ML20215K692

Proposed Tech Specs,Adding Addl Monitored Release Points for Gaseous Effluents

ML20215K692
Person / Time
Site:	Hatch
Issue date:	05/01/1987
From:	GEORGIA POWER CO.
To:
Shared Package
ML20215K689	List: ML20215K686 ML20215K692
References
TAC-65244, TAC-65245, NUDOCS 8705110306
Download: ML20215K692 (10)

Text

1 r

TABLE 3.14.2-1 (SHEET 2 0F 4)

N RADIOACTIVE GASEOUS EFFLUEleT MolllTORIllG INSTRUMENTATION x

Minimum C

Channels 3

Instrument OPERABLE Apolicability Pa ramete r ACTION

~4 4.

Main Stack Monitoring System Radioactivity Rate

-105 a.

leoble Gas Activity Monitor (1)

Measurement +

Verify Presence or

~ 107-b.

todine Sampler Cartridge (1)

Ca rt ridge Verify Presence of 107 c.

Particulate Sampler Filter (1)

Fil te r d.

Effluent System Flowrate Measuring Devices (1)

Sys tem F lowra te.

_104 Mea surement Sampler Flowrate 104 w

e.

Sampler Flowrate Measuring (1)

Device Measurement

~

A 5.

Condenser Offgas Pretreatment Monitor Radioactivity Rate 108 Noble Gas Activity Monitor (1)

Measurement Radioactivity Rate 105 6.

Building Exhaust (1)

Monitor for Augmented Measurement Ventilation ke S.

CL (M3 E

N m

8705110306 870501 PDR ADOCK 05000321 P

PDR

h TABLE 4.13.2-1 (SHEET 2 OF 3) 4

-4 O

RADIOACTIVE CASEOUS EFFLUENT MONITORING

^

INSTRUMENTATION SURVEILLANCE REQUIREMENTS c2:

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST e-*

3. Recombiner Building Ventilation Monitoring System a.

Noble Cas D*

M R

Q(1)

Activity Monitor b.

lodine Sampler W'(3)

NA NA NA Ca rt ridge c.

Pa rt icula te W'(3)

NA NA NA Sample Filter d.

Sampler Flowrate D*

NA R

Q Measuring Device

~

~

4. Main Stack p

Monitoring System N

a.

Noble Gas D*

M R

Q(1)

Activity Monitor b.

G od ine Samp l e r W'(3)

NA NA NA c.

Pa rt icu la te W'(3)

NA NA NA Samp le r d.

Flowrate Monitor D*

NA R

Q e.

Sampler Flowrate D*

NA R

Q y

s Monitor o3 5.

Condenser OFFgas Pretreatment Monitor Noble Gas Activity D***

M R

Q(1) y

_ Monitor Nc) 6.

Building Exhaust D*

M*

R*

Q*

Monitor For Augmented y

w Ventila tion k

co

INSTRUMENTATION BASES 3/4.14.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be. calculated in accordance with the methods in the OFFSITE DOSE CALCULATION MANUAL (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.

3/4.14.2 -RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods fn the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The monitoring instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

Surveillance frequencies for augmented ventilation systems are only required when the system is installed and releases are being made via that pathway. The_ augmented ventilation systems are designed to assist normal release paths for temperature control and reduction of excess noble gas concentrations.

Their use is oc a temporary basis only; i.e.,

they are not permanent modifications to tha plant.

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RADI0 ACTIVE EFFLUENTS l

BASES boundary.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to s 500 mrem / year to the total body or to s 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year, j

This specification applies to the release of gaseous effluents from all reactors at the site.

For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

l Sampling for augmented ventilation systems is only required when the system is installed.gnd releases are being made via that pathway. The augmented ventilation systems are designed to assist normal release paths for temperature control and reduction of exces:; noble gas concentrations. Their use is on a temporary basis only; i.e., they are not permanent modifications to the plant.

3/4.15.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.8, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The LCO implements the l

guides set forth in Section II.B of Appendix I.

The ACTION statements I

provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I, assuring that the releases of radioactive material in gaseous effluents will be kept ALARA.

The Surveillance Requirements implement the requirements in Section III.A of Appendix I, which state 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 an individual through the appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the OFFSITE DOSE CALCULATION MANUAL (00CM) 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 l

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with l

10 CFR Part 50, Appendix I, Revision 1, October 1977; and Regulatory Guide 1.111, Methods for Estimating Atmosphere 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 the exclusion area boundary will be based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculaticns consistent with Regulatory Guides 1.109 and 1.111.

l l

l HATCH-UNIT 1 3.15-23 Proposed TS/0114q/118 l

l I

.;-,~..

TABLE 3.3.6.10-1 (SHEET 1 CF 3)

RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION l

1 M

Minimum n

Channeis Z

I nst rument OPERABLE Anoticability Pa rame te r ACTION e

1.

Main Condenser Ofrgas Treatment E

System Explosive Gas Monitoring g

System to Hydrogen Monitor (1).

. % Hydrogen 106 2.

Reactor Building Vent Stack Monitoring System a.

Noble Gas Activity Monitor (1)

Radioactivity Rate 105 Measurement +

b.

todine Sampler Cartridge (1)

Verify Presence of 107 Cartridge c.

Particulate Sampler Filter (1)

Verify Presence of 107 Filter w

d.

Effluent System Flowrate 1

Measurement Device (1)

System Flowrate 104 Measurement w$

e.

Sampler Flowrate o

Measurement Device (1)

Sampler Flowrate 104 50 Mea surement 3.

Main Stack Monitoring System a.

Noble Gas Activity Monitor (1)

Radioactivity Rate 105 Measurement +

b.

lodine Sampler Cartridge (1)

Verify Presence 107 of Cartridge o

c.

Particulate Sampler Filter (1)

Verify Presence 107

]

of Filter we

'D d.

Effluent System Flowrate (1)

System Flowrate 104 Measuring Devices Mea surement

-4R e.

Sampler Flowrate Measuring (1)

Sampler Flowrate 104 o

Device Measurement w

4.

Condenser Offgas Protreatment Q

Monitor C

Noble Gas Activity Monitor (1)

Radoactivity Rate 108 co Mea su rement 5.

Building Exhaust-(1)

Radioactivity Rate ~

105 Monitor for Augmented Measurement Ventitation Proposed TS/01159/118 -

.. -. - ~.....

TABLE 4.3.6.10-1 (SHEET 1 CF 2)

RADIOACTIVE CASEOUS EFFLUENT MONITORING

{

Z INSTRUMENTATl006 SURVEILLANCE REQUIREMENTS 3

i g

Z CHAleNEL s

CHAssteEL SOURCE CHANNEL FUteCTiossAL Instrument CHECM CHECK CALIBRATICII TEST j

c N

1.

Main Condenser Orrgas Treatment to

. System Explosive Gas Monitoring i

Hydrogen Monitor D**

NA Q(2)

M 2.

Reactor Building I

Vent Stack

{

Monitoring System 1

a a.

Noble Gas Activ-D*

M R

Q(1)

{

ity Monitor l

b.

todine Sampler W'(3)

NA NA NA Ca rt ridge l

c.

Particulate W'(3)

NA NA NA y

Sampler Filter i

i A

g d.

Erfluent System D*

NA R

.Q Y

Flowrate m

Measuring Device

}

O e.

Sampler Flowrate D*

16A R

Q l

Measuring Device I

j 3.

Main Stack Monitoring

]

System

)

a.

Noble Gas D*

M R

Q(1) 1 Activity Monitor 4

l b.

Iodine Sampler W'(3)

NA NA NA 1

7 Ca rtridge I

O

]

c.

Particulate W'(3)

NA NA NA e

Sampler an" H

'Flowrate Monitor D*

NA R

Q d.

R e.

Sampler Flowrate D*

NA R

Q j

o Monitor 5

N.

Condenser Orrgas

.o Pretreatment Monitor N

U Noble Gas Activity D***

M R

Q (1) j CD Monitor 4

l 5.

Building Exhaust D*

M*

R*

Q*

{

Monitor for Augmented Venti la tion 4

}

i I

k

' RADIOACTIVE EFFLUENTS t

BASES 4

1 i

boundary.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose ra'es above background to an individual at or beyond the exclusion area boundary to s 500 mres/ year to the total body or to s 3000 mrem / year to the skin.

These release rate limits also restrict, L

I at all times, the corresponding thyroid dose rate above 4

background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.

This specification applies to the release of gaseous effluents from all reactors at the site.

For units with shared radwaste treatment systems, the gaseous effluents from the shared system 0

are proportioned among the units sharing that system.

[

Sampling for augmented ventilation systems is only required when the i"

system is installed 4.nL releases are being made via that pathway. The augmented ventilation systems are designed to assist normal release paths i

for temperature control and reduction of excess noble gas concentrations. Their use is on a temporary basis only; 1.e., they are 3

j not permanent modifications to the plant.

4 3/4.11.2.2 DOSE. NOBLE GASES

)

This specification is provided to implement the requirements of Sections II.8, III.A, and IV.A of Appendix I,10 CFR Part 50.

The LCO implements the guides set forth in Section II.B of 1

j Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I, assuring that the releases of radioactive material in gaseous effluents will be kept ALARA.

The Surveillance Requirements implement the requirements in Section III.A of Appendix I, which state 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 an individual through the appropriate j

pathways is unlikely to be substantially underestimated.

The dose calculations established in the OFFSITE DOSE CALCULATION 4

MANUAL (ODCM) for calculating the doses due to the actual 4

release rates of radioactive noble gases in gaseous effluents 4

will be consistent with the methodology provided in Regulatory 4

Guide 1.109, Calculation of Annual Doses to Man from Routine l

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977; and Regulatory Guide 1.111, Methods for Estimating l

Atmosphere Transport and Dispersion of Gaseous Effluents in l

Routine Releases from Light-Water-Cooled Reactors, Revision 1, 1

July 1977. The 00CM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

HATCH - UNIT 2 8 3/4 11-3 Proposed TS/0117q/118 l

l 1

1 1

e TABLE 4.11.2-1 ($HEET 1 OF 3)

-4Q RADICACTIVE GASEOUS WASTE SAMPLIIeG AND AMALYSIS PROGRAM Sampling Analysis Type of Lowe r L imi t o r cz Caseous Release Type Frequency Frequency Activity Analysis (uCi/ml) Detection'*8 A.

Environmental M'**

M'**

Principa l Gamma Emitters 8 ' 8 1 x 10*8 N

Release Points Gra b Sample 1.

Main Stack H-3 1 x 10-'

2.

Reactor Building Vent 3.

Building Exhaust for Augmented Ventilation B.

All Release Continuous'*8 W'*8 l-131 1 x 10-s a Types (as listed Cha rcoa l 1-133 1 x 10 -' "

in A above)

Sample W"'

Principa l Gamma Emitters

1 x 10-

i Continuous

Pa rt icula te (I-131. Others) yg Sample Continuous **

M Gross Alpha 1 x 10-' '

8

-.y Composite Pa rt icula te O

Sample Continuous'**

Q Sr-89, Sr-90 1 x 10

Composite Pa rt icula te Sample m

O uO we 83a

-e E,4 N

.,,a O

D N

e w

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued)

FIRE DETECTION INSTRUMENTATION (Continued)

In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.3.6.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the OFFSITE DOSE CALCULATION MANUAL (00CM) 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.

3/4.3.6.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The monitoring instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

Surveillance frequencies for augmented ventilation systems are only required when the system is installed g,nj releases are being made via that pathway. The augmented ventilation systems are designed to assist normal release paths for temperature control and reduction of excess noble gas concentrations. Their use is on a temporary basis only:

1.e.,

they are not permanent modifications to the plant.

3/4.3.7 TURBINE OVER$ PEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

HATCH - UNIT 2 8 3/4 3-5 Proposed TS/0117q/118

-