ML20054G331

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Marked-up Proof & Review Copy of ETS Tables 3.3-12,4.3-8, 3.3-13 & 3.12-1 Re Radioactive Liquid Effluent Monitoring Instrumentation & Surveillance Requirements & Radioactive Gaseous Waste Monitoring,Sampling & Analysis Program
ML20054G331
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/14/1982
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20054G327 List:
References
NUDOCS 8206210445
Download: ML20054G331 (7)
v • d • e


Text

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k am TABLE 3.3-12

" "E E$ 3 E >$ RADIDACTIVE LIQUIO EFFLUENT MONITORING INSTRUMENTATION 9 cm 02 x4 .

e MINIMUM 35 H

o" CHANNELS' j

I~

ACTION

  • oo 8@ INSTRUMENT OPERABLE 3 ub3  ! j QA 1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC  ! ,

TERMINATION OF RELEASE .

i 1 3/ ,

a. Liquid Radwaste Effluent Line - RM-L5 or RM L9 1 32
b. Nuclear (Processed Steam Generator) Blowdown Effluent Line RM-LI Ior RML-9 l

l c. Steam Generator Blowdown Effluent Line 1 32 .

1. Unprocessed during Power Operation - PM-L10 or RM-L3 1 32
2. Unprocessed during Startup - RM-L3

, ka 33 1

Y d. Turbine Building Sump Effluent Line - RM-LB

2. FLOW RATE MEASUREMENT DEVICES *

~

i, 1/ tank 34

a. Liquid Radwaste Effluent Line - Tanks 1 and 2 1 34
b. Penstocks Minimum Flow Interlock ** 1 34
c. C e ndensa te-Demi neral4 a ec-E ff4 ueat-L4 n 1 34 ,
c. R. Nuclear Blowdown Effluent Line d, 4 Steam Generator (Unprocessed) Blowdown Effluent Line
3. TANK LEVEL INDICATING DEVICES 4 1 35
a. Condensate Storage Tank s

" T Flow rate for the monitor RM-L9 is determined by adding flow rates for monitors RM-L5 and RM-L7.

    • Minimum dilution flow is assured by an interlock terminating liquid waste releases if minimum a

g dilution flow is not available.

R$

F INSTRUMENTATION N. -.ci TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 36 With the number of channels OPERABLE less than require y the Minimum Channels OPERABLE requirement, effluent rele, es may continue for up to 14 days provided liquid Waste Effluent Monitor RM-L9 is OPERABLE'or prior to initiatingA release:

a.

/

At least two independent so.:p'tes are analyzed in accordance with Specification 4.1.1.1.3, and

b. A east two technically qualified members of the facillty staff independen,tfy verify the release rate calculations and discharge line valving. ~

\

Otherwise, suspend release o radioactive effluents via this pathway.

ACTION 37 - WiththenumberofchannelsOPE$ABLElessthanrequiredbythe ' '

Minimum Channels OPERABLE requirement, effluent releases via this pathway may cohtinue for up t'o s30 days provided Liquid Waste Effluent ,Mo'nitor RM-L9 is OPERABLE or grab samples are r analyzed for gross radioactivity (beta'and gamma) at a limit of detection o. Vat least 10 7 microcuries/gm.

/

a./ At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the s cific activity of the secondary coolant is greater th 0.01 microcuries/gm DOSE EQUIVALENT I-131.

/ b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific avity of the secondary coolant is less than or equal to 0.01 microcuries/gm DOSE EQUIVALENT I-131. .

] e

[ -

e/e ba-SUMMER - UNIT 1 3/4'3-70 W 3 1982 f

@f L W'S! \  ;

v. TABLE 4.3-8 C

" RADIOACTIVE LIQUID EFFLUENT MONITORING' INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,I e

c ANALOG CHANNEL CilANNEL OPERATIONAL h CilANNEL SOURCE CNECK CALIBRATION TEST H CllECK INSTRUMENT

1. GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION j OF RELEASE D P R(3) Q(1) ,
a. Liquid Radwaste Effluent Line - RM-LS, RM-L9 E - U3) QO)
b. Nuclear Blowdown Effluent Line - RM-L7, RM-L9 D D M R(3) Q(1)
c. Steam Generator Blowdown Effluent Line -

E RM-L3, RM-LIO s

y. d. Turbine Building Sump Q(1)

D H R(3) p Effluent Line - RM-L8 l

2. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line j D(4) N.A. R Q P"-LE, "-L9 e D(4) N.A. R Q
b. Penstocks Minimum Flow Interlock

"^

- c. Cender, ate 0=iner:Mact Ef fluent lire D(') S D(4) N.A. R Q C.f. Nuclear Blowdown Effluent Line 0(4) H.A. R Q d.y.SteamGeneratorslowdown '

$ Effluent Line R:: L3, RM L7, EM L10

o TANK LEVEL INDICATING DEVICES
3. l N.A. R l Q

$ a. Condensate Storage Tanks D N 1 t

i 1

m TABLE 3.3-13 c .

o RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION e

c MINIMUM CilANidLS ACTION 5

H OPERABLE APPLICABILITY INSTRUMENT e

1. WASTE GAS tl0LDUP SYSTEM
a. Noble Gas Activity Monitor - Providing
  • 38' 1

Alarm and Automatic Termination of Release '

RH-A10 or RM-A3

2. WASTE GAS 110LDUP SYSTEM EXPLOSIVE GAS -

l MONITORING SYSTEM

    • 44 2
a. Oxygen Monitor /Recombiner
    • 42 s 1

,,.y,

% 3. MAIN PLANT VENT EXilAUST SYSTEM

a. Noble Gas Activity Monitor - Providing
  • 40 I

Alarm and Automatic Termination of Release from Waste Gas lloldup System -

RM-A3

  • 43 1
b. Iodine Sampler
  • 39" Y3 1

, c. Particulate Sampler

  • 39 1
d. Flow Rate Heasuring Device a 39 m I g e. Sampler Flow Rate Measuring Device i

c 43

TABLE b -2

~

v, RAD 10 ACTIVE GASEOUS WASTE MONTTORING AND SAMPLING AND ANALYSTS PROGRAM i

m

" Minimum Lower Limit

' Sampling Analysis of Detection -

si Gaseous Release Type Frequency Frequency Type of Activity Analysis (LLD)(pCi/ml)"

g A. Waste Gas Storage P P 4

Tank Each Tank Each Tank Principal Gamma Emmitters 9 1x10 Grab Sample 81 Reactor Building P P b ~4

-36" Purge Line Each Purgeb ,c Each Purge Principal Gamma Emitters 9 1x10

-6" Purge Line -6

. H-3 M0 D

B2 Reactor Building M M

~4

-6" Purge Line Grab Sample Principal Gamma Emmitters 9 1x10 t'

(if continuous) -6 H-3 1x10 D

C. Main Plant Vent MD '" M q

-6 H-3 1x10

~

d D.1. Reactor Building Continupus W I-131 1x10 Purge Sampler Charcoal Sample I-133 1x10 d ~11

2. Main Plant Vent Continupus W Principal Gamma Emitters 9 1x10 Sampler Particulate Sample I-131, others . .

Continupus M c

.77 G,oss Alpha Sampler Composite .

r 1x10 Particulate Sample Continugus Q -11 g Sampler Composite ' Sr-89, Sr-90 1x10 Particulate Sample +-

-6 Continu us Noble Gas Noble Gases 2x10 .;

y Monitor Monitor Gross Beta

. - - - - - -- -- - a

( RADI0 ACTIVE EFFLUENTS pgg GAS STORAGE TANKS !L h LIMITING CONDITION FOR OPERATION h ..

3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 50,000 curies noble gaises (considered as Xe-133). /60,000

  • > :, \,j APPLICABILITY: At all times. ,

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b. The provisions of Specifications 3.0.3 and"3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS '

4.11.2.6 The quantity of radioactive material contained in each gm storage tank shall be determirfed to be 'within the above limir, at Meast crice per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials ,are being added to the tank.

P C

/

SUMMER - UNIT 1 3/4 11-18 T

(

l

,. J

V E Table 3.12-1 (continued)

SE '

"m'

' Sampling and Type and Frequency ',

Exposure Pathway flinimum Number of Sample Locations and Collection of Analysis .

E and/or Sample Criteria for Selection Frequency El .

w INtiESTION 2 Semi-monthly when Gamma isotopic and I-131 VII. Hilk(g) A Samples from milking animals in 3 locations animals are on analysis semi-monthly (6) within 5 km distant pasture, (6) animals are on pasture; having the highest. dose- monthly other monthly (3) at other times.

pntential. If there times.(3) are none then, 1 sample from milking animals in r each of 3 areas between Ri 5 to 8 km distant wher e -

  1. " doses are calculated ;o . ,

be greate{ than 1 mrem

{f os per year. ,

t' B 1 Control sample to be -

taken at the location of '

a dairy > 20 miles dis- 8 tant and not in the most ,

prevalent wind direc-tion.(1) .

1 Indicator grass (for- Gamma Isotopic.

C age) sample to be taken Monthlywhen)-

available.(3 at one of the locations .

beyond but as close to the exclusion boundary I 97 as practicable where  !

Ibi the highest offsite c=

sectoral grousul level concentrations are ,

S - anticipated.(1)  :

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