

2RE-4270) D M R(4) N.A. Q(3)

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (XFT-5288) D(5) N.A. R Q N.A.

CPSES - UNITS 1 AND 2- ODCM PART I13/4-6 Rev. 30