Text

Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H
	ML031260483
Person / Time
Site:	Brunswick
Issue date:	04/28/2003
From:	Noll W; Carolina Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BSEP-03-0003
	Download: ML031260483 (233)
	v • d • e

INDEX 6.0 TOTAL DOSE (40CFR190 CONFORMANCE) ....................... ............... 6-2

6.1 INTRODUCTION

....................................... 6-2 6.2 GENERAL ...................................... . 6-2 6.3 CALCULATIONS OF TOTAL BODY DOSE ............................... 6-3 6.3.1 Direct Radiation ...................................... 6-3 6.3.2 Inhalation Dose ...................................... 6-3 6.3.3 Ingestion Pathway ...................................... 6-3 6.3.4 Other Uranium Fuel Cycle Sources ...................................... 6-3 6.4 THYROID DOSE ....................................... 6-4 ODCM (BSEP) 6-1 Rev. 25

6.0 TOTAL DOSE (40CFR190 CONFORMANCE)

6.1 INTRODUCTION

Compliance with 40CFR190 as prescribed by ODCM Specification 7.3.14 is to be demonstrated only when one or more of ODCM Specifications 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a, 7.3.9.b is exceeded by a factor of 2. Once this occurs, the Company has 30 days to submit this report.

6.2 GENERAL To perform the calculations to evaluate conformance with 40CFR1 90, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates of dose to a MEMBER OF THE PUBLIC (i.e.,

calculations for compliance with 1OCR50, Appendix I). To accomplish this, the following calculational rules are used:

6.2.1 Doses to a MEMBER OF THE PUBLIC via the liquid release pathway are considered to be <1 mrem/yr. (Ref: NUREG 0543).

6.2.2 Doses to a MEMBER OF THE PUBLIC due to a milk pathway will be evaluated only as can be shown to exist. Otherwise, doses via this pathway will be estimated as <1 mremlyr.

6.2.3 Environmental sampling data which demonstrates that no pathway exists may be used to delete a pathway to man from a calculation.

6.2.4 To sum numbersiepresented as "less than" (<), use the value of the largest number in the group.

(i.e., <5+<1 +<1 +<3=5) 6.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector.

6.2.6 The calculational locations for a MEMBER OF THE PUBLIC will only be at residences or places of employment.

NOTE: Additional assumptions may be used to provide situation-specific parameters, provided they are documented along with their concomitant bases.

ODCM (BSEP) 6-2 Rev. 25

6.3 CALCULATIONS OF TOTAL BODY DOSE Estimates will be made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist at a location are considered.

6.3.1 Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be determined by:

1. Determining the direct radiation dose at the plant boundary in each sector, DB. -

2. Extrapolating that dose to the calculational location as follows:

DD DB,0(1.49E + 6)

DLIO (X2, 0)

D,0 = dose at calculational location in sector 0 1.49E + 6 = square of mean distance to the site boundary (1220 m).

XL,0 = distance to calculational locations in sector 0 in meters.

6.3.2 Inhalation Dose The inhalation dose will be determined at the calculational locations for each age class'at risk according to the methods outlined in Section 3.3 of this manual.

6.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as

<1 mrem/yr.

6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as <1 mrem/yr.

ODCM (BSEP) 6-3 Rev. 25

6.4 THYROID DOSE The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if existing). The calculational methods will be those identified in Section 3.3 of this manual.

6.4.1 Dose projections can incorporate planned plant operations such as power reduction or outages for the projected period.

me ODCM (BSEP) 6-4 Rev. 25

SECTION 7.0 RADIOACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 Brunswick Units 1 and 2 7-0 Rev. 25

INDEX 7.1.0 USE AND APPLICATION . , ............................ 7.1.1-1 7.1.1 Definitions .7.1.1-1 7.1.2 Logical Connectors ..................... 7.1.2-1 7.1.3 Completion Times .7.1.3-1 7.1.4 Frequency ..................... 7.1.4-1 7.2.0 Not used ............. 7.2.0-1 7.3 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS 7.3.0 Offsite Dose Calculation Manual Specification (ODCMS)

Applicability ...................................... 7.3.0-1 7.3.0 Test Requirement (TR) Applicability ...................................... 7.3.0-3 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation ........................ 7.3.1-1 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation ................... 7.3.2-1 7.3.3 Concentration-Liquid Effluents ......................... ,.,,,.,.7.3.3-1 7.3.4 Dose-Liquid Effluents ......................... ,..... 7.3.4-1 7.3.5 Liquid Radwaste Treatment System ......................... 7.3.5-1 7.3.6 Liquid Holdup Tanks ........................ 7.3.6-1 7.3.7 Dose Rate-Gaseous Effluents ........................ 7.3.7-1 7.3.8 Dose-Noble Gases ........................ 7.3.8-1 7.3.9 Dose1-131,1-133, Tritium, and Radionuclides in Particulate Form .. ,,. .... 7.3.9-1 7.3.10 Gaseous Radwaste Treatment System ................................... ,.,,,,,,.7.3.10-1 7.3.11 Ventilation Exhaust Treatment System .. 7.3.11-1 Explosive Gas Mixt;?*e_..7.3.12-1 7.3.12 7.3.12~~~~~~~~

EpoieGsMxu..................................................,..,.................7.3.1 7.3.13 Drywell Venting or Purging .7.3.13-1 7.3.14 Total Dose (40 CFR Part 190) ..................... ,.,.,,,,.,.,.7.3.14-1 7.3.15 Radiological Environmental Monitoring Program.., 7.3.15-1 7.3.16 Land Use Census .............................. 7.3.16-1 7.3.17 Interlaboratory Comparison Program ........................... ,.,.,,,,.,,,,.,,,7.3.17-1 7.4.0 REPORTING REQUIREMENTS .7.4.0-1 7.4.1 Annual Radiological Environmental Operating Report .......................... 7.4.0-1 7.4.2 Radioactive Effluent Release Report .................................................... 7.4.0-1 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS .7.5.0-1 BASES B 7.3.0 Offsite Dose Calculation Manual Specification (ODCMS)

Applicability ...... B 7.3.0-1 (continued)

Brunswick Units 1 and 2 7-i Rev. 25

INDEX (continued)

B 7.3.0 Test Requirement (TR) Applicability ......................................... B 7.3.0-6 B 7.3.1 Radioactive Liquid Effluent Monitoring Instrumentation ..................... B 7.3.1-1 B 7.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation ................ B 7.3.2-1 B 7.3.3 Concentration-Liquid Effluents ......................................... B 7.3.3-1 B 7.3.4 Dose-Liquid Effluents ......................................... B 7.3.4-1 B 7.3.5 Liquid Radwaste Treatment System ........................ B 7.3.5-1 B 7.3.6 Liquid Holdup Tanks ............. B 7.3.6-1 B 7.3.7 Dose Rate-Gaseous Effluents ..................... B 7.3.7-1 B 7.3.8 Dose Rate-Noble Gases ................. B 7.3.8-1 B 7.3.9 Dose 1-131,1-133, Tritium, and Radionuclides in Particulate Form ..... B 7.3.9-1 B 7.3.10 Gaseous Radwaste Treatment System ........................... ....... B 7.3.10-1 B 7.3.11 Ventilation Exhaust Treatment System ................................. B 7.3.11-1 B 7.3.12 Explosive Gas Mixture .................................. B 7.3.12-1 B 7.3.13 Drywell Venting or Purging ................................. B 7.3.13-1 B 7.3.14 Total Dose (40 CFR Part 190) ................................. B 7.3.14-1 B 7.3.15 Radiological Environmental Monitoring Program ............................. B 7.3.15-1 B7.3.16 Land Use Census ................................. B7.3.16-1 B 7.3.17 Interlaboratory Comparison Program ................................. B 7.3.17-1 Brunswick Units 1 and 2 7-ii Rev. 25

LIST OF TABLES Table 7.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation ........................ 7.3.1-7 Table 7.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation ............ ....... 7.3.2-8 Table 7.3.3-1 Radioactive Liquid Waste Sampling and Analysis Program ................. 7.3.3-3 Table 7.3.3-2 Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels................................................................................................... 7.3.3-6 Table 7.3.7-1 Radioactive Gaseous Waste Sampling and Analysis Program ............. 7.3.7-3 Table 7.3.15-1 Radiological Environmental Monitoring Program ................................ 7.3.15-7 Table 7.3.15-2 Limits for the Level of Radioactivity in Environmental Samples ........ 7.3.15-12 Table 7.3.15-3 Detection Capabilities for Environmental Sample Analysis ............... 7.3.15-13 Brunswick Units 1 and 2 7-iii Rev. 25

LIST OF FIGURES Figure 7.1.1-1 SITE BOUNDARY .......................... 7.1.1-5 Brunswick Units 1 and 2 7-iv Rev. 25

Definitions 7.1.1 7.1.0 USE AND APPLICATION ODCMS 7.1.1 Definitions r------------------------------------------------------------I NOTE I The defined terms of this section appear in capitalized type and are applicable throughout theseI Offsite DoseI-------

Calculation Manual Specifications and Bases.

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

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

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

(continued)

Brunswick Units 1 and 2 7.1 .1-1 Rev. 25

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

GASEOUS RADWASTE A GASEOUS RADWASTE TREATMENT SYSTEM is any system TREATMENT 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.

LIQUID RADWASTE A LIQUID RADWASTE TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to collect, treat and process radioactive liquid waste streams for reuse or for controlled discharge from the restricted area in compliance with established regulatory requirements.

MEMBER(S) OF MEMBER(S) OF THE PUBLIC shall include all persons who THE PUBLIC are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

MODE A MQDE shall be as required by Technical Specifications.

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

PURGE-PURGING 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 containment.

(continued)

Brunswick Units 1 and 2 7.1.1 -2 Rev. 25

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2923 MWt for Unit I and 2558 MWt for Unit 2.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased nor otherwise controlled by the licensee, as defined by Figure 7.1.1-1. For the purpose of effluent release calculations, the boundary for atmospheric releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.

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

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purpose of protection of individuals from exposure to radiation and radioactive materials or any area within-the SITE BOUNDARY used for residential quarters or industhal, commercial, institutional or recreational purposes.

VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM is any TREATMENT SYSTEM 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 adsorbers 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.

(continued)

Brunswick Units 1 and 2 7.1 .1-3 Rev. 26 l

Definitions 7.1.1 ODCMS 7.1.1 Definitions (continued)

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

Brunswick Units 1 and 2 7.1 .1-4 Rev. 25

Definitions 7.1.1

\e-r4) t-'

..... CP FEA RIE L0 \~ <PROPERTY 4 BOUNDARY SITE AREA BOUNDARY I

'EXCLUSION AREA J BOUNDARY Figure 7.1.1-1 (page 1 of 1)

SITE BOUNDARY Brunswick Units 1 and 2 7.1 .1-5 Rev. 25

Logical Connectors 7.1.2 7.1.0 USE AND APPLICATION ODCMS 7.1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Offsite Dose Calculation Manual Specifications (ODCMS) to discriminate between, and yet connect, discrete Conditions, Required Compensatory Measures, Completion Times, Tests, and Frequencies. The only logical connectors that appear in ODCMS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

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

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

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Brunswick Units 1 and 2 7.1 .2-1 Rev. 25

Logical Connectors 7.1.2 ODCMS 7.1.2 Logical Connectors (continued)

EXAMPLES EXAMPLE 7.1.2-1 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Verify ...

met.

AND A.2 Restore...

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

(continued)

Brunswick Units 1 and 2 7.1 .2-2 Rev. 25

Logical Connectors 7.1.2 ODCMS 7.1.2 Logical Connectors (continued)

EXAMPLES EXAMPLE 7.1.2-2 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. ODCMS not A.1 Trip ...

met.

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Align...

This example represents a more complicated use of logical connectors.

Required Compensatory Measures A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Compensatory Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Compensatory Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Brunswick Units 1 and 2 7.1 .2-3 Rev. 25

Completion Times 7.1.3 7.1.0 USE AND APPLICATION ODCMS 7.1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Offsite Dose Calculation Manual Specifications (ODCMS) specify minimum requirements for unit systems or variables. The COMPENSATORY MEASURES associated with an ODCMS state Conditions that typically describe the ways in which the requirements of the ODCMS can fail to be met. Specified with each stated Condition are Required Compensatory Measure(s) and Completion Times(s).

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

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

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

(continued)

Brunswick Units 1 and 2 7.1 .3-1 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

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

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

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

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

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

The above Completion Time extension does not apply to a Completion Time with a modified 'time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Compensatory Measures versus the time of Condition entry) or as a time modified by the phrase "from discovery. . ." Example 7.1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 7.1.3-3 may not be extended.

(continued)

Brunswick Units 1 and 2 7.1 .3-2 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

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

EXAMPLE 7.1.3-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE B. Required 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

Condition B has two Required Compensatory Measures. Each Required Compensatory Measure has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

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

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

(continued)

Brunswick Units 1 and 2 7.1 .3-3 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-2 (continued)

COMPENSATORY MEASURES .

CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

When a pump is declared inoperable, Condition A is entered. If the pump is not restored tJ^QPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Compensatory Measures B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Compensatory Measures of Condition B may be terminated.

(continued)

Brunswick Units 1 and 2 7.1 .3-4 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-3 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One A.1 Restore Function X 7 days Function X subsystem to subsystem OPERABLE status. AND inoperable.

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

. 10 days from discovery of failure to meet the ODCMS C. One C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X subsystem to subsystem OPERABLE status.

inoperable.

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

inoperable.

(continued)

Brunswick Units 1 and 2 7.1 .3-5 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-3 (continued)

(continued)

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

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

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the ODCMS was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely withoyt ever restoring systems to meet the ODCMS. The separate Completion Time modified by the phrase "from discovery of failure to meet the ODCMS" is designed to prevent indefinite continued operation while not meeting the ODCMS. This Completion Time allows for an exception to the normal "time zero' for beginning the Completion Time %clock". In this instance, the Completion Time 'time zero' is specified as commencing at the time the ODCMS was initially not met, instead of at the time the associated Condition was entered.

(continued)

Brunswick Units 1 and 2 7.1 .3-6 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-4 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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

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

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

(continued)

Brunswick Units 1 and 2 7.1 .3-7 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-5 (continued)

COMPENSATORY MEASURES r---------------------------------------------I NOTE I ISeparate Condition entry

_ _ _ _ _ _ _ _ __is allowed for each

_ _ _ _ _inoperable

_ _ _ valve.

CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not me The Note above the COMPENSATORY MEASURES Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the COMPENSATORY MEASURES Table.

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

(continued)

Brunswick Units 1 and 2 7.1 .3-8 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-5 (continued)

(continued)

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

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

EXAMPLE 7.1.3-6 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY COMPLETION MEASURE TIME A. One channel A.1 Perform TR 7.3.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

. OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to

< 50% RTP.

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

(continued)

Brunswick Units 1 and 2 7.1 .3-9 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-6 (continued)

(continued)

Entry into Condition A offers a choice between Required Compensatory Measure A.1 or A.2. Required Compensatory Measure A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per TR 7.3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Compensatory Measure A.1 begins when Condition A is entered and the initial performance of Required Compensatory Measure A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Compensatory Measure A.1 is followed and the Required Compensatory Measure is not met within the Completion Time (plus the extension allowed by TR 7.3.0.2), Condition B is entered. If Required Compensatory Measure A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

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

(continued)

Brunswick Units 1 and 2 7.1 .3-10 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-7 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPLETION COMPENSATORY TIME MEASURE A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

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

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensa ory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

Required Compensatory Measure A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter' interval begins upon performance of Required Compensatory Measure A.1.

If after Condition A is entered, Required Compensatory Measure A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by TR 7.3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues (continued)

Brunswick Units 1 and 2 7.1 .3-1 1 Rev. 25

Completion Times 7.1.3 ODCMS 7.1.3 Completion Times (continued)

EXAMPLES EXAMPLE 7.1.3-7 (continued)

(continued) from the time Condition A was initially entered. If Required Compensatory Measure A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Compensatory Measure A.2 has not expired.

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

Brunswick Units 1 and 2 7.1 .3-1 2 Rev. 25

Frequency 7.1.4 7.1.0 USE AND APPLICATION ODCMS 7.1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Test Requirement (TR) of the Offsite Dose Calculation Manual has a specified Frequency in which the Test must be met in order to meet the associated Offsite Dose Calculation Manual Specification (ODCMS). An understanding of the correct application of the specified Frequency is necessary for compliance with the TR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 7.3.0, Test Requirement (TR)

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

Sometimes special situations dictate when the requirements of a Test are to be met. They are "otherwise stated" conditions allowed by TR 7.3.0.1.

They may be stated as clarifying Notes in the Test, as part of the Test, or both. Example 7.1.4-4 discusses these special situations.

Situations where a Test could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated ODCMS is within its Applicability, represent potential TR 7.3.0.4 conflicts. To avoid these conflicts, the TR (i.e., the Test or the Frequency) is stated such that it is only 'required' when it can be and should be performed. With a TR satisfied, TR 7.3.0.4 imposes no restriction.

The use of "met or 'performed" in these instances conveys specific meanings. A Test is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Test, even without a Test specifically being 'performed," constitutes a Test not "met."

'Performance" refers only to the requirement to specifically determine the (continued)

Brunswick Units 1 and 2 7.1 .4-1 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

DESCRIPTION ability to meet the acceptance criteria. TR 7.3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied:

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

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

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

EXAMPLE 7.1.4-1 TEST REQUIREMENTS TEST FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 7.1.4-1 contains the type of TR most often encountered in the ODCMS. The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Test must be performed at least one time. Performance of the Test initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by TR 7.3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the TR is not required to be met per TR 7.3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the ODCMS). If the interval specified by TR 7.3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the ODCMS, and the performance of the Test is not otherwise modified (refer to Examples 7.1.4-3 and 7.1.4-4), then TR 7.3.0.3 becomes applicable.

(continued)

Brunswick Units 1 and 2 7.1 .4-2 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-1 (continued)

(continued)

If the interval as specified by TR 7.3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the ODCMS for which performance of the TR is required, the Test must be performed within the Frequency requirements of TR 7.3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of TR 7.3.0.4.

EXAMPLE 7.1.4-2 TEST REQUIREMENTS .

TEST FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 7.1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 7.1.4-1. The logical connector 'AND' indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to> 25% RTP, the Test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of once' indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by TR 7.3.0.2.

(continued)

Brunswick Units 1 and 2 7.1 .4-3 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-2 (continued)

(continued)

'Thereafter" indicates future performances must be established per TR 7.3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 7.1.4-3 TEST REQUIREMENTS TEST FREQUENCY I NOTE I

'Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after, I2 25% RTP.

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

As the Note modifies the required performance of the Test, it is construed to be part of the 'specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches Ž 25% RTP to perform the Test. The Test is still considered to be within the 'specified Frequency." Therefore, if the Test were not performed within the 7 day interval (plus the extension allowed by TR 7.3.0.2), but operation was < 25% RTP, it would not constitute a failure of the TR or failure to meet the ODCMS. Also, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power 2 25% RTP.

(continued)

Brunswick Units 1 and 2 7.1 .4-4 Rev. 25

Frequency 7.1.4 ODCMS 7.1.4 Frequency (continued)

EXAMPLES EXAMPLE 7.1.4-3 (continued)

(continued)

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Test. If the Test were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Test within the specified Frequency, and the provisions of TR 7.3.0.3 would apply.

EXAMPLE 7.1.4-4 TEST REQUIREMENTS TEST FREQUENCY r------------------------------I NOTE Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 7.1.4-4 specifies that the requirements of this Test do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Test continues at all times, as described in Example 7.1.4-1. However, the Note constitutes an otherwise stated' exception to the Applicability of this Test. Therefore, if the Test were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by TR 7.3.0.2) interval, but the unit was not in MODE 1, there would be no failure of the TR nor failure to meet the ODCMS. Therefore, no violation of TR 7.3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1.

Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), TR 7.3.0.4 would require satisfying the TR.

Brunswick Units 1 and 2 7.1 .4-5 Rev. 25

7.2.0 Not used.

Brunswick Units 1 and 2 7.2.0-1 Rev. 25

ODOMS Applicability ODCMS Applicability 7.3.0 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS) APPLICABILITY ODCMS 7.3.0.1 ODCMSs shall be met during the MODES or other specified conditions in the Applicability, except as provided in ODCMS 7.3.0.2.

ODCMS 7.3.0.2 Upon discovery of a failure to meet an ODCMS, the required Compensatory Measures of the associated Conditions shall be met, except as provided in ODCMS 7.3.0.5.

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

ODCMS 7.3.0.3 Not used.

ODCMS 7.3.0.4 When an ODCMS is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated COMPENSATORY MEASURES to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This ODCMS shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES, or that are part of a shutdown of the unit.

Exceptions to this ODCMS are stated in the individual ODCMSs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated COMPENSATORY MEASURES to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.

ODCMS 7.3.0.5 Equipment removed from service or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to ODCMS 7.3.0.2 for the system returned to service under administrative control to perform the required testing.

(continued)

Brunswick Units 1 and 2 7.3.0-1 Rev. 25

ODCMS Applicability 7.3.0 7.3.0 ODCMS APPLICABILITY (continued)

ODCMS 7.3.0.6 ODCMSs and associated COMPENSATORY MEASURES shall apply to both units except as follows:

a. Whenever the ODCMS refers to systems or components which are not shared by both units, the ODCMS and associated Applicability and COMPENSATORY MEASURES shall apply to each unit individually (e.g., in the event of an inoperability in a non-shared system, the appropriate COMPENSATORY MEASURES will apply only to the unit with the inoperable system);

b. Whenever the ODCMS only applies to one unit, this will be identified in the Applicability of the ODCMS; and

c. Whenever certain portions of the ODCMS, Applicability, or COMPENSATORY MEASURES contain operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.

Brunswick Units 1 and 2 7.3.0-2 Rev. 25

TR Applicability 7.3.0 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY TR 7.3.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability for individual ODCMSs, unless otherwise stated in the TR.

Failure to meet a Test whether such failure is experienced during the performance of the Test or between performances of the Test, shall be failure to meet the ODCMS. Failure to perform a Test within the specified Frequency shall be failure to meet the TRMS except as provided in TR 7.3.0.3. Tests do not have to be performed on inoperable equipment or variables outside specified limits.

TR 7.3.0.2 The specified Frequency for each TR is met if the Test 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,0 the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this ODCMS are stated in the individual ODCMSs.

TR 7.3.0.3 If it is discovered that a Test was not performed within its specified Frequency, then compliance with the requirement to declare the ODCMS not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Test.

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

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

(continued}

Brunswick Units 1 and 2 7.3.0-3 Rev. 25

TR Applicability 7.3.0 7.3.0 TR APPLICABILITY (continued)

TR 7.3.0.4 Entry into a MODE or other specified condition in the Applicability of an ODCMS shall not be made unless the ODCMS's Tests have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES or that are part of a shutdown of the unit.

TR 7.3.0.5 TRs shall apply to both units (e.g., a single Test performed at the specified Frequency will satisfy the TR for both units) except as follows:

a. Whenever the ODCMS refers to systems or components which are not shared by both units, the associated TR shall apply to each unit individually (e.g., individual tests must be performed on each of the two units' non-shared systems or components; a single Test on a non-shared system of one unit performed at the specified Frequency will not satisfy the TR for the non-shared system of the other unit);

b. Whenever a TR only applies to one unit, this will be identified by a note to the TR; and

c. Whenever certain portions of the TRs, contain test parameters, acceptance criteria, or frequencies which are different for each unit, this will be identified in parentheses, notes, or the body of the requirement.

Brunswick Units 1 and 2 7.3.0-4 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.1 The radioactive liquid effluent monitoring instrumentation channels in Table 7.3.1-1 shall be OPERABLE.

APPLICABILITY: In accordance with Table 7.3.1-1.

COMPENSATORY MEASURES r -------------------------------------------------------------

NOTE I 1Separate Condition entry is allowed for each required channel.-

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A.1 Enter the Condition Immediately liquid effluent monitoring referenced in -

instrumentation channels Table 7.3.1-1 for the inoperable. channel.

B. As required by Required B.1 Perform TR 7.3.3.1 on two Prior to release Compensatory independent samples of through the liquid Measure A.1 and the batch to be released. radwaste effluent referenced in line Table 7.3.1-1. AND B.2 Verify the associated Prior to release release rate calculations through the liquid and the discharge valve radwaste effluent lineup using two qualified line members of the technical staff.

AND B.3 Restore the channel to 30 days OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3. 1-1 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required C.1 Estimate the flow rate Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Compensatory through the associated during releases Measure A.1 and pathway using pump through the referenced in performance curves or associated line Table 7.3.1-1. tank level indicators.

AND C.2 Restore the channel to 30 days OPERABLE status.

D. As required by Required D.1 Collect and analyze a grab Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory sample for gross Measure A.1 and radioactivity (beta or referenced in gamma) of the associated Table 7.3.1-1. effluent. The LLD shall be

< 1.0 E-7 pCVgm.

AND D.2 Restore the channel to 30 days OPERABLE status.

E. As required by Required E.1 Collect and analyze a grab Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Compensatory sample for principal Measure A.1 and gamma emitters per referenced in Table 7.3.3-1.

Table 7.3.1-1.

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

(continued)

Brunswick Units 1 and 2 7.3.1-2 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME F. As required by Required F.1 Estimate the flow rate Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Compensatory through the associated Measure A.1 and pathway using the V-notch referenced in weir or another acceptable Table 7.3.1-1. method.

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

G. As required by Required G.1 Estimate the tank liquid Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Compensatory level. during all liquid Measure A.1 and additions and referenced in deletions to and Table 7.3.1-1. AND from the tank G.2 Restore the channel to 30 days OPERABLE status.

H. Required Compensatory H.1 Suspend effluent releases Immediately Measure B.1, B.2, C.1, via the associated D.1, E.1, F.1, or G.1 and pathway.

associated Completion Time not met. AND H.2

, NOTE Only applicable for Function 6.

Suspend liquid additions Immediately to the Condensate Storage Tank.

(continued)

Brunswick Units 1 and 2 7.3. 1-3 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME

1. Required Compensatory 1.1 Prepare and submit, in the Upon submittal of Measure B.3, C.2, D.2, Radioactive Effluent current calendar E.2, F.2, or G.2 and Release Report, the year Radioactive associated Completion reason the channel was Effluent Release Time not met. not restored to Report OPERABLE status within 30 days.

TEST REQUIREMENTS r -------------------------------------------------------------

I NOTE

Refer to Table 7.3.1-1 to determine which TRs apply for each Radioactive Liquid Effluent Monitoring Instrumentation Function.

TEST FREQUENCY TR 7.3.1.1 NOTE For Function 6, only required to be met during liquid additions to the tank.

Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 7.3.1.2 NOTE Only required to be met during continuous, periodic, or batch releases.

Verify indication of flow. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Brunswick Units 1 and 2 7.3.1 -4 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.1.3 Perform SOURCE CHECK. 31 days TR 7.3.1.4 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of automatic isolation of the pathway and control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Circuit failure.

c. Downscale failure.

d. Instrument controls not set in "operate" mode.

TR 7.3.1.5 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.1.6 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Circuit failure.

c. Downscale failure.

d. Instrument controls not set in "operate" mode.

(continued)

Brunswick Units 1 and 2 7.3.1-5 Rev. 26 l

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.1.7

-7 TR r------------------------------------

NOTE For Functions 1 and 3, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall be used.

Perform CHANNEL CALIBRATION. 24 months Brunswick Units 1 and 2 7.3. 1-6 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation 7.3.1 Table 7.3.1-1 (page 1 of 1)

Radioactive Liquid Effluent Monitoring Instrumentation FUNCTION(a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A1 1 Liquid Radwaste Radioactivity At all times 1 B TR 7.3.1.1 (c)

Effluent Monitor(b) TR 7.3.1.3 TR 7.3.1.4 TR 7.3.1.7

2. Liquid Radwaste Effluent Flow At all times 1 C TR 7.3.1.2 NA Measurement Device TR 7.3.1.5 TR 7.3.1.7

3. Main Service Water System At all times 1 D TR 7.3.1.1 (c)

Effluent Radioactivity Monitor TR 7.3.1.3 TR 7.3.1.6 TR 7.3.1.7

4. Stabilization Pond Effluent (d) 1 E TR 7.3.1.1 NA(e)

Composite Sampler TR 7.3.1.5 TR 7.3.1.7

5. Stabilization Pond Effluent (d) 1 F TR 7.3.1.1 NA Flow Measurement Device TR 7.3.1.5 TR 7.3.1.7

6. Condensate Storage Tank At all times 1 G TR 7.3.1.1 NA(M)

Level Indicating Device TR 7.3.1.5 TR 7.3.1.7 (a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Provides alarm and automatic termination of release.

(c) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.3, "Concentration-Liquid Effluents,' are not exceeded.

(d) At all times other than when the line is valved out and locked.

(e) Flow Totalizer 2-DST-FOIS-5026 provides a trip signal to the composite sampler that will initiate sampling.

(f) 1(2) CO-LIT-1 160 provides local level indication and also provides a signal to 1(2) CO-LI-11 60A and 1(2) CO-LI-1160B.

Brunswick Units 1 and 2 7.3.1 -7 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ODCMS 7.3.2 The radioactive gaseous effluent monitoring instrumentation channels in Table 7.3.2-1 shall be OPERABLE.

APPLICABILITY: In accordance with Table 7.3.2-1.

COMPENSATORY MEASURES r -------------------------------------------------------------

aNOTE I-Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One or more radioactive A.1 Enter the Condition Immediately gaseous effluent referenced in monitoring instrumentation Table 7.3.2-1 for the channels inoperable. channel.

B. As required by Required B.1 Take a grab sample at the Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory associated sample Measure A.1 and location.

referenced in Table 7.3.2-1. AND B.2 Analyze the grab sample 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after required by Required completion of Compensatory Required Measure B.1 for gross Compensatory noble gas activity. Measure B.1 AND B.3 Restore the channel to 30 days OPERABLE status.

(continued}

Brunswick Units 1 and 2 7.3.2-1 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. As required by Required C.1.1 Initiate actions to establish Immediately Compensatory auxiliary sampling Measure A.1 and equipment to continuously referenced in collect samples from the Table 7.3.2-1. associated effluent release pathway as required by Table 7.3.7-1.

OR C.1.2 NOTE Only applicable for ODCM test requirements, sample analysis, or system purging. Reference ODCMS 7.3.0.5 for post maintenance test requirements.

Initiate continuous sample 45 minutes collection from associated release pathway as required by Table 7.3.7-1 with auxiliary sampling equipment.

AND C.2 Restore the channel to 30 days OPERABLE status.

(continued)

Brunswick Units 1 and 2 7.3.2-2 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (c ontinued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D. As required by Required D.1 Estimate the flow rate Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Compensatory through the associated Measure A.1 and pathway.

referenced in Table 7.3.2-1. AND D.2 Restore the channel to 30 days OPERABLE status.

E. Required Compensatory E.1 Suspend effluent releases Immediately Measure B.1, B.2, C.1.1, via the associated C.1.2, and D.1 and pathway.

associated Completion Time not met.

(continued)

Brunswick Units 1 and 2 7.3.2-3 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME F. As required by Required % NOTE I Compensatory Required Compensatory Measure A.1 and Measures F.1 and F.2 are only I referenced in applicable if two channels are I Table 7.3.2-1. iinoperable in the operating t recombiner train.-

F.1 Take a grab sample from Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the operating recombiner train.

AND F.2 Analyze the grab sample 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after required by Required completion of Compensatory Required Measure F.1. Compensatory Measure F.1 AND F.3 Verify proper functioning In accordance with of the operating approved recombiner train by procedures monitoring recombiner temperature.

AND F.4 Restore the channel(s) to 30 days OPERABLE status.

G. Required Compensatory G.1 Suspend operation of the Immediately Measure F.1, F.2, or F.3 associated recombiner and associated Completion train.

Time not met.

(continued)

Brunswick Units 1 and 2 7.3.2-4 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME H. Required Compensatory H.1 Prepare and submit in the Upon submittal of Measure B.3, C.2, D.2, Radioactive Effluent current calendar or F.4 and associated Release Report, the year Radioactive Completion Time not met. reason the channel was Effluent Release not restored to Report OPERABLE status within 30 days.

1. As required by Required 1.1 Verify GASEOUS Immediately Compensatory RADWASTE Measure A.1 and TREATMENT SYSTEM is referenced in not bypassed.

Table 7.3.2-1.

AND 1.2 Verify the main stack Immediately effluent noble gas monitor is OPERABLE.

AND 1.3 Restore the channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

J. Required Compensatory J.1 Be in MODE 2. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure and associated Completion Time of AND Condition I not met.

J.2 Prepare and submit in the Upon submittal of Radioactive Effluent current calendar Release Report, the year Radioactive reason the channel was Effluent Release not restored to Report OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

(continued)

Brunswick Units 1 and 2 7.3.2-5 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 COMPENSATORY MEASURES continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME K. As required by Required K.1 Suspend effluent releases Immediately Compensatory Measure via the associated A.1 and referenced in pathway.

Table 7.3.2-1.

TEST REQUIREMENTS r -------------------------------------------------------------

R NOTE Refer to Table 7.3.2-1 to determine which TRs apply for each Radioactive Gaseous Effluent 0 Monitoring Instrumentation Function.-

TEST FREQUENCY TR 7.3.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 7.3.2.2 Perform CHANNEL CHECK. 7 days TR 7.3.2.3 Perform SOURCE CHECK. 31 days TR 7.3.2.4 Perform CHANNEL FUNCTIONAL TEST. 31 days (continued)

Brunswick Units 1 and 2 7.3.2-6 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 TEST REQUIREMENTS (continued)

TEST FREQUENCY I

TR 7.3.2.5 Perform CHANNEL FUNCTIONAL TEST, including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Downscale failure.

c. Instrument controls not set in "operate" mode.

TR 7.3.2.6 Perform CHANNEL FUNCTIONAL TEST. 92 days TR 7.3.2.7 Perform CHANNEL FUNCTIONAL TEST; including 92 days demonstration of control room annunciation in response to any of the following:

a. Alarm/trip setpoint exceeded.

b. Downscale failure.

TR 7.3.2.8 Perform CHANNEL FUNCTIONAL TEST including 92 days control room-annunciation in response to any of the following:

a. Alarm/ttrip setpoint exceeded.

b. Circuit failure.

c.

I Downscale failure.

d. Instrument controls not set in "operate" mode.

(continued)

Brunswick Units 1 and 2 7.3.2-7 Rev. 26 I

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Tr-ST RPEQIRFMENTS (continued)

IV.______-_,

TEST FREQUENCY r

TR 7.3.2.9 Perform CHANNEL CALIBRATION. The CHANNEL 92 days CALIBRATION shall include the use of standard gas samples containing a nominal:

a. Two volume percent hydrogen, balance nitrogen; and

b. Four volume percent hydrogen, balance nitrogen.

TR 7.3.2.10 NOTE For Functions 1.a, 2.a, 3.a, 4, and 6, previously established calibration procedures or sources that have been related to the initial CHANNEL CALIBRATION shall:

,be used._- _ _ _ _ _ _ _ _ _ _ _ -__ _ _ _ _

Perform CHANNEL CALIBRATION. 24 months Brunswick Units 1 and 2 7.3.2-8 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 1 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION(a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/TRIP MODES OR CHANNELS REFERENCED REQUIREMENTS SETPOINT OTHER PER FROM REQUIRED VALUE SPECIFIED FUNCTION COMPENSATORY CONDITIONS MEASURES A1

1. Main Stack Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3 2.3 TR 7.3.2.5 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10

e. Sampler Flow Rate At all times 1 D TR 7.3.2.1 (c)

Measurement Device TR 7.3.2.6 TR 7.3.2.10

2. Reactor Building Ventilation Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3.2.3 TR 7.3.2.7 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3 2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10 (continued)

(a} Specific instrumentation identification numbers are provided in Appendix E.

(by Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7. 'Dose Rate-Gaseous Effluents,' are not exceeded (c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7. Dose Rate-Gaseous Elfluents.' are not exceeded Brunswick Units 1 and 2 7.3.2-9 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3 2-1 (page 2 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION(a) APPLICABLE REQUIRED CONDITIONS TEST ALARMTRIP MODES OR CHANNELS REFERENCED REQUIREMENTS SETPOINT OTHER PER FROM REQUIRED VALUE SPECIFIED FUNCTION COMPENSATORY CONDITIONS MEASURES A1

2. Reactor Building Ventilation Monitoring System (continued)

e. Sampler Flow Rate At all times 1 D TR 7.3.2 1 (c)

Measurement Device TR 7.3.2.6 TR 7.3 2.10

3. Turbine Building Ventilation Monitoring System

a. Noble Gas Activity At all times 1 B TR 7.3.2.1 (b)

Monitor TR 7.3.2.3 TR 7.3.2.5 TR 7.3.2.10

b. Iodine Sampler At all times 1 C TR 7.3 2.2 NA Cartridge

c. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter

d. System Effluent Flow At all times 1 D TR 7.3.2.1 NA Rate Measurement TR 7.3.2.6 Device TR 7.3.2.10

e. Sampler Flow Rate At all times 1 D TR 7.3.2.1 (c)

Measurement Device TR 7.3.2.6 TR 7.3.2.10

4. Main Condenser Off-Gas At all times 1 B TR 7.3.2.1 (b)

Treatment System Noble TR 7.3.2.3 Gas Activity Monitor(d) TR 7.3.2.6 (Downstream of AOG TR 7.3 2.10 Treatment System)

(continued)

(a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Alarmrtrip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7. Dose Rate-Gaseous Effluents, are not exceeded.

(c) Alarrn/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3.7, Dose Rate-Gaseous Effluents,' are not exceeded.

(d) Provides alarm.

Brunswick Units 1 and 2 7.3.2-1 0 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3 2-1 (page 3 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION(a) APPLICABLE REQUIRED CONDITIONS TEST ALARM/

MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A 1

5. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System

a. Recombiner Train A (e) 2 F TR 7.3.2.1 (c)

TR 7.3 2.4 TR 7.3.2.9

b. Recombiner Train B (e) 2 F TR 7.3.2.1 (c)

TR 7.3.2.4 TR 7.3 2.9

6. Main Condenser Air (f) 1 I TR 7.3.2.1 (b)

Ejector Noble Gas TR 7.3.2.3 Radioactivity Monitor(d) TR 7.3.2.8 (Prior to input to TR 7.3.2.10 Treatment System)

7. Hot Shop Ventilation Monitoring System

a. Iodine Sampler At all times 1 C TR 7.3.2.2 NA Cartridge

b. Particulate Sampler At all times 1 C TR 7.3.2.2 NA Filter (continued)

(a) Specific instrumentation identification numbers are provided in Appendix E.

(b) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of ODCMS 7.3.7, 'Dose Rate-Gaseous Effluents.' are not exceeded.

(c) Alarm/trip setpoints shall be determined in accordance with associated design specification(s) and set to ensure the limits of ODCMS 7.3 7. Dose Rate-Gaseous Effluents

are not exceeded.

(d) Provides alarm.

(e) During associated recombiner train operation.

(I) During operation of the main condenser air ejector.

Brunswick Units 1 and 2 7.3.2-1 1 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation 7.3.2 Table 7.3.2-1 (page 4 of 4)

Radioactive Gaseous Effluent Monitoring Instrumentation FUNCTION(a) APPUCABLE REQUIRED CONDmONS TEST ALARMV MODES OR CHANNELS REFERENCED REQUIREMENTS TRIP OTHER PER FROM REQUIRED SETPOINT SPECIFIED FUNCTION COMPENSATORY VALUE CONDITIONS MEASURES A.1

8. Radioactive Materials Container and Storage Building Decontamination Facility

a. Iodine Sampler (g) 1 K TR 7.3.2.1 NA Cartridge

b. Particulate Sampler Filter (9) 1 K TR 7.3.2.1 NAQ) (

9. Low Level Warehouse

a. Particulate Sampler (h) 1 (a) Specific instrumentation Identification numbers are provided In Appendix E K TR 7.3.2.2 NA (i)

I.

(g) During operation of the Radioactive Materials Container and Storage Building Decontamination Facility.

I (h) During operation of the Low Level Warehouse ventilation system.

(i) Local alarm.

Brunswick Units 1 and 2 7.3.2-1 2 Rev. 26 l

Concentration-Liquid Effluents 7.3.3 7.3.3 CONCENTRATION-LIQUID EFFLUENTS ODCMS 7.3.3 The concentration of radioactive material released to UNRESTRICTED AREAS after dilution in the discharge canal shall be limited to:

a. 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 for radionuclides other than dissolved or entrained noble gases; and

b. 2 x 10'4lCi/rn total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Concentration of A.1 Initiate action to restore Immediately radioactive material concentration to within released to limits.

UNRESTRICTED AREAS not within limits.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.3.1 Verify the concentration of radioactive material In accordance with released to UNRESTRICTED AREAS is within limits. Table 7.3.3-1 (continued)

Brunswick Units 1 and 2 7.3.3-1 Rev. 25

Concentration-Liquid Effluents 7.3.3 TEST REQUIREMENTS (continued) T TEST FREQUENCY

+

TR 7.3.3.2 r-------------------------------1-_

1 NOTE

'Only required to be performed if stabilization pond or

,service water samples analyzed in accordance with lTable 7.3.3-1 indicate concentrations of any

,gamma-emitting radionuclides greater than the trigger level of 5 x 106ACi/ml.

Verify concentration of radioactive material released In accordance with to UNRESTRICTED AREAS is within limits. Table 7.3.3-2 for liquid wastes exceeding the trigger level Brunswick Units 1 and 2 7.3.3-2 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 1 of 3)

Radioactive Liquid Waste Sampling and Analysis Program LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS SAMPLE LOWER TYPE FREQUENCY FREQUENCY TYPE LIMIT OF DETECTION (LLD)(a)(e)

Sample Tanks, Prior to release of Prior to release of Principal Gamma 5 x 10-7(b) PCVmI Detergent Drain each batch each batch Emitters(g)

Tank, and Salt Water Release 1-131 1 x10 6 pCVml Tanks (Batch Release),(h) Prior to release of 31 days Dissolved and 1 x 1o-SjiCiml one batch once per entrained gases AND 31 days (Gamma Emitters)

Circulating Water Prior to release of 31 days Gross Alpha 1 x 10 7 pCVml Pit each batch Composite(c)

H-3 1 x 1j05PCVmI Prior to release of 92 days Sr-89, Sr-90 5 x 10- 8pCvml each batch Composite(c)

Fe-55 1 x 10 6pCVml

2. Stabilization Pond Prior to each release Prior to each release Principal Gamma S x 10-7(b)PCVmI (d) Emitters (9)

AND AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during periods of release(f) periods of release([)

3. Service Water(d) 7 days during system 7 days during system Principal Gamma 5x 10 -7 (b)

(Potential operation operation Emitters (9)

Continuous Release)

Brunswick Units 1 and 2 7.3.3-3 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 2 of 3)

Radioactive Liquid Waste Sampling and Analysis Program (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.

(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.

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

(d) The stabilization pond and service water liquid release types represent potential release pathways and not actual release pathways. Test of these pathways is intended to alert the plant to a potential problem; analysis for principal gamma emitters should be sufficient to meet this intent. If analysis for principal gamma emitters indicates a problem (i.e., exceeds the trigger level of 5x1 0-6 pCVml), then complete sampling and analyses shall be performed as per Table 7.3.3-2.

(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 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 Cb E. V.2.22 x 106 . Y. eCI'e)

Where:

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

Gb = (Nltb)VZ

= standard deviation of background (cpm)

Brunswick Units 1 and 2 7.3.3-4 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-1 (page 3 of 3)

Radioactive Liquid Waste Sampling and Analysis Program N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield xi radioactive decay constant of ith nuclide (sec-)

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an *a priorin (before the fact) limit representing the capability of a measurement system and not as an Oa posteriori" (after the fact) limit for a particular measurement.

(f) The stabilization pond is typically released over a several-day period. The pond is to be sampled and analyzed prior to commencing release. When composite sampling instrumentation becomes available and is OPERABLE, daily grab sampling of the stabilization pond effluent will not be required during release and the composite sample will be analyzed on a weekly basis.

(g) The principal gamma emitters for which the LLD specifications apply exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(h) 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 to assure representative sampling.

Brunswick Units 1 and 2 7.3.3-5 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-2 (page 1 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels LIQUID RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE SAMPLE LOWER TYPE FREQUENCY FREQUENCY ANALYSIS LIMIT OF TYPE DETECTION (LLD)(a)(e)

1. Stabilization Pond Prior to each Prior to each release Principal Gamma 5 x 1O-7Qb) ACVI/

release Emitters(g)

AND AND 1-131 1 x 1O0 6 pCVml 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during periods of release(f) periods of release(f)

Prior to one release 31 days Dissolved and 1 x 10o5pCiml once per 31 days entrained gases (Gamma Emitters)

Prior to each 31 days Gross Alpha 1 x 10-7iCVmI release Composite(c)

H-3 1 x 10 5pCmlI Prior to each 92 days Sr-89, Sr-90 5 x1j0 8jCVml release Composite(c)

Fe-55 1 x 10 6pCVml

2. Service Water 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 7 days Principal Gamma 5 x 1-7(b)

(Continuous Composite(c) Emitters (9)

Release)(h) 1-131 1 x 10 6 pCVmI 31 days 31 days Dissolved and 1 x 10o5 ACimI Grab Sample entrained gases (Gamma Emitters) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 31 days Gross Alpha 1 x 10O7,xCiml Composite(c)

H-3 1 x 10-5pCVml 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (d) 92 days Sr-89. Sr-90 5 x 10 8jiCvml Composite(c)

Fe-55 1 x 10 6 jxCvml Brunswick Units 1 and 2 7.3.3-6 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-2 (page 2 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels (a) The detectability limits for activity analyses are based on technical feasibility limits and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable; and when nuclides are measured below the stated limits, they should also be reported.

(b) When operational limitations preclude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch; and a weekly sample composited from proportional aliquots from each batch released during the week shall be analyzed for principal gamma-emitting radionuclides.

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

(d) Until such time as continuous proportional composite samplers are installed on the service water discharge line, daily grab sampling of the service water effluent will be required for use in making up the composite.

(e) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 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 ab E-V 2.22 x 106-Y e-ie)

Where:

LLD is the 'a priori" lower limit of detection as defined above (as microcuries per unit mass or volume) b = (N/tb)"

= standard deviation of background (cpm)

N = background count rate (cpm)

Brunswick Units 1 and 2 7.3.3-7 Rev. 25

Concentration-Liquid Effluents 7.3.3 Table 7.3.3-2 (page 3 of 3)

Radioactive Liquid Waste Sampling and Analysis Program for Potential Release Pathways Which Have Exceeded Trigger Levels tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield i= radioactive decay constant of ith nuclide (sec')

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an 'a priori' (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

(f) The stabilization pond is typically released over a several-day period. The pond is to be sampled and analyzed prior to commencing release. When composite sampling instrumentation becomes available and is OPERABLE, daily grab sampling of the stabilization pond effluent will not be required during release and the composite sample will be analyzed on a weekly basis.

(g) The principal gamma emitters for which the LLD specifications apply exclusively are the following radionuclides: 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. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(h) A continuous release is the discharge of liquid waste of a nondiscrete volume, e.g.,

from a volume or a system that has an input flow during the continuous release.

Brunswick Units 1 and 2 7.3.3-8 Rev. 25

Dose-Liquid Effluents 7.3.4 7.3.4 DOSE-LIQUID EFFLUENTS ODCMS 7.3.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to:

a.

3 mrem to the total body and < 10 mrem to any organ during any calendar quarter; and

b. < 6 mrem to the total body and

20 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES r -------------------------------------------------------------

I NOTE I Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, "Total Dose (40 _ 190)," when liquid_effluent

_ CFR __ dose results-__ in exceeding

__ _ _limit.

an annual total_ dose _ _

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Submit a Special Report 30 days NOTE to the NRC that identifies Required Compensatory causes for exceeding Measure A.1 shall be 1 limits, corrective actions completed if this Condition taken to reduce releases, is entered. and corrective actions to

__ assure that subsequent Calculated dose from the releases will be in release of radioactive compliance with the materials in liquid effluents required limits.

to UNRESTRICTED AREAS not within limits.

Brunswick Units 1 and 2 7.3.4-1 Rev. 25

Dose-Liquid Effluents 7.3.4 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.4.1 Verify the cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.4-2 Rev. 25

Liquid Radwaste Treatment System 7.3.5 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM ODCMS 7.3.5 The Liquid Radwaste Treatment System shall be used to reduce radioactive materials in liquid wastes prior to their discharge.

APPLICABILITY: During release of liquid radioactive water when the projected doses due to the liquid effluent, from the site to UNRESTRICTED AREAS, would exceed 0.12 mrem to the total body or 0.4 mrem to any organ in a 31 day period.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. ----------------- 1A.1 Submit a Special Report 30 days NOTE to the NRC that includes Required Compensatory ,explanation of why liquid Measure A.1 shall be l radwaste was being completed if this Condition discharged without is entered. treatment, identification of any required inoperable equipment or subsystem Liquiarged was nute and the reasons for the discharged withoutinoperability, the corrective actions taken to restore the required inoperable equipment to OPERABLE status, and a summary description of the corrective actions taken to prevent recurrence.

Brunswick Units 1 and 2 7.3.5-1 Rev. 25

Liquid Radwaste Treatment System 7.3.5 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.5.1 Verify required valve alignments to ensure Liquid Prior to release of Radwaste Treatment System is in use to reduce liquid effluents radioactive materials in liquid waste.

TR 7.3.5.2 Determine the projected doses due to liquid releases 31 days from the site to UNRESTRICTED AREAS in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.5-2 Rev. 25

Liquid Holdup Tanks 7.3.6 7.3.6 LIQUID HOLDUP TANKS ODCMS 7.3.6 The quantity of radioactive material, excluding tritium and dissolved or entrained gases, suspended in solution in the condensate storage tank, auxiliary surge tank and outdoor temporary tank shall be maintained within limits.

APPLICABILITY: At all times.

COMPENSATORY MEASURES NOTE Separate Condition

-________entry is allowed for each tank.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Quantity of radioactive A.1 Suspend addition of Immediately material in one or more of radioactive materials to the specified liquid holdup the associated tank.

tanks not within limit.

AND A.2 Restore quantity of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months radioactive material in the tank to within limit.

AND A.3 Prepare and submit in the Upon submittal of Radioactive Effluent the current Release Report, a calendar year description of the events Radioactive leading to the Effluent Release non-compliance. Report Brunswick Units 1 and 2 7.3.6-1 Rev. 25

Liquid Holdup Tanks 7.3.6 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.6.1 NOTE Only required to be performed when radioactive materials are being added to the tank. l Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the condensate storage tank is

10 Ci by analyzing a representative sample of the tank's contents.

TR 7.3.6.2 TR7362 r---------------------------------

NOTE

'Only required to be performed when radioactive materials are being added to the tank.-

Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the auxiliary surge tank is < 10 Ci by calculation using dose measurement(s) of the tank area.

TR 7.3.6.3 r----------------------------------

NOTE Only required to be performed when radioactive materials are being added to the tank. X Verify the quantity of radioactive material, excluding 7 days tritium and dissolved or entrained gases, in the outdoor temporary tank is

10 Ci by analyzing a representative sample of the tank's contents.

Brunswick Units 1 and 2 7.3.6-2 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 7.3.7 DOSE RATE-GASEOUS EFFLUENTS ODCMS 7.3.7 The dose rate at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

a. For nobles gases, < 500 mrem per year to the total body and

< 3000 mrem per year to the skin; and

b. For iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half lives > 8 days, s 1500 mrem per year to any organ.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Dose rate from the release A.1 Initiate action to restore Immediately of radioactive materials in dose rate to within limits.

gaseous effluents from the site at or beyond the SITE BOUNDARY not within limits.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.7.1 Verify the dose rate due to noble gases in gaseous In accordance with effluents is within limits in accordance with the ODCM methodology and parameters in the ODCM.

TR 7.3.7.2 Verify dose rate due to iodine-1 31, iodine-1 33, In accordance with tritium, and all radionuclides in particulate form with Table 7.3.7-1 half lives > 8 days in gaseous effluents is within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.7-1 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 1 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program GASEOUS RELEASE SAMPLE SAMPLE ANALYSIS SAMPLE ANALYSIS SAMPLE LOWER TYPE FREQUENCY FREQUENCY TYPE UMIT OF DETECTION (LLD)(a)

1. Drywell Purge Prior to each purge Prior to each Principal Gamma 1 x 10 4 jtChiml Grab Sample purge Emitters(b)

2. Environmental 31 days(c)(d) 31 days Principal Gamma 1 x 10 4 ChVml Release Points Grab Sample Emitters(b)

a. Continuous H-3 1 x 1 0-6pChilml Release:

Main Stack Reactor Building Continuous(e) 7 days(0(9) 1-131 1 x 10o12 pChi/ml Vents Charcoal Sample Turbine Building Vents Hot Shop(h) Continuous(e) 7 days(0(9) Principal Gamma 0"pChVml 1 x lo-1 Building Vents Particulate Emitters(b) (1-131, Sample others)

Continuous(e) 31 days Gross Alpha 1 x 10-1 1pChi/ml Composite Particulate Sample Continuous(e) 92 days Sr-89, Sr-90 1 x10-1 1pChlml Composite Particulate Sample I Continuous(e) Noble Gas Noble Gases, 1 x 10 6 pChiml Monitor Gross Beta or Gamma

b. Batch Release: During RMCSB(e) Each batch Radioactive operation only release: I Materials Charcoal Sample 1-131 1 x 10-12 XChl/ml Container and Storage During fachlity(e) Each batch Building operation release:

Decontamina- Particulate Principle Gamma 1 x 1o-1 1 pChVml tion Facility Sample Emitters(b) (1-131, (RMCSB) others)

Low Level Warehouse During facility(e) operation 31 days Composite Gross Alpha 1 x10 11 jpChVml I Particulate Sample During facility(e) 92 days Sr-89, Sr-90 i x lo-11 1pChi/mI operation Composite Particulate Sample

3. Incinerated Oil(i) Prior to eachO) batch Prior to each Principal Gamma 5 x 10-7jChi~ml release Grab Sample batch releasei) Emitters(b)

BrunsWick Units 1 and 2 7.3.7-2 Rev. 26 I

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 2 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program (a) The lower limit of detectability (LLD) is the smallest concentration of a radioactive material in an unknown sample that will be detected with a 95% probability with a 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 Ob E-V.2.22 x 106 y.Y-e -te)

Where:

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

Ob = (N/tb)"

- standard deviation of background (cpm)

N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 x 106 = conversion factor (dpm/microcurie)

Y = fractional radiochemical yield H

= radioactive decay constant of ith nuclide (sec ')

te = elapsed time between sample collection and counting (sec)

Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an 'a priori" (before the fact) limit representing the capability of a measurement system and not as an Na posteriori" (after the fact) limit for a particular measurement.

Brunswick Units 1 and 2 7.3.7-3 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 3 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program (b) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-1 33m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

(c) With a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, or following shutdown or start-up, sampling and analyses shall also be performed unless (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the main condenser air ejector noble gas activity monitor shows that activity has not increased by more than a factor of 3.

(d) If during refueling, the tritium concentration in the spent fuel pool water exceeds 2 x 10 pCi/ml, tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. Spent fuel pool water will be sampled at least once per 7 days during refueling.

(e) 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 ODCMS 7.3.7, 7.3.8, and 7.3.9.

(f) Sample cartridges/filters 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).

(g) Sampling shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up, or 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. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the main condenser air ejector noble gas monitor shows that activity has not increased more than a factor of 3. This footnote does not apply to the Hot Shop environmental release point.

(h) Monthly grab samples to be analyzed for principal gamma emitters and tritium are not applicable for the Hot Shop environmental release point. In addition, the Hot Shop release point does not have a noble gas monitor and, therefore, the noble gas activity analysis requirements of Table 7.3.7-1 are not applicable.

Brunswick Units 1 and 2 7.3.7-4 Rev. 25

Dose Rate-Gaseous Effluents 7.3.7 Table 7.3.7-1 (page 4 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program (i) Releases from incinerated oil may be discharged via points other than the main vent (e.g., incinerator). Release shall be accounted for based on pre-release grab sample data.

(j) Samples of waste oil to be incinerated shall be collected from and be representative of oil in liquid form.

Brunswick Units 1 and 2 7.3.7-5 Rev. 25

Dose-Noble Gases 7.3.8 7.3.8 DOSE-NOBLE GASES ODCMS 7.3.8 The air dose at and beyond the SITE BOUNDARY due to noble gases in gaseous effluents from the site shall be limited to the following:

a.

10 mrads gamma radiation and < 20 mrads beta radiation during any calendar quarter; and

b. < 20 mrads gamma radiation and < 40 mrads beta radiation during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES r -------------------------------------------------------------

I NOTE I EEnter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, Total I'Dose (40 CFR 190)," when gaseous effluent (noble gases) dose results in exceeding an annual '

'total dose limit. - - - - - - - - - - - - - - - - - ----

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. ----------------- A.1 Submit a Special Report 30 days NOTE to the NRC that identifies Required Compensatory causes for exceeding the Measure A.1 shall be limits, corrective actions completed if this Condition taken to reduce releases, is entered. and corrective actions to

- assure that subsequent Calculated air dck~e from releases are within limits.

radioactive noble gases in gaseous effluents at or beyond the SITE BOUNDARY not within limits.

Brunswick Units 1 and 2 7.3.8-1 Rev. 25

Dose-Noble Gases 7.3.8 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.8.1 Verify the cumulative dose contributions from noble 31 days gases in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.8-2 Rev. 25

Particulate Form Dose-l-1 31, 1-133, Tritium, and Radionuclides in Dose--1-131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 7.3.9 DOSE-1-131, 1-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM ODCMS 7.3.9 The dose to a MEMBER OF THE PUBLIC at and beyond the SITE BOUNDARY from iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half lives > 8 days, in gaseous effluents released from the site shall be limited to the following:

a. < 15 mrems to any organ during any calendar quarter;

b.

30 mrems to any organ during any calendar year; and

c. < 0.1% of the limits of ODCMS 7.3.9.a and ODCMS 7.3.9.b as a result of burning contaminated oil.

APPLICABILITY: At all times.

COMPENSATORY MEASURES r ------------------------------------------------------------- I I NOTE I I'Enter applicable Conditions and Required Compensatory Measures of ODCMS 7.3.14, NTotal I IDose (40 CFR 190)," when gaseous effluent (1-131, 1-133, tritium, radionuclides in particulate 1

, form) dose results in exceeding an annual total dose limit. -__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. ----------------- A.1 Submit a Special Report 30 days NOTE X to the NRC that identifies Required Compensatory causes for exceeding the Measure A.1 shall be limits, corrective actions completed if this Condition taken to reduce releases,

,is entered. . and corrective actions to

__ assure subsequent Calculated dose from the releases are within limits.

release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives

> 8 days, in gaseous effluents at or beyond the SITE BOUNDARY not within limits.

Brunswick Units 1 and 2 7.3.9-1 Rev. 25

Dose-- -131, 1-133, Tritium, and Radionuclides in Particulate Form 7.3.9 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.9.1 Verify the cumulative dose contributions from 31 days iodine-131, iodine-1 33, tritium, and radionuclides in particulate form with half lives > 8 days, in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.9-2 Rev. 25

GASEOUS RADWASTE TREATMENT SYSTEM GASEOUS RADWASTE TREATMENT SYSTEM 7.3.10 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM ODCMS 7.3.10 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the Main Condenser Air Ejector (evacuation) System is in operation.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. GASEOUS RADWASTE A.1 Place GASEOUS 7 days TREATMENT SYSTEM RADWASTE not in operation. TREATMENT SYSTEM in operation.

B. .B.1 Submit a Special Report 30 days NOTE to the NRC that identifies Required Compensatory : the required inoperable Measure B.1 shall be equipment and the completed if this Condition reasons for the is entered. inoperability, corrective

__ actions taken to restore the required inoperable Required Compensatory equipment to OPERABLE measure and associatedstusanasmar Completion Time not met, scition o the description of the corrective actions taken to prevent recurrence.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.10.1 Verify GASEOUS RADWASTE TREATMENT 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SYSTEM in operation by checking the readings of the relevant instruments.

Brunswick Units 1 and 2 7.3. 10-1 Rev.25

SYSTEM VENTILATION EXHAUST TREATMENT VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM ODCMS 7.3.11 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge.

APPLICABILITY: During release of gaseous radioactive wastes when the projected doses due to gaseous effluent, from the site to areas at or beyond the SITE BOUNDARY, when averaged over 31 days, would exceed 0.6 mrem to any organ in a 31 day period.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. ____________----1 A.1 Submit a Special Report 30 days NOTE to the NRC that identifies Required Compensatory the inoperable equipment

! Measure A.1 shall be or subsystems and the completed if this Condition reason for inoperability, is entered. the corrective actions

_ - taken to restore the inoperable equipment to Gaseous waste being OPERABLE status, and a discharged without summary description of treatment. the corrective actions taken to prevent recurrence.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.11.1 Verify required valve alignment to ensure Prior to release of VENTILATION EXHAUST TREATMENT SYSTEM is gaseous effluents in use to reduce radioactive materials in gaseous waste.

,co.t_.. as (continued)

Brunswick Units 1 and 2 7.3.1 1-1 Rev. 25

VENTILATION EXHAUST TREATMENT SYSTEM 7.3.11 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.11.2 TR 73.1.2 ---------------------------------

NOTE Only required to be performed when the lVENTILATION EXHAUST TREATMENT SYSTEM is:

,not in use.

Determine the projected doses due to gaseous 31 days releases from the site to areas at or beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.11-2 Rev. 25

I Explosive Gas Mixture 7.3.12 7.3.12 EXPLOSIVE GAS MIXTURE ODCMS 7.3.12 The concentration of hydrogen in the Main Condenser Offgas Treatment System shall be S 4% by volume.

APPLICABILITY: When the Main Condenser Air Ejector System is in operation.

COMPENSATORY MEASURES r----------------------------------------------------------- I I NOTE ODCMS 3.0.4 is not applicable. - - - - - - - - - -__- - - --_ _ _--_ _ _ _ _ _ _ _ _

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Hydrogen concentration in A.1 Restore hydrogen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the Main Condenser concentration to within Offgas Treatment System limit.

> 4% by volume.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.12.1 Verify the concentration of hydrogen in the Main Continuously Condenser Offgas Treatment System is

4% by volume by monitoring waste gases with the required hydrogen monitors of ODCMS 7.3.2, "Radioactive Gaseous Effluent Monitoring Instrumentation."

Brunswick Units 1 and 2 7.3.1 2-1 Rev. 25

Drywell VENTING or PURGING 7.3.13 7.3.13 DRYWELL VENTING OR PURGING ODCMS 7.3.13 The drywell shall be purged to the environment at a rate in conformance with ODCMS 7.3.7, "Dose Rate-Gaseous Effluents."

APPLICABILITY: When the drywell is being vented or purged.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of ODCMS A.1 Suspend VENTING and Immediately not met. PURGING of the drywell.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.13.1 Perform a sample analysis in accordance with Prior to each Table 7.3.7-1. drywell PURGE Brunswick Units 1 and 2 7.3.1 3-1 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 7.3.14 TOTAL DOSE (40 CFR PART 190)

ODCMS 7.3.14 The dose or dose commitment to any MEMBER OF THE PUBLIC over the calendar year due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to:

a. < 25 mrems to the total body or any organ (except the thyroid); and

b.

75 mrem to the thyroid.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 I------------.---- --------------------

a NOTE Is NOTE Required Compensatory Estimates of radiation exposure Measures A.1 and A.2 from uranium fuel cycle sources shall be completed if this shall include the effects of all Condition is entered. effluent pathways and direct radiation, including releases Calculated dose for - covered by this Special Report.

uranium fuel cycle sources to any MEMBER OF THE Submit a Special Report 30 days PUBLIC not within limits. to the NRC that includes corrective actions taken to prevent recurrence, the schedule for achieving conformance with required limits, an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC from uranium fuel cycle sources for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

AND (continued)

Brunswick Units 1 and 2 7.3.1 4-1 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. (continued) A.2 NOTES

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

2. Special Report submitted is considered a timely request and a variance is granted until NRC action on the request is complete.

Submit a request for a 30 days variance in accordance with 40 CFR 190 in the Special Report to the NRC.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.14.1 Determine cumulative dose contributions from liquid In accordance with and gaseous effluents in accordance with ODCM TR 7.3.4.1, TR 7.3.8.1 and TR 7.3.9.1, and the methodology and parameters in the ODCM.

(continued)

Brunswick Units 1 and 2 7.3.14-2 Rev. 25

Total Dose (40 CFR Part 190) 7.3.14 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 7.3.14.2 r---------------------_------------

NOTE Only required to be performed when calculated doses from the release of radioactive materials in

'liquid or gaseous effluents exceed twice the limits of ODCMSs 7.3.4.a, 7.3.4.b, 7.3.8.a, 7.3.8.b, 7.3.9.a.,

or 7.3.9.b.

Determine cumulative dose contributions from direct In accordance with radiation from the reactor units and from radwaste ODCM storage tanks in accordance with methodology and parameters in the ODCM.

Brunswick Units 1 and 2 7.3.14-3 Rev. 25

Radiological Environmental Monitoring Program Radiological Environmental Monitoring Program 7.3.15 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ODCMS 7.3.15 . The Radiological Monitoring Program shall be as follows:

a. Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 7.3.15-1.

b. Each sample location specified in Table 7.3.15-1 shall contain required milk or leafy vegetable samples

c. The level of radioactivity as the result of plant effluents for each radionuclide in each environmental sampling medium at a required location shall be less than the limits specified in Table 7.3.15-2, when averaged over the calendar quarter;

d. The total level of radioactivity as the result of plant effluents in each environmental sampling medium at a required location shall be less than the limit specified in Table 7.3.15-2, when averaged over the calendar quarter; and

e. The potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides other than those in Table 7.3.15-2 in each environmental sampling medium at a required location shall be less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. -A.1 Prepare and submit, in the Upon submittal of NOTE Annual Radiological current calendar Required Compensatory Environmental Operating year Annual Measure A.1 shall be Report, a description for Radiological completed if this Condition not conducting the Environmental is entered. Radiological Operating Report

___ ____ Environmental Monitoring sampling and analysis One or more samples not requirements as required collected or analyzed as and the corrective actions specified in Table 7.3.15-1. to prevent recurrence.

(continued)

Brunswick Units 1 and 2 7.3.15-1 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. B.1 Identify locations for 30 days NOTES obtaining replacement

1. Separate Condition entry lsamples and replace, in is allowed for each the Radiological sample location. I Environmental Monitoring Program, the location(s)

2. Required Compensatory from which samples are Measure B.2 shall be unavailable with the new completed if this location(s).

Condition is entered. A One or eore sample B.2 Prepare and submit, in the Upon submittal of locations requith Radioactive Effluent current calendar requtable7 milk5 esh Release Report, the year Radioactive veguietal smplkrfesh laycause of the unavailability Effluent Release unavailable, of samples, the new Report locations for obtaining replacement samples, and the revised figure(s) and table for the ODCM reflecting the new locations.

(continued)

Brunswick Units 1 and 2 7.3.15-2 Rev. 25

Radiological Environmental Monitoring Program 7.3."15 rC.OAPINIZAT0PY wv~v Q, S MFASq RF5S (continuied)i CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C.---- C.1 Submit a Special Report 30 days r--------------__ to the NRC which includes X NOTES

1. Separate Condition entry the cause(s) for exceeding is allowed for each the limit(s) and the sample location. corrective actions to reduce radioactive

12. Required Compensatory effluents so that the Measure C.1 shall be potential annual dose to a MEMBER OF THE completed if this Condition is entered., PUBLIC is less than the calendar year reporting limits of ODCMS 7.3.4, One or more sample ODCMS 7.3.8, and locations with the level of ODCMS 7.3.9.

radioactivity for one or more radionuclides as the result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.

OR One or more sample locations with the total level of radioactivity as a result of plant effluents in an environmental sampling medium not within the limits of Table 7.3.15-2 when averaged over the calendar quarter.

J ________________________________ 3 ___________________

(continued)

Brunswick Units 1 and 2 7.3.15-3 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME D. -- D A--------------__ r-----------~---------

NOTES NOTE

1. Separate Condition entry: Only required if the radionuclides1 is allowed for each are the result of plant effluents.

sample location.

Submit a Special Report 30 days

2. Required Compensatory to the NRC which includes Measures D.1 and D.2 the methodology and shall be completed if this parameters used for Condition is entered. estimating the potential annual dose, the cause(s)

One or more sample for exceeding the limit(s) locations with the potential and the corrective actions annual dose to a MEMBER to reduce radioactive OF THE PUBLIC from all effluents so that the radionuclides other than potential annual dose to a those in Table 7.3.15-2 not MEMBER OF THE within limits. PUBLIC is less than the calendar year limits of ODCMS 7.3.4, ODCMS 7.3.8, and ODCMS 7.3.9.

AND D.2 r-- -- -- -- -------

NOTE Only required if the radionuclides are not the result of plant effluents.

Describe the condition in Upon submittal of the Annual Radiological the current Environmental Operating calendar year Report. Annual Radiological Environmental Operating Report 1 ___________________________________________________ _____________________________

Brunswick Units 1 and 2 7.3. 15-4 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.15.1 Verify radiological environmental monitoring In accordance with samples collected at the locations given in the table Table 7.3.15-1 and figure(s) in the ODCM and analyzed as specified in Table 7.3.15-1 are within limits.

Detection capabilities for the analyses are specified in Table 7.3.15-3.

Brunswick Units 1 and 2 7.3. 15-5 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 1 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a) COLLECTION FREQUENCY OF FREQUENCY ANALYSIS

1. Direct Radiation Forty locations, either with two or 92 days Gamma dose:

(b) more dosimeters or with one or 92 days more instruments for measuring and recording dose rate continuously to be placed as follows An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY as is reasonably accessible and practical.

An outer ring of stations, one in each of the meteorological sectors at distances of 8 km or greater from the site as is reasonably accessible and practical.

The balance of the stations to be placed in special interest areas such as population centers, nearby residences.

schools. and one or two areas to serve as control stations.

2. Airborne- Samples from the following five Continuous sampler 1-131 analysis of Radioiodine and locations: operation radioiodine canisters:

Particulate Sample collection: 7 days 7 days Three samples from different or as required by dust loading, whichever is more AND sectors as close to the SITE BOUNDARY as is reasonably frequent. Gross beta accessible, one of which radioactivity analysis being at the highest of particulate calculated annual average sampler following ground level DIO. filter change(d)

One sample from the vicinity AND of a nearby community.

Gamma isotopic One sample from a control analysis(e) of location, as for example composite (by greater than 15 km distant location): 92 days and in a less prevalent wind direction(c).

(continued)

Brunswick Units I and 2 7.3.1 5-6 Riev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 2 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a) COLLECTION - FREQUENCY OF FREQUENCY ANALYSIS

3. Waterborne

a. Surface(f) Two locations: composite(g) Gamma isotopic sample collection: analysis(e): 31 days One sample upstream. 31 days AND One sample downstream.

Tritium analysis:

92 days

b. Sediment from One sample from downstream 184 days Gamma Isotopic I Shoreline area with existing or potential analysis(e): 184 days recreational value.

4. Ingestion Samples from the following four With animals on pasture: Gamma isotopic(e) and locations: 14 days 1-131 analyses:

a. Milk14 days when animals One sample from milking At other times: 31 days are on pasture animals in each of three locations within 8 km of the AND site having the highest Gamma 'e' and dose potential (when isotopicea available).(h) 1-131 analyses:

31 days at other times One sample from milking animals at a control location greater than 15 km distance from the site and in a less prevalent wind direction.

(continued)

Brunswick Units 1 and 2 7.3.15-7 Rev. 26 I

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 3 of 5)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY NUMBER OF SAMPLES AND SAMPLING AND TYPE AND AND/OR SAMPLE SAMPLE LOCATIONS(a) COLLECTION FREQUENCY OF FREQUENCY ANALYSIS

4. (continued)

b. Fish and Samples from the following When in season: 184 days Gamma isotopic Invertebrates locations:

I analysis(e) on edible portion: 184 days One sample of each of three recreationally important species in vicinity of plant discharge area (one free swimming species, one bottom feeding species, and one shellfish species).

One sample of each similarly edible species I from an area not influenced by plant discharge to serve as control samples.

I

c. Broadleaf Samples from the following When available: 31 days Gamma lsotopic(e)

Vegetation three locations: and 1-131 analyses:

31 days when Samples of broadleaf available vegetation grown in two sectors of historically high D/Q values at the SITE BOUNDARY if milk sampling is not performed.

Ond sample of similar broadleaf vegetation grown at a distance of greater than 15 km from the site in a less prevalent wind direction if milk sampling is not performed.

Brunswick Units 1 and 2 7.3.15-8 Rev. 26 I

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 4 of 5)

Radiological Environmental Monitoring Program (a) Specific parameters of distance and direction sector from the site, and additional description where pertinent, shall be provided for each and every sample location in Table 7.3.15-1 in a table and figure(s) in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

(b) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(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 that provide valid background data may be substituted.

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

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

Brunswick Units 1 and 2 7.3.1 5-9 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-1 (page 5 of 5)

Radiological Environmental Monitoring Program (f) The "upstream' sample shall be taken at a distance beyond significant influence of the discharge. The "downstream' sample shall be taken in an area beyond but near the mixing zone. 'Upstream' samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

(g) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. Composite samples shall be collected with equipment that is capable of collecting an aliquot at time intervals that are short (e.g., once per 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) relative to compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(h) When less than three (3) milking animal locations are available for testing within an 8-km distance, sampling of broadleaf vegetation shall be performed as indicated in Table 7.3.15-1, 4.c, in lieu of milk sampling.

-Brunswick Units 1 and 2 7.3.15-10 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-2 (page 1 of 1)

Limits for the Level of Radioactivity in Environmental Samples(a)

ANALYSIS WATER AIRBORNE FISH MILK BROADLEAF (pCiI) PARTICULATE (pCi/kg, wet) (pCiA) VEGETATION AND GASES (pCikg)

(pCri-r 3)

H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 I

Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) The Limits are for samples that have only one radionuclide detected. When a sample contains more than one radionuclide, the total level of radioactivity limit is concentration(1) + concentration2) +. . . . < 1.0.

limitn) lim31(2)

Brunswick Units 1 and 2 7.3.15-11 Rev. 26 l

Radiological Environmental Monitoring Program 7.3.15 Table 7.3 15-3 (page 1 of 3)

Detection Capabilities for Environmental Sample Analysis(a)

Lower Limit of detection (LLD)(b)

ANALYSIS WATER AIRBORNE FISH MILK BROADLEAF SEDIMENT (pC/IA) PARTICULATE (pCi/Kg, wet) (pCi/I) VEGETATION (pCikg, dry)

OR GASES (pC/m 3) (pCi/kg, wet)

Gross Beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1(c) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Brunswick Units 1 and 2 7.3.15-12 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 2 of 3)

Detection Capabilities for Environmental Sample Analysis (a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) The LLD is defined for purposes of the specifications, as the smallest concentration of radioactive material in an unknown sample that will be detected with 95% probability with a 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 ab E-V 2.22* Y e te.

Where:

LLD is the "a priori' lower limit of detection as defined above, as picocuries per unit mass or volume.

Ob = (N/tb)yZ

= standard deviation of background (cpm)

N = background count rate (cpm) tb = time background counted for (min)

E = counting efficiency, as counts per disintegration V = volume or mass of sample 2.22 = conversion factor (dpm/pCi)

Y = fractional radiochemical yield

= radioactive decay constant of ith nuclide (sec')

te = elapsed time between sampling collection and counting (sec)

Brunswick Units 1 and 2 7.3.15-13 Rev. 25

Radiological Environmental Monitoring Program 7.3.15 Table 7.3.15-3 (page 3 of 3)

Detection Capabilities for Environmental Sample Analysis Typical values of E, V, Y, and te should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs shall be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(c) LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCV1 may be used.

Brunswick Units 1 and 2 7.3.15-14

. _. ._ . . pai. v9r LW

Land Use Census Land Use Census 7.3.16 7.3.16 LAND USE CENSUS ODCMS 7.3.16 A land use census shall be conducted and:

a. Shall identify the location of the nearest milk animal, residence, and garden of greater than 50m 2 (500 ft2) producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles);

b. Shall identify (for elevated releases as defined in Regulator Guide 1.1 11, Revision 1, July 1977) the location of all milk animals and all gardens of greater than 50m 2 producing broadleaf vegetation in each of the 16 meteorological sectors within a distance of 5 km (3 miles);

c. The calculated dose and dose commitment at each identified location shall be less than the most recent values calculated by TR 7.3.9.1; and

d. The calculated dose and dose commitment at each identified location, via the same exposure pathways, shall be < 120% of the actual dose and dose commitment from the current sample location identified in Table 7.3.15-1, excluding the central station location.

r------------------------------------------------

NOTE In lieu of the garden census of ODCMS 7.3.1 6.a, broadleaf vegetable sampling of at least 3 different kinds of vegetation may be performed at the SITE BOUNDARY in each of 2 different direction sectors with the highest D/Qs. Specifications for broadleaf vegetation sampling of Table 7.3.15-1 (item 4.c) shall be followed, including analysis of control samples.

APPLICABILITY: At all times.

Brunswick Units 1 and 2 7.3.16-1 Rev. 25

Land Use Census 7.3.16 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of NOTE Annual Radiological current calendar Required Compensatory Environmental Operating year Annual Measure A.1 shall be Report, a description for Radiological completed if this Condition not conducting the land Environmental

'is entered. use census and the Operating Report corrective actions to Land use census not prevent recurrence.

conducted.

OR All required locations not identified.

B. _-___-B.1 Identify new location(s) in Upon submittal of NOTE - the Radioactive Effluent the current Required Compensatory Release Report. calendar year Measure B.1 shall be Radioactive completed if this Condition Effluent Release is entered. Report One or more identified locations with the calculated dose or dose commitment greater than the values calculated by TR 7.3.9.1.

(continued)

Brunswick Units 1 and 2 7.3. 16-2 Rev. 25

Land Use Census 7.3.16 (continued) vvw g o5*-- - - MFASIJRES rnMPFINJATORY --_--- I- ---

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. C.1 Add the new location to 30 days r ----------------- I the Radiological NOTE IRequired Compensatory Environmental Monitoring I Measure C.1 shall be Program.

Icompleted if this Condition Iis entered. AND C.2 Delete the sampling After October 31 of One or more identified the year in which location having the lowest locations with the land use census calculated dose or dose calculated dose or dose was conducted commitment, via the same commitment, via the same exposure pathway, from exposure pathway, > 120%

of the actual dose or dose the Radiological Monitoring program.

commitment from the current location identified in Table 7.3.15-1. AND C.3 Identify the new Upon submittal of location(s) in the the current Radioactive Effluent calendar year Release Report, and the Radioactive revised figure(s) and table Effluent Release for the ODCM reflecting Report the new location.

Brunswick Units 1 and 2 7.3.1 6-3 Rev. 25

Land Use Census 7.3.16 TEST REQUIREMENTS TEST FREQUENCY TR 7.3.16.1 Conduct a land use census during the growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities; identify all required locations, and verify the calculated dose and dose commitments at each identified location is within limits.

Brunswick Units 1 and 2 7.3.16-4 Rev. 25

Interlaboratory Comparison Program 7.3.17 7.3.17 INTERLABORATORY COMPARISON PROGRAM ODCMS 7.3.17 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program approved by the NRC.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. A.1 Prepare and submit, in the Upon submittal of NOTE Annual Radiological current calendar Required Compensatory Environmental Operating year Annual Measure A.1 shall be Report, corrective actions Radiological completed if this Condition , to prevent recurrence. Environmental is entered. Operating Report Requirements of ODCMS 7.3.17 not met.

TEST REQUIREMENTS TEST FREQUENCY TR 7.3.17.1 Perform the analyses required by the Interlaboratory In accordance with Comparison Program. the ODCM Brunswick Units 1 and 2 7.3.1 7-1 Rev. 25

Reporting Requirements Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS ODCMS 7.4.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include:

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impact of the plant operation on the environment;

b. Results of the land use census required by ODCMS 7.3.16;

c. A summary description of the radiological environmental monitoring program;

d. At least two legible maps of all sampling locations keyed to a table giving distances and directions from the centerline of one reactor (one map shall cover stations near the SITE BOUNDARY and the second map shall include more distant stations);

e. Results of the Interlaboratory Comparison Program required by ODCMS 7.3.17;

f. Discussion of all deviations from the sampling schedule of Table 7.3.15-1; and

g. Discussion of all analyses in which the LLD required by Table 7.3.15-3 was not achievable.

ODCMS 7.4.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the Radioactive Effluent Release Report shall include:

(continued)

Brunswick Units 1 and 2 7.4.0-1 Rev. 25

Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)

ODCMS 7.4.2 Radioactive Effluent Release Report (continued)

a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released for the facility as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis similar to the format of Appendix B thereof.

b. Information specified below for each class of solid waste (as defined by 10 CFR Part 61, when implemented) shipped offsite during the report period:

1. Container volume;

2. Total curie quantity (specify whether determined by measurement or estimate);

3. Principal radionuclides (specify whether determined by measurement or estimate);

4. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms);

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity);

and

6. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

c. A list and description of unplanned releases from the site to the UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

d. Any changes made during the reporting period to the Process Control Program (PCP) or the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to ODCMS 7.3.16.

(continued)

Brunswick Units 1 and 2 7.4.0-2 Rev. 25

Reporting Requirements 7.4.0 7.4.0 REPORTING REQUIREMENTS (continued)

ODCMS 7.4.2 Radioactive Effluent Release Report (continued)

e. A summary of radioactivity released from the site by incineration of radioactive waste oil.

f. An annual summary of hourly meteorological data collected over the previous calendar year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission of this summary of required meteorological data with the Radioactive Effluent Release Report, the summary of required meteorological data may be retained in a file that shall be provided to the NRC upon request.

g. An assessment of radiation doses due to radioactive liquid and gaseous effluents released from the station during the previous calendar year.

Brunswick Units 1 and 2 7.4.0-3 Rev. 25

Major Changes to Radioactive Waste Treatment Systems Major Changes to Radioactive Waste Treatment Systems 7.5.0 7.5.0 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ODCMS 7.5.1 Licensee initiated major changes to the liquid, gaseous, and solid Radioactive Waste Treatment Systems shall be reported to the NRC as part of the Radioactive Effluent Release Report or as part of the annual UFSAR update. 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 10 CFR Part 50.59;

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 that shows the predicted release of radioactive materials in the liquid and gaseous effluents and quantity of solid waste differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change that shows the expected maximum exposure to an 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 and in solid wastes, to the actual releases 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 by the PNSC.

ODCMS 7.5.2 The change shall become effective upon review and acceptance by the PNSC.

Brunswick Units 1 and 2 7.5.0-1 R ev. 25

ODCMS Applicability B 7.3.0 B 7.3.0 OFFSITE DOSE CALCULATION MANUAL SPECIFICATION (ODCMS)

APPLICABILITY BASES ODCMSs ODCMS 7.3.0.1 through ODCMS 7.3.0.6 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

ODCMS 7.3.0.1 ODCMS 7.3.0.1 establishes the Applicability statement within each individual ODCMS as the requirement for when the ODCMS is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each ODCMS).

ODCMS 7.3.0.2 ODCMS 7.3.0.2 establishes that upon discovery of a failure to meet an ODCMS, the associated COMPENSATORY MEASURES shall be met.

The Completion Time of each Required Compensatory Measure for a COMPENSATORY MEASURES Condition is applicable from the point in time that a COMPENSATORY MEASURES Condition is entered. The Required Compensatory Measures establish those remedial measures that must be taken within specified Completion Times when the requirements of an ODCMS are not met. This ODCMS establishes that:

a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with an ODCMS; and

b. Completion of the Required Compensatory Measures is not required when an ODCMS is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Compensatory Measures. The first type of Required Compensatory Measure specifies a time limit in which the ODCMS must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Compensatory Measure is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the ODCMS is not applicable. (Whether stated as a Required Compensatory Measure or not, correction of the entered (continued)

Brunswick Units 1 and 2 B 7.3.0-1 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Condition is a compensatory measure that may always be considered (continued) upon entering COMPENSATORY MEASURES.) The second type of Required Compensatory Measure specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Compensatory Measures provides an acceptable level of safety for continued operation.

Completing the Required Compensatory Measures is not required when an ODCMS is met or is no longer applicable, unless otherwise stated in the individual ODCMSs.

The nature of some Required Compensatory Measures of some Conditions necessitates that, once the Condition is entered, the Required Compensatory Measures must be completed even though the associated Condition no longer exists. The individual ODCMS's COMPENSATORY MEASURES specify the Required Compensatory Measures where this is the case.

The Completion Times of the Required Compensatory Measures are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the COMPENSATORY MEASURES include, but are not limited to, performance of Tests, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering COMPENSATORY MEASURES for these reasons must be done in a manner that does not compromise safety. Intentional entry into COMPENSATORY MEASURES should not be made for operational convenience.

Alternatives that would not result in redundant equipment being inoperable should be used instead. Doing so limits the time both subsystems/ divisions of a safety function are inoperable. Individual ODCMSs may specify a time limit for performing a TR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Compensatory Measures are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Compensatory Measures, the unit may enter a MODE or other specified condition in which another ODCMS becomes applicable. In this case, the Completion Times of the associated (continued)

Brunswick Units 1 and 2 B 7.3.0-2 Rev. 25

ODCMS Applicability ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.2 Required Compensatory Measures would apply from the point in time (continued) that the new ODCMS becomes applicable and the COMPENSATORY MEASURES Condition(s) are entered.

ODCMS 7.3.0.3 Not used.

ODCMS 7.3.0.4 ODCMS 7.3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an ODCMS is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:

a. Unit conditions are such that the requirements of the ODCMS would not be met in the Applicability desired to be entered; and

b. Continued noncompliance with the ODCMS requirements, if the Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the Required Compensatory Measures.

Compliance with Required Compensatory Measures that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Compensatory Measures.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before unit startup.

The provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES. In addition, the provisions of ODCMS 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

(continued)

Brunswick Units 1 and 2 B 7.3.0-3 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.4 Exceptions to ODCMS 7.3.0.4 are stated in the individual Tests.

(continued) Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of an ODCMS.

Tests do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by TR 7.3.0.1. Therefore, changing MODES or other specified conditions while in a COMPENSATORY MEASURES Condition, either in compliance with ODCMS 7.3.0.4 or where an exception to ODCMS 7.3.0.4 is stated, is not a violation of TR 7.3.0.1 or TR 7.3.0.4 for those Tests that do not have to be performed due to the associated inoperable equipment. However, TRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected ODCMS.

ODCMS 7.3.0.5 ODCMS 7.3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with COMPENSATORY MEASURES. The sole purpose of this ODCMS is to provide an exception to ODCMS 7.3.0.2 (e.g., to not comply with the applicable Required Compensatory Measure(s)) to allow the performance of TRs to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the COMPENSATORY MEASURES is limited to the time absolutely necessary to perform the allowed TRs. This ODCMS does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is taking an inoperable channel or trip system out of the tripped condition after it has been tripped to comply with Required Compensatory Measures since it must be untripped to perform the TRs.

(continued)

Brunswick Units 1 and 2 B 7.3.0-4 Rev. 25

ODCMS Applicability B 7.3.0 BASES ODCMS 7.3.0.5 An example of demonstrating the OPERABILITY of other equipment is (continued) taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of a TR on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a TR on another channel in the same trip system.

ODCMS 7.3.0.6 ODCM 7.3.0.6 delineates the applicability of each ODCMS and associated COMPENSATORY MEASURE to Brunswick Unit 1 and Brunswick Unit 2 operations.

Brunswick Units 1 and 2 B 7.3.0-5 Rev. 25

TR Applicability B 7.3.0 B 7.3.0 TEST REQUIREMENT (TR) APPLICABILITY BASES TRs TR 7.3.0.1 through TR 7.3.0.5 establish the general requirements applicable to all ODCMSs and apply at all times, unless otherwise stated.

TR 7.3.0.1 TR 7.3.0.1 establishes the requirement that TRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the ODCMS apply, unless otherwise specified in the individual TRs. This ODCMS is to ensure that Tests are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Test within the specified Frequency, in accordance with TR 7.3.0.2, constitutes a failure to meet an ODCMS.

Systems and components are assumed to be OPERABLE when the associated TRs have been met. Nothing in this ODCMS, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the TRs; or

b. The requirements of the Test(s) are known to be not met between required Test performances.

Tests do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated ODCMS are not applicable, unless otherwise specified.

Tests, including Tests invoked by Required Compensatory Measures, do not have to be performed on inoperable equipment because the COMPENSATORY MEASURES define the remedial measures that apply. Tests have to be met and performed in accordance with TR 7.3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in accordance with TR 7.3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the (continued)

Brunswick Units 1 and 2 B 7.3.0-6 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.1 Applicability due to the necessary unit parameters not having been (continued) established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

TR 7.3.0.2 TR 7.3.0.2 establishes the requirements for meeting the specified Frequency for Tests and any Required Compensatory Measure with a Completion Time that requires the periodic performance of the Required Compensatory Measure on a "once per..." interval.

TR 7.3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Test scheduling and considers plant operating conditions that may not be suitable for conducting the Test (e.g., transient conditions or other ongoing Test or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Test at its specified Frequency. This is based on the recognition that the most probable result of any particular Test being performed is the verification of conformance with the TRs.

As stated in TR 7.3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Compensatory Measure, whether it is a particular Test or some other remedial action, is considered a single compensatory measure with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such a compensatory measure may verify that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

(continued)

Brunswick Units 1 and 2 R 7.3.0-7 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.2 The provisions of TR 7.3.0.2 are not intended to be used repeatedly (continued) merely as an operational convenience to extend Test intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

TR 7.3.0.3 TR 7.3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Test has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less, applies from the point in time that it is discovered that the Test has not been performed in accordance with TR 7.3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Tests that have been missed. This delay period permits the completion of a Test before complying with Required Compensatory Measures or other remedial measures that might preclude completion of the Test.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Test, the safety significance of the delay in completing the required Test, and the recognition that the most probable result of any particular Test being performed is the verification of conformance with the requirements.

When a Test with a Frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, TR 7.3.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the Test.

TR 7.3.0.3 also provides a time limit for completion of Tests that become applicable as a consequence of MODE changes imposed by Required Compensatory Measures.

(continued)

Brunswick Units 1 and 2 B 7.3.0-8 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.3 Failure to comply with specified Frequencies for TRs is expected to be (continued) an infrequent occurrence. Use of the delay period established by TR 7.3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Test intervals.

If a Test is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon expiration of the delay period. If a Test is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Compensatory Measures for the applicable ODCMS Conditions begin immediately upon the failure of the Test.

Completion of the Test within the delay period allowed by this ODCMS, or within the Completion Time of the COMPENSATORY MEASURES, restores compliance with TR 7.3.0.1.

TR 7.3.0.4 TR 7.3.0.4 establishes the requirement that all applicable TRs must be met before entry into a MODE or other specified condition in the Applicability. This ODCMS ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.

However, in certain circumstances failing to meet a TR will not result in TR 7.3.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated TR(s) are not required to be performed, per TR 7.3.0.1, which states that Tests do not have to be performed on inoperable equipment. When equipment is inoperable, TR 7.3.0.4 does not apply to the associated TR(s) since the requirement for the TR(s) to be performed is removed. Therefore, failing to perform the Test(s) within the specified Frequency does not result in a (continued)

Brunswick Units 1 and 2 B 7.3.0-9 Rev. 25

TR Applicability B 7.3.0 BASES TR 7.3.0.4 TR 7.3.0.4 restriction to changing MODES or other specified conditions of (continued) the Applicability. However, since the ODCMS is not met in this instance, ODCMS 7.3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.

The provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with COMPENSATORY MEASURES. In addition, the provisions of TR 7.3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

The precise requirements for performance of TRs are specified such that exceptions to TR 7.3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the TRs are specified in the Frequency, in the Test, or both. This allows performance of Tests when the prerequisite condition(s) specified in a Test procedure require entry into the MODE or other specified condition in the Applicability of the associated ODCMS prior to the performance or completion of a Test. A Test that could not be performed until after entering the ODCMS Applicability would have its Frequency specified such that it is not Oduem until the specific conditions needed are met. Alternately, the Test may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of TRs' annotation is found in ODCMS Section 7.1.4, Frequency.

TR 7.3.0.5 TR 7.3.0.5 delineates the applicability of the test activities to Brunswick Unit 1 and Brunswick Unit 2 operations.

Brunswick Units 1 and 2 B 7.3.0-10 Rev. 25

Radioactive Liquid Effluent Monitoring Instrumentation B 7.3.1 B 7.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the 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. The purpose of tank level indicating devices is to assure the detection and control of leaks that, if not controlled, could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

The initial CHANNEL CALIBRATION for the Table 7.3.1-1, Functions 1 and 3, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for the initial requirement. Subsequent to CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.

Brunswick Units 1 and 2 B 7.3.1 -1 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 B 7.3.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION BASES The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the 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 and 64 of Appendix A to 10 CFR Part 50.

The main condenser air ejector monitoring instrumentation, the main condenser offgas treatment system monitor, and the explosive gas monitoring instrumentation shown in Table 7.3.2-1 are not considered effluent monitoring instrumentation in the same sense as the other instrumentation listed in the table. Therefore, their alarm/trip setpoints are not necessarily set to ensure that the limits of ODCMS 7.3.7 are not exceeded.

The main condenser air ejector monitoring instrumentation channels are provided to monitor and control gross radioactivity removed from the main condenser. The alarm/trip setpoints for the main condenser air ejector monitor are set to ensure that the limits of Technical Specification 3.7.5 are not exceeded. The alarm/trip setpoint for this monitor shall be calculated in accordance with NRC approved methods to provide reasonable assurance that the potential total body accident dose will not exceed a fraction of the limits specified in 10 CFR Part 100.

This specification also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the offgas treatment system (hydrogen monitors).

The initial CHANNEL CALIBRATION for the Table 7.3.2-1, Functions 1.a, 2.a, 3.a, 4 and 6, instruments was performed using National Bureau of Standards traceable sources which verified that each detector would operate properly over its intended energy range and measurement range. For instruments which were operational prior to this specification being implernented, previously established calibration procedures may be substituted for the initial requirement. Subsequent CHANNEL CALIBRATIONS will be performed using sources that have been related to the initial calibration in order to ensure that each detector is still operational, but the sources need not span the full ranges used in the initial CHANNEL CALIBRATION.

(continued)

Brunswick Units 1 and 2 B 7.3.2-1 Rev. 25

Radioactive Gaseous Effluent Monitoring Instrumentation B 7.3.2 BASES Regulatory Guide 1.21 requires continuous sampling of iodine and particulate in gaseous effluents and subsequent analysis at least weekly. However, a short downtime period of the sample devices is necessary to accomplish applicable ODCM test requirements, sample analysis, or system purging. This time will be accounted for in sample volume calculations. As such, 45 minutes is provided to initiate the auxiliary sampling system or restore the normal sampling devices to OPERABLE status.

Reference ODCMS 7.3.0.5 and B 7.3.0.5 for the performance of post maintenance testing.

Upon identification of a loss of radioactive gaseous effluent monitoring instrumentation, steps shall be taken immediately to install auxiliary sampling. If this cannot be accomplished, releases via the associated effluent pathway shall be secured. Any monitor downtime will be accounted for in sample volume calculations.

Brunswick Units 1 and 2 B 7.3.2-2 Rev. 25

Effluents Concentration-Liquid Concentration-iquid Effluents B 7.3.3 B 7.3.3 CONCENTRATION-LIQUID EFFLUENTS BASES This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS after dilution in the discharge canal will be less than or equal to 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 for radionuclides other than dissolved and entrained noble gases. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will not result in exposures within (1) the Section I.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1302(b)(2)(i) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-l35is 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.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the Lower Limits of Detection (LLbs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manuals, HASL-300 (revised annually),

Currie, L. A. 'Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., 'Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975}.

Note that for batch releases, recirculation of at least two tank volumes shall be considered adequate for thorough mixing.

The stabilization pond and service water liquid release types represent potential release pathways and not actual release pathways. Tests of these pathways is intended to alert the plant to a potential problem; analysis for principal gamma emitters should be sufficient to meet this intent. If analysis for principal gamma emitters indicates a problem (i.e., exceeds the trigger level of 5x104 ipCi/ml), then complete sampling and analyses shall be performed as per Table 7.3.3-2. The trigger level of 5x104 JLCi/ml was chosen as being sufficient to provide reasonable assurance of accountability of all nuclides released based upon lower limits of detection and expected concentrations.

Brunswick Units 1 and 2 B 7.3.3-1 Rev. 25

Dose-Liquid Effluents Dose-iquid Effluents B 7.3.4 B 7.3.4 DOSE-LIQUID EFFLUENTS BASES This specification is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix 1,10 CFR Part 50. ODCMS 7.3.4 implements the guides set forth in Section I.A of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of 10 CFR Part 50 to assure that releases of radioactive material in liquid effluents to UNRESTRICTED AREAS 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 a MEMBER OF THE PUBLIC 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 will be 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 l," April 1977.

The dose or dose commitment to a MEMBER OF THE PUBLIC is based on the 10 CFR Part 50, Appendix I, guideline of:

a. 1.5 mrem to the total body and 5.0 mrem to any organ during any calendar quarter, and

b. 3 mrem to the total body and 10 mrem to any organ during any calendar year, from radioactive material in liquid effluents from each reactor unit to UNRESTRICTED AREAS.

This specification is written for a two unit site.

Brunswick Units 1 and 2 B 7.3.4-1 Rev. 25

Liquid Radwaste Treatment System B 7.3.5 B 7.3.5 LIQUID RADWASTE TREATMENT SYSTEM BASES The requirement that appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept was low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section I.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 I.A of Appendix I, 10 CFR Part 50, for liquid effluents.

Mechanical filtration as per system design is considered to be an appropriate component of the Liquid Radwaste Treatment System.

The requirements of 0.12 mrem total body or 0.4 mrem to any organ in a 31 -day period is based on two reactor units having a shared Liquid Radwaste Treatment System.

Brunswick Units 1 and 2 B 7.3.5-1 Rev. 25

Liquid Holdup Tanks B 7.3.6 B 7.3.6 LIQUID HOLDUP TANKS BASES The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Since the condensate storage tanks have continuous influent and effluent, stratification should not occur. Samples taken from the operating condensate transfer pump(s) vent or drain shall be deemed representative of this system.

Appropriate alternatives to the COMPENSATORY MEASURES and TEST REQUIREMENTS are acceptable if they provide reasonable assurance that in the event of an uncontrolled release of the tank's content, the resulting concentrations would be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

Brunswick Units 1 and 2 B 7.3.6-1 Rev. 25

Dose Rate-Gaseous Effluents B 7.3.7 B 7.3.7 DOSE RATE-GASEOUS EFFLUENTS BASES This specification is provided to ensure that the dose rate at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose rate 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 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2, of 10 CFR Part 20 (10 CFR Part 20.1302(b)(2)(i)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/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 mrems/year.

This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of waste oil.

With regard to footnotes (c) and (g) of Table 7.3.7-1, (1) to determine whether the Dose Equivalent 1-131 concentration in the primary coolant has increased by more than a factor of 3, the iodine-131 analysis performed after the transient will be compared to the most recent routine analysis for Dose Equivalent 1-131 concentration performed before the transient; and (2) to determine whether the main condenser air ejector noble gas monitor has increased by more than a factor of 3, the activity indicated on the monitor's chart recorder after the transient will be compared to the activity indicated on the recorder just before the transient occurred.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the Lower Limits of Detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques,' Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Brunswick Units 1 and 2 B 7.3.7-1 Rev. 25

Gases Dose Rate-Noble Dose Rate-Noble Gases B 7.3.8 B 7.3.8 DOSE RATE-NOBLE GASES BASES This specification is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.8 implements the guides set forth in Section ll.B of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of Appendix I, to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable.! The TEST REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the 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 will be 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 l," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY will be based upon the historical annual average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.

Brunswick Units 1 and 2 B 7.3.8-1 Rev. 25

Dose - lodine-1 31, lodine-1 33, Tritium, and Radionuclides in Particulate Form B 7.3.9 B 7.3.9 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM BASES This specification is provided to implement the requirements of Section II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. ODCMS 7.3.9 implements the guides set forth in Section I.C of Appendix I. The COMPENSATORY MEASURES provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept mas low as is reasonably achievable." The ODCM calculational methods specified in the TEST 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 a MEMBER OF THE PUBLIC 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 required to be consistent with the methodology provided in Regulatory Guide 1.109, Calculating 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 1.1 11, "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 specification for iodine-131, iodine-1 33, tritium, and radioactive material in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: (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.

The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.

Doses due to the incineration of waste oil will be determined in accordance with the ODCM.

Brunswick Units 1 and 2 B 7.3.9-1 Rev. 2.5

SYSTEM GASEOUS RADWASTE TREATMENT GASEOUS RADWASTE TREATMENT SYSTEM B 7.3.1 0 B 7.3.10 GASEOUS RADWASTE TREATMENT SYSTEM BASES This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept 'as low as 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 IL.D of Appendix I to 10 CFR Part

50. The GASEOUS RADWASTE TREATMENT SYSTEM refers to the 30-minute offgas holdup line, stack filter house filtration, and the Augmented Off-Gas-Treatment System.

Brunswick Units 1 and 2 B 7.3. 10-1 Rev. 25

VENTILATION EXHAUST TREATMENT SYSTEM VENTILATION EXHAUST TREATMENT SYSTEM B 7.3.11 B 7.3.11 VENTILATION EXHAUST TREATMENT SYSTEM BASES in This requirement provides reasonable assurance that the releases of radioactive materials gaseous effluents will be kept "as low as reasonably achievable." This specification implements CFR the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 Part 50. The Part 50, and the design objectives given in Section I.D of Appendix I to 10 CFR specified limits governing the use of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and I1.C of Appendix I, 10 CFR Part 50, for gaseous effluents. At the Brunswick Steam Electric Plant, the only VENTILATION EXHAUST TREATMENT SYSTEMS shall be those installed for the Turbine Buildings' ventilation.

Brunswick Units 1 and 2 B 7.3.11-1 Rev. 25

Explosive Gas Mixture B 7.3.12 B 7.3.12 EXPLOSIVE GAS MIXTURE BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen. Maintaining the concentration of hydrogen below the flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

Brunswick Units 1 and 2 B 7.3.12-1 Rev. 25

Drywell VENTING or PURGING B 7.3.13 B 7.3.13 DRYWELL VENTING or PURGING BASES This specification provides reasonable assurance that releases from drywell VENTING or PURGING operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.

Brunswick Units 1 and 2 B 7.3.13-1 Rev. 25

Total Dose (40 CFR Part 190)

B 7.3.14 B 7.3.14 TOTAL DOSE (40 CFR PART 190)

BASES This specification is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. 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 Part 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 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 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCMSs 7.3.3 through 7.3.14. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Brunswick Units 1 and 2 B 7.3.14-1 Rev. 25

Radiological Environmental Monitoring Program B 7.3.15 B 7.3.15 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways.

The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limits of Detection (LLDs). The LLDs required by Table 7.3.15-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as 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.

Detailed discussion of the LLD and other detection limits can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry' Anal. Chem 40, 586-93 (1968), and Hartwell, L. K., 'Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Groundwater is not monitored by this specification because plant liquid effluents are not tapped as a source for drinking or irrigation purposes.

In the absence of the availability of leafy vegetables intended for human consumption, sampling of indigenous broadleaf vegetation may be performed since the objective of sampling broadleaf vegetation (i.e., to approximate fallout from plant operation) is satisfied in either case.

Brunswick Units 1 and 2 B 7.3.15-1 Rev. 25

Land Use Census Land Use Census B 7.3.16 B 7.3.16 LAND USE CENSUS BASES This specification is provided to ensure that changes in the use of the area at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made, if required, as a result of the census. The best information from door-to-door surveys, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 2

10 CFR Part 50. Restricting the census to gardens of greater than 50 m 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 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine the minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broadleaf vegetation (i.e., similar to lettuce and cabbage; and (2) a vegetation yield of 2 kgim .

Brunswick Units 1 and 2 B 7.3.1 6-1 Rev. 25

Interlaboratory Comparison Program Interlaboratory Comparison Program B 7.3.17 B 7.3.17 INTERLABORATORY COMPARISON PROGRAM BASES to The requirement for participation in the Interlaboratory Comparison Program is provided 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 are assurance program for environmental monitoring in order to demonstrate that the results reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Brunswick Units 1 and 2 B 7.3.17-1 Rev. 25

LIST OF TABLES Table No. Title Page APPENDIX A A-1 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS ............................................................. A-5 A-2 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS .................. A-6 A-3 DIQ VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS .............. A-7 A-4 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS .............. A-8 A-5 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS .......................... A-9 A-6 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS .............. A-10 A-7 X/O VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS ............... A-11 A-8 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS ................... A-12 A-9 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE REACTOR BUILDINGS ............... A-13 A-10 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS ............... A-14 A-11 DEPLETED X/O VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS ........................... A-15 A-12 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE REACTOR BUILDINGS .A-16 A-13 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK ....A-17 A-14 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK ....... A-18 ODCM (BSEP) A-1 Rev. 25

LIST OF TABLES (Cont'd)

Table No. Title Paqe APPENDIX A A-15 DIQ VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE STACK ....A-1 9 A-1 6 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK ..... A-20 A-17 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK . A-21 A-1 8 DIQ VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE STACK . A-22 A-1 9 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR GROUND LEVEL CALCULATIONS WITH NRC "XOQDOQ' PROGRAM ............................................... ,.. A-23 A-20 BRUNSWICK PLANT SITE INFORMATION TO BE USED FOR ELEVATED RELEASE CALCULATIONS WITH NRC 6XOODOQ PROGRAM ...................................A-26 ODCM (BSEP) A-2 Rev. 25

APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) engaged the services of Dames and Moore to assess the transport and dispersion of the effluent in the atmosphere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide (RG) 1.1 11, Revision 1 (USNRC, 1977). The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.

Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3)the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight line described in XOQDOQ Pro-gram for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (Draft) NUREG 0324 (USNRC, September 1977) would be used for generating the required analyses of Appendixl. To provide a more realistic accounting of the variability of wind around the plant site, terrain/ recirculation correction factors (TCF) were to be determined from a combined puff-advection/straight-line scheme for a one-year meteorological data base.

Dames and Moore was provided a one-year record of meteorological data from the on-site meteorological program at the Brunswick Steam Electric Plant. This data consisted of all collected parameters at both the 11.46-meter and 104.55-meter tower levels for the year 1977. The description of the model used and the results of the computations are presented in Reference 1. The following tables from Reference 1 provide the basis for the meteorological dilution factor development of the Technical Specifications for Appendix I and were the source of the X/Q and D/Q values utilized to show compliance with 10CFR20 and 10CFR50 for noble gases and radioiodines and particulates.

Tables A-1 through A-6 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground-level release for both standard distances and special locations.

Tables A-7 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for mixed-mode release for both standard distances and special locations.

ODCIM (BSEP) A-3 Rev. 25

Tables A-1 3 through A-1 8 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for elevated release for both standard distances and special locations.

Values for X/Q, depleted X/Q, and DIQ for releases to special locations are from the standard distance tables. The values used are from the distance nearest the special location in the appropriate sector.

Future Operation Computations The NRC "XOQDOQ" Program (Revision 1) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest without a terrain/recirculation factor. The input to bXOQDOQ" for ground-level releases are presented in Table A-19 and for elevated releases in Table A-20. The resulting computations will have applied the TCFs to produce a final atmospheric diffusion estimate for the site.

In general, it is concluded that the straight-line model is as reasonable a projection of concentrations as the puff-advection model. By inclusion of the terrain correction factors developed by a combination of the puff-advection/straight-line scheme with the results of the XOQDOQ Program, ready evaluation of on-site meteorological data may be made.

Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Specifications: Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Brunswick Facility, Dames and Moore, January 18, 1979.

ODCM (BSEP) A-4 Rev. 25

TABLE A-1 X/Q Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Dairy* Meat* Resident* Garden*

Sector Boundary NNE 2.3E-06 0. 9.4E-07 9.4E-07 9.4E-07 NE 2.9E-06 1.4E-07 0. . 0. 0.

ENE 3.2E-06 0. 0. 0. 0.

E 3.9E-06 0. 1.5E-06 1.5E-06 0.

ESE 5.2E-06 0. 5.2E-06 1.OE-06 1.OE-06 SE 3.4E-06 0. 3.4E-06 3.4E-06 0.

SSE 7.5E-06 0. 7.5E-06 7.5E-06 7.5E-06 S 3.8E-06 0. 0. 1.6E-06 9.8E-07 SSW 2.8E-06 0. 1.2E-06 1.2E-06 1.2E-06 SW 2.5E-06 0. 2.5E-06 2.5E-06 2.5E-06 WSW 1.8E-06 0. 3.8 E-07 7.5 E-07 7.5 E-07 W 1.5E-06 0. 0. 1.5E-06 1.5E-06 WNW 1.2E-06 0. 0. 1.2E-06 1.2E-06 NW 9.7E-07 0. 0. 9.7E-07 9.7E-07 NNW 1.3E-06 0. 0. 1.3E-06 1.3E-06 N 1.4E-06 0. 0. 1.4E-06 1.4E-06

A zero indicates that this point was not calculated.

ODCM (BSEP) A-5 Rev. 25

TABLE A-2 Depleted X/Q Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Dairy* Meat* Resident* Garden*

Sector Boundary NNE 2.OE-06 0. 8.1 E-07 8.1 E-07 8.1 E-07 NE 2.6E-06 1.OE-07. 0. 0.

ENE 2.9E-06 0. 0. 0. 0.

E 3.4E-06 0. 1.3E-06 1.3E-06 0.

ESE 4.6E-06 0. 4.6E-06 8.7E-07 8.7E-07 SE 3.1 E-06 0. 3.1 E-06 3.1 E-06 0.

SSE 6.8E-06 0. 6.8E-06 6.8E-06 6.8E-06 S 3.5E-06 0. 0. 1.3E-06 8.1 E-07 SSW 2.5E-06 0. 1.OE-06 1.OE-06 1.OE-06 SW 2.4E-06 0. 2.4E-06 2.4E-06 2.4E-06 WSW 1.5E-06 0. 3.2E-07 6.4E-07 6.4E-07 W 1.3E-06 . 0. 0. 1.3E-06 1.3E-06 WNW 1.1 E-06 0. 0. 1.1 E-06 1.1 E-06 NW 8.7E-07 0. 0. 8.7E-07 8.7E-07 NNW 1.1 E-06 0. 0. 1.1 E-06 1.1 E-06 N 1.2E-06 0. 0. 1.2E-06 1.2E-06

A zero indicates that this point was not calculated.

ODCM (BSEP) A-6 Rev. 25

TABLE A-3 DIQ Values at the Special Locations for Releases From the Turbine Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Deposition (Meter**-2)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Sector Site Dairy* Meat* Resident* Garden*

Boundary NNE 1.3E-08 0. 4.8E-09 4.8E-09 4.8E-09 NE 1.9E-08 5.7E-10 0. 0. 0.

ENE 9.4E-09 0. 0. 0. 0.

E 8.6E-09 0. 3.1 E-09 3.1 E-09 0.

ESE 1.3E-08 0. 1.3E-08 2.2E-09 2.2E-09 SE 8.4E-09 0. 8.4E-09 8.4E-09 0.

SSE 1.5E-08 0. 1.5E-08 1.5E-08 1.5E-08 S 8.3E-09 0. 0. 3.2E-09 1.8E-09 SSW 7.7E-09 0. 3.OE-09 3.OE-09 3.0E-09 SW 1.1 E-08 0. 1.1 E-08 1.1 E-08 1.1 E-08 WSW 7.OE-09 0. 1.3E-09 2.7E-09 2.7E-09 W 5.1 E-09 0. 0. 5.1 E-09 5.1 E-09 WNW 3.8E-09 0. 0. 3.8E-09 3.8E-09 NW 3.5E-09 0. 0. 3.5E-09 3.5E-09 NNW 5.OE-09 0. 0. 5.OE-09 5.OE-09 N 6.3E-09 0. 0. 6.3E-09 6.3E-09

A zero indicates that this point was not calculated.

ODCM (BSEP) A-7 Rev. 25

TABLE A-4 X/Q Values at the Standard Distances for Releases from the Turbine Buildings.

Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Design .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Dist Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.5E-05 2.3E-06 9.4E-07 5.9E-07 3.5E-07 2.4E-07 1.9E-07 1.5E-07 1.2E-07 9.OE-08 NE 0. 2.0E-05 2.9E-06 1.3E-06 7.3E-07 4.5E-07 3.4E-07 2.7E-07 2.OE-07 1.7E-07 1.4E-07 ENE 0. 2.1 E-05 3.2E-06 1.2E-06 6.5E-07 4.8E-07 3.6E-07 2.9E-07 2.1 E-07 1.8E-07 1.4E-07 E 0. 2.9E-05 3.9E-06 1.5E-06 9.1 E-07 6.6E-07 4.4E-07 3.5E-07 2.8E-07 2.2E-07 1.9E-07 ESE 0. 3.2E-05 5.2E-06 2.2E-06 1.0E-06 6.5E-07 4.4E-07 3.6E-07 2.9E-07 2.4E-07 1.9E-07 SE 0. 2.3E-05 3.4E-06 1 .6E-06 7.9E-07 4.8E-07 3.3E-07 2A4E-07 2.2E-07 1.8E-07 1.6E-07 SSE 0. 4.4E-05 7.5E-06 3.1 E-06 1.8E-06 1.2E-06 7.7E-07 5.1 E-07 3.9E-07 3.2E-07 2.5E-07 S 0. 2.7E-05 3.8E-06 1.6E-06 9.8E-07 7.2E-07 4.9E-07 3.7E-07 2.9E-07 2.2E-07 1.8E-07 SSW 0. 1.9E-05 2.8E-06 1.2E-06 8.OE-07 4.9E-07 2.9E-07 2.3E-07 2.2E-07 1.3E-07 1.1E-07 SW 0. 1.8E-05 2.5E-06 1.1 E-06 6.6E-07 4.9E-07 2.8E-07 2.2E-07 1.7E-07 1.4E-07 1.1 E-07 WSW 0. 1.5E-05 1.8E-06 7.5E-07 3.8E-07 2.8E-07 1.8E-07 1.5E-07 1.2E-07 9.5E-08 7.9E-08 W 0. 1.3E-05 1.5E-06 6.9E-07 3.3E-07 2.2E-07 1.5E-07 1.1 E-07 9.4E-08 8.1 E-08 5.2E-08 WNW 0. 1.OE-05 1.2E-06 6.OE-07 -2.8E-07 1.6E-07 1.3E-07 8.6E-08 7.2E-08 5.4E-08 4.4E-08 NW 0. 7.1 E-06 9.7E-07 3.5E-07 2.1 E-07 1.6E-07 1.2E-07 7.8E-08 6.6E-08 4.6E-08 3.9E-08 NNW 0. 8.9E-06 1.3E-06 5.4E-07 2.7E-07 1.7E-07 1.3E-07 1.1 E-07 9.3E-08 6.6E-08 5.3E-08 N 0. 9.2E-06 1.4E-06 5.1 E-07 3.3E-07 2.1 E-07 1.6E-07 1.3E-07 1.1 E-07 8.1 E-08 7.0E-08 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 125 Number of Calms Upper Level 0 0DCM (BSEP) A-8 Rev. 25

TABLE A-5 Depleted X/Q Values at the Standard Distances for Releases from the Turbine Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Design .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Dist Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.5E-05 2.0E-06 8.1 E-07 4.82-07 2.8E-07 1.9E-07 1.5E-07 1.1E-07 8.9E-08 6.8E-08 NE 0. 1.8E-05 2.6E-06 1.1 E-06 6.1 E-07 3.7E-07 2.6E-07 2.1 E-07 1.5E-07 1.2E-07 1.OE-07 ENE 0. 2.OE-05 2.9E-06 1.OE-06 5.5E-07 3.9E-07 2.8E-07 2.2E-07 1.6E-07 1.3E-07 1.OE-07 E 0. 2.7E-05 3.4E-06 1.3E-06 7.6E-07 5.3E-07 3.5E-07 2.6E-07 2.2E-07 1.6E-07 1.4E-07 ESE 0. 3.OE-05 4.6E-06 1.9E-06 8.7E-07 5.3E-07 3.5E-07 2.8E-07 2.3E-07 1.7E-07 1.4E-07 SE 0. 2.2E-05 3.1E-06 1.3E-06 6.6E-07 3.9E-07 2.6E-07 1.9E-07 1.6E-07 1.3E-07 1.2E-07 SSE 0. 4.2E-05 6.8E-06 2.7E-06 1.5E-06 9.9E-07 6.1 E-07 4.0E-07 3.0E-07 2.4E-07 1.9E-07 S 0. 2.5E-05 3.5E-06 1.3E-06 8.1 E-07 5.9E-07 3.9E-07 2.9E-07 2.2E-07 1.6E-07 1.4E-07 SSW 0. 1.9E-05 2.5E-06 1.OE-06 6.6E-07 4.OE-07 2.32-07 1.8E-07 1.6E-07 1.0E-07 8.3E-08 SW 0. 1.7E-05 2.4E-06 9.8E-07 5.5E-07 3.9E-07 2.3E-07 1.7E-07 1.3E-07 1.1 E-07 9.OE-08 WSW 0. 1.4E-05 1.5E-06 6.4E-07 3.2E-07 2.2E-07 1.4E-07 1.1 E-07 9.2E-08 7.OE-08 5.9E-08 W 0. 1.2E-05 1.3E-06 5.9E-07 2.7E-07 1.8E-07 1.1E-07 8.3E-08 7.2E-08 6.1 E-08 3.8E-08 WNW 0. 9.9E-06 1.1E-06 5.2E-07 2.4E-07 1.3E-07 1.OE-07 6.6E-08 5.5E-08 4.1 E-08 3.3E-08 NW 0. 6.7E-06 8.72-07 3.OE-07 1.8E-07 1.3E-07 9.4E-08 6.1 E-08 5.1 E-08 3.5E-08 3.OE-08 NNW 0. 8.5E-06 1.1 E-06 4.7E-07 2.2E-07 1.3E-07 1.1E-07 8.3E-08 7.2E-08 5.OE-08 3.9E-08 N 0. 8.6E-06 1.2E-06 4.4E-07 2.8E-07 1.7E-07 1.3E-07 1.02-07 8.2E-08 6.1 E-08 5.1 E-08 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 125 Number of Calms Upper Level 0 ODCM (BSEP) A-9 Rev. 25

TABLE A-6 D/Q Values at the Standard Distances for Releases from the Turbine Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Design Dist .25 .75 - 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 8.6E-08 1.3E-08 4.8E-09 2.82-09 1.5E-09 9.9E-10 7.7E-10 5.7E-10 4.3E-10 3.32-10 NE 0. 1.3E-07 1.9E-08 7.6E-09 4.0E-09 2.3E-09 1.6E-09 1.3E-09 8.8E-10 6.8E-10 5.7E-10 ENE 0. 5.8E-08 9.4E-09 3.2E-09 1.6E-09 1.12-09 7.5E-10 5.5E-10 3.9E-10 3.0E-10 2.3E-10 E 0. 6.2E-08 8.6E-09 3.1 E-09 1.7E-09 1.1 E-09 6.9E-10 5.1 E-10 3.9E-10 2.9E-10 2.3E-10 ESE 0. 7.2E-08 1.3E-08 5.0E-09 2.2E-09 1.2E-09 7.6E-10 6.0E-10 4.7E-10 3.5E-10 2.6E-10 SE 0. 5.1E-08 8.4E-09 3.3E-09 1.6E-09 8.6E-10 5.6E-10 3.8E-10 3.3E-10 2.6E-10 2.2E-10 SSE 0. 8.2E-08 1.5E-08 5.8E-09 3.OE-09 1.8E-09 1.1E-09 6.8E-10 4.9E-10 3.8E-10 2.9E-10 S 0. 5.6E-08 8.3E-09 3.2E-09 1.8E-09 1.2E-09 7.5E-10 5.4E-10 3.9E-10 2.9E-10 2.3E-10 SSW 0. 5.2E-08 7.7E-09 3.OE-09 1.9E-09 1.1E-09 5.8E-10 4.3E-10 3.8E-10 2.2E-10 1.8E-10 SW 0. 7.5E-08 1.1E-08 4.3E-09 2.42-09 1.6E-09 8.8E-10 6.4E-10 4.6E-10 3.7E-10 3.1 E-10 WSW 0. 6.0E-08 7.OE-09 2.7E-09 1.3E-09 8.8E-10 5.2E-10 4.OE-10 3.3E-10 2.4E-10 2.OE-10 W 0. 4.1 E-08 5.1 E-09 2.0E-09 9.2E-10 5.7E-10 3.6E-10 2.62-10 2.1 E-10 1.7E-10 1.OE-10 WNW 0. 3.4E-08 3.8E-09 1.7E-09 7.3E-10 3.9E-10 3.0E-10 1.9E-10 1.5E-10 1.1E-10 8.4E-11 NW 0. 2.7E-08 3.5E-09 1.1 E-09 6.6E-10 4.7E-10 3.3E-10 2.1 E-10 1.7E-10 1.1E-10 9.6E-11 NNW 0. 3.6E-08 5.0E-09 1.9E-09 8.5E-10 5.0E-10 3.8E-10 2.8E-10 2.4E-10 1.6E-10 1.3E-10 N 0. 4.4E-08 6.3E-09 2.1 E-09 1.3E-09 8.OE-10 5.6E-10 4.5E-10 3.5E-10 2.5E-10 2.1 E-10 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 125 Number of Calms Upper Level 0 ODCM (BSEP) A-1 0 Rev. 25

TABLE A-7 X/Q Values at the Special Locations for Releases From the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Boundary Dairy* Meat' Resident* Garden*

Sector NNE 1.OE-07 0. 7.8E-08 7.8E-08 7.8E-08 NE 2.OE-07 4.1 E-08 0. 0. 0.

ENE 6.5E-08 0. 0. 0. 0.

E 4.8E-08 0. 3.5E-08 3.5E-08 0.

ESE 6.9E-08 0. 6.9E-08 3.9E-08 3.9E-08 SE 4.1 E-08 0. 4.1 E-08 4.1 E-08 0.

SSE 7.6E-08 0. 7.6E-08 7.6E-08 7.6E-08 S 4.5E-08 0. 0. 3.5E-08 2.8E-08 SSW 4.7E-08 0. 4.7E-08 4.7E-08 4.7E-08 SW 6.4E-08 0. 6.4E-08 6.4E-08 6.4E-08 WSW 4.1 E-08 0. 3.9E-08 4.3E-08 4.3E-08 W 3.4E-08 0. 0. 3.4E-08 3.4E-08 WNW 1.8E-08 0. 0. 1.8E-08 1.8E-08 NW 1.9E-08 0. 0. 1.9E-08 1.9E-08 NNW 3.2E-08 0. O. 3.2E-08 3.2E-08 N 4.OE-08 0. 0. 4.0E-08 4.OE-08

A zero indicates that this point was not calculated.

ODCM (BSEP) A-11 Rev. 25

TABLE A-8 Depleted X/Q Values at the Special Locations for Releases From the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Dairy* Meat* Resident* Garden*

Sector Boundary NNE 9.1 E-08 0. 7.8E-08 7.8E-08 7.8E-08 NE 1.9E-07 3.7E-08 0. 0. 0.

ENE 6.1 E-08 0. 0. 0. 0.

E 4.4E-08 0. 3.2E-08 3.2E-08 0.

ESE 6.4E-08 0. 6.4E-08 3.7E-08 3.7E-08 SE 3.8E-08 0. 3.8E-08 3.8E-08 0.

SSE 7.1 E-08 0. 7.1 E-08 7.1 E-08 7.1 E-08 S 4.2E-08 0. 0. 3.3E-08 2.7E-08 SSW 4.3E-08 0. 4.4E-08 4.4E-08 4.4E-08 SW 6.0E-08 0. 6.OE-08 6.OE-08 6.OE-08 WSW 3.9E-08 0. 3.8E-08 4.2E-08 4.2E-08 W 3.3E-08 0. 0. 3.3E-08 3.3E-08 WNW 1.7E-08 0. 0. 1.7E-08 1.7E-08 NW 1.8E-08 0. 0. 1.8E-08 1.8E-08 NNW 3.OE-08 0. 0. 3.OE-08 3.OE-08 N 3.7E-08 0. 0. 3.7E-08 3.7E-08

A zero indicates that this point was not calculated.

ODCM (BSEP) A-1 2 Rev. 25

TABLE A-9 D/Q Values at the Special Locations for Releases From the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Deposition (Meter**-2)

Calculation Points: Special Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Boundary Dairy* Meat* Resident* Garden*

Sector NNE 2.OE-09 0. 1.1 E-09 1.1 E-09 1.1 E-09 NE 4.3E-09 2.7E-10 0. 0. 0.

ENE 1.1 E-09 0. 0. 0. 0.

E 4.6E-10 0. 2.5E-10 2.5E-10 0.

ESE 1.1 E-09 0. 1.1 E-09 3.3E-10 3.3E-10 SE 7.6E-10 0. 7.6E-10 7.6E-10 0.

SSE 1.2E-09 0. - 1.2E-09 1.2E-09 1.2E-09 S 5.7E-10 0. 0. 3.4E-10 2.3E-10 SSW 7.7E-10 0. 5.2E-10 5.2E-10 5.2E-10 SW 1.2E-09 0. 1.2E-09 1.2E-09 1.2E-09 WSW 8.9E-10 0. 4.1 E-10 5.9E-10 5.9E-10 W 6.6E-10 0. 0. 6.6E-10 6.6E-10 WNW 2.7E-10 0. 0. 2.7E-10 2.7E-10 NW 3.1E-10 0. 0. 3.1E-10 3.1E-10 NNW 4.OE-10 0. 0. 4.0E-10 4.0E-10 N 5.6E-10 0. 0. 5.6E-10 5.6E-10

A zero indicates that this point was not calculated.

ODCM (BSEP) A-13 Rev. 25

TABLE A-1 0 X/Q Values at the Standard Distances for Releases from the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Design .25 .75- 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Dist Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 5.6E-07 1.OE-07 7.8E-08 6.3E-08 5.2E-08 4.1 E-08 3.6E-08 3.1 E-08 2.7E-08 2.4E-OE NE 0. 5.5E-07 2.OE-07 1.5E-07 1.2E-07 9.4E-08 7.6E-08 6.3E-08 5.3E-08 4.6E-08 4.1 E-OE ENE 0. 1.6E-06 6.5E-08 5.8E-08 5.4E-08 4.9E-08 4.3E-08 3.9E-08 3.5E-08 3.1 E-08 2.9E-0E E 0. 2.9E-07 4.8E-08 3.5E-08 2.9E-08 2.7E-08 2.3E-08 2.2E-08 1.82-08 1.7E-08 1.5E-OE ESE 0. 1.2E-07 6.9E-08 5.0E-08 3.9E-08 3.5E-08 3.1 E-08 2.6E-08 2.3E-08 2.0E-08 1.7E-0E SE 0. 7.8E-08 4.1 E-08 3.6E-08 2.7E-08 2.OE-08 1.8E-08 1.7E-08 1.5E-08 1.3E-08 1.2E-OE SSE 0. 2.2E-07 7.6E-08 5.6E-08 4.2E-08 3.5E-08 2.9E-08 2.5E-08 2.2E-08 1.9E-08 1.6E-0E S 0. 4.2E-07 4.5E-08 3.5E-08 2.8E-08 2.5E-08 2.4E-08 2.1E-08 1.8E-08 1.6E-08 1.4E-OE SSW 0. 5.9E-07 4.7E-08 4.7E-08 4.1 E-08 3.7E-08 2.9E-08 2.7E-08 2.3E-08 2.OE-08 1.8E-Of SW 0. 1.8E-07 6.4E-08 5.5E-08 4.42-08 3.8E-08 3.1 E-08 2.7E-08 2.4E-08 2.1 E-08 1.9E-Of WSW 0. 8.9E-08 4.1 E-08 4.3E-08 3.9E-08 3.4E-08 2.82-08 2.5E-08 2.5E-08 2.2E-08 1.9E-Of W 0. 3.6E-08 3.4E-08 3.8E-08 3.7E-08 3.1 E-08 2.8E-08 2.6E-08 2.2E-08 2.1 E-08 1.8E-Of WNW 0. 4.1 E-08 1.8E-08 2.2E-08 2.42-08 2.3E-08 2.0E-08 1.8E-08 1.6E-08 1.4E-08 1.2E-Of NW 0. 3.OE-08 1.9E-08 2.3E-08 2.0E-08 1.9E-08 1.9E-08 1.6E-08 1.42-08 1.3E-08 1.2E-0O NNW 0. 4.9E-07 3.2E-08 2.7E-08 2.4E.-08 2.0E-08 1.8E-08 1.6E-08 1.5E-08 1.4E-08 1.3E-01 N 0. 6.3E-07 4.0E-08 3.OE-08 2.9E-08 2.7E-08 2.6E-08 2.62-08 2.1 E-08 1.8E-08 1.72-01 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 125 Number of Calms Upper Level 0 ODCM (BSEP) A-14 Rev. 25

TABLE A-1 1 Depleted x/Q Values at the Standard Distances for Releases from the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Sect Design Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 5.4E-07 9.1 E-08 7.8E-08 5.9E-08 4.9E-08 3.8E-08 3.3E-08 2.8E-08 2.5E-08 2.2E-08 NE 0. 5.3E-07 1.9E-07 1.4E-07 1.1E-07 8.7E-08 7.1 E-08 5.9E-08 5.OE-08 4.3E-08 3.7E-08 ENE 0. 1.5E-06 6.1 E-08 5.6E-08 5.2E-08 4.7E-08 4.1 E-08 3.7E-08 3.3E-08 3.0E-08 2.8E-08 E 0. 2.8E-07 4.4E-08 3.2E-08 2.7E-08 2.5E-08 2.2E-08 2.1 E-08 1.8E-08 1.6E-08 1.4E-08 ESE 0. 1.1 E-07 6.4E-08 4.6E-08 3.7E-08 3.3E-08 2.9E-08 2.4E-08 2.2E-08 1.8E-08 1.6E-08 SE 0. 7.4E-08 3.8E-08 3.3E-08 2.5E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 SSE 0. 2.1 E-07 7.1 E-08 5.2E-08 3.9E-08 3.2E-08 2.6E-08 2.3E-08 2.OE-08 1.7E-08 1.5E-08 5 0. 4.OE-07 4.2E-08 3.3E-08 2.7E-08 2.3E-08 2.3E-08 1.9E-08 1.7E-08 1.5E-08 1.3E-08 SSW 0. 5.9E-07 4.3E-08 4.4E-08 3.9E-08 3.5E-08 2.7E-08 2.6E-08 2.2E-08 1.9E-08 1.7E-08 SW 0. 1.7E-07 6.0E-08 5.2E-08 4.2E-08 3.6E-08 2.9E-08 2.5E-08 2.2E-08 2.OE-08 1.7E-08 WSW 0. 8.2E-08 3.9E-08 4.2E-08 3.8E-08 3.2E-08 2.7E-08 2.4E-08 2.4E-08 2.1 E-08 1.8E-08 W 0. 3.4E-08 3.3E-08 3.6E-08 3.6E-08 3.0E-08 2.7E-08 2.5E-08 2.1 E-08 2.0E-08 1.7E-08 WNW 0. 3.9E-08 1.7E-08 2.1 E-08 2.3E-08 2.2E-08 1.9E-08 1.7E-08 1.6E-08 1.3E-08 1.1 E-08 NW 0. 2.9E-08 1.8E-08 2.3E-08 2.02-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.3E-08 1.2E-08 NNW 0. 4.5E-07 3.0E-08 2.5E-08 2.3E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 N 0. 5.8E-07 3.7E-08 2.9E-08 2.8E-08 2.6E-08 2.5E-08 2.4E-08 2.0E-08 1.7E-08 1.6E-08 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 12 Number of Calms Upper Level 0 ODCM (BSEP) A-1 5 Rev. 25

TABLE A-1 2 D/Q Values at the Standard Distances for Releases from the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Design Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Ml .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.1 E-08 2.OE-09 1.1E-09 7.2E-10 5.OE-10 3.5E-10 2.8E-10 2.2E-10 1.7E-10 1.5E-10 NE 0. 1.1E-08 4.3E-09 2.3E-09 1.5E-09 9.8E-10 7.2E-10 5.3E-10 4.2E-10 3.3E-10 2.7E-10 ENE 0. 1.9E-08 1.1E-09 5.8E-10 3.9E-10 2.8E-10 2.2E-10 1.7E-10 1.4E-10 1.1E-10 9.7E-11 E 0. 2.1 E-09 4.6E-10 2.5E-10 1.6E-10 1.2E-10 9.0E-11 7.5E-11 5.7E-11 4.8E-11 3.8E-11 ESE 0. 1.3E*09 1.1 E-09 5.4E-10 3.3E-10 2.4E-10 1.9E-10 1.3E-10 1.1E-10 8.3E-11 6.9E-11 SE 0. 1.3E-09 7.6E-10 4.9E-10 2.8E-10 1.8E-10 1.3E-10 1.1 E-10 8.9E-11 6.7E-11 6.1 E-11 SSE O. 2.4E-09 1.2E-09 6.7E-10 4.1 E-10 2.8E-10 2.1 E-.10 1.6E-10 1.3E-10 1.OE-10 8.2E- 11 S 0. 3.6E-09 5.7E-10 3.4E-10 2.3E-10 1.7E-10 1.4E-10 1.OE-10 8.2E-11 6.5E-11 5.5E-11 SSW 0. 8.OE-09 7.7E-10 5.2E-10 3.5E-10 2.6E-10 1.8E-10 1.5E-10 1.1E-10 9.3E-11 7.4E-11 SW 0. 3.4E-09 1.2E-09 7.3E-10 4.5E-10 3.3E-10 2.3E-10 1.7E-10 1.4E-10 1.2E-10 9.4E-11 WSW 0. .1.8E-09 8.9E-10 5.9E-10 4.1 E-10 2.9E-10 2.1 E-10 1.7E-10 1.5E-10 1.2E-10 1.OE-10 W 0. 7.9E-10 6.6E-10 4.3E-10 2.9E-10 1.9E-10 1.5E-10 1.2E-10 8.6E-11 7.7E-11 6.4E-11 WNW 0. 5.8E-10 2.7E-10 2.OE-10 1.7E-10 1.3E-10 8.8E-11 6.8E-11 5.5E-11 4.2E-11 3.3E-11 NW 0. 5.4E-10 3.1 E-10 2.3E-10 1.5E-10 1.1E-10 8.9E-11 6.9E-11 5.4E-11 4.4E-11 3.9E-11 NNW 0. 5.3E-09 4.OE-10 2.2E-10 1.6E-10 1.OE-10 7.6E-11 6.1 E-11 5.OE-11 4.2E-11 3.4E-11 N 0. 8.7E-09 5.6E-10 2.8E-10 2.1 E-10 1.6E-10 1.4E-10 1.1E-10 8.1 E-11 6.4E-11 5.7E-11 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 12 Number of Calms Upper Level 0 ODCM (BSEP) A-1 6 Rev. 25

TABLE A-13

- x/Q Values at the Special Locations for Releases From the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Concentration Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Dairy* Meat* Resident* Garden*

Sector Boundary NNE 1.3E-08 0. 2.3E-08 2.3E-08 2.3E-08 NE 2.5E-08 2.4E-08 0. 0. 0.

ENE 7.2E-09 0. 0. 0. 0.

E 3.6E-09 0. 7.6E-09 7.6E-09 0.

ESE 7.7E-09 0. 7.7E-09 1.3E-08 1.3E-08 SE 8.7E-09 0. 8.7E-09 8.7E-09 0.

SSE 1.2E-08 0. 1.2E-08 1.2E-08 1.2E-08 S 4.7E-09 0. 0. 8.5E-09 9.6E-09 SSW 6.0E-09 0. 1.4E-08 1.4E-08 1.4E-08 SW 1.3E-08 0. 1.3E-08 1.3E-08 1.3E-08 WSW 9.OE-09 0. 1.8E-08 1.6E-08 1.6E-08 W 1.OE-08 0. 0. 1.OE-08 1.OE-08 WNW 5.3E-09 0. 0. 5.3E-09 5.3E-09 NW 6.5E-09 0. 0. 6.5E-09 6.5E-09 NNW 4.2E-09 0. 0. 4.2E-09 4.2E-09 N 4.5E-09 0. 0. 4.5E-09 4.5E-09

A zero indicates that this point was not calculated.

ODCM (BSEP) A-17 Rev. 25

TABLE A-14 Depleted X/Q Values at the Special Locations for Releases From the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Depleted Concentrations Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Dairy* Meat* Resident* Garden*

Sector Boundary NNE 1.2E-08 0. 2.2E-08 2.2E-08 2.2E-08 NE 2.5E-08 2.3E-08 0. 0. 0.

ENE 7.1 E-09 0. 0. 0. 0.

E 3.6E-09 0. 7.6E-09 7.6E-09 0.

ESE 7.5E-09 0. 7.5E-09 1.2E-08 1.2E-08 SE 8.7E-09 0. 8.7E-09 8.7E-09 0.

SSE 1.2E-08 0. 1.2E-08 1.2E-08 1.2E-08 S 4.6E-09 0. 0. 8.5E-09 9.6E-09 SSW 6.0E-09 0. 1.4E-08 1.4E-08 1.4E-08 SW 1.3E-08 0. 1.3E-08 1.3E-08 1.3E-08 WSW 9.OE-09 0. 9.2E-08 1.5E-08 1.5E-08 W 1.OE-08 0. 0. 1.OE-08 1.OE-08 WNW 5.1 E-09 0. 0. 5.1 E-09 5.1 E-09 NW 6.5E-09 0. 0. 6.5E-09 6.5E-09 NNW 4.1 E-09 0. 0. 4.1 E-09 4.1 E-09 N 4.5E-09 0. 0. 4.5E-09 4.5E-09

A zero indicates that this point was not calculated.

ODCM (BSEP) A-18 Rev. 25

TABLE A-15 DIQ Values at the Special Locations for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Deposition (Meter**-2)

Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Boundary Dairy* Meat* Resident* Garden*

Sector NNE 6.OE-10 0. 5.3E-10 5.3E-10 5.3E-10 NE 1.4E-09 2.2E-10 0. 0. 0.

ENE 3.2E-10 0. 0. 0. 0.

E 1.6E-10 0. 1.3E-10 1.3E-10 0.

ESE 4.1 E-10 0. 4.1 E-10 2.OE-10 2.0E-10 SE 4.2E-10 0. 4.2E-10 4.2E-10 0.

SSE 5.4E-10 0. 5.4E-10 5.4E-10 5.4E-10 S 2.OE-10 0. 0. 1.9E-10 1.4E-10 SSW 2.7E-10 0. 2.9E-10 2.9E-10 2.9E-10 SW 5.6E-10 0. 5.6E-10 5.6E-10 5.6E-10 WSW 3.8E-10 0. 3.OE-10 3.6E-10 3.6E-10 W 3.9E-10 0. 0. 3.9E-10 3.9E-10 WNW 1.7E-10 0. 0. 1.7E-10 1.7E-10 NW 2.OE-10 0. 0. 2.OE-10 2.OE-10 NNW 1.5E-10 0. 0. 1.5E-10 1.5E-10 N 1.9E-10 0. 0. 1.9E-10 1.9E-10 A zero indicates that this point was not calculated.

ODCM (BSEP) A-19 Rev. 25

TABLE A-1 6 X/Q Values at the Standard Distances for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Sect Design Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.5E-09 1.3E-08 2.3E-08 2.5E-08 2.4E-08 2.1E-08 1.9E-08 1.7E-08 1.5E 08 1.4E-08 NE 0. 2.5E-09 2.5E-08 4.0E-08 4.4E-08 4.2E-08 3.8E-08 3.3E-08 3.OE-08 2.6E-08 2.4E-08 ENE 0. 8.7E-10 7.2E-09 1.6E-08 2.1 E-08 2.2E-08 2.1 E-08 2.OE-08 1.9E-08 1.8E-08 1.7E-08 E 0. 7.5E-10 3.6E-09 7.6E-09 8.9E-09 1.OE-08 9.3E-09 9.4E-09 8.1E-09 7.6E-09 7.5E-09 ESE 0. 1.1E 09 7.7E-09 1.1 E-08 1.3E-08 1.3E-08 1.3E-08 1.1 E-08 1.OE-08 9.3E-09 8.5E-09 SE 0. 1.6E-09 8.7E-09 1.1 E-08 1.OE-08 9.1 E-09 8.9E-09 8.0 E-09 7.3E-09 6.5E-09 6.5E-09 SSE O. 1.5E-09 1.2E-08 1.6E-08 1.6E-08 1.5E-08 1.3E-08 1.3E-08 1.1E-08 1.OE-08 8.9E-09 s 0. 7.7E-10 4.7E-09 8.5E-09 9.6E-09 9.7E-09 1.1E-08 9.4E-09 8.3E-09 7.7E-09 7.2E-09 SSW 0. 4.9E-10 6.OE-09 1.4E-08 1.6E-08 1.7E-08 1.4E-08 1.4E-08 1.2E-08 1.1 E-08 1.OE-08 SW 0. 1.5E-09 1.3E-08 1.8E-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.3E-08 1.1 E-08 1.OE-08 WSW 0. 1.5E-09 9.OE-09 1.6E-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 1.3E-08 1.2E-08 W 0. 1.4E-09 1.OE-08 1.5E-08 1.7E-08 1.6E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 1.1 E-08 WNW 0. 8.4E-10 5.3E-09 8.4E-09 1.1 E-08 1.2E-08 1.OE-08 9.3E-09 8.6E-09 7.3E-09 6.7E-09 NW 0. 1.0E-09 6.5E-09 1.0E-08 1.0E-08 1.0E-08 1.0E-08 9.5E-09 8.6E-09 7.6E-09 7.5E-09 NNW 0. 1.1 E-09 4.2E-09 7.6E-09 9.2E-09 8.5E-09 8.OE-09 7.4E-09 7.0E-09 6.9E-09 6.1 E-09 N 0. 8.1 E-10 4.5E-09 8.4E-09 1.1 E-08 1.2E-08 1.3E-08 1.3E-08 1.1 E-08 9.3E-09 9.2E-09 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 0 Number of Calms Upper Level 0 ODCM (BSEP) A-20 Rev. 25

TABLE A-17 Depleted XIQ Values at the Standard Distances for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Depleted Concentration (Sec./Cubic Meter)

Calculation Points: Standard Model: Straight Line (ANNXOO9)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 RPnn fktMnnarr in Milc3/Vilarnters Aftd Sect Design Dist .25 .75, 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.5E-09 1.2E-08 2.2E-08 2.4E-08 2.4E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 NE 0. 2.5E-09 2.5E-08 4.0E-08 4.3E-08 4.1 E-08 3.7E-08 3.2E-08 2.9E-08 2.5E-08 2.3E-08 ENE 0. 8.7E-10 7.1E-09 1.6E-08 2.1E-08 2.2E-08 2.0E-08 1.9E-08 1.8E-08 1.7E208 1.7E-08 F: n 7.5-10 3.6EA-09 7.AE-09 8.9E-09 9.3E-09 9.3E-09 9.4E-09 8.1 E-09 7.6lE-o b.Ut-UYz ESE 0. 1.1 E-09 7.5E-09 1.1E-08 1.2E-08 1.3E-08 1.3E-08 1.1 E-08 1.OE-08 9.3E-09 8.2E-09 SE 0. 1.6E-09 8.7E-09 1.1E-08 1.OE-08 8.5E-09 8.2E-09 8.0E-09 7.2E-09 6.3E-09 6.3E-09 SSE 0. 1.5E-09 1.2E-08 1.6E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.OE-08 9.3E-09 8.1E-09 S 0. 7.7E-10 4.6E-09 8.5E-09 9.6E-09 9.7E-09 1.1E-08 9.4E-09 8.2E-09 7.4E-09 6.9E-09 SSW 0. 4.9E-10 6.0E-09 1.4E-08 1.6E-08 1.6E-08 1.4E-08 1.4E-08 1.1 E-08 1.0E-08 9.3E-09 SW 0. 1.5E-09 1.3E-08 1.8E-08 1.OE-08 1.8E-08 1.5E-08 1.4E-08 1.2E-08 1.1E-08 1.OE-08 WSW 0. 1..5E-09 9.O-09 1.52-08 9.2E-08 1.72-08 1.52-08 1.32-08 1.4E-08 1.2E-08 1.1 E-08 W 0. 1.4E-09 1.0E-08 1.5E-08 1.12E-08 1.5E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 1.1 E-08 WNW 0. 8.4E-10 5.1 E-09 8.4E-09 1.1 E-08 1.2E-08 1.OE-08 9.3E-09 8.6E-09 7.3E-09 6.5E-09 NW 0. 1.OE-09 6.5E-09 1.OE-08 1.OE-08 9.6E-09 1.OE-08 8.7E-09 7.8E-09 7.3E-09 7.1 E-09 NNW 0. 1.1 E-09 4.1 E-09 7.5E-09 9.2E-09 8.5E-09 8.0E-09 7.3E-09 6.8E-09 6.6E-09 6.0E-09 N 0. 8.1 E-10 4.5E-09 8.4E-09 1.11E-08 1.1 E-08 1.3E-08 1.3E-08 1.OE-08 9.3E-09 9.2E-09 Number of Valid Observations 8678 Number of Invalid Observations 82 Number of Calms Lower Level 0 Number of Calms Upper Level 0 ODCM (BSEP) A-21 Rev. 25

TABLE A-18 D/Q Values at the Standard Distances for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Deposition (Meter**-2)

Calculation Points: Standard Model: Straight Line (ANNX009)

Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles/Kilometers Aftd Sect Design Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.2E-09 6.OE-10 5.3E-10 4.3E-10 3.4E-10 2.5E-10 2.OE-10 1.6E-10 1.4E-10 1.2E-10 NE 0. 1.4E-09 1.4E-09 1.1 E-09 8.8E-10 6.7E-10 5.2E-10 3.9E-10 3.1 E-10 2.6E-10 2.2E-10 ENE 0. 1.8E-09 3.2E-10 3.02-10 2.5E-10 2.OE-10 1.6E-10 1.3E-10 1.1E-10 9.3E-11 8.1 E-11 E 0. 2.2E-10 1.6E-10 1.3E-10 1.OE-10 8.7E-11 6.6E-11 5.7E-11 4.4E-11 3.7E-11 3.1 E-11 ESE 0. 1.9E-10 4.1 E-10 2.7E-10 2.0E-10 1.7E-10 1.4E-10 1.1E-10 8.2E-11 6.6E-11 5.6E-11 SE 0. 3.2E-10 4.2E-10 3.1 E-10 2.1 E-10 1.4E-10 1.1E-10 8.7E-11 7.3E-11 5.8E-11 5.3E-11 SSE 0. 5.8E-10 5.4E-10 3.9E-10 2.8E-10 2.1 E-10 1.7E-10 1.4E-10 1.1E-10 8.5E-11 7.1 E-11 S 0. 5.4E-10 2.0E-10 1.9E-10 1.4E-10 1.1E-10 1.1E-10 8.3E-11 6.6E-11 5.5E-11 4.6E-11 SSW 0. 1.1 E-09 2.7E-10 2.9E-10 2.4E-10 1.9E-10 1.4E-10 1.3E-10 9.5E-11 7.9E-11 6.5E-11 SW 0. 7.6E-10 5.6E-10 4.3E-10 3.1 E-10 2.4E-10 1.8E-10 1.4E-10 1.1E-10 9.5E-11 8.0E-11 WSW 0. 4.1 E-10 3.8E-10 3.6E-10 3.0E-10 2.3E-10 1.7E-10 1.4E-10 1.3E-10 1.OE-10 8.6E-11 W 0. 2.8E-10 3.9E-10 3.OE-10 2.1E-10 1.5E-10 1.3E-10 1.OE-10 7.8E-11 6.9E-1I 5.9E-11 WNW 0. 2.4E-10 1.7E-10 1.5E-10 1.4E-10 1.OE-10 7.4E-11 5.8E-11 4.8E-11 3.7E-11 2.9E-11 NW 0. 2.6E-10 2.OE-10 1.7E-10 1.2E-10 8.8E-11 7.5E-11 6.0E-11 4.8E-11 4.0E-11 3.6E-11 NNW 0. 7.2E-10 1.52-10 1.3E-10 1.OE-10 7.3E-11 5.4E-11 4.3E-11 3.6E-11 3.2E-11 2.6E-11 N 0. 8.1 E-10 1.92-10 1.5E-10 1.3E-10 1.1E-10 9.9E-11 7.92-11 6.OE-11 4.9E-11 4.4E-11 Number of Valid Observations 8E378 Number of Invalid Observations 8&)

Number of Calms Lower Level 0 Number of Calms Upper Level 0 ODCM (BSEP) A-22 Rev. 25

TABLE A-1 9 Brunswick Plant Site Information To Be Used for Ground Level Calculations with NRC "XOQDOQ" Program Card Columns Description Value to be Used in Type XOQDOQ 1 1 Print input data 1 38 Calculate annual X/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted X/Os (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution 21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 11 6-20 Half-life (days) used in the X/Q calculations 101.00 2.26 8.00

Appropriate data to be supplied.

ODCM (BSEP) A-23 Rev. 25

TABLE A-19 (Cont'd)

Card Columns Description Value to be Used in Type XOQDOQ 5 N/A N/A 6 1-80 Joint wind frequency distribution .

7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond to All are 0 distances in Card Type 8 10 1-25 Number of receptor locations for a particular receptor type Site Boundary 16 Dairy 1 Meat 5 Residence 14

__Garden 11 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence

Appropriate data to be supplied.

ODCM (BSEP) A-24 Rev. 25

TABLE A-19 (Cont'd)

Card Columns Description Value to be Used in Type XOQDOQ 1-16 Cont'd Title of receptor type for receptor locations (Cont'd) Garden 12 1-80 Receptor direction and distance (See Table 1) 13 1-80 Title for release point whose characteristics are described on Card

Type 14 14 1-5 Vent average velocity (m/sec) 1.0 6-10 Vent inside diameter (m) 1.0 11-15 Height of vent release point (m) 0.000 16-20 Height of the vent's building (m) 56.9 21-25 Minimum cross-sectional area for the vent's building (M2) 2120.0 26-30 Wind height used for vent elevated release 11.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0

Appropriate data to be supplied.

ODCM (BSEP) A-25 Rev. 25

TABLE A-20 Brunswick Plant Site Information To Be Used for Elevated Release Calculations with NRC "XOQDOQ" Program Card Columns Description Value to Be Used in Type XOQDOQ 1 1 Print input data 1 4 Release to be elevated 100% of the time 1 38 Calculate annual X/Qs for points of interest 1 39 Calculate annual X/Q averages for site radial segments 1 41 Print out set distance X/Qs and D/Qs1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted X/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution

21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 5 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 104 6-20 Half-life (days) used in the X/Q calculations 101.00 2.26

Appropriate data to be supplied.

ODCM (BSEP) A-26 Rev. 25

TABLE A-20 (Cont'd)

Columns Description Value to Bo Used in Card Type _____ODQ Half-life (days) used in the X/Q calculations (Cont'd) 8.00 6-20 (Cont'd) 5 N/A N/A 6 1-80 Joint wind frequency distribution 1-5 Wind velocity units correction 200.00 7

0.75 6-75 Maximum wind speed in each wind class (m/sec) 3.50 7.50 12.50 18.50 25.00 26.00 Distance in meters at which terrain heights are given All are 100 8 1-80 1-80 Terrain heights (in meters, above plant grade) correspond to All are 0 9

distances in Card Type 8 10 1-25 Number of receptor locations for a particular receptor type 16 Site Boundary 1

Dairy 5

Meat 14 Residence 11 Garden

Appropriate data to be supplied.

A-27 Rev. 25 ODCM (BSEP)

TABLE A-20 (Cont'd)

Card Columns Description Value to Be Used in Type XOQDOQ 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Garden 12 1-80 Receptor direction and distance (See Table 1) 13 1-80 Title for release point whose characteristics are described on Card

Type 14 14 1-5 Vent average velocity (m/sec) 4.66 6-10 Vent inside diameter (m) 3.58 11-15 Height of vent release point (m) 100.9 16-20 Height of the vent's building (m) 0.0 21-25 Minimum cross-sectional area for the vent's building (M2) 0.00 26-30 Wind height used for vent elevated release 104.0 31-35 Vent heat emission rate (cal/sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0

Appropriate data to be supplied.

ODCM (BSEP) A-28 Rev. 25

LIST OF TABLES Table No. Title Page APPENDIX B B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY .......... B-5 B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ....................................... B-6 B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY ............... B-7 B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ....................................... B-8 B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY .......... B-9 B-6 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-10 B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY .......... B-11 B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-12 B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY ............. B-13 B-1 0 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-14 B-11 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY........B-15 B-1 2 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-16 ODCM (BSEP) B-1 Rev. 25

LIST OF TABLES (Cont'd)

Table No. Title Paoe APPENDIX B (continued)

B-1 3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY ..........B-17 B-1 4 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-18 B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY ........ B-19 B-1 6 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-20 B-1 7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY ............. B-21 B-1 8 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-22 B-1 9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY ....... B-23 B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-24 B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY ......... B-25 B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT..................................... B-26 B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY ...... B-27 B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%) PERIOD 1-1-77 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT ..................................... B-28 ODCM (BSEP) B-2 Rev. 25

LIST OF TABLES (Cont'd)

Title Paae Table No.

APPENDIX B (continued)

B-29 B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY ............

B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%) PERIOD 1-1-77 B-30 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT .....................................

B-31 B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY .....

B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%) PERIOD 1-1-77 B-32 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT .....................................

B-33 B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY .........

B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%) PERIOD 1-1-77 B-34 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT .....................................

B-35 B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY ......

B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%) PERIOD 1-1-77 B-36 THROUGH 12-31-77, BRUNSWICK STEAM ELECTRIC PLANT .

ODCM (BSEP) B-3 Rev. 25

APPENDIX B Calculation of V; and B.Values for the Elevated Plume Values of V1 and Bi were calculated for the elevated plume release from the Brunswick stack using the NRC computer program RABFIN. This program was used to determine the controlling location based upon the releases of Table 3.2-1. In addition it was used to develop the V1 and Bi values for the various noble gas radionuclides at the site boundary at each of the 16 sectors. Table B-7 presents the V, and B.values for the NE sector which is the controlling location for noble gases for showing compliance with 10CFR20 and 10CFR50. Table B-8 presents the joint frequency distribution for the NE sector. Tables B-1 through B-6 and B-9 through B-32 present the V; and Bi values and the joint frequency distribution for the remaining sectors. The inputs which were utilized in the RABFIN code are presented below.

1. Height of Stack - 100.9 (m)

2. Stack Diameter - 3.6 (m)

3. Exit Velocity - 5.0 m/sec

4. Wind Height - 104.6 (m)

ODCM (BSEP) B-4 Rev. 25

TABLE B-1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ENE SITE BOUNDARY*

Noble Gas Radionuclides V1 Total Body Bi Gamma Air mrem / yr') (mrad/yr" l.1Ci I sec J tCi / secJ Kr-83m 1.64E-09 1.42E-07 Kr-85m 9.03E-05 1.34E-04 Kr-85 1.34E-06 2.02E-06 Kr-87 4.1OE-04 6.17E-04 Kr-88 1.06E-03 1.60E-03 Kr-89 6.41 E-04 9.63E-04 Xe-131m 2.13E-05 3.35E-05 Xe-133m 1.61 E-05 2.62E-05 Xe-133 1.69E-05 2.63E-05 Xe-135m 2.13E-04 3.23E-04 Xe-1 35 1.45E-04 2.17E-04 Xe-137 5.51 E-05 8.33E-05 Xe-1 38 6.51 E-04 9.77E-04 Xe-139 1.96E-05 2.94E-05 Ar-41 7.74E-04 1.16E-03

'The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-5 Rev. 25

TABLE B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 0.17 0.00 0.01 0.01 0.07 0.03 0.05 4 3.30 0.02 0.17 0.61 1.21 0.83 0.46 5 4.81 0.02 0.18 0.81 1.63 1.39 0.78 6 1.14 0.05 0.20 0.28 0.27 0.14 0.20 7 0.46 0.01 0.12 0.15 0.09 0.09 0.00 Total .9.88 0.10 0.68- - 1.86' 3.27 .. 2.48; 1.49-.

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.75 6.75 Harmonic 0.00 5.27 5.27 ODCM (BSEP) Rev. 25

TABLE B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES N SITE BOUNDARY*

Noble Gas Radionuclides V; Total Body B. Gamma Air (mrem/yr' (mrad/yr) tCi / secJ kICi / secJ Kr-83m 8.97E-10 1.26E-07 Kr-85m 4.38E-05 6.50E-05 Kr-85 6.45E-07 9.78E-07 Kr-87 1.96E-04 2.94E-04 Kr-88 5.16E-04 7.75E-04 Kr-89 2.67E-04 4.01 E-04 Xe-131 m 1.05E-05 1.66E-05 Xe-133m 7.95E-06 1.31 E-05 Xe-1 33 8.40E-06 1.32E-05 Xe-1 35m 9.77E-05 1.48E-04 Xe-1 35 7.00E-05 1.05E-04 Xe-1 37 2.20E-05 3.33E-05 Xe-138 3.1 OE-04 4.65E-04 Xe-139 6.0OE-06 9.01 E-06 Ar-41 3.70E-04 5.56E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-7 Rev. 25

TABLE B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.01 0.00 0.00 0.00 0.01 0.00 0.00 3 0.11 0.00 0.00 0.01 0.07 0.03 0.00 4 1.79 0.01 0.16 0.70 0.65 0.18 0.09 5 2.00 0.00 0.15 0.46 0.65 0.29 0.45 6 0.68 0.02 0.06 0.29 0.12 0.07 0.12 7 0.15 0.02 0.10 0.01 0.00 0.01 0.01 Total 4.74 0.05 - 0.47.. l.47- 150 058 0:67 - ,...

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (rn/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.00 6.00 Harmonic 0.00 4.61 4.61 ODCM (BSEP) B-8 Rev. 25

TABLE B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY*

Noble Gas - VI Total Body B.Gamma Air Radionuclides (mrem/ yr' (mrad/ yrj pCi / sec JjCi / sec)

Kr-83m 1.78E-09 3.05E-07 Kr-85m 8.12E-05 1.21 E-04 Kr-85 1.18E-06 1.79E-06 Kr-87 3.63E-04 5.46E-04 Kr-88 9.34E-04 1.40E-03 Kr-89 5.84E-04 8.77E-04 Xe-131 m 1.96E-05 3.11 E-05 Xe-133m 1.4.8E-05 2.44E-05 Xe-133 1.57E-05 2.48E-05 Xe-135m 1.91 E-04 2.89E-04 Xe-1 35 1.29E-04 1.94E-04 Xe-1 37 5.09E-05 7.69E-05 Xe-138 5.76E-04 8.65E-04 Xe-1 39 1.93E-05 2.90E-05 Ar-41 6.82E-04 1.02E-03

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-9 Rev. 25

TABLE B-6 JOINT FREQUENCY DISTRIBUTION FOR NNE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 l 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.07 0.00 0.00 0.01 0.05 0.01 0.00 3 0.45 0.00 0.00 0.03 0.25 0.15 0.02 4 4.51 0.01 0.16 0.56 1.79 1.38 0.61 5 2.90 0.00 0.17 0.21 0.88 0.78 0.86 6 0.65 0.02 0.12 0.22 0.09 0.07 0.13 7 0.45 0.05 0.14 0.08 0.07 0.10 0.01 Total 9.03 . 0:08 0.59- 1.1-1 .3.13-. 2.49 -1.63',-

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity .

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 7.13 7.13 Harmonic 0.00 5.63 5.63 ODCM (BSEP) B-10 Rev. 25

TABLE B-7 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NE SITE BOUNDARY*

Noble Gas V, Total Body Bi Gamma Air Radionuclides (mrem/yr' (mrad / yr

~t Ci secJ ItCi/sec Kr-83m 2.93E-09 5.97E-07 Kr-85m 1.22E-04 1.81 E-04 Kr-85 1.74E-06 2.64E-06 Kr-87 5.39E-04 8.11 E-04 Kr-88 1.36E-03 2.05E-03 Kr-89 9.47E-04 1.42E-03 Xe-131m 2.96E-05 4.73E-05 Xe-i 33m 2.23E-05 3.72E-05 Xe-1 33 240E-05 . 3.80E-05 Xe-1 35m 2.94E-04 4.46E-04 Xe-135 1.92E-04 2.89E-04 Xe- 137 8.47E-05 1.28E-04 Xe- 138 8.60E-04 1.29E-03 Xe-i 39 3.57E-05 5.37E-05 Ar-41 1.01 E-03 1.51 E-03

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-i 1 Rev. 25

TABLE B-8 JOINT FREQUENCY DISTRIBUTION FOR NE SECTOR (%)

PERIOD 1-1 -77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (rn/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.00 0.01 2 0.21 0.00 0.00 0.00 0.05 0.10 0.06 3 1.13 0.00 0.00 0.03 0.28 0.50 0.32 4 7.30 0.01 0.15 0.63 2.50 2.51 1.50 5 5.15 0.03 0.09 0.30 1.21 1.99 1.53 6 1.04 0.01 0.06 0.32 0.33 0.24 0.08 7 0.41 0.01 0.12 0.10 0.13 0.03 0.02 3 Total. 1S.26 0.-0.6 - .p.42 1.38 4.51 5.37 3.52.

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity _

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 7.81 7.81 Harmonic 0.00 6.63 6.63 ODCM (BSEP) B-1 2 Rev. 25

TABLE B-9 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY*

V, Total Body B1 Gamma Air Noble Gas Radionuclides (mrem Jyr" r mrad / yr) tIFCi I sec t j. /~secJ Kr-83m 9.82E-10 6.1 OE-08 Kr-85m 6.43E-05 9.54E-05 Kr-85 9.71 E-07 1.47E-06 Kr-87 2.99E-04 4.49E-04 Kr-88 7.78E-04 1.17E-03 Kr-89 4.59E-04 6.90E-04 Xe-131 m 1.49E-05 2.33E-05 Xe-133m 1.13E-05 1.82E-05 Xe-133 1.16E-05 . 1.80E-05 Xe-135m 1.53E-04 2.32E-04 Xe-1 35 1.04E-04 - 1.56E-04 Xe-137 3.89E-05 5.89E-05 Xe-138 4.73E-04 7.1 OE-04 Xe-139 1.37E-05 2.05E-05 Ar-41 5.66E-04 8.49E-04

The listed dose parameters are for radionuclides that may be detected ingaseous effluents.

ODCM (BSEP) B-13 Rev. 25

TABLE B-10 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31 -77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.00 0.00 0.01 0.00 2 0.03 0.00 0.00 0.00 0.01 0.01 0.01 3 0.09 0.00 0.00 0.03 0.02 0.01 0.03 4 1.42 0.01 0.15 0.55 0.32 0.23 0.16 5 2.07 0.03 0.10 0.62 0.74 0.50 0.08 6 1.08 0.02 0.14 0.30 0.38 0.15 0.09 7 0.64 0.03 0.13 0.24 0.10 0.08 0.06 Total 5.34 0.09 . 0.52. 1.74 1,.57. r/3.99z,, Q.43-Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity . .

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.80 5.80 Harmonic 0.00 4.41 4.41 ODCM (BSEP) B-14 Rev. 25

TABLE B-i 1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY*

Noble Gas V1 Total Body B; Gamma Air Radionuclides rmrem/yr) (mrad/ yr) jCi /sec) IiCi / sec Kr-83m 1.1OE-09 1.90E-07 Kr-85m 5.59E-05 8.31 E-05 Kr-85 8.23E-07 1.25E-06 Kr-87 2.55E-04 3.83E-04 Kr-88 6.50E-04 9.76E-04 Kr-89 4.38E-04 6.58E-04 Xe-131 m 1.33E-05 2.1 OE-05 Xe-133m 1.01 E-05 1.64E-05 Xe-133 1.05E-05 1.65E-05 Xe-135m 1.36E-04 2.07E-04 Xe-135 8.94E-05 1.34E-04 Xe-1 37 3.86E-05 5.84E-05 Xe-1 38 4.05E-04 6.08E-04 Xe-139 1.75E-05 2.63E-05 Ar-41 4.79E-04 7.19E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-15 Rev. 25

- TABLE B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (mlsec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.06 0.00 0.00 0.01 0.00 0.05 0.00 2 0.15 0.00 0.00 0.01 0.03 0.06 0.05 3 0.31 0.00 0.00 0.02 0.13 0.03 0.13 4 1.71 0.00 0.07 0.31 0.58 0.46 0.29 5 2.02 0.01 0.08 0.31 0.52 0.80 0.30 6 0.85 0.03 0.06 0.17 0.18 0.36 0.05 7 0.46 0.01 0.07 0.12 0.07 0.07 0.12 Total . 5.56. 0.05 0.28. 0.95 1.51. 1.83 -0.94 Entrapment 0.00 . 0;00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 7.15 7.15 Harmonic 0.00 5.67 5.67 ODCM (BSEP) B-16 Rev. 25

TABLE B-13 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SE SITE BOUNDARY*

Noble Gas V; Total Body B. Gamma Air Radionuclides (rmrem/yr (mrad/ yr)

/ sec) m rCi j.Lci / sec)

Kr-83m 1.34E-09 3.71 E-07 Kr-85m 5.76E-05 8.56E-05 Kr-85 8.42E-07 1.28E-06 Kr-87 2.60E-04 3.91 E-04 Kr-88 6.65E-04 9.98E-04 Kr-89 4.39E-04 6.59E-04 Xe-131 m 1.40E-05 2.23E-05 Xe-133m 1.06E-05 1.76E-05 Xe-133 1.12E-05 1.77E-05 Xe-135m 1.39E-04 2.1 OE-04 Xe-135 9.18E-05 1.38E-04 Xe-1 37 3.86E-05 5.84E-05 Xe-138 4.13E-04 6.21 E-04 Xe-139 1.65E-05 2.48E-05 Ar-41 4.89E-04 7.34E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-17 Rev. 25

TABLE B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Total 1.50 3.00 5.00 7.50 10.00 12.50 Stability 0.11 0.00 0.00 0.00 0.00 0.06 0.05 1

0.31 0.00 0.00 0.01 0.14 0.15 0.01 2

0.53 0.00 0.00 0.14 0.18 0.18 0.03 3

1.44 0.02 0.08 0.25 0.51 0.41 0.17 4

1.46 0.01 0.09 0.31 0.50 0.46 0.09 5

0.89 0.02 0.05 0.02 0.30 0.44 0.06 6

0.63 0.01 0.13 0.09 0.14 0.21 0.05 7

Total 5.37 06 035 00 .0.82 1.77 1.91 -

0.00 0.00 0.00 0.00 0.00 0.00 Entrapment 0.23 0.70 1.24 1.93 2.71 3.48 Ground Velocity . -

0.74 2.21 3.93 6.14 8.59 11.05 Elevated Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.78 6.78 Harmonic 0.00 5.37 5.37 B-1 8 Rev. 25 ODCM (BSEP)

TABLE B-15 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY*

V1 Total Body Bi Gamma Air Noble Gas Radionuclides (mrem / yr' rmrad/ yrA pCi /sec J0 /~isecJ Kr-83m 1.29E-09 2.74E-07 Kr-85m 5.96E-05 8.85E-05 Kr-85 8.78E-07 1.33E-06 Kr-87 2.70E-04 4.07E-04 Kr-88 6.97E-04 1.05E-03 Kr-89 4.51 E-04 6.78E-04 Xe-131 m 1.43E-05 2.27E-05 Xe-133m 1.09E-05 1.79E-05 -

Xe-133 1.14E-05 . 1.80E-05 Xe-135m 1.43E-04 2.17E-04 Xe-1 35 9.53E-05 1.43E-04 Xe-1 37 3.96E-05 5.99E-05 Xe-138 4.30E-04 6.45E-04 Xe-139 1.71 E-05 2.57E-05 Ar-41 5.1OE-04 7.65E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-19 Rev. 25

TABLE B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.01 0.00 2 0.13 0.00 0.00 0.02 0.02 0.09 0.00 3 0.49 0.00 0.00 0.14 0.24 0.09 0.02 4 2.35 0.05 0.16 0.32 0.80 0.70 0.32 5 1.40 0.00 0.08 0.23 0.46 0.58 0.05 6 0.84 0.02 0.05 0.13 0.18 0.31 0.15 7 0.32 0.03 0.02 0.05 0.07 0.13 0.02 Total 5.55 0.10 0.31 0.89 1.78 1.91 0.56 Entrapment . 0.00 0.00 0.00 0.0Q 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.81 6.81 Harmonic 0.00 5.21 5.21 ODCM (BSEP) B-20 Rev. 25

TABLE B-17 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES S SITE BOUNDARY*

Noble Gas V1 Total Body Bi Gamma Air Radionuclides (mrem/ yr (mrad / yr)

VSCi I sec J V Ii sec)

Kr-83m 8.80E-10 9.50E-08 Kr-85m 5.11 E-05 7.59E-05 Kr-85 7.66E-07 1.16E-06 Kr-87 2.34E-04 3.53E-04 Kr-88 6.13E-04 9.19E-04 Kr-89 3.71 E-04 5.57E-04 Xe-131 m 1.20E-05 1.88E-05 Xe-133m 9.1 OE-06 1.48E-05 Xe-133 9.44E-06 l.47E-05 Xe-1 35m 1.20E-04 1.82E-04 Xe-1 35 8.23E-05 1.24E-04 Xe-137 3.19E-05 4.83E-05 Xe-138 3.71 E-04 5.56E-04 Xe-139 1.33E-05 2.OOE-05 Ar-41 4.44E-04 6.66E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-21 Rev. 25

TABLE B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.03 0.00 0.00 0.00 0.03 0.00 0.00 3 0.16 0.00 0.00 0.02 0.14 0.00 0.00 4 1.74 0.01 0.13 0.28 0.55 0.54 0.23 5 1.32 0.03 0.08 0.25 0.45 0.46 0.05 6 0.93 0.02 0.08 0.17 0.24 0.33 0.09 7 0.37 0.05 0.03 0.05 0.12 0.07 0.05 Total 4.55 0.11 . 0.32 0.77 1.53 1.40 - 0.42 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.57 6.57 Harmonic 0.00 4.84 4.84 ODCM (BSEP) B-22 Rev. 25

TABLE B-19 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SSW SITE BOUNDARY*

Noble Gas V1 Total Body Bi Gamma Air Radionuclides (mrem I yr (mrad / yr)

~tCi I sec) kpCi / sec)

Kr-83m 1.1OE-09 1.39E-07 Kr-85m 5.60E-05 8.31 E-05 Kr-85 8.22E-07 1.25E-06 Kr-87 2.53E-04 3.81 E-04 Kr-88 6.51 E-04 9.76E-04 Kr-89 4.06E-04 6.1 OE-04 Xe-131 m 1.33E-05 2.1 OE-05 Xe-1 33m 1.01 E-05 1.65E-05 Xe-133 1.06E-05 1.66E-05 Xe-1 35m 1.34E-04 2.03E-04 Xe-135 - 8.94E-05 1.34E-04 Xe-1 37 3.52E-05 5.32E-05 Xe-1 38 4.02E-04 6.04E-04 Xe-139 1.21 E-05 1.81 E-05 Ar-41 4.77E-04 7.15E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-23 Rev. 25

TABLE B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 0.19 0.00 0.00 0.07 0.05 0.06 0.01 4 2.47 0.01 0.03 0.53 0.99 0.62 0.29 5 1.88 0.01 0.15 0.37 0.56 0.74 0.05 6 1.12 0.01 0.12 0.14 0.28 0.55 0.02 7 0.51 0.01 0.03 0.10 0.22 0.13 0.02 Total 6.17 0.04 0.33 1.21 2.10 2.10 0.39 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.61 6.61 Harmonic 0.00 5.44 5.44 ODCM (BSEP) B-24 Rev. 25

TABLE B-21 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY*

Noble Gas V1 Total Body Bi Gamma Air Radionuclides (mrem / yr) (mrad / yr)

IalCi / sec ) gCi / sec Kr-83m 1.40E-09 3.22E-07 Kr-85m 6.11 E-05 9.08E-05 Kr-85 8.94E-07 1.35E-06 Kr-87 2.73E-04 4.11 E-04 Kr-88 7.1OE-04 1.07E-03 Kr-89 4.19E-04 6.29E-04 Xe-131 m 1.48E-05 2.36E-05 Xe-133m 1.12E-05 1.86E-05 Xe-133 1.19E-05 1.88E-05 Xe-135m 1.41 E-04 2.14E-04 Xe-1 35 9.75E-05 1.47E-04 Xe-1 37 3.60E-05 5.44E-05 Xe-138 4.33E-04 6.50E-04 Xe-139 1.16E-05 1.74E-05 Ar-41 5.15E-04 7.73E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-25 Rev. 25

TABLE B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (%)

PERIOD 1-1 -77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (mfsec) --

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.00 0.00 0.01 0.00 2 0.10 0.00 0.00 0.02 0.07 0.01 0.00 3 0.53 0.00 0.02 0.10 0.30 0.09 0.02 4 2.32 0.01 0.14 0.50 0.98 0.52 0.17 5 1.71 0.02 0.09 0.39 0.40 0.68 0.13 6 0.88 0.05 0.05 0.20 0.46 0.12 0.00 7 0.56 0.00 0.07 0.15 0.22 0.12 0.00 Total 6.11 0.08 0.37 1.36 2.43 1.55 - 0.32.

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 V elocity _ _ _ __ _ _ _ _ _ _ __ _ _

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 6.22 6.22 Harmonic I 0.00 1 4.98 1 4.98 ODCM (BSEP) B-26 Rev. 25

TABLE B-23 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WSW SITE BOUNDARY*

V; Total Body Bi Gamma Air Noble Gas Radionuclides r mrem / yrA (mrad / yr) pif / sec) liCi/sec)

Kr-83m 1.42E-09 3.1 OE-07 Kr-85m 6.27E-05 9.31 E-05 Kr-85 9.16E-07 1.39E-06 Kr-87 2.80E-04 4.21 E-04 Kr-88 7.26E-04 1.09E-03 Kr-89 4.28E-04 6.42E-04 Xe-1 31 m 1.52E-05 2.42E-05 Xe-1 33m 1.15E-05 1.90E-05 Xe-133 1.22E-05 1.93E-05 Xe-135m 1.45E-04 2.20E-04 Xe-135 9.99E-05 1.50E-04 Xe-137 3.67E-05 5.55E-05 Xe-1 38 4.44E-04 6.67E-04 Xe-139 1.12E-05 1.68E-05 Ar-41 5.27E-04 7.91 E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-27 Rev. 25

TABLE B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.02 0.00 0.00 2 0.18 0.00 0.01 0.00 0.14 0.00 0.03 3 0.36 0.00 0.01 0.15 0.15 0.05 0.00 4 2.64 0.00 0.15 0.54 1.12 0.75 0.08 5 1.73 0.02 0.09 0.37 0.84 0.39 0.02 6 0.87 0.02 0.08 0.25 0.37 0.14 0.01 7 0.36 0.03 0.03 0.13 0.17 0.00 0.00 Total 6.16 0.07 0.37 1.44 2.81 1.33 0.14-Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity . -

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.97 5.97 Harmonic 0.00 4.91 4.91 ODCM (BSEP) B-28 Rev. 25

TABLE B-25 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES W SITE BOUNDARY*

Noble Gas V1 Total Body BS Gamma Air Radionuclides rem/yr (mrad / yr

~t Ci I sec ) RCi / sec)

Kr-83m 1.33E-09 3.17E-07 Kr-85m 5.83E-05 8.66E-05 Kr-85 8.61 E-07 1.30E-06 Kr-87 2.57E-04 3.87E-04 Kr-88 6.92E-04 1.04E-03 Kr-89 3.34E-04 5.01 E-04 Xe-131m 1.42E-05 2.27E-05 Xe-133m 1.08E-05 1.79E-05 Xe-133 1.14E-05 1.80E-05 Xe-1 35m 1.24E-04 1.89E-04 Xe-1 35 9.33E-05 1.40E-04 Xe-137 2.72E-05 4.11 E-05 Xe-1 38 4.05E-04 6.08E-04 Xe-1 39 6.46E-06 9.70E-06 Ar-41 4.89E-04 7.34E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-29 Rev. 25

TABLE B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.05 0.00 0.00 0.00 0.05 0.00 0.00 2 0.10 0.00 0.00 0.00 0.10 0.00 0.00 3 0.37 0.00 0.05 0.18 0.12 0.02 0.00 4 1.95 0.02 0.10 0.47 1.07 0.29 0.00 5 2.00 0.01 0.14 0.53 1.07 0.22 0.03 6 0.85 0.07 0.10 0.29 0.36 0.01 0.02 7 0.37 0.06 0.08 0.18 0.05 0.00 0.00 Total 5.69 0.16 0.47 1.65 2.82 0.54 0.05.

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity I AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.30 5.30 Harmonic 0.00 4.13 4.13 ODCM (BSEP) B-30 Rev. 25

TABLE B-27 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES WNW SITE BOUNDARY*

Noble Gas V1 Total Body Bj Gamma Air Radionuclides (mrem/yr) (mrad/ yr' KLuCi/ sec) g4Ci/sec)

Kr-83m 9.41 E-10 2.22E-07 Kr-85m 4.43E-05 6.58E-05 Kr-85 6.61 E-07 1.OOE-06 Kr-87 1.98E-04 2.98E-04 Kr-88 5.34E-04 8.01 E-04 Kr-89 2.54E-04 3.81 E-04 Xe-131 m 1.07E-05 1.70E-05 Xe-1 33m 8.13E-06 1.34E-05 Xe-133 8.52E-06 1.34E-05 Xe-1 35m 9.52E-05 1.44E-04 Xe-1 35 7.12E-05 1.07E-04 Xe-1 37 2.05E-05 3.09E-05 Xe-138 3.12E-04 4.68E-04 Xe-1 39 4.91 E-06 7.38E-06 Ar-41 3.77E-04 5.66E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-31 Rev. 25

TABLE B-28 JOINT FREQUENCY DISTRIBUTION FOR WNW SECTOR (%)

PERIOD 1-1 -77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.09 0.00 0.00 0.08 0.01 0.00 0.00 3 0.24 0.00 0.05 0.17 0.02 0.00 0.00 4 1.03 0.01 0.10 0.45 0.45 0.02 0.00 5 1.19 0.03 0.14 0.37 0.50 0.13 0.02 6 0.63 0.05 0.12 0.28 0.17 0.01 0.00 7 0.19 0.03 0.03 0.07 0.06 0.00 0.00 Total 3.38 0.12 0.44 1.43 1.21 0.16. 0.02 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity .

AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.65 4.65 Harmonic 0.00 3.58 3.58 ODCM (BSEP) B-32 Rev. 25

TABLE B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NW SITE BOUNDARY*

Noble Gas Vi Total Body Bi Gamma Air Radionuclides (mrem / yr) (mrad / yr)

.jCi /sec JpCi / sec)

Kr-83m 1.02E-9 2.45E-07 Kr-85m 4.69E-05 6.97E-05 Kr-85 6.96E-07 1.05E-06 Kr-87 2.09E-04 3.14E-04 Kr-88 5.61 E-04 8.41 E-04 Kr-89 2.66E-04 4.OOE-04 Xe-131 m 1.14E-05 1.81 E-05 Xe-133m 8.64E-06 1.43E-05 Xe-1 33 9.09E-06 1.43E-05 Xe-135m 1.01 E-04 1.53E-04 Xe-1 35 7.53E-05 1.13E-04 Xe-1 37 2.15E-05 3.24E-05 Xe-138 3.29E-04 4.94E-04 Xe-139 5.39E-06 8.09E-06 Ar-41 3.96E-04 5.95E-04

The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

ODCM (BSEP) B-33 Rev. 25

TABLE B-30 JOINT FREQUENCY DISTRIBUTION FOR NW SECTOR (%)

PERIOD 1-1 -77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.12 0.00 0.01 0.08 0.03 0.00 0.00 3 0.24 0.00 0.02 0.17 0.05 0.00 0.00 4 1.14 0.01 0.16 0.54 0.33 0.09 0.01 5 1.08 0.02 0.12 0.40 0.28 0.10 0.16 6 0.57 0.05 0.17 0.17 0.16 0.01 0.01 7 0.35 0.03 0.07 0.12 0.13 0.00 0.00 Total 3.51 0.11 0.55 1.49 0.98 0.20 0.18. -

Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity .

Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 4.81 4.81 Harmonic 0.00 3.59 3.59 ODCM (BSEP) B-34 Rev. 25

TABLE B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNW SITE BOUNDARY*

B1 Ga m.i Vi Total Body Bi Gamma Air Noble Gas -

Radionuclides (mrem / yr) mrad / yr"

( )-tCi / sec J ( PCi / sec) 6.97E-10 9.17E-08 Kr-83m ------- _ 4-~

5.87E-05 Kr-85m 3.96E-05 .

9.04E-07 Kr-85 5.96E-07 Kr-87 1.80E-04 2.71 E-04 Kr-88 4.83E-04 7.24E-04

[

Kr-89 2.39E-04 3.59E-04

_9.37E-06 -- 1.47E-05 Xe-1 31 m

_7.1 OE-06 1.15E-05 Xe-1 33m 7.36E-06 1.15E-05 Xe-1 33 8.70E-05 1.32E-04 Xe-1 35m _I_0E-_

35 6.39E-05 9.60E-05

-Xe-1 4 2.94E-05 Xe-13a7 1.94E-05 I 4.25E-04 Xe-1 38 2.83E-04 ____________I 9.13E-06 Xe-1 39 6.08E-06 5.4E0 3.42E-04 5.14E-04 Ar-41 detected in gaseous effluents.

The listed dose parameters are for radionuclides that may be B-35 Rev. 25 ODCM (BSEP)

TABLE B-32 JOINT FREQUENCY DISTRIBUTION FOR NNW SECTOR (%)

PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (mlsec)

Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.02 0.00 0.00 0.01 0.01 0.00 0.00 3 0.12 0.00 0.00 0.06 0.06 0.00 0.00 4 1.00 0.01 0.14 0.36 0.37 0.09 0.03 5 1.17 0.02 0.12 0.27 0.25 0.12 0.39 6 0.82 0.02 0.13 0.23 0.17 0.03 0.24 7 0.34 0.05 0.10 0.14 0.00 0.05 0.00 Total 3.47 0.10 0.49 1.07 0.86 0.29 0.66 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground 0.23 0.70 1.24 1.93 2.71 3.48 Velocity Elevated 0.74 2.21 3.93 6.14 8.59 11.05 Velocity AVERAGE WIND SPEED (m/sec)

Mean Ground Elevated Combined Arithmetic 0.00 5.89 5.89 Harmonic 0.00 4.02 4.02 ODCM (BSEP) B-36 Rev. 25

LIST OF TABLES Table No. Title Page APPENDIX CII C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS ......................................... C-14 C-2 PARAMETERS FOR THE MEAT PATHWAY ......................................... C-15 C-3 PARAMETERS FOR VEGETABLE PATHWAY .................................. 0, C-16 ODCM (BSEP) C-1 Rev. 25

APPENDIX C DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with 10CFR 20 and Appendix I of 10CFR50 for gaseous effluents. These dose parameters Pi and R.were calculated using the methodology outlined in NUREG 0133, Regulatory Guide 1.109 Revision 1, and letter to J. W. Davis, "Dose Factors for Hf-181 and SN-113",

BSEP File: B10-10530, May 24, 1988. The following sections provide the specific methodology which was utilized in calculating the P.and R,values for the various exposure pathways.

C.1 CALCULATION OF P, The parameter Pi contained in the radioiodine and particulate portion of Section 3.2, includes pathway transport parameters of the ith radionuclide, the receptor's usage of the pathway media and the dosimetry of the exposure. Pathway usage rates and the internal dosimetry are functions of the receptor's age; however, the youngest age group, the infant, will always receive the maximum dose under the exposure conditions for ODCM, Section 1, 3.11.2.1 (b). For the infant exposure, separate values of PI may be calculated for the inhalation pathway which is combined with a W parameter based on (X/Q), and the food (milk) and ground pathway which is combined with a W parameter normally based on (D/Q), except for tritium.

The following sections provide in detail the methodology which was used in calculating the Pi values for inclusion into this ODCM.

C.1.1 Inhalation Pathway P = K' (BR) DFAj (C.1-1) where:

P = dose parameter for radionuclide i for the inhalation pathway, mrem/yr per IICVM3 K' = a constant of unit conversion

= 106 pipCVci BR - = the breathing rate of the infant age group, m3/yr DFAi = the maximum organ inhalation dose factor for the infant age group for radionuclide i, mrem/pCi ODCM (BSEP) C-2 Rev. 25

The age group considered is the infant group. The infant's breathing rate is taken as 1400 m3/yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the infant, DFAj, are presented in Table E-10 of Regulatory Guide 1.109, BSEP File:

B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113, "May 24,1988, and NUREG CR4653 for Am-241, in units of mrem/pCi. The total body is considered as an organ in the selection of DFAi.

The incorporation of breathing rate of an infant and the unit conversion factor results in the following:

P = 1.4 x 109 DFA, (C.1-2)

C.1.2 Ground Plane Pathway PG = K' K " DFG,(1-eX0)/Y (C.1-3) where:

PiG = Dose parameter for radionuclide i for the ground plane pathway, mrem/yr per pCisec per m K' = A constant of unit conversion

= O16 pC'jICi K" = A constant of unit conversion

= 8760 hr/yr i = The radiological decay constant for radionuclide i, sec l t = The exposure period

= 3.15x 107 sec (1 year)

DFGi = The ground plane dose conversion factor for radionuclide i, mrem/hr per pCiM 2 The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removaf mechanism for each radionuclide.

The ground plane dose conversion factors for radionuclide i, DFGj, are presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May24, 1988, and NUREG CR4653 for Am-241.

ODCM (BSEP) C-3} Rev. 25

Resolution of the units yields:

P -G 8.76 x 109 DFG1(1 -e -.It)i (C.1-4)

C.1.3 Milk PK r OF (Uap) F. DFLm e_;'" (C.1-5)

= YP (Xi + XIJ FI ~ t where:

P = Dose parameter for radionuclide i for the cow milk or goat milk pathway, mrem/yr per iCi/sec per m K' = A constant of unit conversion

= 106 pCWCi OF = The cow's or goat's consumption rate of feed, kg/day (wet weight)

Up = The infant's milk consumption rate, liters/yr 2

Yp = The agricultural productivity by unit area, kg/r Fm = The stable element transfer coefficient, pCiliter per pCiday r = Fraction of deposited activity retained on cow's or goat's feed grass DFLi = The maximum organ ingestion dose factor for radionuclide i, mrem/pCi i = The radiological decay constant for radionuclide i sec'1 Xw = The decay constant for removal of activity on leaf and plant surfaces by weathering, sec-1

= 5.73 x 10-7 sec' (corresponding to a 14 day half-time) t = The transport time from pasture to cow or goat to milk to infant, sec A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering processes.

ODCM (BSEP) C-4 Rev. 25

Various parameters which were utilized to determine the Pi values for the cow and goat milk pathways are provided in Table C-1. Table E-1 of Regulatory Guide 1.109, Revision 1, provides the stable element transfer coefficients, Fm, and Table E-14 of the same regulatory guide provides the ingestion dose factors, DFLi, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-i 13," May 24, 1988, and NUREG CR4653 for AM-241, for the infant's organs. The organ with the maximum value of DFLi was used in the determination of P. for this pathway. The incorporation of the various constants of Table C-1 into Equation C.1-5 results in the following:

For cow's milk for radioiodines and particulates:

PM 2.14 x 1010 rFm DFL eve" (C.1-6)

For the goat milk pathway for radioiodines and particulates:

PM 2.8 x log rFm DFL eA,;" (C.1 -7)

For tritium, the concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.

PTM = K'K"'FmQFUapDFLT [0.75 (0.5/H)] (C.1-8) where:

PTM = Dose parameter for tritium for the cow milk and goat milk pathways, mrem/yr per gCViM 3 K"' = A constant of unit conversion

= 103 gm/kg H = Absolute humidity of the atmosphere, gm/M3 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water DFLT = Maximum organ ingestion dose factor for tritium, mrem/pCi ODCM (BSEP) C-5 Rev. 25

C.2 CALCULATION OF RI The Radioiodine and Particulate ODCM Specification 7.3.9 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. RI values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.

C.2.1 Inhalation Pathway R = K' (BR)a (DFAi)a (C.2-1) where:

Rl = Dose factor for each identified radionuclide i of the organ of interest, mrem/yr per tCVm3 K' = A constant of unit conversion

= 106 pCVICi (BR)a = Breathing rate of the receptor of age group a, m3/yr (DFAi)a = Organ inhalation dose factor for radionuclide i for the receptor of age group a, mremlpCi ODCM (BSEP) C-6 Rev. 25

The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109, Revision 1.

Age Group (a) Breathing Rate (m3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA,)a for the various age groups are given in Tables E-7 through E-1 0 of Regulatory Guide 1.109, Revision 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-1 13," May 24, 1988, and NUREG CR4653 for AM-241.

C.2.2 Ground Plane Pathway RG = I K'K"(SF)DFGi (1 e-I t )/ X, (C.2-2) where:

RG = Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest, mrem/yr per gCi/sec per mr2 K' = A constant of unit conversion

= 106 pCvgCi K" = A constant of unit conversion

= 8760 hr/year Xi = The radiological decay constant for radionuclide i, sec' t = The exposure time, sec

=- 4.73 x 108 sec (15 years)

DFG1 = The ground plane dose conversion factor for radionuclide i; mrem/hr per pCiVm 2 ODCM (BSEP) C-7 Rev.25

SF = The shielding factor (dimensionless)

II = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor 1,is equal to one. For radioiodines, the value of 1,may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2.

A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of DFG, values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

C.2.3 Grass-Cow or Goat Milk Pathway R. =IIKIQFUaPFm(DFLj)aeAIf

~ffr(1 ~e_'Lte) BV(1 -X&ittb )1+~~~ r(1- ez;Ete) B(1 -e-Xitb Br 1 -kithl e->t 4 1 i)+ + (1-fpf5 ) L [ sE +

I.P~ y~x PxjS (C.2-3) where:

M = Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, mrem/yr per [iCVsec per m 2 K' = A constant of unit conversion

= 106 pCVjiCi OF = The cow's or goat's feed consumption rate. kg/day (wet weight)

Uap = The receptor's milk consumption rate for age group a, liters/yr 2

Yp = The agricultural productivity by unit area of pasture feed grass, kg/M 2

YS = The agricultural productivity by unit area of stored feed, kg/M Fm = The stable element transfer coefficients, pCi/liter per pCi/day C-8 Rev. 25 ODCM (BSEP)

r = Fraction of deposited activity retained on cow's feed grass (DFLi)a = The organ ingestion dose factor for radionuclide i for the receptor in age group a, mremlpCi XE, = Xi +

xi = The radiological decay constant for radionuclide i, sect Xw = The decay constant for removal of activity on leaf and plant surfaces by weathering sec 1

= 5.73x10-7 sec& (corresponding to a 14 day half-life) tf = The transport time from feed to cow or goat to milk, to receptor, sec th = The transport time from harvest to cow or goat consumption, sec tb = Period of time that soil is exposed to gaseous effluents, sec Bv = Concentration factor for uptake of radionuclide i from the soil by the edible> parts of crops, pCiKg (wet weight) per pCVKg (dry soil)

P = Effective surface density for soil, Kg (dry soil)/m2 fp = Fraction of the year that the cow or goat is on pasture fS = Fraction of the cow feed that is pasture grass while the cow is on pasture te = Period of pasture grass and crop exposure during the growing season, sec Ii = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values Tables 3.3-9 through 3.3-16.

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8-month grazing period.

ODCM (BSEP) C-9 Rev. 25

Table C-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R1 is based on X/Q:

RTM = K'K"'FmQFUaP(DFLi)a [0.75(2*)] (C-2-4) where:

RTM Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mremfyr per AiCVm 3 K' = A constant unit of conversion, 106 pCi/p.Ci K"' = A constant unit of conversion

= 103gm/kg H = Absolute humidity of the atmosphere, gm/M 3 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water Other parameters and values as defined previously. A value for H of 8 grams/meter 3, was used in lieu of site-specific information.

C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:

Re= IK'QFUapFI (DFLi)a e ,ts

{fPfS[ pEte) + + (1-f f ) [r E, ) + ] earth}

(C.2-5) where:

RB Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, mrem/yr per jliCVsec per m 2 ODCM (BSEP) C-10 Rev. 25

Ff = The stable element transfer coefficients, pCi/Kg per pCi/day Uap = The receptor's meat consumption rate for age group a, kg/yr ts = The transport time from slaughter to consumption, sec th = The transport time from harvest to animal consumption, sec te = Period of pasture grass and crop exposure during the growing season, sec I = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor 1,is equal to one. For radioiodines, the value of 1,may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8.

All other terms remain the same as defined in Equation C.2-3.

Table C-2 contains the values which were used in calculating R.for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, R.is based on XIQ.

RTB K'K"KFfQFUab(DFLj)a [0.75( H-) (C.2-6) where:

RTB Dose factor for the meat ingestion pathway for tritium for any organ of interest, mrem/yr per PCVM3 All other terms are as defined in Equation C.2-4 and C.2-5, above.

C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

ODCM (BSEP) C-1 1 Rev. 25

Riv = K'(DFL,)a rUfe ~ - IE.Ie +, ( - e )+ ethr(1e-XeEle )+Bi, (1- e-,t

{UfL e r[1e + B.,( )]+ Usf e -, [YA + <

YVXEI PUfa L YVXE, PX1 J (C.2-7) where:

RV = Dose factor for vegetable pathway for radio nuclide i for the organ of interest mrem/yr per ViCVsec per m-2 K' = a constant of unit conversion

= 106 pCiljci La = The consumption rate of fresh leafy vegetation by the receptor age group a, kg/yr

= The consumption rate of stored vegetation by the receptor in age group a, kg/yr fg = The fraction of the annual intake of stored vegetation grown locally fL = The fraction of annual intake of fresh, leafy vegetables grown locally tL = The average time between harvest of leafy vegetation and its consumption, sec th = The average time between harvest of stored vegetation and its consumption, sec Yv = The vegetation area density, kg/M2 te = Period of leafy vegetable exposure during growing season, sec Ii = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor I is equal to one. For radioiodines, the value of li may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5.

All other factors were defined above.

ODCM (BSEP) C-12 Rev. 25

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculation of Ri. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri is bases on X/Q:

RTV KK'K"' [UafL + Usfg] (DFL)a [0.075 (- ] (C.2-8) where:

RTV Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per PiCVm3 All other terms remain the same as those in Equations C.2-4 and C.2-7.

ODCM (BSEP) C-13 Rev. 25

TABLE C-1 PARAMETERS FOR COW AND GOAT MILK PATHWAYS Reference Parameter Value (Reg. Guide 1.109, Rev. 1) 50 (cow) Table E-3 QF (kg/day) 6 (goat) Table E-3 0.7 Table E-15 Yp (kg/m 2) 1.73 x 105 (2 days) Table E-15 tf (seconds) 1.0 (radioiodines) Table E-15 r

0.2 (particulates) Table E-15 (DFLi)a (mrerm/pCi) Each radionuclide Tables E-11 to E-14*

Each stable element Table E-1 (cow)*

Fm (pCil/ per pCi/day)

Table E-2 (goat)**

4.73 x 108 (15 yr) Table E-15 tb (seconds) 2.0 Table E-15 Ys (kg/mr) 0.7 Table E-15 Yp (kg/m2 )

7.78 x 106 (90 days) Table E-15 th (seconds) 330 infant Table E-5 Uap (liters/yr) 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 2.59 x 106 (pasture) Table E-15 te (seconds) 5.18 x 106 (stored feed)

Each stable element Table E-1 BN^ pCi/Kg (wet weight) per pCiKg (dry soil)

P Kg (dry soil)/m2 240 Table E-15 for Hf-181 and Sn-113," May 24,

Reference 1, BSEP File: B1i0-10530, Letter to J. W. Davis "Dose Factors 1988, and NUREG CR4653 for AM-241.

- Where goat data was not available, cow value Fm was assumed.

C-14 Rev. 25 ODCM (BSEP)

TABLE C-2 PARAMETERS FOR THE MEAT PATHWAY Reference Parameter Value (Reg. Guide 1.109, Rev. 1) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/day) Each stable element Table E-1*

Uap (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFLi)a (mrem/pCi) Each radionuclide Tables E-11 to E-14 Yp (kg/M2 ) 0.7 Table E-15 Ys (kg/M2) 2.0 Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 ts (seconds) 1.73 x 1O6 (20 days) Table E-15 t

h (seconds) 7.78 x 1o6 (90 days) Table E-15 te (seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed)

OF (kg/day) 50 Table E-3 By pCiKg (wet weight) Each stable element Table E-1*

per pCUKg (dry soil)

P kg (dry soil)/m2 240 Table E-15 Reference 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-1S1 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.

ODCM (BSEP) C-15 Rev. 25

TABLE C-3 PARAMETERS FOR THE VEGETABLE PATHWAY Reference Parameter Value (Req. Guide 1.109, Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFLi)a (mrem/Ci) Each radionuclide Tables E-1 1 to E-14*

UL (kg/yr) -Infant 0 Table E-5

-Child 26 Table E-5

-Teen 42 Table E-5

-Adult 64 Table E-5 Us(kgtyr) -Infant 0 Table E-5

-Child 520 Table E-5

-Teen 630 Table E-5

-Adult 520 Table E-5 tL (seconds) 8.6x104 (1 day) Table E-15 th (seconds) 5.18 x 106 (60 days) Table E-15 Yv (kg/rn2 ) 2.0 Table E-15 te (seconds) 5.18 x 106 (60 days) Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 P (Kg[dry soilym2 ) 240 Table E-15 Bv (pCi/Kg[wet Each stable element Table E-1*

weight) per pCVkg

[dry soil])

Reference 1, BSEP File: B10-10530, Letter to J. W. Davis "Dose Factors for Hf-181 and Sn-113," May 24, 1988, and NUREG CR4653 for AM-241.

ODCM (BSEP) C-16 Rev. 25

APPENDIX D LOWER LIMIT OF DETECTION (LLD)

The following discussion of LLD is taken from NUREG-0473, Rev. 2, February 1, 1980.

It represents the bases for LLD footnotes (e) in Table 7.3.3-1, (e) in Table 7.3.3-2, (a) in Table 7.3.7-1, and (b) in Table 7.3.15-3 of the BSEP ODCM Specifications. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD=466b E

V

2.22x 106 . Y

exp(-XAt)

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),

X 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 plants effluents, not environmental samples).

The value of Sb used iri the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation.

ODCM (BSEP) D-1 Rev. 25

APPENDIX E RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Liquid Effluent Monitoring Instruments A. Liquid Radwaste Radioactivity Monitor 2-D12-RM-K604 B. Liquid Radwaste Effluent Flow 2-G16-FIT-N057 Measurement Device C. Main Service Water Effluent Radioactivity 1 (2)-Dl2-RM-K605 Monitor D. Stabilization Pond Effluent Composite 2-DST-XE-5027 Sampler E. Stabilization Pond Effluent Flow 2-DST-FIT-5026 Measurement Device F. Condensate Storage Tank Level Indicating 1 (2)-CO-LIT-i1 60 Device Gaseous Effluent Monitoring Instruments

1. Main Stack Monitoring System

a. Noble Gas Activity Monitor 2-D12-RM-23S (2-D12-RE-4982)

b. Iodine Sampler Cartridge IRSH35 Prefilters A or B

c. Particulate Sampler Filter IRSH35 Prefilters A or B

d. System Effluent Flow Rate 2-VA-FIQ-5902-1 OR -2 Measurement Device

e. Sampler Flow Rate Measurement 2-D12-FE-4597 Device

2. Reactor Building Ventilation Monitoring System

a. Noble Gas Activity Monitor 1(2)-CAC-AQH-1264-3

b. Iodine Sampler Cartridge 1(2)-CAC-AQH-1 264-2 (collection cartridge only)

c. Particulate Sampler Filter 1(2)-CAC-AQH-1264-1 (collection filter only)

d. System Effluent Flow Rate 1(2)-VA-FIQ-3356 Measurement Device

e. Sampler Flow Rate Measurement 1(2)-CAC-FI-i264 Device ODCM (BSEP) E-1 Rev. 25

APPENDIX E (Cont'd)

RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont'd)

3. Turbine Building Ventilation Monitoring System

a. Noble Gas Activity Monitor 1(2)-D12-RM-23 1(2)-D1 2-RE-4563)

b. Iodine Sampler Cartridge 1(2)-IRTB32 FPrefilters A or B

c. Particulate Sampler Filter 1(2)-IRTB32 F'refilters A or B

d. System Effluent Flow Rate 1(2)-VA-FIQ-3358 Measurement Device

e. Sampler Flow Rate Measurement 1(2)-D12-FE-4542 Device

4. Main Condenser Off-Gas Treatment System (AOG) Monitor

a. Noble Gas Activity Monitor 1(2)-AOG-RM-1 03

5. Main Condenser Off-Gas Treatment System Ex:plosive Gas Monitoring Syste

a. Recombiner Train A

1. First Hydrogen Monitor 1(2)-OG-AIT-4284 -

S,tream 1

2. Second Hydrogen Monitor 1(2)-OG-AIT-4324 -

Stream 2

b. Recombiner Train B

1. First Hydrogen Monitor 1(2)-OG-AIT-4324 -

Stream 1

2. Second Hydrogen Monitor 1~

(2)-OG-AIT-4284 -

Stream 2

6. Main Condenser Air Ejector Radioactivity Monitor

a. Noble Gas Activity Monitor 1(2)-D12-RM-K601 A and B

7. Hot Shop Ventilation Monitoring System

a. Iodine Sampler Cartridge

b. Particulate Sampler Filter ODCM (BSEP) E-2 Rev. 25

APPENDIX E (Cont'd)

RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS (Cont'd)

8. Radioactive Materials Container and Storage Building Decontamination Facility

a. Iodine Sampler Cartridge

b. Particulate Sampler Filter ODCM (BSEP) E-3 Rev. 25

APPENDIX F LIQUID AND GASEOUS EFFLUENT SYSTEM DIAGRAMS ODCM (BSEP) F-i Rev. 25

FIGURE F-1 Liquid Radwaste Effluent System

.RADIATION MONITORING BLOCK I

STATION VALVE LIQUID IOCFR20 AND

_.- - 42 SEC IOCFT50 EFFLUENT LIMITS /

POTENTIAL LIQUID RELEASE PATHWAYS

MAIN SERVICE WATER DISCHARGE LINES HAVE CONTINUOUS RADIOACTIVITY MONITORS.

THE STABILIZATION POND EFFLUENT TO THE INTAKE CANAL HAS A PROPORTIONAL COMPOSITE SAMPLER AND A FLOW MEASURING DEVICE.

THE REACTOR BUILDING COMPONENT COOLING WATER (SERVICE WATER)

LINE HAS CONTINUOUS LOW PURITY RADIOACTIVITY MONITORS.

HIGH ACTIVITY LIQUID WASTES NOTES LIQUID PROCESS

SOLID RADWASTE SYSTEM - NOT USED b HIGH INTEGRITY MEDIA CONTAINER - STORAGE/BURIAL ODCM (BSEP) F-2 Rev. 26 I

FIGURE F-2 Gaseous Radwaste Effluent System GASEOUS RADWASTE TO MEET 10CFR20 AND IOCFRS0 EFFLUENT LIMITS I

I SECONDARY CONTAINMENT ISOLATION RAD MONITOR UNIT 1 REACTOR BULDNGVENTILATION MONC RN NOTATONS IVENTILATION EXHAUST SYSTEM

OTHER PATHWAYS MONITORED FOR RELEASE

- BUILDING EXFILTRATON

- CIRO WATER PIPING VENTILATION UNIT 1 TURBINE BUILDING - CHARCOAL AND HEPA VENTIUATnON EXHAUST -I FILTER SYSTEM . i SYSTEM - - WASTE OIL INCINERATION GSASEOUS RADWA8TE THE HCV-102 VALVE AUTOMATICALLY

_ TO MEET ISOLATES 15 MIN AFTER HIGH READING FILE SYI IODINE CARTRIDGEAND I ON THE CORESPONDING CONDENSER HOT SHOP 10CFR20 AND AIR EJECTOR RAD MONITOR FILTERRSYSTEMI-.4PA PARTICLATE FILTER L 10CFRS0 I O I NE CA RT I DGELA N EFFLUENT EACH VENTILATION MONITORING UMITS SYSTEM CONTAINS:

. NOBLE GAS ACTMVTY MONITOR IODINE CARTRIDGE AND IODINE SAMPLER CARTRIDGE RMCNSDECON i HEPA FILTER SYSTEM I PARTICULATE FILTER -PARTICULATE SAMPLER FILTER MONITOR -SYSTEM FLOW MONITOR

. SAMPLER FLOW MONITOR ILOW 4LEVEL WAREHOUSE FILTER SYSTEM IEPAPARTICULATE FLTR l VENILTIN XHUS _" HEA ILERSYTE __ MONITORl SECONDARY CONTAINMENT ISOLATION RAD MONITOR UNIT 2 REACTOR BUILDING __ VENTILATION IMONTRN VENTILATION EXHAUST _SYSTEM-

. f UNIT 2 TURBINE BUILDING CHARCOAL AND HEPA VENTILATION MONIRIN IVENTILA;TION ST

_3 _ FILTER SYSTEM _ SYSTEM - 7 ODCM (BSEP) F-3 Rev. 26 [

APPENDIX G ODCM SOFTWARE PACKAGE In order to minimize calculational errors and to facilitate the use of the ODCM, BSEP has developed an ODCM software package. All applicable calculations listed in the ODCM have been included in this software.

During periods when the ODCM software is not available, the following alternate method may be used to assess dose or dose rates to the public from liquid or gaseous effluents:

Dt = (Dh x Ct)/Ch where: Dt = the unknown dose/dose rate for the time period Dh = the known dose/dose rate from historical data Ct = the total curies released for the time period Ch = the total curies used to calculate the known dose/dose rate When the ODCM software becomes available again, all doses to the public will be reassessed using the software package.

ODCM (BSEP) G-1 Rev. 25

APPENDIX H METHODOLOGY AND CALCULATIONS FOR BURNING WASTE OIL To permit burning of slightly contaminated waste oil in the clean trash incinerator, an insignificant fraction (0.1%) of the following regulations must be met: 10CFR20; 10CFR50, Appendix I; and 40CFR190. The following sections contain the methodology and the calculations to determine the concentration and the cumulative total activity to be used in procedures to demonstrate compliance with the above regulations.

I. Compliance with 10CFR20 for 1-131, 1-133. Particulates, and Tritium The inhalation dose rate associated with burning waste oil is insignificant by definition. Regulatory Guide 1.109 states, "A pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered." Since the release rate by incineration of waste oil is < 10% of the plant's total release rate, the dose rate via waste oil is insignificant.

10CFR20 Limit = 1500 mrem/yr (Inhalation to a child's most critical organ)

Insignificant = 150 mrem/yr (10% of limit) 0.1% of 10CRF20 = 1.5 mrem/yr, this more than meets the above criteria and is a consistent fraction as listed in ODCM Specification 7.3.9.c.

Since the limit is going to be limited to 0.1% of 10CFR20, the maximum release rate (gCVsec) can be calculated by the following equation:

Q0 1.5 mrem / yr (Rj) (X/Q) where =

R= Dose factor for the most restrictive organ to a child (lung) for inhalation using Co-60 (7.06E6 mremlyr/gCVm 3)

X/ Q = Annual average relative concentration for release from the Turbine Building, 7.5E-6 sec/M 3 Since the incinerator operates > 500 hrs/yr and the stack height is considered to be ground level, the meteorology used for dilution will be the same as the Turbine Buildings (ground level continuous). From Appendix A, Table A-1 the most restrictive sector is SSE (7.5E-6 sec/i 3).

For the source term mix, 100% of the activity is assumed to be Cobalt-60. Most of the activity in the slightly contaminated oil is corrosion and activation products with occasional detection of Cesium-134 and Cesium-1 37.

ODCM (BSEP) H-1 Rev. 25

APPENDIX H (Cont'd)

No iodines will be permitted in the waste oil for incineration. Cobalt-60 is the most restrictive radionuclide for the inhalation pathway to a child's lung (Table 3.3-18).

Therefore, 1.5 mrem/yr 3

(7.06E6 mrem / yr / iCi / m3 ) (7.5E -6 sec/ M )

0. = 2.83E-2 jCi/sec The maximum oil flow rate for burning oil in the incinerator is six gal/min. The maximum flow rate in cc/sec is calculated as follows:

(6 gal/min) (min/60 sec) (3785 cc/gal) = 378.5 cc/sec of The main fuel oil tank for the incinerator shall not contain more than 20% by volume slightly contaminated oil. Therefore, the maximum waste oil flow rate would be 1.2 gal/min in lieu of 6 gal/min. For additional conservatism, the flow rate will equal 6 gallons/min for burning oil.

by The maximum concentration (ViCVcc) of waste oil to be burned can be determined the following equation:

Max. Conc. (giCVcc) = 2!i f Where:

f = waste oil flow rate 378.5 cc/sec Max. Conc. (Ci/cc) = 83E8 /

378.5 cc! sec

- 7.48E- 5 Ci/cc The maximum concentration of waste oil to be incinerated is limited to 7.48E-5 gC/cc and which is 0.1% of 10CFR20 limits. This shall be controlled by procedures, sampling, analyzing the waste oil prior to burning. Limiting the concentration to an insignificant release rate meets the intent of ODCM Specification 7.3.7.

II. Compliance with 10CFR50. Appendix I for 1-131 1-133, Particulates and Tritium ODCM Specification 7.3.9.c limits the burning of waste oil in the incinerator to 0.1% of two times 10CFR50, Appendix I (two-unit site). For conservatism, burning of waste oil shall be limited to 10CFR50, Appendix I.

ODCM (BSEP) H-2 Rev. 25

APPENDIX H (Cont'd)

Therefore:

0.001 x 7.5 mrems = 0.0075 mrem to any organ during any calendar quarter 0.001 x 15 mrems = 0.0150 mrem to any organ during any calendar year The cumulative dose for the above yearly limit is determined by the following equation:

0.015 (mrem) < 3.17E-8 [(RG+ Rm+RRV +RB) (DI tb) (Q1011) +(Rj)(XIQ) (Qi0j)]

The above equation can be further reduced as follows:

0.015 (mrem)

3.17E-8 [(oI'0)[(R'G +RM+RV +RF) (D/ Qu) + (R1) (X/Qt)1 The activity in the slightly contaminated waste oil is long lived fission, corrosion, and activation products. There is no lodine-131 or Iodine-133 in the oil. Using the most conservative radionuclides (Cesium-1 34, Cesium-137, and Cobalt-60), a quarterly and of yearly activity can be calculated for all organs and all age groups for the summation all pathway doses. The maximum activity to'be released for a calendar quarter and calendar year can be determined as follows:

0.015 (3. 1 7 E- 8 )[RG + RIM + RV + R )(D/Qb) + (R4)(XIQt) where:

3.17E-8 = The inverse of the number of seconds in a year RG= Dose factor for an organ for radionuclide i for the ground plane exposure pathway, mrem/yr per jtCVsec per Table 3.3-1 ODCM (BSEP) H-3 Rev. 25

APPENDIX H (Cont'd)

RM= Dose factor for an organ for radionuclide i for the cow milk pathway, mrem/yr per pCisec per rn , Tables 3.3-8, 3.3-9, 2

3.3-10, and 3.3-11, there is no goat milk production within 5 miles of site R= Dose factor for an organ for radionuclide i for the vegetable pathway, mrem/yr per IxCisec per mr , Tables 3.3-2, 3.3-3 2

and 3.3-4 RB= Dose factor for an organ for radionuclide i for the meat pathway, mrem/yr per pCi/sec per mr , Tables 3.3-5, 3.3-6, 2

and 3.3-7 R, = Dose factor for an organ for radionuclide i for the inhalation pathway, mrem/yr per VCVm , Tables 3.3-16, 3.3-17, 3.3-18, 3

and 3.3-19 D/Qtb = Annual average deposition for release from the Turbine Buildings, NE Sector

= 1.9E-8 m2 , most restrictive, from Appendix A, Table A-3 X/Qt = Annual average relative.concentration for releases from the Turbine Buildings, SSE sector

7.5E-6 sec/M 3 , most restrictive, from Appendix A, Table A-i release in any The most restrictive age group and organ is Child Bone. The maximum is 436 x 1/2

quarter calendar year is 436 pCi. The maximum release in any calendar 218 pCi.

shall be All slightly contaminated waste oil that is to be burned in the incinerator and yearly limit (218 1iCi) controlled by procedures demonstrating that the quarterly limit used for calculating (436 0Ci) are not exceeded. Doubling these piCi limits shall be end of each calendar percent of technical specification limit in the annual report. At the the ODCM.

year a dose assessment will be made using the methodology in H-4 Rev. 26 ODCM (BSEP)

APPENDIX H (Cont'd)

Summary of Co-60, Cs-137, and Cs-134 jiCi Release Yearly Limit by Age Group and Organ T Body GI-Tract Bone Liver Kidney Thyroid Lunq Skin Co-60 Adult 1,132 965 1,158 1,147 1,158 1,158 1,044 988 Teen 1,120 977 1,158 1,142 1,158 1,158 999 988 Child 1,091 1,037 1,158 1,134 1,158 1,158 1,025 988 Infant 1,153 1,151 1,158 1,155 1,158 1,158 1,070 988 Cs-137 Adult 1,179 2,349 1,112 928 1,564 2,418 2,053 2,075 Teen 1,278 2,333 826 1,292 2,418 1,812 2,075 Child 1,474 2,349 436* 453 1,001 2,418 1,603 2,075 Infant 1,910 2,390 575 1,205 2,418 1,714 2,075 Cs-134 Adult 1,063 3,471 1,623 1,125 1,857 3,652 2,766 3,129 Teen 1,163 3,452 1,233 649 1,478 3,652 2,337 3,129 Child 1,441 3,517 672 442 1,120 3,652 2,017 3,129 Infant 2,258 3,594 851 513 1,417 3,652 2,217 3,129

Most restrictive quantity in pCi resulting in 0.1% of IOCFR50 Appendix I limit.

Ill. Compliance with 40CRF190 The annual (calendar year) 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.

Incinerating waste oil is limited to 0.015 mrem to the most critical organ (including the whole body) using all pathways. 40CFR1 90 is automatically complied with since 0.015 mrem is < 0.1% of 25 mrem.

ODCM (BSEP) H-5 Rev. 25

BSEP-03-0003, Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H

Contents

Text

6.1 INTRODUCTION

6.1 INTRODUCTION

7.5E-6 sec/M 3 , most restrictive, from Appendix A, Table A-i release in any The most restrictive age group and organ is Child Bone. The maximum is 436 x 1/2

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BSEP-03-0003, Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H

Text

6.1 INTRODUCTION

6.1 INTRODUCTION

7.5E-6 sec/M 3 , most restrictive, from Appendix A, Table A-i release in any The most restrictive age group and organ is Child Bone. The maximum is 436 x 1/2

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