Text

SO123-ODCM, Rev. 3, Offsite Dose Calculation Manual Nuclear Organization
	ML11119A234
Person / Time
Site:	San Onofre
Issue date:	04/26/2011
From:	Mccann R; Southern California Edison Co
To:	; NRC/FSME, Office of Nuclear Reactor Regulation
References
	SO123-ODCM, Rev. 3
	Download: ML11119A234 (141)
	v • d • e

Enclosure 2:

SO123-ODCM, Revision 3

February 26, 2010 Mr. R. T. Ridenoure

SUBJECT:

Revision 3 of the San Onofre Nuclear Generating Station (SONGS) Offsite Dose Calculation Manual (ODCM), S0123-ODCM.

In accordance with Technical Specification 5.5.2.1, Revision 3 to the SONGS Dose Calculation Manual has been prepared and reviewed for your approval.

This revision incorporates the current changes to the Land Use Census, adds a new airborne control sample location to the Radioactive Environmental Monitoring Program (REMP), and revises the radwaste tank pump capacities.

None of the changes in this revision will adversely affect the accuracy or reliability of effluent dose calculations or set point determinations. Your approval for this revision is requested.

Copies of this letter are being forwarded to the Nuclear Safety Group as required by Technical Specification 5.5.2.1.

Please contact me ifthere are any questions.

R. L. McCann Manager, Chemistry Z Approved by: Approved in SAP Ross T. Ridenoure Vice President & Site Manager Attachment

2/26/2010

SUBJECT:

SONGS OFFSITE DOSE CALCULATION MANUAL Revision 3 Enclosed is Revision 3 to the SONGS Offsite Dose Calculation Manual (ODCM). This revision accomplishes thefollowing objectives: 1) incorporates the latest updates related to the 2009 Land Use Census (LUC)-from the J.W. Scott to D. Dick Memorandum for File, "2010 Dose Parameters for San Onofre Nuclear Generating Station," dated February 10, 2010, 2) revises capacities of Radwaste Tank pumps per U2.3 UFSAR change NO. 2009-33, and 3) adds a new airborne control sample location in Table .5-4 and Figure 5-5 from the J.W. Scott to D. Dick Memorandumfor File, "Creation of New Air Sample Location" dated February 17, 2010.

Editorial corrections were made to Appendix B, pages B1-1 to B2-2, to correct the revision to rev l from rev 0.

No 50.59 or EOE reviews were required or performed for the editorial changes.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations.

The level of radioactive effluent control required by 10CFR20, 40CFR1 90, 10CFR50.35a and Appendix Ito I OCFR50 will be maintained.

Throughout the document, change bars are marked in one of four ways as follows:

A Addition D Deletion F Editorial/Format change R Revision Page # changes due to new revision Reason Title Pages Change from previous revision to Rev 3 R Page # changes due'to U2/3 UFSAR Change # 2009-33 Reason 1-13 revised Radwaste Tank Pump flow rates R Page.# changes due to LUC Reason 2-29 updated Units.2&3 CLF R A1-4 added new R, table A A1-5 revised R table, including pathway name R A1-6 revised Ritable, including pathway name R A1-9 revised Ri table R Al-10 revised Ritable, including pathway name R A1-11 added new Rtable A S0123-ODCM Rev 3 PAGE I OF 2

Page # changes due to LUC (continued)

A1-12 revised Ri table A1-14 revised Ri table, including pathway name A1-16 revised Ri table, including pathway name A1-17 revised Ritable, including pathway name A1-19 revised Ri table, including pathway name, distance, XJQ and DIQ A1-21 revised Ritable, including pathway name, X/Q and D/Q A1-24 added new R, table before deleted Ritable for surfcamp.com A1-26 A1-26 revised Rtable Page # changes to REMP (see Memorandum to file dated 2/17/2010) 5-18 updated table 5-4, Radiological Environmental Monitoring Sample Locations, added new airborne sampler location 5-27 updated figure 5-5, Radiological Environmental Monitoring Sample Locations - San Diego County, added new airborne sampler location Page # changes due to editorial corrections Appendix corrected footer, App B, to rev 1 from rev 0 B, B1-1 to B2-2 SO1 23-ODCM Rev 3 PAGE 2 OF 2

OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS)

S0123-ODCM Revision 3 02-26-10

ODCM TABLE OF CONTENTS P..e LIST OF FIGURES .................

LIST OF TABLES .................. . . . . . . . . . . . . . . . . . . . . V INTRODUCTION .................. ... . vi 1.0 LIQUID EFFLUENTS ........... 1-1 thru 1-27 1.1 C oncentration ................................. ... 1-1 1.1.1 Specification........................... ... 1-1 1.1.1.1, 1.1.1.2 Surveillances ....................

... 1-1 1 .2 Do s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 1-6 1.2.1 Specification ............................ ... 1-6 1.2.1.1 Surveillance........................... 1-6 1.3 Liquid Waste Treatment ......................... ... 1-7 1.3.1 Specification ............................ ... 1-7 1.3.1 .1, 1.3.1.2, 1.3.1.3 Surveillances ............... ... 1-7 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation. ... 1-9 1.4.1 Batch Release Setpoint Determination ........ ..1-11 1.4.2 Continuous Release Setpoint Determination .... ... 1-15 1.5 Dose Calculations for Liquid Effluents .............. ... 1-24 1.6 Representative Sampling ........................ 1-27 2.0 GASEOUS EFFLUENTS ............................. 2-1 thru 2-31 2.1 Dose Rate ...................... ................. ... 2-1 2.1.1 Specification ............... ................. ... 2-1 2.1.1.1, 2.1.1.2 Surveillances ....... ................. ... 2-1 2.2 Dose - Noble Gas ................ ................. ... 2-5 2.2.1 Specification ............... ................. ... 2-5 2.2.1.1 Surveillance .............. ................. ... 2-5 2.3 Dose - Radioiodines, Radioactive Materials in Particulate Form and Tritium ............................... 2-6 2.3.1 Specification .............................. 2-6 2.3.1.1 S urveillance ............................. 2-6 SO1 23-ODCM Revision 0 02-27-07

ODCM TABLE OF CONTENTS (Continued)

Page 2.4 Gaseous Radwaste Treatment ................................. 2-7 2.4.1 Specification ....................................... 2-7 2.4.1.1 S urveillance ....................................... 2-7 2.4.1.2, 2.4.1.3 Surveillances .................................. 2-8 2.5 Deleted, moved to Section 3 2.6 Gaseous Effluent Monitor Setpoints ............................ 2-10 2.6.1 Plant Stack ................................ ..... 2-10 2.6.2 Condenser Evacuation System .......................... 2-13 2.6.3 Containm ent Purge ................................... 2-15 2.6.4 Waste Gas Header ................................... 2-18 2.7 Gaseous Effluent Dose Rate ................................. 2-21 2.7.1 Noble G ases ........................................ 2-21 2.7.2 Radioiodines and Particulates ........................... 2-22 2.8 Gaseous Effluent Dose Calculation ............................ 2-23 2.8.1 Noble G ases ...................................... 2-23 2.8.1.1 Historical Meteorology .............................. 2-23 2.8.1.2 Concurrent Meteorology ............................. 2-24 2.8.2 Radioiodines and Particulates ........................ 2-25 2.8.2.1 Historical Meteorology .............................. 2-25 2.8.2.2 Concurrent Meteorology ............................. 2-26 3.0 PROJECTED DOSES .......................................... 3-1 thru 3-5 3.1 Liquid Dose Projection ....................................... 3-1 3.2 Gaseous Dose Projection ..................................... 3-1 3 .3 Total Dose ................................................ 3-2 3.3.1 Specification ....................................... 3-2 3.3 .1.1 S urveillance ....................................... 3-2 3.4 Total Dose Calculations ...................................... 3-3 3.4.1 Total Dose to Most Likely Member of the Public ............ 3-3 3.4.1.1 Annual Total Organ Dose ............................. 3-3 3.4.1.2 Annual Total Whole Body Dose ........................ 3-4 3.4.1.3 Annual Total Thyroid Dose ............................ 3-5 SO1 23-ODCM Revision 0 02-27-07

ODCM TABLE OF CONTENTS (Continued) 4 .0 E Q UIP ME NT ................................................ 4-1 thru 4-22 4.1 Radioactive Liquid Effluent Monitoring Instrumentation ........... ... 4-1 4.1.1 S pecification .................................... ... 4-1 4.1.1.1, 4.1.1.2 S urveillances ............................... 4-1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation ......... ... 4-9 4.2.1 S pecification .................................... S4-9 4 .2 .1.1 S urve illance .................................... ... 4-9 4.3 Operability of Radioactive Waste Equipment ................... ... 4-19 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ................. 5-1 thru 5-27 5.1 Monitoring Program ............................. . . . . . . . . . . . . 5 -1 5.1.1 Specification ........................... . . . . . . . . . . . . 5 -1 5.1.1.1 S urveillance ........................... ........ ... 5 -2 5.2 Land Use Census ............................... ........ ... 5-11 5.2.1 Specification ........................... . . .. . . . . . .. 5 -1 1 5.2.1.1 S urveillance ........................... . . .. . .. . . .. 5-1 1 5.3 Interlaboratory Comparison Program ................ ........ .... 5-12 5.3.1 Specification ........................... ......... ... 5-12 5.3.1.1 Surveillance ........................... ......... ... 5-12 5.4 Annual Radiological Environmental Operating Report ... .. ...... ... . 5 -13 5.5 Sam ple Locations ............................... ............ 5-14 6.0 A DM INISTRATIVE ................................... ......... 6-1 thru 6-17 6.1 Definitions ... ................ ... ...... .. .... ... . . . . . . . . . . . . 6-1 6.2 Adm inistrative Controls ........................... .. ...... .... 6-8 6.3 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) ............................ ............ 6-10 6 .4 Ba se s . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . 6-1 1 SO1 23-ODCM Revision 0 iii 02-27-07

ODCM LIST OF FIGURES Figure Title Page 1-2 Site Boundary for Liquid Effluents ................................... 1-8 2-2 Site Boundary for Gaseous Effluents ................................. 2-9 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems ............ 4-20 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems .......... 4-21 4-7 Solid W aste Handling ............................................ 4-22 5-1 Radiological Environmental Monitoring Sample Locations 1 M ile R adius .. ......... ... ....... ..... ........... ... ........... 5-23 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile R adius ...... ..... ... ... ....... .. .... .. .. .. ......... ...... 5-2 4 5-3 Radiological Environmental Monitoring Sample Locations 10 Miles R adius ..... ........................................... 5-25 5-4 Radiological Environmental Monitoring Sample Locations Orange County ................................................ 5-26 5-5 Radiological Environmental Monitoring Sample Locations San D iego C ounty ............................................... 5-27 SO1 23-ODCM iv Revision 0 02-27-07

ODCM LIST OF TABLES Table Title Page 1-1 Radioactive Liquid Waste Sampling and Analysis Program .... .. . .. . .. . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants ................................. ......... 1-23 1-4 Dose Commitment Factors A1 .... . . . . . . . . . . . . . . . . . . . . . . . ......... 1-25 2-1 Radioactive Gaseous Waste Sampling and Analysis Program 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants ................................. ......... 2-20 2-4 Dose Factors for Noble Gas and Daughters ................ ........ 2-27 2-5 Dose Param eters Pik .................................. ........ 2-28 2-6 Units 2 and 3 Controlling Location Factors ................. ......... 2-29 2-7 SYF Controlling Location Factors ........................ ......... 2-30 2-8 NIA (Unit 1) Controlling Location Factor ................... 2-31 4-1 Radioactive Liquid Effluent Monitoring Instrumentation ........ ......... 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ............................. 4-6 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation ..... ......... 4-10 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirem ents ............................. ......... 4-14 5-1 Radiological Environmental Monitoring Program ............. ......... 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environm ental Sam ples ................................ ......... 5-7 5-3 Maximum Values for the Lower Limits of Detection (LLD) ...... ......... 5-8 5-4 Radiological Environmental Monitoring Sample Locations.... ......... 5-15 5-5 PIC Radiological Environmental Monitoring Locations ........ ......... 5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map ............. ......... 5-22 6-1 O perational Modes ................................... ......... 6-6 6-2 Frequency Notation ................................... ......... 6-7 SO1 23-ODCM Revision 0 v 02-27-07

ODCM LIST OF APPENDICES Title Appendix Ri TABLES .............................................. S1 23-ODCM-A Supplemental Information for the Effluent Controls Program .......... SO1 23-ODCM-B S01 23-ODCM Revision 1 vi 02-29-08

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents consistent with RG 1.109 and NUREG 0133. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. The environmental section contains the requirements for the radiological environmental monitoring program.

The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology.

SO1 23-ODCM Revision 0 vii 02-27-07

1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECIFICATION 1.1.1 The concentration of radioactive material released from the site (see Figure 1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.

APPLICABILITY: At all times ACTION:

a. With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS

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

.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.

S0123-ODCM 1-1 Revision 0 02-27-07

TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (PCi/ml)a A. Batch Waste P P Principal Gamma 5x10-7 Released Each Batch Each Batch Emittersf 1-131 1xl 0-6 P M Dissolved and lxi 0-5 One Batch/M Entrained Gases (Gamma emitters)

P M H-3 1x10-5 Each Batch Compositeb Gross Alpha lxlO07 P Q Sr-89, Sr-90 5x 10-'

Each Batch Compositeb F e-55 1x10-6 NOTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing System Neutralization Sump, FFCPD sumps (high conductivity, low conductivity) and holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown.

B. Continuous D W Principal Gamma 5x 10-7 Releasese, Grab Sample Compositec Emittersf 1-131 lx10i1 M M Dissolved and 1x10-5 Grab Sample Entrained Gases (Gamma emitters)

D M H-3 1x 10-5 Grab Sample Composite' Gross Alpha lxi 0-7 D Q Sr-89, Sr-90 5x 10a Grab Sample Compositec Fe-55 lx10-1 NOTE CONTINUOUS RELEASE POINTS: Turbine Plant Sump*, Blowdown Processing System Neutralization Sump-, S/G Blowdown Bypass Line*-, S/G Blowdown, Auxiliary Building Sump.p S0123-ODCM 1-2 Revision 0 02-27-07

TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD)

Type Frequency Frequency Analysis (PCi/ml)a C. Continuous 3xW W Principal Gamma 5x10-1 Releasee Grab Sample Compositeb'9 Emitters' North 3'x W M H-3 lx10-5 Industrial Area Grab Sample CWmpHsite3b'G lxi 0-7 Yard Drain Sump Gross Alpha 3xW Q Sr-89, Sr-90 5xl 0 Grab Sample Compositeb'g Fe-55 lxl 0OE S0123-ODCM 1-3 Revision 0 02-27-07

TABLE 1-1 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 sb E . V . 2.22 x 106 . Y. exp (-At) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

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

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

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

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

Typical values of E, V, Y and At 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 the measurement system and not as a posteriori (after the fact) limit for a particular measurement.!

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

SO123-ODCM 1-4 Revision 0 02-27-07

TABLE 1-1 (Continued)

TABLE NOTATION

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

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d. A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

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

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-i 37, Ce-1 41, Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, and those isotopes listed in Reg. Guide 1.21, shall also be identified and reported.

g. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7821 is the turbine plant sump.

The first sump when transferring outlying sumps shall be treated as a batch release.

Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301 MU619 for Steam Generator 2E088, S21301 MU618 for Steam Generator 2E089, S31301 MU619 for Steam Generator 3E088 and S31 301 MU618 for Steam Generator 3E089) is verified locked shut.

SO 123-ODCM 1-5 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.2 DOSE SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:

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

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

APPLICABILITY: At all times ACTION:

a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

SURVEILLANCE REQUIREMENTS

.1 Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.

S0 123-ODCM 1-6 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, woyld exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:

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

.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1.

.2 During plant operation (either unit in Mode 1-4), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 1 5-minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

.3 In plant shut-down (both units in Mode 5,6), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes prior to processing liquids unless the appropriate liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

Per reactor unit SO 123-ODCM 1-7 Revision 0 02-27-07

SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 1-2 3 OTRE RAN W=EAR GENERATLMG STATM29 0'o e6 UNIT NIAUNIT& "' 3 Waff I Vahzt tamI ,

101L=

SC.LLZ a rim 0-m mo = w L. P

/

SO 123-ODCM 1-8 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1, the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

CmR F+R -<M(PC1-Pef where:

Cm = setpoint, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, pCi/ml R = permissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F F = dilution water flow in volume per unit time.

= 185,000 gpm per circulating water pump (4 total)*

= 17,000 gpm per saltwater pump (2 total)

The design flowrate of each circulating water pump is 205,000 gpm.

The value used in the determination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated.

NOTE: Since the values of R are much smaller than F, the term (F + R) in equation (1-1) may be replaced by F.

S0123-ODCM 1-9 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued)

MPCeff = effective effluent maximum concentration permissible limit (IJCi/ml) at the release point to the unrestricted area for the radionuclide mixture being released:

1_ (1-2)

(MPCI)

E where:

n = number of radionuclides identified in sample analysis Fj = fractional concentration of the ith radionuclide as obtained by sample analysis MPCi = MPC of the ith radionuclide (10CFR20; App B, Table II, Column 2)

Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

RW7813 = Radwaste Effluent discharge SG 88.2 = Unit 2 Steam Generator E-088 SG89.2 = Unit 2 Steam Generator E-089 SG 8B_ 3 = Unit 3 Steam Generator E-088 SG 89 _3 = Unit 3 Steam Generator E-089 B2 = Unit 2 Blowdown Processing System Neutralization Sump B3 = Unit 3 Blowdown Processing System Neutralization Sump T2 = Unit 2 Turbine Plant Sump T3 = Unit 3 Turbine Plant Sump Y = NIA Yard Drain Sump The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10CFR20, Appendix B, Table II, Column 2. The administrative values shall be assigned such that:

(RW 7813 + SG 88 2 + SG 89-2 + SG8B.3 + SG 89 .3 + B 2 + B3 + T 2 + T3 + Y) < 1 .0.

The administrative values shall be periodically reviewed based on actual release data and revised as necessary.

SO 123-ODCM 1-10 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (Cm) are set to meet the condition of equation (1-1) for the MPCeff limit. The method by which this is accomplished is as follows:

STEP 1: The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis.

C = (iuc') (C-)

+., + (Co) + (ct) + (CFe) + (Cxo) (1-3) where:

C = total concentration in each batch tank, pCi/ml zjC'Yi = sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, excluding Xe-1 33, pCi/ml Ca = gross alpha concentration determined in the previous monthly composite sample, pCi/ml CS = Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, pCi/ml Ct H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/ml CFe = Fe-55 concentration as determined in the previous quarterly composite sample, pCi/ml Cxe = Xe-1 33 concentration as determined by isotopic analysis, pCi/ml S 123-ODCM 1-11 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued)

STEP 2: The effective MPC (MPCeff) for each batch tank (or sump) is determined using:

(1-4)

( /c 1

MPCeff :

(iy QIj C M PPCC~

SMiM+/- (C1C )

P~ tM C aP~ )

aM

+/-

P C Fe where:

MPC~i, MPCS, the limiting concentrations of the appropriate MPCt, radionuclide from 10CFR20, Appendix B, MPCFe, Table II, Column 2 MPCa NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 pCi/ml total activity.

STEP 3: The setpoint, Cm (pCi/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, ZjC'Yj, F, MPCeff, and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit Cm, pCi/ml.

(1-5)

CPM max = .(Cm, pCi/ml)

(Cal. Const., pCi/cc/cpm)

SO 123-ODCM 1-12 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3RT-7813)

The value for Cm, the concentration limit at the detector, is determined by using:

Cm (RW 7 8 1 3 ) (F) (YjC'yj) (1-6)

(R) (MPCef) where:

RW 78 13 = Radwaste Effluent discharge administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total)

C = Total concentration in each batch sample

-=C'Y = total gamma isotopic concentration, excluding Xe-133, pCi/ml R = typical effluent release rate.

Values of R for each tank are as follows:

Radwaste Primary Tanks = 285 gpm (per pump)

Radwaste Secondary Tanks = 275 gpm (per pump)

Primary Plant Makeup Tank = 160 gpm (per pump)

Condensate Monitor Tanks = 100 gpm (per pump)

MPCeff from equation (1-4)

NOTE: If Cm < Z1C'*, then no release is possible. To increase Cm, increase the administrative value RW 7813, and/or increase dilution flow F (by running more dilution pumps in the applicable discharge structure),

and/or decrease the effluent flow rate R and recalculate Cm using the new RW 78 13 , F, R as applicable and equation (1-6).

Sa 123-ODCM 1-13 Revision 3 02-26-10

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP/FULL FLOW CONDENSATE POLISHER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (BATCH) (2RT-7817, 3RT-7817)

The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using:

(1-7)

' (2 2) (F) (ZiC'yj)

(R) (C/MPCeff)

(1-8)

C3 < (B3) (F) ( ,C',i)

(R) (C/MPCeff) where:

C2 = instantaneous concentration at detector 2RT-781 7 in pCi/cc C3 = instantaneous concentration at detector 3RT-781 7 in pCi/cc B2 = Unit 2 BPS Neutralization Sump administrative value B3 = Unit 3 BPS Neutralization Sump administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total)

ZiC'y = total gamma isotopic concentration, excluding Xe-133, pCi/ml, (STEP 1)

R Typical release flow rates:

BPS Neutralization Sump = 500 gpm FFCPD High Conductivity Sump = 500 gpm FFCPD Low Conductivity Sump = 600 gpm FFCPD Holdup Tank = 1000 gpm C = total concentration in each batch sample, pCi/ml MPCeff = value of MPCeff from equation (1-4) for the sample analysis NOTE: If C2 or C3 <_ ZiC'fi, then no release is possible. To increase C2 or C 3, increase the administrative value B2 or B3, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new B2 or B3, F, R as applicable and equation (1-7) or (1-8).

S0123-ODCM 1-14 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (Cm) are set to meet the condition of equation (1-1) for the effective MPC (MPCefr) limit.

The method by which this is accomplished is as follows:

STEP 1: The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown processing system neutralization sump, turbine plant sump, and yard drain sump) from the sum of the respective measured concentrations as determined by analysis:

C = ,C',,) + (C.) + (C5) + (Ct) + (CFe) + (Cxe) (1-3) where:

C = total concentration (Pci/ml)

ZiC'Y = total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-1 33, pCi/ml Ca = total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, pCi/ml C = total measured concentration of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis for the release stream, pCi/mI Ct total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the release stream, pCi/ml CFe = total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml Cxe = Xe-133 concentration as determined by isotopic analysis, pCi/ml SO 123-ODCM 1-15 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued)

STEP 2: The effective MPC (MPCeff) for each release stream (steam generator blowdown, blowdown processing system neutralization sump, turbine plant sump, or NIA yard drain sump) is determined using:

1 (1-4)

MPCeff =

MPrv$CJ II C /MCt (

+(ýCCSl) +( M PCJ1 +

PCa/

J +

(CFe' where:

MPCYI, MPCS, the limiting concentrations of the appropriate MPCt, radionuclide from 10CFR20, Appendix B, Table II, MPCFe, Column 2 MPCa STEP 3: The setpoint, Cm (pCi/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, ZjC'Yj, F, MPCeff, and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.

STEP 4: Ifthe monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit Cm, pCi/ml.

(1-5)

CPM = (Cm, PCi/mI)

(Cal. Const., pCi/cc/cpm)

S0 123-ODCM 1-16 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT-7817, 3RT-7817)

The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using:

(1-7)

C2

P2) (F) (ZC'Yj)

(R) (C/MPCeff)

__________c__i (1-8)

C3 _< (F) ýjC'Yj)

(R) (C/M PCeff) where:

C2 = instantaneous concentration at detector 2RT-7817 in pCi/cc C3 = instantaneous concentration at detector 3RT-7817 in pCi/cc B2 = Unit 2 Blowdown Processing System Neutralization Sump administrative value B3 = Unit 3 Blowdown Processing System Neutralization Sump administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total)

ZiC'Yj = total gamma isotopic concentration, excluding Xe-1 33, pCi/ml, (STEP 1)

R = effluent flow rate, gpm, (STEP 1), (maximum of 500 gpm)

C = total concentration, pCi/ml MPCeff = value of MPCeff from equation (1-4) for the sample analysis NOTE: IfC2 or C3 _<-iC'yi, then no release is possible. To increase C2 or C3, increase the administrative value B2 or B3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C 2 or C3 using the new B2 or B3, F, R as applicable and equation (1-7) or (1-8).

SO 123-ODCM 1-17 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759)

The value for C, 9 .2, C 53-2, CH93 or C5 3 _3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:

(1-9) 5 (SG88 _2) (F) (ZiC'yi)

(R) (C/MPCeff)

(1-10)

C 5 3 -2 * (SG89 _2) (F) (ZiC'yi)

(R) (C/MPCeff)

(1-11)

C 59 -3 (SG88 3 ) (F) (XiC',i)

(R) (C/MPCeff) '

(1-12)

C 53 -3 * (SG89 _3) (F) (ZiC'Yi)

(R) (C/MPCeff) where:

C59-2 = instantaneous concentration at detector 2RT-6759 in pCi/ml C53-2 = instantaneous concentration at detector 2RT-6753 in pCi/ml C59-3 = instantaneous concentration at detector 3RT-6759 in pCi/ml C53-3 = instantaneous concentration at detector 3RT-6753 in pCi/ml SG88- 2 = Unit 2 E088 Steam Generator Blowdown administrative value SG89-2 = Unit 2 E089 Steam Generator Blowdown administrative value SG88-3 = Unit 3 E088 Steam Generator Blowdown administrative value SG 89-3 = Unit 3 E089 Steam Generator Blowdown administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total)

SO 123-ODCM 1-18 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759) (Continued) 7-iC'Yi = total gamma isotopic concentration, excluding Xe-133, pCi/ml, (STEP 1)

R = maximum blowdown bypass effluent flowrate per steam generator, 200 gpm, (STEP 1)

C = total concentration, pCi/ml MPCeff = value of MPCeff from equation (1-4) for the sample analysis NOTE: If C 9_2, C53-2) C. 9 -3,or C53-3 < ZC'Y (for the respective steam generator),

then5 no release is possible. To 1increase C5,_2, C53-2, C5,-3 or C,3-3, increase the administrative value SG88 2 , SG 89_2, SG8M_3 or S G8, 3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate R and recalculate C5,- 2 , C 53- 2, C 5,- 3 or C53 -3 using the new values of SG 89 _2, SG 88 .2, SG 893 or SG 883, F, R as applicable and equation (1-9), (1-10), (1-11) or (1-12).

SO123-ODCM 1-19 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-7821)

The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using:

2 r2) (F)(*iC'yi) (1-13)

(R) (C/MPCeff)

(1-14) 03 (T3) (F) (Z0C'y)

(R)(C/MPCoeff) where:

C2 = instantaneous concentration at detector 2RT-7821 in pCi/cc C3 = instantaneous concentration at detector 3RT-7821 in pCi/cc T2 = Unit 2 Turbine Plant Sump administrative value T3 = Unit 3 Turbine Plant Sump administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total) zC'yi= total gamma isotopic concentration, excluding Xe-1 33, pCi/ml, (STEP 1)

R = effluent flow rate, gpm, (STEP 1), typically flow rate:

= 100 gpm (per pump)

C = total concentration, pCi/mI MPCeff = value of MPCeff from equation (1-4) for the sample analysis NOTE: If C2 or C3 _<ZiC'yi, then no release is possible. To increase C2 or C3, increase the administrative value T2 or T3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new T2 or T3 , F, R as applicable and equation (1-13) or (1-14).

SO 123-ODCM 1-20 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-7821) (Continued)

Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 2(3)RT-7821, is in service and the normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:

a. The release permit shall account for the entire volume of water discharged from the Turbine Plant Sump.

b. The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal and temporary paths.

b. Procedures shall require the immediate termination of the discharge via the temporary path if the monitor on the normal path alarms.

Sa 123-ODCM 1-21 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.4 NIA YARD DRAIN SUMP MONITOR (RT-2101)

There is one Yard Drain Sump on site, located in the North Industrial Area. It can be released through either the Unit 2 or Unit 3 outfall. The same radiation monitor is used for either outfall.

The value for Cyos, the concentration limit at the detector, is determined by using:

(Y) (F)(z'C'yi) (1-15)

(R) (C/MPCeff) where:

CYDS = instantaneous concentration at detector RT-2101 in pCi/ml Y = NIA Yard Drain Sump administrative value F = dilution water flow in volume per unit time

= 185,000 gpm per circulating water pump (4 total)

= 17,000 gpm per saltwater pump (2 total) 7iC'yi = total gamma isotopic concentration, pCi/ml, (STEP 1)

R = effluent flow rate, gpm, typical flow rates:

= 2300 gpm or 4100 gpm C = total concentration, pCi/ml MPCeff = value of MPCeff from equation (1-4) for the sample analysis NOTE: If Cs <. ZiC'yi, then no release is possible. To increase CYDS, increase the administrative value Y, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate CYDS using the new Y, F, R as applicable and equation (1-15).

SO123-ODCM 1-22 Revision 0 02-27-07

TABLE 1-3 Liquid Effluent Radiation Monitor Calibration Constants (a)

(pCi/cc/cpm)

MONITOR Co-60 Ba-1 33 Cs-1 37 2RT-6753 2.07E-8 1.90E-8 2RT-6759 1.90E-8 1.90E-8 3RT-6753 1.92E-8 1.92E-8 3RT-6759 1.98E-8 1.97E-8 (a) This table provides typical (+/- 20%) calibration constants for the liquid effluent radiation monitors.

S0 123-ODCM 1-23 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.5 DOSE CALCULATION FOR LIQUID EFFLUENTS The liquid releases considered in the following dose calculations are described in Section 1.4. The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the following expression.

DT = Z*i[Ai Zj(Atj Cij Fj)] (1-16) where:

AiT = Site-related adult ingestion dose commitment factor to the total body or an organ, T,for each identified principal gamma and beta emitter, i, from Table 1-4 in mrem/hr per pCi/ml.

Cii = average concentration of radionuclide, i, in the undiluted liquid effluent during time period, At,, in pCi/ml.

DT = dose commitment to the total body or an organ, T,from the liquid effluent for the time period, At,, in mrem.

Fj = near field average dilution factor (actually mixing ratio) for C,, during the time period, At,. This factor is the ratio of the maximum undiluted liquid waste flow during time period, At1, to the average flow from the site discharge structure to unrestricted receiving waters, maximum liquid radioactive waste flow or: discharge structure exit flow Atj = length of the jth time period over which C.j and Fj are averaged for all liquid releases, in hours.

SO 123-ODCM 1-24 Revision 0 02-27-07

TABLE 1-4 DOSE COMMITMENT FACTORS*, AiT (mrem/hr per pCi/ml)

Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+O 1.23E+0 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11 E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01 E+2 5.40E+2 1.83E+4 Zn-65 1.61 E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.OOE+2 Sr-90 1.23E+5 3.01 E+4 3.55E+3 Sr-91 9.18E+1 3.71E+0 4.37E +2 Sr-92 3.48E+1 1.51 E+0 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91 m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+O 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51 E+4 Nb-95 1.84E+O 1.03E+0 5.51 E-1 1.01 E+0 6.22E+3 Nb-95m 1.84E+0 1.03E+O 5.51E-1 1.01 E+O 6.22E+3 Nb-97 1.55E-2 3.91 E-3 1.43E-3 4.56E-3 1.44E+1 Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-1 1, Table A-1 USNRC NUREG-01 72, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-ODCM 1-25 Revision 0 02-27-07

TABLE 1-4 (Continued)

DOSE COMMITMENT FACTORS*, Ai, (mrem/hr per pCi/ml)

Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ag-i 1Dm 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-1 13 2.26E+5 Sn-1 17m 2.26 E+5 Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-1 32 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1-132 1.06E+,1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.1 6E+2 1-134 5.56E+0 1.51 E+I 5.40E+O 2.62E+2 2.40E+1 1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+ 1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+D 1.20E+1 5.94E+O 8.81E+O 8.70E-1 5.12E-5 Ba-139 7.85E+O 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+D 3.38E+3 La-140 1.57E+D 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-1 43 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-1 47 3.96E+O 4.58E+0 2.74E-1 2.68E+O 2.20E+4 W-187 9.16E+D 7.66E+O 2.68E+O 2.51 E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 NOTE: where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-1i1, Table A-1 USNRC NUREG-01 72, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-ODCM 1-26 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.6 Representative Sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirementsof Regulatory Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in S01 23-111-5.23, "Generating Effluent Release Permits Using The Vax Computer" and S0123-111-5.2.23, "Units 2/3 Liquid Effluents".

S 123-ODCM 1-27 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS 2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For all radioiodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENTS

.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7.

.2 The dose rate due to radioiodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

SO 123-ODCM 2-1 Revision 0 02-27-07

TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (pCi/ml)a Batch P P Principal Gamma Emitters9 1x104 Waste Gas Each Tank Each Tank Decay Tank Grab Sample Continuous Principal Gamma Emitters9 1x104

-Tritium lx10-6 W' 1-131 1x10- 12 Continuousf Charcoal Sampler Sample 1-133 1x.10' Wd Continuousf Particulate Principal Gamma Emitters9 1x10-11 Sampler Sample (J-131and Others)

M Continuousf Composite Gross Alpha 1x l0-11 Sampler Particulate Sample Q

Continuousf Composite Sr-89 and Sr-90 1x10 11 Sampler Particulate Sample Continuous! Noble Gas Noble Gases 1x10-Monitor Monitor Gross Beta or Gamma

Sampling frequencies for noble gases and tritium are:

CONTINUOUS PATHWAYS: Containment Purge - 42" Each Purgebc, Containment Purge - 8" Monthly Grabb Condenser Air Ejector Monthly Grabb Plant Vent Stack Weekly Grabb'e South Yard Facility Particulate and Iodine sampling onlyh SO123-ODCM 2-2 Revision 0 02-27-07

TABLE 2-1 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD =4.66 sb E - V - 2.22 x 106

Y - exp (-XAt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

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

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

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

, is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

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

Typical values of E, V, Y and At 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 the measurement system and not as a posteriori (after the fact) limit for a particular measurement.*

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

S0123-ODCM 2-3 Revision 0 02-27-07

TABLE 2-1 (Continued)

TABLE NOTATION

b. Analyses shall also be performed on the affected unit and plant vent stack following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period. 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) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

c. 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.

d. (i) 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 sampler).

(ii) Sampling shall also be performed on the affected unit and plant vent stack 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 a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. 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) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement is not applicable to the South Yard Facility.

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

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.

g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-133m, Xe-1 35, and Xe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-1 41 and Ce-1 44 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

h. Radioactive airborne effluents only expected to be particulate and iodine.

S0123-ODCM 2-4 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 2-2) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 1 0 mrad for beta radiation and,

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

APPLICABILITY: At all times ACTION:

a. With calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 2.2.1.

SURVEILLANCE REQUIREMENTS

.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

SO 123-ODCM 2-5 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.3 DOSE - RADIOIODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limited to the following:

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

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

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of tritium, radioiodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding-the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

SURVEILLANCE REQUIREMENTS

.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

S0123-ODCM 2-6 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT SPECIFICATION 2.4.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2-2), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 2-2) when averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY: At all times ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for 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

.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.

These doses are per reactor unit.

SO123-ODCM 2-7 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT -(Continued)

SURVEILLANCE REQUIREMENTS (Continued) 2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

.3 In plant shut-down (Mode 5, 6), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutes prior to processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.

SO123-ODCM 2-8 Revision 0 02-27-07

aE2:1 $T-9 WiJ

2. Ca%-t;VVOVS EX"AUS-VS.41I.

SACK al 2:5 $7-' 'iJ

, V.'9I iUILOINGCVS[TIU1IO" fXHt $jA - NO IUTGNREAI.

EX.4JSt OUCTINGI,

-, CO~

ct N~

E IVACCATION S$STMEIXHAUST W.L72I'.4 l".l S. TURI 31E OLANOSEALSYSIEM CF 1xHAUST IEL7 F1.4 Mi CAMP JOS EP.,

/ A- i. *o-.ooo"

.It W.*

/ 3/4

/

N. ' t. C 'C

/

N

"" -SAN ONOFRE NUCLEAR GENERATING STATION SITE BOUNDARY FOR GASEOUS EFFLUENTS Figure 2-2 S0123-ODCM 2-9 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setpoints Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

PVS = Plant Vent Stack CAE = Condenser Air Ejector CP = Containment Purge SY = South Yard WG = Waste Gas The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points on site to the environment will not result in a release exceeding the limits of Specification 2.1.1. The sum total of all these administrative values for the site shall be less than or equal to 1.0.

The administrative values shall be periodically reviewed based on actual release data and revised as necessary.

2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate andthe meteorological dispersion factor.

Total Body The concentration at the detector corresponding to a 500 mrem/yr total body dose rate at the exclusion area boundary is determined by:

5 0 0 mrem/yr)(10_6 m 3/cc) (2-1)

(PVS) (2120m 3isecf) (

(flow rate, cfm)(X/Q, sec/m 1) [ (Ki. mremtyr Ctot Skin The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by:

6 (2-2)

(PVS) (2120 cfm ) (3000 mrem/yr)(10- m 3/cc)

Cdet I -m 3/sec)

(flow rate, cfm)ýX/Q, sec/in3) [ [

(L +/-11.1 Mlmrem/yr(

' ~ pCi/rn 3 C~ i C)0 Jjo S0123-ODCM 2-10 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 (Continued) where:

Cdet = the instantaneous concentration at the detector, pCi/cc PVS = an administrative value used to account for potential activity from other gaseous release pathways, typically 0.38.

K. = total body dose conversion factor from Table 2-4 for 3 the i gamma emitting noble gas, mrem/yr per pCi/m Li 2-4 for

= skin Dose Conversion Factor from Table 3 the ith noble gas, mrem/yr per pCi/m Mi

= air Dose Conversion Factor from Table 3 2-4 for the i1h noble gas, mrem/yr per pCi/m 1.1 = conversion factor to convert gamma air dose to skin dose Ci = concentration of the ith noble gas as determined by sample analysis, pCi/cc Ctot

= total concentration of noble gases as determined by sample analysis, pCi/cc = ZCi flow rate = total plant vent stack flow rate, cfm,

= typically 164,000 cfm 2120 = conversion constant, cfm per m 3/sec 500 mrem/yr = total body dose rate limit, as specified by Specification 2.1.1 .a 3000 mrem/y = skin dose rate limit as specified by Specification 2.1.1 .a X/Q = historical annual average dispersion factor for any landward3 sector, sec/m3

= 4.8E-6 sec/mi S0 123-ODCM 2-11 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1.1 Maximum Permissible Alarm Setpoint for 2/3RT-7808, 2RT-7865-1 and 3RT-7865-1 The smaller of the values of Cdet from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (pCi/cc) to an equivalent release rate in pCi/sec, as follows:

(Cdet, pCi/cc)(flow rate, cfm)(28320) (2-3)

Amax =

(S)(60) where:

Amax = maximum permissible release rate, pCi/sec Cdet = smaller of the values of Cdet determined in equations (2-1) and (2-2).

flow rate = plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 = conversion from ft3 to cc 60 = conversion from minutes to seconds S correction factor to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks, typically 2 for split stack monitoring and 1 for combined stack monitoring The release rate setpoint shall not be set greater than the maximum release rate determined above, when the monitor is being used to meet the requirements of Specification 2.1.1.

Sa123-ODCM 2-12 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air Ejector Monitors For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion area boundary is determined by using:

Total Body (24) cfm (500 mrem/yr) (10-6 m3icc)

(CAE)(0.5) 2120 C -et m 3/sec)

(Flow rate, cfm)3)/Q sec/m cfm)~se/n 3 (Ki' mrem/yr r Ci]

,Ci/m 3 ) Ct)J The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using:

Skin where: (CAE) = an administrative value used to account for potential activity from other gaseous release pathways, typically 0.1.

0.5 = an administrative value used to account for releases from both SONGS 2 and SONGS 3 condenser air ejectors simultaneously.

Other parameters are specified in 2.6.1 and/or 2.6.2.2.

(2-5)

(CAE)(0.5)(2120 cfm e (3000 mrem/yr) (106M3/cc)

Cdet :m 3/sec) rmy (Flow rate, cfm) (X/Q, sec/m3)[ i"L ÷ 1.1M,, mrem/yrM ( Ct'ot SO 123-ODCM 2-13 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 (Continued)

The smaller of the values Cdet from equations (2-4) or (2-5) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows:

The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm value corresponding to the concentration, Cdet, [smaller value from equation (2-4) or (2-5)].

The calibration constant used is based on Kr-85 or on Xe-1 33, whichever yields a lower detection efficiency (higher value in terms of pCi/cc/cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.

.2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranqe Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, Cdet (pCi/cc), to an equivalent release rate in pCi/sec.

Amax = (Cdet, pCi/cc) (flow rate, cc/sec) (2-6) where:

Amax = maximum permissible release rate, pCi/sec Cdet = smaller value of Cdet, as obtained from equations (2-4) and (2-5) flow rate = flow rate of the condenser air ejector, cc/sec

- 4.719E5 cc/sec (conservatively assumed as design flow rate)

S0123-ODCM 2-14 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

NOTE: 2(3)RT-7865 is not designed to monitor main purge.

The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion boundary is determined by using:

Total Body (2-7)

(CP)(P2)(2120 cfm (e500mrem/yr) (10-6 m 3/cc)

Cdet2 -

(Flow rate, cfm) (X/Q, sec/m3) z i( Kit mrem/yr C)

S pCi/M 3 ct0ot (2-8)

(Cp)(P 3)( 2120 mcfm/ 3 3/sec) (500 mrem/yr) (10-6 m /cc)

(Kit ) Lctot Cdet3 =

(Flow rate, cfm) (X/Q, sec/m mrem/yr C 3)[_i pCi/in 3 The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using:

Skin (2-9)

(CP)(P2)( 2120 mCfm ( 3000 mrem/yr) (10-6 m3/cc) m3sc Cdet2 -

(Flow rate, cfm) (X/Q, sec/m 3) zKi (Li

+ 1 1. M, mrem/yr pCi/m 3

)v-ilCi SO123-ODCM 2-15 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued)

(CP)(p 3)1 2120 m cfm) 3/sec) ( 3000 mrem/yr) (10-6 m 3/cc)

Cdet3 _\

(Flow rate, cfm) (X/Q' sec/m 3) + 1.1M,, mrem/yr i L(L ii where:

Cdet2 instantaneous concentration of the Unit 2 detector, pCi/cc.

Cdet3 = instantaneous concentration of the Unit 3 detector, pCi/cc.

CP = administrative value used to account for potential activity from other gaseous release pathways, typically 0.38.

P2 and P3 are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions P 2 and P3 will be assigned such that P2 + P3 -<1 .0.

Flow rate observed maximum flowrate in cfm from the unit specific monitor 7828.

Default values will be the following conservative measured flows:

= 50,000 cfm main purge [2(3)RT-7828 only]

= 3,000 cfm mini-purge (The above values replace the smaller design flowrates.)

Other parameters are as specified in 2.6.1 above. The smaller of the values of maximum permissible Cdet2 from equation (2-7) or (2-9) and Cdet3 from equations (2-8) or (2-10) is to be used in determining the maximum permissible monitor alarm setpoints.

SO123-ODCM 2-16 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued) 2.6.3.1 Maximum Permissible Alarm Setting for 2(3)RT-7865-1 The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (pCi/sec) is determined by converting the concentration at the detector, Cdet (PCi/cc),to an equivalent release rate in pCi/sec.

Amax = (Cdet, pCi/cc) (flow rate, cc/sec) (2-6) where:

Amax = maximum permissible release rate, pCi/sec Cdet = smaller value of Cdet, as obtained from equation (2-7, 2-9) for Unit 2 or (2-8, 2-10) for Unit 3.

flow rate = flow rate, cc/sec 1.416E6 cc/sec for mini-purge.

.2 Maximum Permissible Alarm Setting (RT-7828)

The maximum permissible alarm setting for RT-7828 is in pCi/cc and is the smaller of the values of Cdet (pCi/cc) from equations (2-7) and (2-9) for Unit 2 or equations (2-8) and (2-10) for Unit 3.

S0123-ODCM 2-17 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 For the purpose of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Since the waste gas header discharges to the plant vent stack, either 3RT-7865-1 or 2/3RT-7808 may be used to monitor waste gas header releases.

The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr or a skin dose rate of 3000 mrem/yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (Ci) and (Ctot) being obtained from the waste gas decay tank to be released.

2.6.4.1 Maximum Permissible Alarm Setpoint for 3RT-7865-1 and 2/3RT-7808 The smaller of the values of Cdet from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (pCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (pCi/cc) to an equivalent release rate in pCi/sec, as follows:

Amax (Cdet, pCi/cc)(flow rate, cfm)(28320) (2-3)

(S)(60) where:

Amax = maximum permissible release rate, pCi/sec Cdet = smaller of the values of Cdet determined in equations (2-1) and (2-2) flow rate = plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 = conversion from ft3 to cc 60 = conversion from minutes to seconds S = correction factor for 3RT-7865-1 viewing only half the total plant vent stack flow, typically 2 for 3RT-7865-1 and 1 for 2/3RT-7808.

S0123-ODCM 2-18 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 (Continued) 2.6.4.2 A release from the waste gas header is not possible if:

/f C (2-11)

(ZiC) I\ >Cdet where:

ziC = total gamma activity (MCi/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis f = waste gas header effluent flow rate, cfm F = plant vent stack flowrate (cfm) used in equations (2-1) and (2-2)

Cdet smaller of the values of Cdet determined in equations (2-1) and (2-2) with Ci being obtained from the waste gas holdup tank to be released If a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Plant Vent Stack Monitor setpoint in accordance with the following:

f<(we) (Cdet)(F) (2-12) zi Ci where:

f = waste gas header effluent flow rate (cfm)

F = plant vent stack flow rate (cfm) used in equation (2-1) or (2-2)

Cdet = smaller of the value of Cdet from equation (2-1) or (2-2)

ZiC1 = total gamma activity (pCi/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis.

WG = an administrative value to account for the potential activity from other releases in the same release pathway, typically 0.9.

SO 123-ODCM 2-19 Revision 0 02-27-07

Table 2-3 Gaseous Effluent Radiation Monitor Calibration Constants(a)

(pCi/cc/cpm)

MONITOR Kr-85 Xe-1 33 2RT-7818A 4.27E-8 6.86E-8 3RT-7818A 3.73E-8 5.12E-8 (a)This table provides typical (+/-20%) calibration constants for the gaseous effluent radiation monitors.

So 123-ODCM 2-20 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7 Gaseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1 .1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions:

2.7.1 FOR NOBLE GASES:

(2-13)

DTB TKi(X/Q) b, 7i r ___ 1(2-14) z (L + 1.1M) (X/Q) Q (

where:

DTB - total body dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr Ds skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr

= the total body dose factor due to gamma emissions from Table 2-4 for each 3identified noble gas radionuclide, i, in mrem/yr per pCi/m Li = skin dose factor due to the beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrem/yr per pCi/m 3 Mi air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per pCi/m3 (conversion constant of 1.1 mrem/mrad converts air dose to skin dose.)

i= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in pCi/sec (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

= 4.8E-6 sec/m3 for Units 2 and 3

= 8.OE-5 sec/m 3 for South Yard Facility SO123-ODCM 2-21 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7.2 FOR ALL RADIOIODINES, TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:

(2-15) bo= -i [ k(Pik Wk) i where:

Do= organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr S= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, pCi/s6c Pik = dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation pathway in mrem/yr per pCi/m 3 . The dose factors are based on the critical individual organ and the child age group.

Wk = highest calculated annual average dispersion (X/Q) or deposition (07Q) factor for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.

= (X/Q), 4.8E-6 sec/m 3 for Units 2/3 for the inhalation pathway. The location is the unrestricted area in the NW sector.

= (X/Q), 8.OE-5 sec/m 3 for South Yard Facility for the inhalation pathway. The location is the unrestricted area in the E sector.

= (X/Q), 1.3E-5 sec/m3 for the NIA (Unit 1) for the inhalation pathway. The location is the unrestricted area in the NW sector. (Historical value)

= (D/Q), 4.3E-8 m-2 for Units 2/3 for the food and ground plane pathways. The location is the unrestricted area in the E sector.

= (D/Q), 8.0E-7 mr2 for South Yard Facility for the food and ground plane pathways. The location is the unrestricted area in the E sector.

= (D/Q), 7.2E-8 sec/m 3 for NIA (Unit 1) for the food and ground pathways. The location is the unrestricted area in the NW sector. (Historical value)

S0123-ODCM 2-22 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8 Gaseous Effluent Dose Calculation 2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions:

2.8.1.1 For historical meteorology:

8 _ZMi [cX--Q)Qi] (2-16)

D = 3.17x10

=

(2-17)

= 3.17X10- 8 Z. Ni 7--Q]

where:

Dy = total gamma air dose from gaseous effluents, mrad DP = total beta air dose from gaseous effluents, mrad 3.1 7x10 8 = inverse seconds per year Mi = air dose factor due to gamma emissions from Table 2-4 for each 3 identified noble gas radionuclide, i, in mrad/yr per pCi/m Ni = air dose due to beta emissions from Table 2-4 for each identified 3 noble gas radionuclide, i, in mrad/yr per pCi/m (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

= 4.8E-6 sec/m 3 for Units 2 and 3

= 8.OE-5 sec/m 3 for South Yard Facility Q= amount of noble gas radionuclide, i, released in gaseous effluents, pCi.

S0123-ODCM 2-23 Revision 0 02-27-07

2.0- GASEOUS EFFLUENTS (Continued) 2.8.1.2 For meteorology concurrent with release:

NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

(2-18)

Dye 4

= 1.14x10- y. Mi zj(Atj (XIQ)je Q)

(2-19)

DPe = 1.14x10 -4 Zi Ni $j(Atj(XIQ)je where:

Dye = total gamma air dose from gaseous effluents in sector e, mrad DPe = total beta air dose from gaseous effluents in sector e, mrad 1.14x10-4 = inverse hours/year Mi air dose factor due to gamma emissions from Table 2-4 for each identified noble gas 3

radionuclide, i, in mrad/yr per pCi/m Ni air dose factor due to beta emissions from Table 2-4 for each identified noble gas 3

radionuclide, i, in mrad/yr per pCi/m Atj length of the jth time period over which (X/Q)j, and Q1j are averaged for gaseous releases in hours (X/Q)jo = atmospheric dispersion factor for time period At- at exclusion boundary location in la ndward sector e determined 3 by concurrent meteorology, sec/m i" average release rate of radionuclide, i, in gaseous effluents during time period, At,, pCi/sec SO123-ODCM 2-24 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2 DOSE FROM TRITIUM, RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half lives greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:

2.8.2.1 For historical meteoroloqy:

(2-20)

Do = 3.17x10 - Z, [Z7k PikWk)Pi]

where:

Do total projected dose from gaseous effluents to an individual, mrem 3.17x10-8 year/second Qi amount of each radionuclide, i, (tritium, radioiodine, radioactive material in particulate form with half lives greater than eight days),

released in gaseous effluents, pCi ZkRikWk sum of all pathways, k, for radionuclide, i, of the Ri W product, in mrem/yr per pCi/sec. The ZkRikWk value for each radionuclide, i, is given in Table 2-6 for Units 2/3, Table 2-7 forSouth Yard Facility, and Table 2-8 for the North Industrial Area (Unit 1 historical value). The value given is the maximum ZkRikWk for all locations and is based on the most restrictive age groups.

Rik dose factor for each identified radionuclide, i, for pathway k, (for the inhalation pathway in mrem/yr per pCi/m 3 and for the food and ground plane pathways in in2-mrem/yr per ICi/sec), at the controlling location.

The Rik's for each controlling location for each age group are given in Appendix A. Data in these tables are derived using the NRC code, PARTS. (See the annual update of revised Ri parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.)

SO123-ODCM 2-25 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.1 For historical meteorology: (Continued)

Wk = annual average dispersion (X/Q)or deposition (D/Q) factor for estimating the dose to an individual at the controlling location for pathway k.

X/Q for the inhalation pathway in sec/m 3 .

The X/Q for each controlling location is given in Appendix A.

(D/Q) for the food and ground plane pathways in m-2 .

The (D/Q) for each controlling location is given in Appendix A.

2.8.2.2 For meteorology concurrent with releases:

NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

we = 1.14 x 0- jZZ k I(Atj)(Rike)(Wjke)I QJ (2-21) where:

Do total annual dose from gaseous effluents to an individual in sector e, mrem.

Atj = length of the jth period over which WkB and Q1j are averaged for gaseous released, hours Q= average release rate of radionuclide, i, in gaseous effluents during time period At,, pCi/sec Rike = dose factor for each identified radionuclide i, for pathway k for sector e (for the inhalation pathway in mrem/yr per pCi/m 3 and for the food and ground plane pathways in m2 mrem/yr per pCi/sec) at the controlling location. A listing of Rik for the controlling locations in each landward sector for each group is given in Appendix A. The e is determined by the concurrent meteorology.

Wjk= dispersion X/Q or deposition D/Q factor for the time period At. for each pathway k for calculating the dose to an individual at the controlling location in sector E using concurrent meteorological3 conditions.

= X/Q for the inhalation pathway, sec/m

= (D/Q) for the food and ground plane pathways, m-2 SO123-ODCM 2-26 Revision 0 02-27-07

TABLE 2-4 DOSE FACTORS FOR NOBLE. GASES AND DAUGHTERS**

Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K. Factor Li Factor Mi Factor N1 Radio- (mrem/yr (mrem/yr (mrad/yr (mrad/yr Nuclide per pCi/m 3) per pCi/m 3) per pCi/m 3 ) per pCi/m 3)

Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr-85 1.61 E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131 m 9.15E+1 4.76E+2 1.56E+2 1.11 E+3 Xe-133m 2.51 E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-1 35 1.81 E+3 1.86E+3 1 .92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3

- Source: USNRC Reg. Guide 1.109, Table B-1 S0123-ODCM 2-27 Revision 0 02-27-07

TABLE 2-5 DOSE PARAMETER Pik*

CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathway Inhalation Pathway Radionuclide (mrem/yr per pCi/m 3 ) Radionuclide (mrem/yr per pCi/m 3)

H -3 1.1E+3 1-131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1 E+5 1-134 5.1 E+4 Co-58 1.1 E+6 1-135 7.9E+5 Co-60 7.1 E+6 Cs-1 34 1.OE+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.0E+8 Cs-137 9.1 E+5 Zr-95 2.2E+6 Ba-1 40 1.7E+6 Nb-95 6.1 E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-1 29m 1.8E+6

Source: USNRC NUREG-01 33, Section 5.2.1.1 SO123-ODCM 2-28 Revision 0 02-27-07

TABLE 2-6 UNITS 2&3 CONTROLLING LOCATION FACTORS1 YkRikWk Radionuclide mrem/yr per pCi/sec Use:

H -3 4.44E-3 R: Camp Mesa Cr-51 1.78E-1 R: Camp Mesa Mn-54 3.92E+1 R: Camp Mesa Co-57 7.86E+0 R: Camp Mesa Co-58 1.32E+1 R: Camp Mesa Co-60 5.30E+2 R: Camp Mesa Sr-89 1.68E+1 Q: SC Res. with Garden Sr-90 6.60E+2 Q: SC Res. with Garden Zr-95 1.50E+1 R: Camp Mesa Nb-95 9.03E+0 E: Deer Consumer/Hunter Ru-103 1.43E+1 E: Deer Consumer/Hunter Te-129m 7.11E+0 R: Camp Mesa Cs-1 34 1.58E+2 R: Camp Mesa Cs-1 36 3.56E+0 R: Camp Mesa Cs-1 37 2.35E+2 R: Camp Mesa Ba-1 40 7.50E+0 R: Camp Mesa Ce-1 41 2.40E+0 R: Camp Mesa Ce-1 44 4.60E+1 R: Camp Mesa 1-131 5.59E+1 R: Camp Mesa 1-132 6.93E-1 R: Camp Mesa I -133 1.30E+1 R: Camp Mesa I -134 1.80E-1 R: Camp Mesa 1-135 2.76E+0 R: Camp Mesa UN-ID 2.11 E+1 R: Camp Mesa These values to be used in manual calculations are the maximum ZkRkWk for all locations based on the most restrictive age group.

S0123-ODCM 2-29 Revision 3 02-26-10

TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS1 7"kRiW Radionuclide mrem/yr per pCi/sec Use:

H -3 1.31 E-3 G: San Onofre Bch Campgd Cr-51 4.15E-2 F: SO St. Pk./Guard Shack Mn-54 9.70E+0 F: SO St. Pk./Guard Shack Co-57 2.41 E+0 F: SO St. Pk./Guard Shack Co-58 3.14E+0 F: SO St. Pk./Guard Shack Co-60 1.35E+2 F: SO St. Pk./Guard Shack Sr-89 1.71 E+0 F: Deer Consumer/Hunter Sr-90 1.04E+2 G: San Onofre Bch Campgd Zr-95 7.26E+0 F: Deer Consumer/Hunter Nb-95 2.88E+1 F: Deer Consumer/Hunter Ru-1 03 4.56E+1 F: Deer Consumer/Hunter Te-129m 2.26E+1 F: Deer Consumer/Hunter Cs-1 34 4.28E+1 F: SO St. Pk./Guard Shack Cs-136 1.04E+0 F: SO St. Pk./Guard Shack Cs-1 37 6.36E+1 F: SO St. Pk./Guard Shack Ba-140 1.39E+0 G: San Onofre Bch Campgd Ce-141 4.29E-1 G: San Onofre Bch Campgd Ce-1 44 8.39E+0 G: San Onofre Bch Campgd 1-131 2.28E+1 F: Deer Consumer/Hunter 1-132 1.22E-1 G: San Onofre Bch Campgd 1-133 2.22E+0 G: San Onofre Bch Campgd 1-134 3.24E-2 G: San Onofre Bch Campgd 1-135 4.60E-1 G: San Onofre Bch Campgd UN-ID 5.36E+O F: SO St Pk./Guard Shack These values to be used in manual calculations are the maximum ZkRikWk for all locations based on the most restrictive age group.

S0 123-ODCM 2-30 Revision 0 02-27-07

TABLE 2-8 NORTH INDUSTRIAL AREA (UNIT 1) CONTROLLING LOCATION FACTORS 1 IkRikWk Radionuclide mrem/yr per pCi/sec Use:

H -3 5.46E-3 A: Camp Mesa Cr-51 2.42E-1 B: Camp Mesa Mn-54 5.54E+1 B: Camp Mesa Co-57 1.17E+1 B: Camp Mesa Co-58 1.80E+1 B: Camp Mesa Co-60 7.82E+2 B: Camp Mesa Sr-89 1.82E+1 Q: SC Res. with Garden Sr-90 7.16E+2 Q: SC Res. with Garden Zr-95 1.93E+1 A: Camp Mesa Nb-95 7.68E+0 B. Camp Mesa Ru-1 03 1.09E+1 E: Deer Consumer/Hunter Te-129m 9.04E+0 A: Camp Mesa Cs-1 34 2.32E+2 B: Camp Mesa Cs-1 36 5.17E+0 B: Camp Mesa Cs-1 37 3.40E+2 B: Camp Mesa Ba-1 40 9.07E+0 A: Camp Mesa Ce-1 41 3.01 E+0 A: Camp Mesa Ce-1 44 5.68E+1 A: Camp Mesa I -131 6.77E+1 A: Camp Mesa I -132 8.36E-1 A: Camp Mesa I -133 1.60E+1 A: Camp Mesa I -134 2.29E-1 A: Camp Mesa I -135 3.40E+0 A: Camp Mesa UN-ID 3.02E+1 B: Camp Mesa These values to be used in manual calculations are the maximum Z-kRikWk for all locations based on the most restrictive age group.

S0 123-ODCM 2-31 Revision 0 02-27-07

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:

1. Determine the monthly total body and organ doses resulting from releases during the previous twelve months.

2. Projected dose = Previous 12 months' dose divided by 12 for the total body and each organ.

3.2 Gaseous Dose Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:

1. Determine the monthly gamma, beta and organ dose resulting from releases during the previous twelve months.

2. Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.

SO123-ODCM 3-1 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.3 TOTAL DOSE SPECIFICATION 3.3.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

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 Specifications 1.2.1 .a, 1.2.1 .b, 2.2.1 .a, 2.2.1 .b, 2.3.1 .a, or 2.3.1 .b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.3.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Specification 3.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCM.

SURVEILLANCE REQUIREMENTS

.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.

SO123-ODCM 3-2 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS

.3.4.1 Total Dose to Most Likely Member of the Public The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months. The transportation of radioactive material is excluded from the dose calculations.

The Annual Total Dose is determined monthly for maximum organ (gas & liquid), whole body (gas & liquid) and thyroid (gas & liquid) to verify that the Site total is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.

.1 Annual Total Organ Dose (DTOTQ)*.

12 2/3 (3-1)

[LD(OG)+ D11(OL)+ Dj- 3 DTT (0) = Z (OG)']

1=1 j=l where:

NOTE: DjH (OG) = 0 for bone

"*All to be summed over the most recent 12 months.

n Dil (OG)= K 7 Ci Ek Rik Wk (3-2) i=1 i= each isotope in specific organ category j= NIA, Unit 2 and Unit 3 1= months 1 - 12**

K = 3.1688E-2 year-pCi sec-Ci S0123-ODCM 3-3 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) n = number of isotopes in the specified organ category Cj = total particulate gas curies released for the month ZrikWk = SONGS controlling location factors (Tables 2-6, k 2-7 or 2-8).

DjI(OL) = liquid organ dose for the specified organ in mrem for the month. [equation (1-16)]

DjH-3(OG)*

. = gas organ dose from tritium in mrem for the month.

[equation (2-15)]

.2 Annual Total Whole Body Dose DToT(WB) 12 2/3 3 (3-3)

DTOT(WB) = Z " [Dj,(WBL)+ Dj- 3 (OG) + 0.9 Djj (y)] +D(DIRECT) 1=1 j=1 where:

j= NIA, Unit 2 and Unit 3

= months 1 - 12, to be summed over the most recent 12 months DJ(WBL) 1 = liquid whole body organ dose in mrem for the whole month. [equation (1-16)]

H-3 Dj1 (OG) = gas organ dose from tritium in mrem for the month.

[equation (2-1 5)]

Djl(y) gamma air dose in mrad for the month.

0.9 converts mrad to mrem.

[equation (2-16)]

n (34) 4 Z D(bkgd)i D (Direct) = Z max[D(beach)i] - P=1ln .0342 q=1 p = for all TLDs per quarter q = for Quarters 1-4 S0123-ODCM 3-4 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Annual Total Whole Body Dose DTOT(VVB) (Continued)

Direct Radiation The direct radiation levels are evaluated most recently using thulium doped TLDs. The TLDs are placed at a minimum of 30 locations around the site. The average dose measured by TLDs 5 to 50 miles from the site is used as background. These sites are subject to change.

The background is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through 58).

This value is the direct dose but must be prorated by the occupancy factor.

Example: Beach time (west boundary, seawall) of 300 hrs/yr, east and north boundaries of 20 hrs/yr, or 8 hrs/yr for the south boundary and west fence of parking lot 1 (top of bluff).

Reference:

E. M. Goldin Memorandum for File, "Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1, 1991.

.3 Annual Total Thyroid Dose DTOT..l 12 2/3 DTOT(T) = Z Z [Djl (OG) + Djl (OL)1 (3-5) 1=1 j=1 where:

j = NIA, Unit 2 and Unit 3 I = months 1 - 12, to be summed over the most recent 12 months Dj1 (OG) = thyroid organ dose from gaseous iodine for the month in mrem. [equation (2-20)]

Dj1 (OL) = liquid thyroid organ dose for the month in mrem.

[equation (1-16)]

SO123-ODCM 3-5 Revision 0 02-27-07

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 1.4.

APPLICABILITY: At all times ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENTS

.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.

.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change in pump operation that affects dilution flow has been completed, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

SO123-ODCM 4-1 Revision 0 02-27-07

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line - 2/3RT-7813 1 28

b. Steam Generator Blowdown Processing System (Neutralization Sump) 1 29 Full Flow Condensate Polisher Effluent Line - 2(3)RT-781 7

c. Turbine Plant Sumps, Auxiliary Building Sump 30 Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line - 2(3)RT-7821

d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT-6759 29 1

e. Steam Generator (E089) Blowdown Effluent Line - 2(3)RT-6753 29

f. Yard Drain Sump - RT-21 01 1 44

2. PROCESS FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 31

b. Steam Generator Blowdown Processing System (Neutralization Sump), 1 Full Flow Condensate Polisher Effluent-Line 31

c. Turbine Plant Sumps, Auxiliary Building Sump Component Cooling Water Sumps, Storage Tank Area Sumps 1 Effluent Line 31

d. Steam Generator (E088) Blowdown Bypass Effluent Line 1 31

e. Steam Generator (E089) Blowdown Bypass Effluent Line 1 31 1 31

f. Yard Drain Sump Effluent Line SO123-ODCM 4-2 Revision 0 02-27-07

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32

4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32

5. CONTINUOUS COMPOSITE SAMPLERS

a. Turbine Plant Sump, Auxiliary Building Sumps - 2(3) APC 5887 1 33

b. Blowdown Processing System Neutralization Sump - 2(3) APC 3772 1 33

c. Steam Generator (E088) Blowdown to Bypass, 1 Steam Generator (E088) Blowdown - 2(3) APC 4077 33

d. Steam Generator (E089) Blowdown to By pass, 1 Steam Generator (E089) Blowdown - 2(3) APC 4076 33 S0123-ODCM 4-3 Revision 0 02-27-07

TABLE 4-1 (Continued)

TABLE NOTATION Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 1.1.1 and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 29 - 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 gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram:

a. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131;

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 microcuries/gram DOSE EQUIVALENT 1-131; or C. Lock closed valve S2(3)1318MU577 and divert flow to T-064 for processing as liquid radwaste.

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, 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 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a limit of detection of at least 10-i microcuries/ml or lock closed valve S2(3)2419MU077 or S2(3)2419MU078 and divert flow to the radwaste sump for processing as liquid radwaste.

SO123-ODCM 4-4 Revision 0 02-27-07

TABLE 4-1 (Continued)

TABLE NOTATION 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 the process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change that affects process flow has been completed. Pump curves may be used to estimate process flow.

Loss of process flow instrument(s) results in the associated gross activity monitor becoming INOPERABLE. Perform the compensatory action for the inoperable gross activity monitor in addition to this compensatory action. [2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813]

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified OPERABLE by performing a channel check at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

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 grab samples are collected daily, and composited and analyzed weekly:

a. at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , not to exceed 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

b. at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for steam generator when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131.

ACTION 44 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, 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 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml).

SO123-ODCM 4-5 Revision 0 02-27-07

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL C3HANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT** CHECK CHECK CALIBRATION TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents Line - 2/3RT-7813 D P R(2) Q(1)

b. Steam Generator Blowdown Processing System

( Neutralization Sump), Full Flow Condensate olisher Effluent Line - 2(3)RT-7817 D M .R(2) Q(1)

c. Turbine Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps Storage Tank Area Sumps Effluent Line - 2(3)RT-7821 D M R(2) Q(1)

d. Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 D M R(2) Q(1)

e. Steam Generator (E089) Blowdown Bypass Effluent Line - 2(3)RT-6753 D M R(2) Q(1)

f. Yard Drain Sump Effluent Line - RT-2101 D M R(2) Q(1)

2. PROCESS FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(3) N/A R Q

b. Steam Generator Blowdown Processing System (Neutralization Sump), Full Flow Condensate Polisher Effluent Line D(3) N/A R Q

c. Turbine Plant Sump, Auxiliary Building Sump, Component Cooling Water Sumps, Storage Tank Area Sumps Effluent Line D(3) N/A R Q

d. Steam Generator (E088) Blowdown Bypass Effluent Line D(3) N/A R Q

e. Steam Generator (E089) Blowdown Bypass Effluent Line D(3) N/A R Q

f. Yard Drain Sump Effluent Line D(3) N/A R Q SO123-ODCM 4-6 Revision 0 02-27-07

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT** Cl--IECK CHECK CALIBRATION TEST

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM D N/A NIA(4) Q ANNUNCIATION)

4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ANNUNCIATION) D N/A N/A Q

5. CONTINUOUS COMPOSITE SAMPLERS

a. Turbine Plant Sump, Auxiliary building Sumps -

2(3) APC 5887 D(5) N/A R Q

b. Blowdown Processing System Neutralization Sump -

2(3) APC 3772 D(5) N/A R Q

c. Steam Generator (E088) Blowdown to Bypass, Steam Generator (E088) Blowdown - 2(3) APC 4077 D(5) N/A R Q

d. Steam Generator (E089) Blowdown to Bypass, Steam Generator (E089) Blowdown - 2(3) APC 4076 D(5) N/A R Q SO 123-ODCM 4-7 Revision 0 02-27-07

TABLE 4-2 (Continued)

TABLE NOTATION

- Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolationt, and Control Room alarm annunciation if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling period.

Down scale failure testing is bounded by administrative limitation on monitor setpoint which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not in the operate mode, procedures shall require that the channel be declared inoperable.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used.

(3) 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.

(4) The Data Acquisition System (DAS) software and hardware do not require Channel Calibration. The DAS software is quality affecting and controlled by the site Software Modification Request process under procedure SO123-V-4.71, Software Development and Maintenance. The DAS hardware is installed plant equipment and controlled by the site design change process utilizing procedure SO1 23-XXIX-2.1 0, Design Change Process or SO1 23-XXIV-1 0.1, Field Change Notice (FCN) and Field Interim Design Change Notice (FIDCN).

(5) CHANNEL CHECK shall consist of verifying compositor switch positions and installed counter setting, and comparing integrator readings to sample volume collected.

SO123-ODCM 4-8 Revision 0 02-27-07

4.0 EQUIPMENT 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with ODCM.

APPLICABILITY: At all times ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-4, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENTS

.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.

S0123-ODCM 4-9 Revision 0 02-27-07

TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2/3RT-7808, or 3RT-7865-1 1

35

b. Process Flow Rate Monitoring Device 1

36a

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor - 2(3)RT-7818, or 2(3)RT-7870-1 1 ** 37

b. Iodine Sampler 1 ** 40

c. Particulate Sampler 1 ** 40

d. Associated P&I Sample Flow Measuring Device 1 ** 36b

e. Process Flow Rate Monitoring Device 1(1) ** 36a

3. PLANT VENT STACK

a. Noble Gas Activity Monitor - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1(2)

37

b. Iodine Sampler 1(2)

40

c. Particulate Sampler 1(2)

40

d. Associated P&I Sample Flow Measuring Device 1(2)

36b

e. Process Flow Rate Monitoring Device - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1 36a

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1

38

b. Iodine Sampler 1

40

c. Particulate Sampler 1

40

d. Associated P&I Sample Flow Measuring Device 1

36b

e. Process Flow Rate Monitoring Device 1

36a SO123-ODCM 4-10 Revision 0 02-27-07

TABLE 4-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

5. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM 1 42 ANNUNCIATION)

6. SOUTH YARD FACILITY (SYF) WORK AREA SYFRU-7904

k

a. Iodine Sampler 1 40

b. Particulate Sampler 1 40

c. Associated P&I Sample Flow Measuring Device 1 "*

41 b

d. Process Flow Rate Monitoring Device 1 41 a

7. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT SYFRU-7905

a. Iodine Sampler 1 40

b. Particulate Sampler 1 40

c. Associated P&I Sample Flow Measuring Device 1

41 b

d. Process Flow Rate Monitoring Device 1

41a SO 123-ODCM 4-11 Revision 0 02-27-07

TABLE 4-3 (Continued)

TABLE NOTATION

At all times.

- MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) 2(3)RT-7818 is not equipped to monitor process flow. If another means of continuously monitoring process flow is not available, then comply with ACTION 36.

(2) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865-1 and 3RT-7865-1 are required to be operable when 2/3RT-7808 is inoperable.

ACTION 35 - 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. At least two independent samples of the tank's contents are analyzed, and

b. , At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

SO 123-ODCM 4-12 Revision 0 02-27-07

TABLE 4-3 (Continued)

TABLE NOTATION 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:

a. The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change that affects process flow has been completed. System design characteristics may be used to estimate process flow.

b. The particulate and iodine (P&I) sample flow rate is estimated or verified at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases.

ACTION 37 - 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 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 gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a. The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during times of building occupation. System design characteristics may be used to estimate flow.

b. The particulate and iodine (P&I) sample flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during times of building occupation.

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified operable by performing a channel check at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

S0123-ODCM 4-13 Revision 0 02-27-07

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2/3RT-7808, 3RT-7865-1 P P R(3) Q(1) *

b. Process Flow Rate Monitoring Device P NA R Q

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor -

2(3)RT-7818, 2(3)RT-7870-1 D M R(3) Q(2)

b. Iodine Sampler W NA NA NA **

c. Particulate Sampler W NA NA NA **

d. Associated Sample Flow Measuring Device D NA R Q

e. Process Flow Rate Monitoring Device (2(3)RT-7870-1) D NA R Q S0123-ODCM 4-14 Revision 0 02-27-07

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

3. PLANT VENT STACK

a. Noble Gas Activity Monitor- D M R(3) Q(2) 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 *

b. Iodine Sampler W NA NA NA

c. Particulate Sampler W NA NA NA

d. Associated Sample Flow Measuring Device D NA R Q

e. Process Flow Rate Monitoring Device D NA R Q

4. CONTAINMENT PURGE SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release -

2(3)RT-7828, 2(3)RT-7865-1 D P(4) R(3) Q(1) *

b. Iodine Sampler W NA NA NA

c. Particulate Sampler W NA NA NA

d. Process Flow Rate Monitoring Device D NA R Q

e. Associated Sample Flow Measuring Device D NA R Q SO123-ODCM 4-15 Revision 0 02-27-07

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

5. SOUTH YARD FACILITY (SYF) WORK AREA

a. Iodine Sampler W NA NA NA

b. Particulate Sampler W NA NA NA *

c. Process Flow Rate Monitoring Device D(5) NA R Q *

d. Associated Sample Flow Measuring Device D(5) NA R Q *

6. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT

a. Iodine Sampler W NA NA NA *

b. Particulate Sampler W NA NA NA

c. Process Flow Rate Monitoring Device D(6) NA R Q *

d. Associated Sample Flow Measuring Device D(6) NA R Q

NOTE: For 5 and 6, ECP 030100131 abandons the MGP radiation monitors and installs flow meters. This section applies to the flow meters and will take effect when ECP turnover is complete.

SO123-ODCM 4-16 Revision 0 02-27-07

TABLE 4-4 (Continued)

TABLE NOTATION

At all times.

- Modes 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.

Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolationt, and Control Room alarm annunciation if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling interval.

t The main containment purge isolation valves are required to be tested in Mode 5 prior to performing initial core alterations. Containment purge valves are not required to be tested for automatic isolation in the event of a mid-cycle outage.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable.

SO1 23-ODCM 4-17 Revision 0 02-27-07

TABLE 4-4 (Continued)

TABLE NOTATION (Continued)

(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 or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used.

(4) Prior to each release and at least once per month.

(5) Daily checks only required during times of building occupation.

(6) CHANNEL CHECK required by Health Physics daily for each day that the CO 2 Decontamination Unit is used.

SO123-ODCM 4-18 Revision 0 02-27-07

4.3 OPERABILITY OF RADIOACTIVE WASTE EQUIPMENT The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown in Figures 4-5 thru 4-7.

SO123-ODCM 4-19 Revision 0 02-27-07

FIGURE 4-5 SONGS RADIOACTIVE LIQUID WASTE TREATMENT SYSTEMS SO123-ODCM 4-20 Revision 1 02-29-08

FIGURE 4-6 SONGS RADIOACTIVE GASEOUS WASTE TREATMENT SYSTEMS

< -----ATMOSPHERE ------ >

a Sample Skid SYF7904 Sal s kid I SYF 7905 rad South Yard ity Facility rea Decon Area st Exhaust 2(3)RT-7865-1 can be aligned to either containment purge or the plant vent stack S0123-ODCM 4-21 Revision 0 02-27-07

FIGURE 4-7 SOLID WASTE HANDLING Spent Resin Particulate Process Filters Low Level Dry Active Waste I,

Protective Clothing LEGEND:

SRT: Spent Resin Tank MPHF: Multi Purpose Handling Facility IX:Ion Exchanger S0123-ODCM 4-22 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 5-1. The requirements are applicable at all times.

APPLICABILITY: At all times ACTION:

a. Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the reasonsfor not conducting the program as required and the plans for preventing a recu rrence.

b. Should the level of radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:

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

c. When radionuclides other than those in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specification(s) 1.2.1, 2.2.1 or 2.3.1, as appropriate.

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 (see Section 5.4).

S0123-ODCM 5-1 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)

ACTION: (Continued)

d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

SURVEILLANCE REQUIREMENTS The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Table 5-4 and Figures 5-1 through 5-5 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

S0 123-ODCM 5-2 Revision 0 02-27-07

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Samrle Locationsa Collection Frequencya TvDe and Freauencv of Analyses

1. AIRBORNE Samples from at least 5 locations Continuous operation of Radioiodine cartridge. Analyze at Radioiodine sampler with sample least once per 7 days for 1-131.

and 3 samples from offsite locations (in collection as required by Particulate sampler. Analyze for Particulates different sectors) of the highest dust loading, but at least gross beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculated annual average ground once per 7 days.d following filter change. Perform level D/Q. gamma isotopicb analysis on each sample when gross beta activity is 1 sample from the vicinity of a > 10 times the yearly mean of community having the highest control samples. Perform gamma calculated annual average ground- isotopic analysis on composite (by level D/Q. location) sample at least once per 92 days.

1 sample from a control location 15-30 km (10-20 miles) distant and in the least prevalent wind directionc

2. DIRECT At least 30 locations including an At least once per 92 days. Gamma dose. At least once per 92 RADIATIONe inner ring of stations in the general days.

area of the site boundary and an outer ring approximately in the 4 to 5 mile range from the site with a station in each sector of each ring. The balance of the stations is in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

Sa123-ODCM 5-3 Revision 0 02-27-07

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Collection Frequencya Type and Frequency of Analyses

3. WATERBORNE

a. Ocean 4 locations At least once per Gamma isotopic analysis of each month and composited' monthly sample. Tritium analysis quarterly of composite sample at least once per 92 days.

b. Drinkingg 2 locations Monthly at each Gamma isotopic and tritium location. analyses of each sample.

c. Sediment 4 locations At least once per Gamma isotopic analysis of each from 184 days. sample.

Shoreline

d. Ocean 5 locations At least once per Gamma isotopic analysis of each Bottom 184 days. sample.

Sediments S0123-ODCM 5-4 Revision 0 02-27-07

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Collection Frequencya Type and Frequency of Analyses

4. INGESTION

a. Nonmigratory 3 locations One sample in season, Gamma isotopic analysis on Marine or at least once per edible portions.

Animals 184 days if not seasonal. One sample of each of the follow-ing species:

1. Fish-2 adult species such as perch or sheephead.

2. Crustaceae-such as crab or lobster.

3. Mollusks-such as limpets, seahares or clams.

b. Local Crops 2 locations Representative Gamma isotopic analysis on edible vegetables, normally portions semiannually and 1-131 1 leafy and 1 fleshy analysis for leafy crops.

collected at harvest time. At least 2 vegetables collected semiannually from each location.

S0123-ODCM 5-5 Revision 0 02-27-07

TABLE 5-1 (Continued)

TABLE NOTATION

a. Sample locations are indicated on Figures 5-1 through 5-5.

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

c. 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 which provide valid background data may be substituted.

d. Canisters for the collection of radioiodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.

e. Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. 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 purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

g. No drinking water pathway exists at SONGS.

S0123-ODCM 5-6 Revision 0 02-27-07

TABLE 5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gases Marine Animals Local Crops Analysis (pCi/I) (pCi/m 3 ) (pCi/Kg, wet) (pCi/Kg, wet)

H-3 2 x 104(a)

Mn-54 1 x 103 3 x 104 Fe-59 4x 102 1x 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-95, Nb-95 4x 102 1-131 2 (b) 0.9 1 x 102 Cs-134 30 10 1 x 10 3 1 x 103 Cs-1 37 50 20 2 x 10 3 2 x 103 Ba-140, La-1 40 2 x 102 (a) 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.

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

S0123-ODCM 5-7 Revision 0 02-27-07

TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISc MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)'

Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pCi/I) (pCi/m 3) (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 x 10-2 H-3 2000(b)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 1-131 1 (d) 7 x 10-2 60 Cs-134 15 5 X 10-2 130 60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140, La-1 40 15 I'

SO123-ODCM 5-8 Revision 0 02-27-07

TABLE 5-3 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

sb LLD =4.66 E - V. 2.22 x 106 . Y - exp (-AAt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

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

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

2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

\ is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ).

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).

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

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

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

S0123-ODCM 5-9 Revision 0 02-27-07

TABLE 5-3 (Continued)

TABLE NOTATION

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

c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5-3, shall be identified and reported.

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

S0123-ODCM 5-10 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENSUS SPECIFICATION 5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times ACTION:

a. With the land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.3.1, pursuant to Technical Specification 5.7.1, identify the new locations in the next Annual Radioactive Effluent Release Report.

b. With the land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 5.1, add the new location within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, 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. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS

.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

SO123-ODCM 5-11 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that complies with Regulatory Guide 4.1 5.

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 Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE REQUIREMENTS A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).

SO123-ODCM 5-12 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

5.4.1 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the Radiological Assessment Branch Technical Position, Revision 1, November 1979 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.

A single submittal may be made for a multiple unit station, combining those sections that are common to all units at the station.

SO123-ODCM 5-13 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5. These sample locations are described in Table 5-4 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figures 5-1 through 5-5.

SO123-ODCM 5-14 Revision 0 02-27-07

Page 1 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION*

Direct Radiation 1 City of San Clemente (Former SDG&E Offices) 5.7 NW 2 Camp San Mateo (MCB, Camp Pendleton) 3.6 N 3 Camp San Onofre (MCB, Camp Pendleton) 2.8 NE 4 Camp Horno (MCB, Camp Pendleton) 4.4 E 6 Old El Camino Real (AKA Old Route 101) 3.0 ESE 8 Noncommissioned Officers' Beach Club 1.4 NW 10 Bluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.4** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bluff) 0.4** ESE 15 Southeast Site Boundary (Office Building) 0.1"* SSE 16 East Southeast Site Boundary 0.4** ESE 17 Deleted 18 Deleted 19 San Clemente Highlands 4.9 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 SDG&E Service Center Yard 8.1 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

- Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber SO 123-ODCM 5-15 Revision 2 02-27-09

Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION*

Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.6 NNW 33 Camp Talega (MCB, Camp Pendleton) 5.9 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.8 NNE 36 Range 208C (MCB, Camp Pendleton) 4.1 NE 38 San Onofre State Beach Park 3.4 SE 40 SCE Training Center - Mesa (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.3** E 44 Fallbrook Fire Station 17.7 E 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber S0123-ODCM 5-16 Revision 2 02-27-09

Page 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION*

Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.9 ESE 50 Oceanside Fire Station (CONTROL) 15.6 SE 53 San Diego County Operations Center 44.2 SE 54 Escondido Fire Station 31.8 ESE 55 San Onofre State Beach (Unit 1, West) 0.2** WNW 56 San Onofre State Beach (Unit 1, West) 0.2** W 57 San Onofre State Beach (Unit 2) 0.1"* SW 58 San Onofre State Beach (Unit 3) 0.1"* S 59 SONGS Meteorological Tower 0.3** WNW 60 Deleted 61 Mesa - East Boundary (Adjacent to PIC #4) 0.7 N 62 MCB - Camp Pendleton (Adjacent to PIC #5) 0.7 NNE 63 MCB - Camp Pendleton (Adjacent to PIC #6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.6 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8) 0.7 E 66 San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.4 ENE 73 South Yard Facility 0.4** ESE Deleted Deleted Deleted 74 Oceanside City Hall (Backup CONTROL) 15.6 SE 75 Gate 25 MCB 4.6 SE 76 El Camino Real Mobil Station 4.6 NW 77 Area 62 Heavy lift pad 4.2 N 78 Horno Canyon (AKA Sheep Valley) 4.4 ESE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

- Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

MCB - Marine Corps Base PIC - Pressurized Ion Chamber SO123-ODCM 5-17 Revision 2 02-27-09

Page 4 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Airborne 1 City of San Clemente (City Hall) 5.1 NW 7 AWS Roof 0.18** NW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa EOF 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E 14 Deleted -

15 Oceanside City Hall (CONTROL) 1 15.6 SE 16 San Luis Rey Substation (CONTROL)1 16.7 SE Soil Samplest I Camp San Onofre 2.8 NE 2 Old Route 101 - (East Southeast) 3.0 ESE 3 Basilone Road/l-5 Freeway Offramp 2.0 NW 5 Former Visitor's Center 0.4** NW 6 Deleted -

7 Prince of Peace Abbey (CONTROL) 15 SE Ocean Water A Station Discharge Outfall - Unit 1 0.6 SW B Outfall - Unit 2 1.5 SW C Outfall - Unit 3 1.2 SSW D Newport Beach (CONTROL) 30.0 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

- Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.

t Soil Samples are not required by Technical Specifications.

1 Air Sampler #16 will replace Air Sampler # 15 as the control air sampler during the week of December 26, 201 0.

SO 123-ODCM 5-18 Revision 3 02-26-10

Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

L.......

DIRECTION*

Drinking Water 4 Camp Pendleton Drinking Water Reservoir 2.0 NW 5 Oceanside City Hall (new CONTROL) 15.6 SE Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (Southeast) 0.6 SE 2 San Onofre Surfing Beach 0.8 WNW 3 San Onofre State Beach (Southeast) 3.5 SE 4 Newport Beach (North End) (CONTROL) 29.2 NW Local Crops 1 Deleted 2 Oceanside (CONTROL)** 15 to 25 SE to ESE 4 San Clemente Resident w/Garden 4.4 NW 6 SONGS Garden 0.4 NNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

- Control location should be in Section G or F, 15 to 25 miles from site. The control location will be selected based on sample availability. The exact location shall be noted in the Annual Radiological Environmental Operating Report.

S0123-ODCM 5-19 Revision 2 02-27-09

TABLE 5-4 Page 6 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles)

....... j DIRECTION*

Non-Migratory Marine Animals A Unit I Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL)** 15 to 150 WNW to NW Kelpt A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D DELETED E Salt Creek (CONTROL) 11 to 13 WNW to NW Ocean Bottom Sediments A DELETED B Unit I Outfall 0.8 SSW C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 17 to 19 NW F SONGS Upcoast 0.9 WSW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.

A location more distant from SONGS in the WNWto NW direction may be used as the CONTROL location.

t Kelp Samples are not required by Technical Specifications.

S0123-ODCM 5-20 Revision 2 02-27-09

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE*

PRESSURIZED ION CHAMBERS (Deqrees)* Meters miles DIRECTION/SECTOR*

S1 San Onofre Beach 2980 1060 0.7 WNW P S2 SONGS Former Evap. Pnd 313° 890 0.6 NW Q S3 Japanese Mesa 3400 1200 0.7 NNW R S4 MCB - Camp Pendleton 30 1130 0.7 N A S5 MCB - Camp Pendleton 19) 1080 0.7 NNE B S6 MCB - Camp Pendleton 460 970 0.6 NE C S7 MCB - Camp Pendleton 700 960 0.6 ENE D S8 MCB - Camp Pendleton 980 1130 0.7 E E S9 San Onofre State Beach 1210 920 0.6 ESE F Distance (meters/miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

S0 123-ODCM 5-21 Revision 2 02-27-09

TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.50 Limit Line Limit Sector* Direction 348.75 0 & 360 11.25 A N 11.25 22.5 33.75 B NNE 33.75 45.0 56.25 C NE 56.25 67.5 78.75 D ENE 78.75 90.0 101.25 E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75 H SSE 168.75 180.0 191.25 J S 191.25 202.5 213.75 K SSW 213.75 225.0 236.25 L SW 236.25 247.5 258.75 M WSW 258.75 270.0 281.25 N W 281.25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW

Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.

S0123-ODCM 5-22 Revision 0 02-27-07

Figure 5-1 Radiological Environmental Monitoring Sample Locations I Mile Radius S0123-ODCM 5-23 Revision 2 02-27-09

Figure 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius SO123-ODCM 5-24 Revision 2 02-27-09

Figure 5-3 Radiological Environmental Monitoring Sample Locations 5 Mile Radius SO123-ODCM 5-25 Revision 2 02-27-09

Figure 5-4 Radiological Environmental Monitoring Sample Locations - Orange County S0123-ODCM 5-26 Revision 2 02-27-09 I,

Figure 5-5 Radiological Environmental Monitoring Sample Locations - San Diego County SO123-ODCM 5-27 Revision 3 02-26-10

6.0 ADMINISTRATIVE 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications.

ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 6.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.

c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY.

S0123-ODCM 6-1 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

DOSE EQUIVALENT 1-131 6.1.5 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30, Tables titled Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activities.

FREQUENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.

GASEOUS RADWASTE TREATMENT SYSTEM 6.1.7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBERS OF THE PUBLIC 6.1.8 MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category complies with the requirements of 10CFR50 and shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions.

Supplemental workers and their dependents are included in this definition while they temporarily reside at Camp Mesa. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

S0123-ODCM 6-2 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

MODE 6.1.9 A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 6-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY 6.1.10 A system, subsystem, train, com ponent or device shall be OPERABLE or have OPERABIL[TY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

PURGE - PURGING 6.1.11 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

SITE BOUNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

S0123-ODCM 6-3 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

SOURCE CHECK 6.1.14 For Victoreen and NMC analog monitors, a SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. [2(3)RT-6753, 2(3)RT-6759, 2(3)RT-781 8A]

For Sorrento Electronics digital monitors a SOURCE CHECK shall be the verification of proper computer response to a check source request. [2(3)RT-7828, 2(3)RT-7865-1, 2(3)RT-7870-1]

For MGPI monitors a SOURCE CHECK shall be the verification of proper computer response to the continuous internal detector, monitor calibration and electrical checks.

[2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813, 2/3RT-7808, RT-2101]

SURVEILLANCE REQUIREMENT: MEETING SPECIFIED FREQUENCY 6.1.15 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

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

If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance.

This provision is not intended to be used repeatedly as a convenient means to extend surveillance intervals beyond those specified. Additionally, it does not apply to any Action Statements.

THERMAL POWER 6.1.16 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

VENTILATION EXHAUST TREATMENT SYSTEM 6.1.17 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

SO123-ODCM 6-4 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued)

VENTING 6.1.18 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process.

S0123-ODCM 6-5 Revision 0 02-27-07

TABLE 6-1 OPERATIONAL MODES REACTIVITY % OF RATED AVERAGE COOLANT OPERATION MODE CONDITION, (Kff} THERMAL POWER(a) TEMPERATURE (°F)

1. POWER OPERATION > 0.99 >5% NA

2. STARTUP > 0.99 < 5% NA

3. HOT STANDBY < 0.99 NA > 350°F

4. HOT SHUTDOWN *0.99 NA 3500F> Tvg >200 F

5. COLD SHUTDOWN (b) < 0.99 NA < 200°F

6. REFUELING (c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

SO123-ODCM 6-6 Revision 0 02-27-07

TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days R At least once per 18 months*

S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling Not to exceed 24 months Interval

A month is defined as a 31-day period.

SO123-ODCM 6-7 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, "Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

A single submittal may be made for a multiple unit staton. The submittal should combine those sections that are common to all units at the Station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SO123-ODCM 6-8 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 (Continued)

The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.1 09, Rev. 1.

The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

S0123-ODCM 6-9 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, & Gaseous)

Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):

1. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was performed pursuant to Quality Assurance Program Description (SCE-1-A), Subsection 17.2.20.3.1.i. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with applicable regulations;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable pursuant to Quality Assurance Program Description (SCE-1 -A), Subsection 17.2.20.3.1 .i.

2. Shall become effective upon review and acceptance pursuant to Quality Assurance Program Description (SCE-1 -A), Subsection 17.2.20.3.1 .i.

SO123-ODCM 6-10 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIQUID EFFLUENTS CONCENTRATION (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix 1,10 CFR 50, to an individual, and (2)the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

DOSE (1.2) 6.4.2 This specification is provided to implement the require-ments of Section II.A, III.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section I.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material -in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

S0123-ODCM Revision 0 6-11 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LIQUID WASTE TREATMENT (1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquideffluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section Il.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above back ground to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

SO123-ODCM Revision 0 6-12 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE - NOBLE GASES (2.2) 6.4.5 This specification is provided to implement the requirements of Sections lI.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the uides set forth in Section IV.A of Appendix I to assure at the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Com liance with 10 CFR Part 50, Appendix I,"Revision 1, October 1M97 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway 1-5, the residency time shall be considered negligible and hence the dose "0". The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.

DOSE - RADIOIODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix Ito assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the S0123-ODCM 6-13 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

SO123-ODCM 6-14 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

TOTAL DOSE (3.3) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

S0123-ODCM 6-15 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumenta-tion also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

MONITORING PROGRAM (5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories. 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 a posteriori (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, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

S0123-ODCM 6-16 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LAND USE CENSUS (5.2) 6.4.12 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a-garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,

1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and

2) a vegetation yield of 2 kg/square meter.

INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

SO123-ODCM 6-17 Revision 0 02-27-07

ML11119A234

Contents

Text

SUBJECT:

SUBJECT:

Reference:

Navigation menu

ML11119A234

Text

SUBJECT:

SUBJECT:

Reference:

Navigation menu

Search