Text

Proposed Tech Specs Pages & Tables,Reflecting Changes to 810915 Radiological & ETS
	ML20031F752
Person / Time
Site:	Summer
Issue date:	10/15/1981
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20031F727	List: ML20031F726; ML20031F733; ML20031F752;
References
	NUDOCS 8110200392
	Download: ML20031F752 (27)
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_ _ _ _ _ _ - _ - _ _ _ _ _ _ _

D m

L>EC Ten n

0 TABLE 3.3-6 Th@E Om L' RADIATION MONITORING INSTRUMENTATION C

oc c MINIMUM T*

5 CHANNELS APPLICABLE ALARH/ TRIP MEASUREMENT

'E 7 [

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.

AREA MONITORS a.

Spent Fuel Pool Area (RM-G8)

_j 4

1

$ 15 mR/hr 10

- 10 mR/hr 25 b.

Reactor Building Manipulator 5

Crane Area (RM-G17A or 1

6

< 1 R/hr 1 - 10 mr/hr 28 RM-G17B)

~

c.

Reactor Building Area 1.

High Range RM-G7 or 1

1, 2, 3 & 4 N/A 1 - 107 R/hr or 30 High Range RM-G18 10 - 10s R/hr

{

2.

PROCESS MONITORS w

a.

Spent Fuel Pool Exhaust -

/06 c PS/ er 4

i Ventilation System (RM-A6)

< 2 x hacr g**d s

6

~

1.

Gaseous Activity 1

- 1-x-10~

pGUce 10 cpm 27

-TKr-857 6

R/A 10 - 10 cpm 27 11.

Particulate Activity 1

b.

Containment

i. Gaseous Activity

- Purge & Exhaust

+A+

6 l

Isolation (RM-A4) 1 6

10 - 10 cpm 28

m

-_.m._,,o 11.

Particulate Activity (RM-A2) - RCS Leakage Detection 1

1, 2, 3 & 4 y/A 10 - 106 cpm 26 c.

Control Room Isolation 1

ALL MODES

$ 2 x backy ound 10 - 10 cpm 29 (RM-A1) c,,

h

^ With fuel in the storage pool or building

- With irradiated fuel in the storage pool

- - Alarm / trip setpoint will be per ti.e Operational Dose Calculation Manua' A en purge exhaust operations are in progress 1

INSTRUMENTATION

(

TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, n..

Prope,/e Seve,//.ae of the monitored area with portable monitoring instrumentation at least-once-per-24-hottrs. Such l,6-en h fo * -, fo 'inefa/o a ),al a o

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.11.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels nPERABLE requirement, comply with the ACTION requirements of 1.gecification 3.9.8.

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,'within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the emergency mode of operation.

ACTION 30 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, -restore the inoperable-Chancel (s)=

-to-OPERABtE Status-withirr-7-days, cr be in at-teast-tt0T-5TANDBt Ati-thin the next C howana-in-et-least-tt07-SMtiTDOWN within-the-fotlowing 6 hem 5 and-irr-C0tD-5HtfTDOWN within-the-subsequent

- ~h* *Mh 74s eH1,er-reske - tAe imer+ L /e 3

cha,me l f opread/-

sMu s pow /e offe,- ms or of m ecase.u-f4e peno,efe,(s) %d Sdmd Sp ee,a l I?e.,f f

tic co m,ssib->

p u s u a n f fz,

.spech cak cc,9. 2 oJ/h,y de plan s b

+cs h e,y &

,u open ue issA u-/ej k sina We sL Ls.

Me v u,.g,

b, Wor c Haram w t/s,'n h *1eYf l2-

$ pu rS, 1

l L

g1 5 1991 SUMMER - UNIT 1 3/4 3-44

C D

R E

TABLE 4.3-3 y

9 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

e ANALOG CilANNEL MODES FOR WilICil 5

CllANNEL CilANNEL OPERATIONAL SURVEILLANCE

]

INSTRUMENT CilECK CALIBRATION TEST IS REQUIRED 1.

AREA MONITORS a.

Spent Fuel Pool Area (RM-G8)

S R

M b.

Reactor Building Manipulator 5

R H

6 Crane Area (RM-G17A or RM-G178) c.

Reactor Building Area 1.

liigh Range (RM-G7)

S R

M 1, 2, 3 & 4 ii.

liigh Range (RM-G18)

S R

M 1, 2, 3 & 4 2.

PROCESS MONITORS i

a.

Spent Fuel Pool Exhaust Area -

l R

Ventilation System (RM-A6) i.

Gaseous Activity 5

R H

{

11.

Particulate Activity S

R H

b.

Containment i.

Gaseous Activity All MODES

- Purge & Exhaust Isolation (RM-A4)

S R

M X

11.

Particulate Activity

- RCS Leakage Detection S

R M

1, 2, 3 & 4 (RM-A2) c.

Control Room Isolation (RM-A1)' S R

M All MODES d.

Noble Gas Effluent Monitors (High Range)

i. Main Plant Vent (RM-A13)

S R

H 1, 2, 3 & 4 m

li. Main Steam Lines

[

(RM-G19A, B, C)

S R

M 1, 2, 3 & 4 g

111. Reactor Building Purge Supply & Exhaust

=

System (RM-A14)

S R

M 1, 2, 3 & 4 "Ulth fuel in the storage pool or building

- With irradiated fuel in the storage pool

INSTRUMENTATION TABLE 3.3-8

\\

/

NETEOROLOGICAL MONITORING INSTRUMENTATION N

/

MINIMUM INSTRUMENT LOCATION OPERABLE 1.

WIND SPEED (MPH)

/

a.

0-100 p, Nominal Elev. 10 meters 1

[

2.

WIND DIRECTION a.

0-540*

/

Nomina Elev. 10 meters 1

AIR TEMPERATURE, / DELTA T("F) 3.

-10to+55 Nominal Elev. 61 meters 1

a.

10 meters (Elevation shown is in relation to ground leve1 Nt meteorological tower.)

\\

C U

3"-l-w=TE SEE

/ EO y

%(sE i

SUMMER - UNIT 1 3/4 3-51 SEP 151981

.... - ~.. -

INSTRUMENTATION TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION CHANNEL INSTRUMENT DESIGNATION & LOCATION MINIMUM OPERABLE 1.

Wind Speed a.

Wind Speed Lower - Primary Met Tower 10m or b.

Wind Speed Upper - Primary Met Tower 61m or 1

c.

Backup Wind Spped - Backup Tower 10m*

2.

Wind Direction a.

Wind Direction Lower Primary Met Tower 10m or b.

Wind Direction Upper Primary Met Tower 61m or 1

c.

Backup Wind Direction Backup Tower 10m*

3.

Atmospheric Stability a.

Delta T 1 Primary Met Tower 61m or b.

Delta T 2 Primary Met Tower 40m or 1

c.

Backup W.D. Sigma Backup Met Tower 10m* or d.

W. D. Sigma Primary Met Tovier 10m Elevations. nominal above grade elevation

Backup Meteorological System is anticipated to be operational by April 1,1982 pending equipment availability.

El 3/4 3-pf L

'WJ h$

9

+#)

s INSTRUh'NTATION s

(

TABLE 4.3-5 d

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' CHANNEL CHANNEL INSTRUMENT CllECK CALIBRATION 1.

WIND SPEED a.

Nominal Elev. 10 meters D

SA 2.

WIND DIRECTION a.

Nominal Elev 10 meters D

SA 3.

AIR TEMPERATI)RE - DELTA T a.

No n Elev. 61-10 meters D

SA (El vation shown is in relation to ground level at eorological tower.)

(

L SUMMER - UNIT 1 3/4 3-52 po

51981

^ ' * ~ ~ ~ ~ ~ ' ~ * ~

INSTRUMENTATION I

TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION-SURVE.LLANCE REQUIREMENTS l

INSTRUMENT gjANNEL CHECK CHANNEL CALIBRATION 1.

Wind Speed a.

Wind Speed Lower (10m)

D SA b.

Wind Speed Upper (61m)

D SA c.

Backup Wind Speed (10m)*

D SA 2.

Wind Direction a.

Wind Direction Lower (10m)

D SA b.

Wind Direction Upper (61m)

D SA c.

Backup Wind Direction (10m)*

D SA 3.

Atmospheric Stability a.

Celta T 1

-(10-61m)

D SA b.

Delta T 2 (10-40m)

D SA c.

Backup Wind Direction Sigma (10m)*D SA J

Elevations given are nominal

$8ackup'.Metcarological System is anticipated to be operational by April,1982 pending equipment availability.

3/4 3-0 k

% -j 4

4

INSTRUMENTATION RADI0ACTIVELIOUIDEFFLUENTMONITORINGINSTRUMENTATION LIMITING CONDITION FOR OPERATION f "lY l

3.3.3.8 The radioactive liquid effluent.onitoring instrumentation channels shown in Table 3.3-12 thall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm /

trip setpoints of these channels shall be determined in accordance with t'1e OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all timis.

ACTION:

With a radioactive liquid effluent monitoring instrumentation channel a.

alarm / trip setpoint less conservative,than required by the abov_e_.

specification, immediately suspend the release of radioactive liquid effluents monitored by the affected ch' nnel or declare the channel a

inoperable, b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

^

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

1 SURVEILLANCE REOUIREMENTS 4.3.3.8 Each radioactive liquid effluent :ionito' ring instrumentation channel shall ba demonstrated OPERABLE by performance of the CMANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

(

/> 7 SU*4ER - UNIT 1 3/4 3-6*I TF/' l'/

l C

D O

1 E

TABLE 3.3 g 9

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION C5 MINIMUM CHANNELS I

INSTRUMENT OPERABLE ACTION l.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARil AND AUTOMATIC TERMINATION OF PELEASE Liquid Radwaste Effluent Line - RM-L5 or RM-L7 1

X31 a.

b.

Steam Generator Blowdown Effluent Line 1.

Unprocessed during Power Operation - RM-LIO or RM-L3 1

32 l

2.

Unprocessed during Startup - RM-L3 1

32 j

R.

3.

Processed - RM-L7 or-RM-Lcf 1

X32

-o Y

c.

Turbine Room Sumo Effluent Line - RM-L8 1

33 d.

Cw4ensate-Deeinbralizer Ef flucat Line---RM-L(?)

1 31 2.

FLOW RATE MEASUREMENT DEVICES r T&** I Liquid Radwaste Effluent Line Q g *4 1/6k 34 a.

b.

Penstocks Minimum Flow Interlock 1

34 c.

Steam Generator Blowdown Effluent Line 1.

Unprocessed during Power Operation ~

1 34 2.

Unprocessed during Startup 1

34 3.

Processed 1

34 c.

Ccadcasate Oc:::ineralizer Ef44ucat Line 1

34

-3.

TAN", LEVEL INDICATING OEVICES 7's' m

St

-ar-Gendensate-Storage-Tank-tij 35

INSTRUMENTATION

(

TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 31 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided t' tt prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and b.

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

ACTION 32 -

WiththenumberofchannelsOP5RAB'LElessthanrequiredbythe Minimum Channels OPERABLE requirement, effluent releases via this pathway.may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ gram:

a.

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

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equ.11 to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.

ACTION 33 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ml.

ACTION 34 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least cnce per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump curves 4may be used to estimate flow.

w/ for-fuk leve/ ind6fio n AeT-ION 35 -

With the number-of-channah OPERABLE 4ess-than-required by the -

Minimum-Channels-OPERABLE requirement, liquid addition = Lv thi=

-tank may continue for up-to-30-days-provided the tank licuid level isr-estimated-during-aM-14 quid-addi-tions-to-the-tank te

(

prevent-overflow O

SUMMER - UNIT 1 3/4 3-69

,.? : 5 1981

INSTRUMENTATION

(

TABLE 3.3-12 (Continued) e.

TABLE NOTATION (CTI0ft-36~

Witti-the nt&c-of-channels 4)PERABLE-less-than-required-by-the-,

N Minimum Channels OPERABLE requirement, effluent releases mayf continue for up to 14 days provided Liquid Waste Effluent f Monitor RM-L9 is OPERABLE or prior to initiating a release:

At least two independent samples are ang) in a.

accordance with Specification 4.11.1.1(3, and

'b At least two technically qualif e mbers of the s

\\facilitystaffindependently,veifythereleaserate ca.lculations and dischar line valving.

Otherwise,s\\

uspend release of ra ioactive effluents via this pathway.

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE'rgquire~ ment, effluent releases via this pathway may,co'ntinue foNi Waste Effluent Monitor RM-L9 is'p to 30 days provided Liquid 0PERABLE or grab samples are analyzed foy gross radioactivity (beta or gamma) at a limit of detectio 'of at leart 10 7 microcuries/gm:

b At~ least once t. r 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when th(specific activity a.

of the secondary coolant is greate than 0.01 microcuries/gm DOSE EQUIVALENT I-131.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specif (gravity of the secondary coolant is less than or equaq

/

0 Al-microcuries/ga-DOSE-EQUIVALENT--I-431-

\\

L.

SEP 151981 SUMMER - UNIT 1 3/4 3-70 w

e e n

I"'

O.

D TABLE 4.3-8 42 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS C$

ANALOG CHANNEL CilANNEL SOURCE CllANNEL OPERATIONAL INSTRUMENT CilECK CllECK CALIBRATION TESI 1.

GROSS BETA OR GAfMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE i

a. Liquid Radwaste Effluents Line - n.M-LS, RM-L9 D P

R(3)

Q(1)

b. Steam Generator Blowdown Effluent Line -

D M

R(3)

Q(1)

RM-L3, RM-L7, RM-L10 t'

c. Turbine Room (Floor Grains) Sump Effluent Line - RM-L8 0

M R(3)

Q(1)

T d

&-Condensate-DemineraMzer 9

P R(4)

Q(1)

Eff-luentene - Rei Ef?}--

i 2.

FLOW RATE MEASUREMENT DEVICES

%g ei

a. Liquid Radwaste Effluent Line - [fa" A #2-D(4)

N.A.

R Q

4 RM-LS, l"i L0

b. Steam Generator Blowdown D(4)

N.A.

R Q

Ef fluent Line - RM-L3, RM-L7, RM-L10 l

c. Penstocks Minimum Flow Interiock D(4)

N.A.

R Q

h

-4. - Cendensate-Demineral4zer-Ef-fluent-Line 9(4)

N,A.

R Q

3.

TANK-1.EVEL--INDICAT4HG-DEVICE 4 l

ci,

~

a,-Condensate-Storage-Tanks D*

N.A.

R Q

)

i

INSTRUMENTATION

(

TABLE 4.3-8 (Continued)

TABLE NOTATION During liquid--addi-tions-to-the tank (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if ary of the following conditions exists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

SelecM

2. A Circuit failures e ( alarm on / )

3 3.

Instrument indicates a downscal failure. C Alem 0*1/ )

3 4.

Instrument controls not set in operate mode.

(2) - The-ANALOG-CHANNEL-OPERATIONAL-TESV-shah-also i.T.ca trate that cor.trel-

=rece alara-annunciation-occurs-if-any-of-the-foHowing-conditions existse

-h-Instrument-indicates-measured-levels-above the alarmsetpointr-2.

Circuit-failu e J.-

Instru.*nt-inoicates-a-h nscale ta!!=e_

4.

Instrument-controis-not-set-in-eperate mcder-(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range.

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

(4) CHANNEL CHECK shall consists of verifying indication of flow during periods of release.

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

& safedec( cwed Lalues ane: O) ku-,L da{ea%- swf v, thy G-) Laz.,f. p wer b mpleher-(

(-D Lost-o1. ocJpd g, npJ,-kn SEP 151981 SUMMER - UNIT 1 3/4 3-72

-o

~ _

r D

D E

TABLE 3.3-13 E9 RADI0 ACTIVE GASE0US EFFLUENT M0HITORI,'IG INSTRUMENTATION t

C 55 MINIMUM CilANNELS j

INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

GASE0US WASTE PROCESSING SYSTEM a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1

38

- RM-A10 oY RA/'- R 3 i

2.

WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS HONITORING SYSTEM a.

Oxygen Monitor /Recombiner 2/recombiner 44 s

l b.

llydrogen Monitor /Recombiner 1/recombiner 42 ih 3.

REACTOR BUILDING PURGE SYSTEM a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of 1

41 Release - RM-A4 b.

Iodine Sampler 1

43 1

,1 e-a W

CD

i INSTRUMENTATION

(

TABLE 3.3-13 (Continued)

TABIE NOTATION At all times during releases via this pathway.

- During waste gas holdup system operation (treatment for primary system offgases).

ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requiremer.t the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

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

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

ACTION 39 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 40 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 41 -

With the number of channels OPERABLE less than required by the

, Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 42 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiners.

ACTION 43 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2. y WiththenumberofchannelsOPERABLf$nelessthanrequiredby ACTION 44 -

the Minimum Channels OPERABLE [i+ days provided one hydrogen requirement, operation of this system may continue for up to analyzer upstream and one hydrogen analyzer downstream are OPERABLE or grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at the location of the inoperable hydrogen analyzer. Wi-th-both-the-channels-inoperatrie, be in at least-(

440T-STANDBY-within-6-hcurs. Supeed use of /4 a reco.* Mice vd ing /m fe achon o-f See} ton 3. II.1 9 gg,,5 399; SUMMER - UNIT 1 3/4 3-76 y

l ll C

D D

E TABLE 4.3-9 (Continued)

Ig RADIDACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS b

ANALOG CllANNEL MODES IN WillCil CHANNEL SOURCE CilANNEL OPERATIONAL SURVEILLANCE P

INSTRUMENT CllECK CllECK CALIBRATION TEST REQUIRED 3.

REACTOR BUILDING PURGE SYSTEM i

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release - RM-A4 D

/M R(3)

Q(1) i

b. Iodine Sampler W

N.A.

i

c. Particulate Sampler W

N.A.

U

d. Flow Rate Measuring Device D

N.A.

R Q

y g

e. Sampler Flow Rate Monitor

'D N.A.

R Q

4.

MAIN PLANT VENT. EXHAUST SYSTEM l

I

a. Noble Gas Activity Monitor -

D M

R(3)

Q(R) i RM-A3

b. Iodine Sampler W

N.A.

4 I

c. Particulate Ser.ipler W

N.A.

1

d. Flow Rate Measuring Device D

N.A.

R R

e. Sampler Flow Rate Monitor D

N.A.

R R

l l

INSTRUMENTATION i

TABLE 2.3-9 (Continued)

ABLE NOTATION At all times.

During waste gas holdup systen operation (treatment for primary system offgases).

(1) The ANALOG HANNEL OPERATIOML TEST shall also demonstrate that automatic isolation cf this pathtray an: centrol room alarm annunciation occurs if any of the following conditi:ns exists:

1.

I stroent indicates musured levels above the' alarm / trip setpoint.

2.

1rcui-failures D /e m M/)

J 3.

Instr =ent indicates a :csnscale failurey Calor on/h 4.

Instr =ent controls no. set in operate mode.

fE)-The-ANALOG ::'ANNEt--OPERATIOVL-TEST-shai-1-also-demonstrate-that-control-

-room-alarm-ennunciat-ion-ocem-if-any-of-the-foHowing-conditions exists; 1.

In s trt-se nt-i nd i c a te s-metsured-leve ls-above-the-elarm-setpoint.

2.

Circuit-f a+1ers.

(

'3.

Ins t r=e n t-i nd ic a tese.cw n s eele-fM4e rer--

-4.

Instrunent-controis-not-set-in-oper-ate "Me-(3) The initial CHANNEL CALIBRAT:0N shall be performed using one or more of the referen e standards cer 'fied by the National Bureau of Standards or using stancards that have ben obtained from suppliers that participate in measurement assurance act'vities with NBS. These standards shall permit cali: rating the systen over its intended range of energy and measurement range.

For subuquent CHANNEL CALIBRATION, sources that have been relatec to the initial :alibration shall be used.

(4) The CHANNEL CALIBRATION shar include the use of standard gas samples containing a nominal:

1.

One vc'ume percent hydr: gen, balance nitrogen, for the outlet hydrogen monitor and 2.

Four.clume percent hyc ogen, balance nitrogen for the inlet hydrogen monitor.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One vo'ume percent oxygen, balance nitrogen, for the outlet oxygen moniter and 2.

Four velume percent oxy;en, balance nitrogen for the inlet oxygen L

monitc.

SUMMER - UNIT 1 3/4 3-79 151E

& SeleJ J c, mil fa:lu.e r --a, o> t,.u. 4. deluhL suseb volkse a) Las-,f-paws. A a-//tfru (3) 1,a gf. o[- Omhee l [W dm4 f f'P'

i TABLE 4.11-1

(

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (pCi/ml)"

A. Batch Waste-P P

_7 Release Each Batch Each Batch Principa} Gamma f,x10 d

Tanks Emitters 1.

Waste

-6 Monitor I-131 lx10 Tanks P

M Dissolved and One Batch /M Entrained Gases 1x10 5

+-Condensete-(Gamma emitters)

-Deminere+-

izer-Backwash P

M H-3 b

heeivmty Each Batch Composite 1x10 5

~7 Tank-Gross Alpha lx10

-6 P-32 lx10

-8 P

Q Sr-89, Sr-90 5x10 b

Each Batch Composite

-6 Fe-55 1x10

~7 B. Continuous

D W

Principa 5x10 Emitters} Gamma c

c Releases Grab Sample Composite

-6 I-131 lx10

1. Steam Generator M

M Dissolved and

-5 Blowdown Grab Sample Entrained Gases 1x10 (Gamma Emitters)

2. Turbine Builging D

M.

H-3 c

c 1x10-5 Sump Grab Sample Composite

3. Se

~7 Gr ss Alpha lx10 at Effluent

-6 P-32 lx10

-8 D

Q Sr-89, Sr-90 5x10 c

c Grab Sample Composite

-6 Fe-55 1x10 h.

SUMMER - UNIT 1 3/4 11-2 e

.-w e

n

~ -

,--w,.

-w-m-

a..

w-,-

m

--e--

n

.-m.,-,

-r,

-RADI0 ACTIVE-EFFLUENTS-

'0'

)

5ETTLING-PCNo -

-blHIT-ING' CONDITION FORlPERATION

~

Ar11r14-TheysantitMf ridioactiveMAriaho'ntAineU-in-each-settling pend '

~~

~

shall be limited by the follcwing expression:

f

< 1. 0 excludin \\ yit am and dissolved or entrained noble gases, where, tN A

\\

j = ')ond inventory limit for single radier.uclide "j h curie.

Cj = 10 CFR 20, ppendix B, Table II, column 2, concentration for single radionuclide

, microcuries/ml.

V = design volume of 1iquid and slurry Jn pond, in gallons.

i s

264 = Conversion unit, microcuries/ curie er milliliter / gallon.

APPLICABILITY: At all times.

ACTION:

~1

)

a.

With the quantity of rpdioactive material in the settling pond exceeding the above }imit, immedia'tely suspend all additions of radicactive materi f to the pond and'within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the pond contentstowith)fthe limit.

b.

The provisions of specifications 3.0.3 andN3.0.4 are not applicable.

/

SURVEILLANCE REQUIREMENTS N

4.11.1.5 The/duantityofradioactivematerialcontainedineachbatchofslurry (used powdex' resin) to be transferred to the settling ponds sha R be determined to be within the above lirait by analyzing a representative sampleNf the slurryf/and batches to be transferred to the settling ponds shall beslimited by t!)e expression:

h<6.0x105 pCi/cm I

C) pCi7ml

)

SUMMER - UNIT 1 3/4 11-8 r;0V 191950

~

elek

-RADI0 ACTIVE-EFFLUENTS-i l-

.\\

SURV6TttAN_CE REQUIREMENTS (Continued)

M

---.----m.._,._.n.,_.

9 = concentration of radioac fv tefials in wet, drained slurry (used j

powdex resin) for radionuel "j" excluding tritium, dissolved or entrained noble gas-an'd radionuclides'wi.th greater than 8 day half-life. The analfs'is shall include at leasT Ca,1'44, Cs-134, Cs-13,,

1 Sr-89,Sr-90, Co-58 and Co-60 in picocuries/ gram.

= 10 CFR 20, Appendix B, Table II column 2 concentration for sin 1 rad i onuc l i de -." j ", _i n - ai crocur.i es/mi ll iliter-I n

=

i

.;~

s I

SUMER - UNIT 1 3/4 11-9 NG'l19 BBQ

l l

RADIOACTIVE EFFLUENTS b-pG/6 w

/

BASES 3/4 lbb5-SETTEING-POMOS-(Continued)

C. = 10 CFR 20, Appendix 8, Table II, Column 2, concentration for sin 1 N adionuclide "j", in microcuries/ milliliter.

For the desisq of filter /demineralizers using pcwder resji ;'ihe slurry wash volume and the weight 9f resin used per batch is fixed by)t 100 milliliters / gram of he cell surface area and the slurry volume thesin weight ratio is constapt'a wet, drained resin with a molsture content of approxTmately 55 to 60% (bulk density of about 58 pounds per clibic feet). T erefore, C) 10 1/gm)(106 'pci/pCi) < 0.006, and

< 6#1 pCi/cm I-j 7

pCi/ml Where the ter:ns'are defined in Specification 4.11.1.5.

JA h limits provide assurance that activity input to the SP will e pmitationimized, and a means of identifying radioactive material in the inventory af Spec 4 H eatica 3 IL L 5.

L.- '

3/a.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specificaticn is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the lis.its specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to conpensate for any increase in the

" atmospheric diffusion factor above that for che site 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 site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 2000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /

year for the nearest cow to the plant.

NOV 191980 k)

SUMMER - UNIT 1 B 3/4 11-3 e

n.

- es. e m,

.

egne =

m -

a

+

y e

C O

O 1BLE 4.Il-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM E

I

~

Minimum Lower Limit of 9

Sampling Analysis Type of Detection (glD)

Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)

~

c-P P

-4 22i A.

Waste Gas Storage Ecch Tank Each Tank Principal Gamma Emitters 9 lx10 Tank Crab Sample P

P B.

Reactor Building 36 Each Purge,c Each Purgt.M,c Principal Gamma Emitters 9 lx10-4 Purge hine Grab

-6 Sample 11-3 1x10 K

-4 C. /. Main Plant Vent M'

M Principal Gamma Emitters 9 lx10 Grab Sample

& /el A Je L.'ne

2. S t

ce

-6 W

W 11-3 1x10 Grab Sample I

d

-12 D.

Iodine and Parti-Continuous W

I-131 lx10 M

culate Sampler Charcoal

-10 4

Sample I-133 lx10

1. Reactor Building Continuous #

W Principal Gamma Emitters d

9 lx10~II Purge Sampler Particulate (I-131,Others)

Sample

2. Main Plant Vent f

_jj Sampler Composite Particulate Sample E. Noble-Gases,-All ContinuousLNoble-Gas Noble-Gases 1x10-6

---Release-Types-as Monitor Gross-Beta-&-Gamme y,q

_li sted-in-A r-Brand-

-C-abovs

'" Was te-Gas-Storage-Tank-

@ Condenser-Vaccuum-Exh= t 3--Auxiliary-Cailding-Exhaust-4 -Fuel-Handling-Bui-lding-Exhaust-

TABLE 4.11-2 (Continued) w X

o TABLE NOTATION

?,nalyses-shal4-also-be: performed-foMowing-shutdse. sta$ tup, er a

-b.

THERMAt. POWER-change-exceeding-15 percent-of-the-RATE 0-T"ER"AL POWER --

within-a-one-hour peried.

c.

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

d.

Samples shall be changed at least once per 7 days and analyses shall be ccepleted within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal frem sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be ccmpleted 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 LLD's may be increased by a factor of 10.

e.

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.

f.

The ratio of the sample ficw rate to the sampled stream flow rate shall be known for the time period covered by cach dose or dose rate

s calculation m.2de in accordance with Specifications 3.11.2.1, 3.11.2.2 g

j and 3.11.2.3.

g.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, 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 detected and reported. Other peaks which are measureable'and identifiable, together with the above nuclides, shall also be identified and reported.

3 E

-v SUMMER - UNIT 1 3/4 11-13 P.0V 191980

+-em.

. ee a

p.,,

w-o

=

ww -

g

- + -.

s

,n

g RADICACTIVE EFFLUENTS L9 GAS STORAGE TANKS

g

...,,~,m..-.

.e__em.

LIMITING CONDITION F')R OPERATION - ~

~

~ ~ ~ ~ "

~ ~"

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

90 000

/

APPLICA8ILITY: 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents.to within tha limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS

~,6 4.ll.2.6.fThe quantity of radioactive material contained in each gas storage

-f tank shall be. determined to be within the above limit at least once per '/ dy r when radioactive materials are being added to the tank, Jenny f4e p,.,yj,, y

9. //. 2. s. 2 r,

m e y e.,.f of c../,,,/,,,,j,,, g,/ j;;/q,,, g>fgy den.w/ conlae, ed i, eac4 wasla tha q un/.f of yaJ.* aJ.'"e

~

Se k.,lc s he // he de fe,- m ia, a c{

f, fa u,.jf..n gas :/A ile. above h,;-/ J

/eas f cace paa 19 fns iof e n l'adioaeh'se mJe,.,a /s han g c,,,

,gj,,

g g y,,

l k,g4p3, 0

.fe s*s' eq 2

?

,e NOV 191950 SumER - UNIT 1 3/4 11-18 w e.m o

sea e

emmee 4

= en as eso e

. eum. **" e M

8*F*

y

C Table 3.12.1 (continued) h s

9 Sample Locations E

Exposure Pathway Criteria for Selection of Sampling and Loca-(1)

Type and Fregt. enc; Z

and/or Sample Sample Number and location Collection Frequency tion MI/Dir of Analysis H

AIRBORNE, (continued)

III. Direct A 5 Indicator samples to Monthly exchange.(5)

's 2, 5, 6, 10, Gamma dose monthly (5) be taken at the loca-Two or more dosi-and 14 tions as given in I.A.

meters at each through D above.

location.

B 3 Additional indic'ator 1

1.3 S samples to be taken in 4

1. 2 -NW-WN W sectors different from 8

1.3 ENE III.A above, beyond R

but as close to the exclusion boundary as y

practicable.

C Control samples t'o be 16 28.0 W 1

~

taken at the locations 17 24.7 SE as given at I.D above.

D. 1 Additional control 18 16.5 S sample to be taken at a location as set forth in I.D above.

1 E. Additional Sites 3

.8 WSW 7

1.7 E 9

2.6 NE 11 3.6 NNE m

12 4.3 N 13 2.9 NNW 15 2.3 SSW m

19 17.9 fSE-S S W g

20 22.0 NW q

4

_ _ _ _ _ _ _ _ _ = - - _ _ _ _ _ _ _ _ _ _ _

P O

O Table 3.12.1 (contin;.ad)

E I

m" Sample locations E

Exposure Pathway Criteria for Selection of Sampling and Loca{y)

Type and frequency Z

and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir of Analysis e

AIRBORNE,(continued)

F AccidentEvaluatiop7)

Quarterly ex-41 3.7 5 Gamma dose quarterly.

Quarl.erly Exchange change.(5) Two or 42 3.6 SSW i

Program more dosimeters at 43 4.7 SW

{

each location.

44 2.3 WSW 45 5.4 WSW 46 3.7 WNW 47 1.0 NW 48

2. 4 f,W w

49 4.6 NNW

)

50

5. 6 N i

g 51 5.6 N 7

52 4.3 NNE 53 3.6 NE 54 2.2 ENE 55 3.2 E 56 2.0 ESE 57 2.7 SE 58 2.4 SSE 59 2.1 SSE 60 5.7 WSW WATERBORNE IV.

Surface A el Indicator sample to Time composite 21(3)(6) 2.7 SSE Gamma isotopic with Water be taken at a location samples with col-quarterly composite by which allows for mixing lection every month location) to be ana-w and dilution in the (corresponds to USGS lyzed for tritium.(7) ultimate receiving continuous sampling w

river.-

site).(5) at co 1

c Rx;IOLOGICAL ENVIRONMENTAL MONI*C9ING

.73

/

3/a.12.2 LAND USE CEN M LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than E00 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For c?cvated

-releases-as-def-ined-in-Regulatory -Guide-bl44 -RevisioWuly-1977, the land 1

--usa-census sha!1 aise identify +he 1 d tinne af all ~ 411< = aim =1e

=ad

=11

-gar 4ns-of-greater then 500 squers feet producing-hesh-leafy veget210:

each-of-the-16-meteorological secters withia e di-stance-of-three ilee. )-

APPLICA8ILITY: At all times.

ACTION:

a.

With a 1.and use census identifying a location (s) which yields a calculated dose or dose commitment, greater than the values currently beirng calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.9.1., prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s).

b.

With a land use census identifying a location (s) which yields a

(

-~'sI calculated dose or dose commitment (via the same exposure pathway)

(st 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which tnis land use census was conducted.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are'not applicable.

. SURVEILLANCE REOUIREMENTS l

4.12.2 The land use census shall be conducted at least once per 12 months

~

between the dates of (June 1 and October 1) using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

" Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census, e

T

(- 2 #

goy 191350 SUMMER - UNIT 1 3/4 12-17

. +. -

+

ML20031F752

Text

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