Text

Drafts ETS for Radiological Effluents
	ML19305D721
Person / Time
Site:	Farley
Issue date:	04/07/1980
From:	; ALABAMA POWER CO.
To:	;
Shared Package
ML19305D719	List: ML19305D718; ML19305D721;
References
	NUDOCS 8004150452
	Download: ML19305D721 (84)
	v • d • e

_ ----

S JOSEPH M. FARLEY NUCLEAR PLANT Radiological Effleunt Technical Soecifications 9

)

.4 i

l l l .

h a

le l5 I

I 8 0 0 415 0 %F e

l

. t -

INDEX DEFINITIONS .

SECTION' PAGE 1.0 DEFINITIONS (Continued)

Scurce Check....................................................... 1-6 .

Process Control Program (PCP)...................................... 1-6 Solidification.....................................................

1-6 0ffsite Dose Calculation Manual.(0DCM)............................. 1-6 Gaseous Radwaste Treatment System.................................. 1-6 Ventilation Exhaust Treatment System............................... 1-6 Purge-Purging...................................................... 1-6 Venting............................................................ 1-7 l FARLEY-UNIT 1 Ia Amendment No.

I

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION P, age 3/4'.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R........................... 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.................... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATI0.............................. 3/4 2-11 3/4.2.5 DNB PARAMETERS........'.................................

3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................... '3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM............. 3/4 3-14 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring................................... 3/4 3-35 Movable Incore Detectors............................. . 3/4 3-39 Seismic Instrumentation................................ 3/4 3-40 Meteorological Instrumentation......................... 3/4 3-43 Gemote Shutdown Instrumentation........................ 3/4 3-46' Chlorine Detection Systems............................. 3/4 3-49 High Energy Line Break Isolation Sensors. . . . . . . . . . . . . . . 3/4 3-50 Post Accident Instrumentation.......................... 3/4 3-53 Fire Detection Instrumentation......................... 3/4 3-56 Radioactive Liquid Effluent Monitoring................. 3/4 3-58 Radioactive Gaseous Ef fl uent Monitoring. . . . . . . . . . . . . . . . 3/4 3-63 l

l l -

FARLEY-UNIT 1 IV Amendment No. 4,

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4'.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS Normal Operation....................................... 3/4 4-1 3/4.4.2 SAFETY VALVES - SHUTD0,WN............................... 3/4 4-4 3/4.4.3 SAFETY VALVES - 0PERATING.............................. 3/4 4-5 3/4.4.4 PRESSURIZER............................................ 3/4 4-6 3/4.4.5 STEAM GENERATORS....................................... 3/4 4-7 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............................. 3/4 4-14 Ope rati onal Leakage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-16 3/4.4.7 CHEMISTRY.............................................. 3/4 4-18 3/4.4.8 SPECIFIC ACTIVITY...................................... 3/4 4-21 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System................................. 3/4 4-25 P re s s u ri ze r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-29 Overpressure Protection Systems........................ 3/4 4-32 3/4.4.10 STRUCTURAL INTEGRITY................................... 3/4 4-32 1

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS........................................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg >,350*F......................... 3/4 5-3 3/4.5.3 ECCS CUBSYSTEMS - T,yg < 350 F......................... 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank................................... 3/4 5-8 Heat Tracing........................................... 3/4 5-9 3/4.5.5 REFUELING WATER STORAGE TANK........................... 3/4 5-10 i

FARLEY-UNIT 1 V Amendment No. 13, l

~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE i

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11,1 LIQUID EFFLUENTS Concentration............................................ 3/4 11-1 Dose.................:................................... 3/4 11-5 Li qui d Was te Trea tment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-6 Liquid Holdup Tanks...................................... 3/4 11-7 3/4 11.2 GASE0US EFFLUENTS Dose Rate................................................ 3/4 11-8 Dose-Noble Gases......................................... 3/4 11-12 ,

Dose-Radioiodines, Particulate, and Radionuclides Other than Noble Gases................... 3/4 11-13 Gaseous Waste Treatment.................................. 3/4 11-14 Explosive Gas Mixture.................................... 3/4 11-15 i Gas Storage Tanks........................................ 3/4 11-16 l

3/4 11.3 SOLID RADIOACTIVE WASTE.................................. 3/4 11-17 !

3/4 11.4 TOTAL 00SE............................................... 3/4 11-19 I 3/4.12 RADIOLOGICAL ENVIRONMENTAL 110NITORING 3/4.12.1 MONITORING PR0 GRAM...................................... 3/4 12-1 c

3/4.12.2 LAND USE CENSUS......................................... 3/4 12-10 3/4.12.3 INTERLABORATORY COMPARISON. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 12-11 i

r FARLEY-UNIT 1 IXa Amendment No. 1 1

l N

. .__ _ ]

,c 9

INDEX

~}" ,

BASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS........................................ B 3/4 ll-'l 3/4.11.2 GASEOUS EFFLUENTS....................................... B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE................................. B 3/4 11-5 3/4.11.4 TOTAL D0SE...........'..................................

. B 3/4 11-5 '

3/4.12 RADIOACTIVE ENVIRONMENTAL' MONITORING ,

3/4.12.1 MONITORING PR0 GRAM...................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS......................................... B 3/4 12-1 ,

3/4.12.3 INTERLABORATORY COMPARIS0N PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . B 3/4 12-1 L

FARLEY-UNIT 1 ,

XVa Amendment No.

1

INDEX l"I i ; !

DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area............................................... 5-1 -

Low Population Zone.......................................... 5-1 Site Boundary For Gaseous Ef fluents. . . . . . . . . . . . . . . . . . . . . . . . . . 5-l' Site Boundary For Liquid Effl uents. . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 CONTAINMENT Configuration.........................................,...... 5-1 Design Pressure and Temperature.............................. 5-4 5.3 REACTOR CORE Fuel Assemblies.............................................. 5-4 Control Rod Assemblies.................................... .. 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature............. ................ 5-4 Vo1ume....................................................... 5-5 .

5.5 METEOROLOGICAL TOWER LOCATI0N................................ 5-5 5.6 FUEL STORAGE Criticality................................................. 5-5 Drainage.................................................... 5-5 Capacity.................................................... 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT......................... 5-6

~

FARLEY-UNIT 1 XVI Amendment .lo.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 - RESPONSIBILITY.............................................. 6-1 6.2 ORGANIZATION 0ffsite..................................................... 6-1 Facility Staff.............,................................. 6-1 6.3 FACILITY STAFF 00ALIFICATIONS............................... 6-5 6.4 TRAINING.................................................... 6-5 -

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

Function.................................................. 6-5 Composition............................................... 6-5 Alternates................................................ 6-5 ;

Meeting Frequency......................................... 6-6 Quorum.................................................... 6-6 ,

Responsibilities.......................................... 6-6 A u t h o r i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 Records................................................... 6-7 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB)

Function.................................................. 6-8 Composition............................................... 6-8 Alternates................................................ 6-8 ;

i r

i

FARLEY-UNIT 1 XVII Amendment No.

Y

e6

j INDEX ADMINISTRATIVE CONTROLS -

SECTION PAGE C o n s u l ta n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-9 -

Meeting Frequency........................................... 6-9 Quorum..........................j........................... '6-9 6-9 Review......................................................

Audits...................................................... 6-10 Authority...................................................

6-11 Records...................................................., 6-11 6.5.3 TECHNICAL REVIEW AND CONTR0L.............................. 6-12 .

6.6 REPORTABLE OCCURRENCE ACTI0N................................ 6-13 !

i

6. 7 S A F ETY L IM I T VIO LAT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14 i

i 6.8 PROCEDURES.................................................. 6-14 i 6.9 REPORTING REQUIREMENTS f

i 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURENCES................. 6-15 l

6.9.2 SPECIAL REP 0RTS........................................... 6-21 1 6.'10 RECORD RETENTION........................................... 6-22 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-23

6.12 HIGH RADIATION AREA........................................ 6-23 r 6.13 PROCESS CONTROL PR0 GRAM'.................................... 6-24 i 6.14 0FFSITE DOSE CALCULATION MANL'AL. . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-24 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEM......................................... 6-25 FARLEY-UNIT 1 XVIII Amendment No.

.I

~

1.0 DEFINITIONS

. DRMT SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM (PCP) 1.28 The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from -

liquid systems is assured.

' SOLIDIFICATION ,

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

OFFSITE DOSE CALCULATION MANUAL (ODCM) gj7ggjgf gf 1.30 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and A parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of of gaseous and liquid effluent monitoring alarm / trip setpoints.

GASEOUS RA0 WASTE TREATMENT SYSTEM 1.31 A GASEQUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment,.

VENTILATION EXHAUST TREATMENT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and instal-led 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. Engi-neered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

PURGE - PURGING 1.33 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 sucn a manner that replacement air or gas is required to purify the confinement.

FARLEY-UNIT 1 1-6 Amendment No.

m

1.0 0FFINITIONS (Continued) l 1 VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or

'other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. '

7 t

i i

l 1

i l

l t

l I

P

i i

l FARLEY-UNIT 1 1-7 -Amendment No. l

I t

. TABLE 1.1 g ;

5 OPERATIONAL MODES -

REACTIVITY % RATED AVERAGE COOLANT MODE CONDITION, K,ff THERMAL POWER

TEMPERATURE

1. POWER OPERATION > 0.99 > 5% > 350*F ,

2. STARTUP > 0.99 1 5% > 350*F

3. HOT STANDBY < 0.99 0 > 350*F

4. HOT SHUTDOWN < 0.99 0 350*F > T

> 200*F avg .

5. COLD SHUTDOWN < 0.99 0 5 200*F

6. REFUELING ** < 0.95 0 5 140*F

^

Excluding decay heat.

- Reactor vessel head unbolted or removed and fuel in the vessel.

k I

FARLEY-UNIT 1 1-8 Amendment No.

L

TABLE 1.2 FREQUENCY NOTATION hf(

lii"di -

NOTATION FREQUENCY S 'At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days. .

M At least once per 31 days '

4 Q

At least once per 92 days.

SA . At least once per 184 days.

R .At least once per 18 months.

S/U Prior to each reactor startup.

, P Completed prior to each release.

N.A. Not applicable.

ii i

i i

i l

FARLEY-UNIT 1 1-9 Amendment No.

- o

INSTRUMENTATION RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION -

LIMITING CONDITION FOR OPERATION

~

3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall 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 the -

0FFSITE DOSE CALCULATION MANUAL (ODCM).

Whe n ere r f b t. discA*- t Va /V Cs * ~2.

APPLICABILITY-

- npt /oc,kt d e/os ed f ACTION:

a. With a radioactive liquid effluent. monitoring instrumentation channel . *'

alarm / trip setpoint less conservative 'than required by the abnve ;

specification, 'immediately suspend the release of radioactive liquid l effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum. number of radioactive liquid eff'luent i monitoring instrumentation channels OPERABLE, take the ACTION shown i

% in Table 3.3-13.

I d. The provisions of Specifications 3.0.3 and 3.0.4 are .ot applicable.

SURVEILLANCE REOUIREMENTS i

4.3.3.10 Each radioactive liquid effluent monitoring' instrumentation channel l shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

- CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the l frequencies shown in Table 4.3-13. l (c. With +ke nem6ee of lig e:d efflee st mon Norley is s+r" ~ e n +=Hel cha sn e ls CPERAbLC less th n f gn;' eAcane Isl oferable . r efu r ee rd of 7, b ), 3. 3 -13(g . ,Neu. gmE any . ;

oh er rejeer+ ret *i!*0 k Y . S ep si k e m f 'o n C,1,1, p r epe.re u d '

S seb,.;+ to M co ~ ~isst e w:tA n s o J,p . y , a,; l e+peet w A!c ( Ia e /ude.5 +4e fe //o winy ;n f o r ,J., w

/* T h e d;f: sed.'oe, o$ +he ;neperst h inf ra m e d W, l

'l ,Ashb M f ken h r es+n , e, f'La j a ,+ ,,, , .f g

l 6 ?E72&&LG s+a.fvs , a.~ L 3,5umm ry aescr,*p NW. 0 Y

A* I' \ Y' ' *' b '(

prevent o. reco r ra n c e , :

FARLEY-UNIT 1 3/4 3-58 Amendment No. i s.

1 -

TABLE 3.3-13 ,

I h! RADI0 ACTIVE LIQUID EFFLUEllT MONITORING INSTRUMENTATION G

f EE MINIMUM Cl CilANNELS

_. INSTRUMENT OPERABLE ACTION

1. GROSS RADI0 ACTIVITY MONITORS PROVIDING AUTOMATIC -

TERMINATION OF RELLASE -

a. Liquid Radwaste Effluent Line (RE-18) 1 28

b. Steam Generato. Blowdown Effluent Line (RE-238) 1 29

2. FLOW RATE MEASUREMENT DEVICES .

o. Liquid Radwaste Effluent Line .

1) Waste Monitor Tank No. 1 'T! 1000f,) 1 30 IIIII

2) Waste Monitor Tank No. 2 'f!-100;") 30 4:3 y> shl 1 M

b. Discharge Canal Oilution Line (FT-S7i)- 1 30 ""1*1 H

c. Steam Generator Blowdown Effluent Lines (FT-llS0)- 1 30 l( -

a 2

n 5

J - . - , , - , _ , - . , . - , - . , ~ , , . , . - _ - - _ __, ,, __

.i . .. . =-

'~

TABLE 3.3-13 (Continued)

TABLE NOTATION

' ACTION 28 - Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 5 days provided that prior to initiating ..

a release: So 5

c. If r cleas e ed . At least two independent samples are analyzed in accordance calc ulsRo n *r t with Specification 4.11.1.1.3, and g P ** e d ** a *"II/.

, b At least two technically qualified members of the Facility y ed he omputer input for release ledepedofly vedEt [ Staff independently rate calculations andverify the line valving; discharge by ~= ++c.4Mc*//y quahfici ec-4cr- Otherwise, suspend release of radioactive effluents via this

- e f -t A <-Fac.;// /y pathway.

5*sF#. !

ACTION 29 - 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 analyzed for gross radigpctivity. (beta or gamma) at :

a limit of detection of at least 10 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 equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.

e ,

ACTION 30 - 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 during ac'wal releases. Pump curves may be used to estimate flow.

i

. i

i i

I I i

l l

.ARLEY-UNIT 1 3/4 3-60 Amendment No.

. e TABLE 4.3-13 .

h3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS M

T CilANNEL EE

q CilANNEL SOURCE CHANNEL FUNCTIONAL

_, INSTRUMENT CllECK CllECK CALIBRATION TEST

1. GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents Line (RE-18) D P R(2) Q(1)

b. Steam Generator Blowdown Effluent Line (RE-238) D M .

.R(2) Q(1)

Ja 2. FLOW RATE MEASUREMENT DEVICES C ::l

Z y> a. Liquid Radwaste Effluent Line (-FT 1005A, l3=s fi 1005S) D(3) N.A. R N.A. =-t=1 c3 H

/hl b. Steam Generator Blowdown Effluent Line D(3) N.A. R N.A.

(-FI 1160)

c. Discharge Canal Dilution Line 'fT-571)- 0(3) N.A. R N.A.

!i

a R

8 e

O.

Ja *

' TABLE 4.3-13 (Centinued)

TABLE NOTATION (1) a. The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip

- setpoint.

2. Loss of control power.

3. Loss of instrument power.

b. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if'any of the following conditions exist:

1. Instrument controls not set in the operate mode.

2. Instrument indicates a downscale failure.

(2) The CHANNEL CALIBRATION shall be performed using cne or more solid or liquid radioactive sources which have been calibrated by a measurement system which is traceable to the National Bureau of Standards radiation measurement system. The : ;;=:c: :h;' pe..m.L c;iibr; ting th: cy:t=

c"r it: Stended ion 3m o f ca:rgy =d c;2u. m.. mat r:r.g:. 7 (3) CHANNEL CHECK shall consist of verifying indication of flow duri.ng 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.

1 FARLEY-UNIT 1 3/4 3-62 Amendment No.

l

\

~

l INSTRUMENTATION l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTP,UMENTATION ,

I LIMITING CONDITION FOR OPERATION i

3.3.3.11 The radioactive gaseous effluent monitoring instrumentatfori channel's shown in Table 3.3-14 shall be OPERABLE with their alarm / trip setpoints set to i ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip ;

setpoints of these channels shall be determined in accordance with the 00CM. i APPLICABILITY: As shown in Table 3.3-14. .

~

ACTION: . l I

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

b. With less than the minimum number of radioactive gaseous effluent .

monitoring instrumentation channels OPERABLE, take the ACTION'shown !

in Table 3.3-14.

l

~

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel ,

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTI0hAL TEST operations at the '

- frequencies shown in Table 4.3-14.

c., vi+t. ri,e nu s er .+ 5.s r-s c H im+ ~ "i% "N" ekann eh 0PERA&LE /ess % *. t b e "inie u~ cl=^"Is eter=4/e

\0 te r vir r a ad o+ M I.e 3, 3 -lY fw e v e r- 14 day s3

s her 6 f a.ay off e, ' r epe+ refstr ed by Q <ar.c c.,% C. 9. t, p repa.re

- d cubit h fh cweissin winis 30 d*ys < speM r 'l'& w%L :.e M n pa. FJ4 as:,.y h.Fe,dy; 4 IJex+;E::c..% & +ga ;aq.,,. 6/,;,,. g y .,'

's P 4 (s) hk e n A e eshe e f4 ; s t,._ ,s 4 OPEYt AALE ddas, ni

( 5-So -a.,y J e.sc ,,p w m of u hm /d /=4 % A p er yni e eeeun~-n.

l FARLEY-UNIT 1 3/4 3-63 Amendment No.

l 1

TABLE 3.3-14 -

A RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION r;

7 E MINIMUM CllANNELS Z INSTRUMENT OPERABLE APPLICABILITY ACTION

1. WASTE GAS Il0LDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM

a. Outlet Oxygen Monitor 1/;::=ti:::r **~ -40 DR Inlet flydro0en, Outlet flydrogen, ** -

b. 1 set /recombiner 40 Inlet Oxygen Monitors

2. STEAM JET AIR EJECTOR -

a. lioble Gas Activity Monitor (RE-15) 1 Modes 1, 2, 3, 4 37

~5 w 3. VENT llEADER SYSTEM g}[gg

^ *

a. Noble Gas Activity Monitor (RE-14/(RE-22) 1 Sfj 37

b. Iodine Sampler 1 41

c. Particulate Sampler 1 41

d. Flow Rate Monitor 1 36 8

8 c

5

.m -. - - w

.l

. . ;

i 1

TABLE 3.3-14 (Continue'd) .

TABLE NOTATION i!

At all times.

\

- During recombiner operation. -

3 ACTION 36 - 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 ,i o T y<

e e[d,f.*e aN ,ha}ypp*}4gg w

ge,]g 4,poyj % g1. <h3 p, f,,"o)"

W WiYh s ei fi,,. a s ti, . - /<a se l

ACTION 37 - t1e num er of channels OPERABLE $ss than /re& 2-yquired by the tijnimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samp.les are takert at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples ithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Nor,. I he*/d e,af are analyzed mefory con gross activity e o w*b M ; k ly .pv ves+ila.+in +1ne N 4 prst.

ACTION 38 - Not Applicable. say /f 3 o f- P C . paw w ** e M cA A nal t ed y % y v er.n a.s.

e iG e.+ /tsti~ .

. ACTION 39 - Not Applicable, one4. g a r- p 'i hoors, ACTION 40 - With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, g^-stf:.. ;f :.:s ,

f;. .p:.; M wog. . . .. . .,; tr. P s -- h j h.;;r:P:, 5 q :.-.... , ;... i..

'- st h .;t ::0T ST""*' itt.i..C{.;;r;.

ACTION 41 - With the number of channels OPERABLE less than required by the !

Minimum Channels OPERABLE requirement, effluent releases via f 2, i the affected pathway may continue fe. ;; t; :: een provided samples are continuously collected with auxiliary sampling '

equipment as required in Table 4.11-2. ,

I A ctia,1 [ ~ S=~e "' .

A' " O-e y e .ejt fci<- t-*sh y, is alak ts a yyy n s.w 4 k *

+-1 a_f+,e4 4 ceeo Aln < r . Wi+L. nan < c+ +Le l cla.an<Is ep .e'ra l, le , a. d 4.gn a F was A yas 7o t

& n., w a.sle p as

&sks no-y conhve prodded cu p.e a.G sex . pl e is tak

n from A es.

s e ry; e.e wask y<.s E* cay k k- a d n =I l 2 Y hour.yted

% & has+ s.

ogg en ont e per FARLEY-UNIT 1 3/4 3-65 Amendment No.

TABLE 4.3-14 h RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ii

?

E CilANNEL MODES IN WHICH Q CilANNEL SOURCE CIIANNEL FUNCTIONAL SURVEILLANCE

_ INSTRUMENT CllECK CllECK CALIBRATION TEST REQUIRED

1. WASTE GAS Il0LDUP aYSTEM EXPLOSIVE -

GAS MONITORING SYSTEM

a. Inlet flydrogen Monitor D N.A. Q(3) M **

b. Outlet flydrogen Monitor D N.A. Q(3) M **

c. Inlet Oxygen Monitor D N.A. Q(4) .

. M **

d. Outlet Oxygen Monitor D N.A. Q(4) M **

Y Cf3

.A ,

2. STEAM JET AIR EJECTOR

a. Noble Ga, Activity Monitor (RE-15) D M R(2)

- (lb Q%) 1,2,3,4

D 3d v3 H

3. VENI lifADI R SYS1FM

a. Noble Gas Activity Monitor (RE-14, "E 22) D M R(2) Q(1)

(ge-x4 b E R(x) t 3

b. Iodine Sampie. W N.A. N.A. p(A.)

N. h *

c. Particulate Sampler W N.A. N.A. N.A.

N ^

g d. Flow Rate Monitor D N.A. R Q

$Y '

8

<+

O l

A --

o

_ _ . . , .s.. . . . . _ . . . __

^

TABLE 4.3-14 (Continued)

BRAFT !

TABLE NOTATION t

At all times. THIS PAGE OPEN PENDING RECE!P !

Ouring recombiner operation.

INFORMATidN cROM THE APPUC: TNT (1) a. The CHANNEL FUNCTIONAL TEST shall demonstrate 'that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

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

> setpoint.

2. Loss of control power. )

. 3. Loss of instrument p.ower.

b. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists. ;

1. Instrument indicates a downstale failure. l l

2. Instrument controls not set in operate mode. ;

(2) The CHANNEL CALIBRATION shall be performed using one or more known solid !

or gaseous radioactive sources which have been calibrated b a measurement j system which is traceable to the National Bureau of Standards radiation -l measurement system. Tt=: ::xxx .; .oii y .-- i t 1 u. e in y $4.. op ..

on. :'. ....cuueu ...3 v.- ene. u oud ..m;; . ;xat rar;- 7 (3) The CHANNEL CALIBRATION shall include the use of standard gas samples c c - s t e : ~- -: ' =1. in ecor Jam wi+L fA< J,s % cat n a s o-La.3 fu e e eis 'ss fre e frons , 1

~

'. Cigav .vi . em. m..t :.yu.w3ca, bela..;; !!itr ;;r (inlit "yt c;=n

{

j

-~,4+,),

> 1cnn nnm Hvdrocen. hainnen Nitrngan f nn+1 c t ", d;;;;r cr i te--) , ;7,d

/V !

i l

t u n , . .. p.---t g.e.-~. , i,m;; ::::; _,, c._ , , _ , , , ,

j (4) The CHANNEL CALIBRATION shall include the use of standard gas samples cc-t 9 4-- ~o. ael . 16 acc erdae c e wi+ A 7 A c J ^-str u m e ^-1 m a n v%; < 4 e r e r 's 's s h we. % s .

i l t.L

.. (!..' . C v sen .un:.,.),

/

(2'_) : n p;. ..at O y ;s... 5:' ..a .::t.

2. 75 pp 0 j;:n. 5 ':nce **'-a-an (autlet o w - . ;...Lv o , ..J ---

3.'- ici .;; ic;rt $'d-c; 9, b:!:"re ""^ a" f * "' "'" ~# t: r 0 l

FAP. LEY-UNIT 1 3/4 3-67 Amendment No.

l 3/4.11 RADI0 ACTIVE EFFLUENTS **

3/4.11.1 LIOUID EFFLUENTS \. 213 CONCENTRATION ,

l LIMITING CONDITION FOR OPERATION i

-l 3.11.1.1 The concentration of radioactive material released from the site <

(see Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. Fordissolved.grentrainednoblegases,the concentration shall be limited to 2 x 10 microcuries/mi total activity.

APPLICABILITY: At all times. ,

ACTION:

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

s. Th1 t 3

- - **I**'

n'y foI c $

gester w;+x ;r f s e a bo g, f; ,;+3 !or .# es%,

~ * '

, ,. e ec ess - 63*****

e-

***tenf..

concen nWto #'**'I*

- "'"'" * # # !#"' * "*Ye.

to -SUkVNLLNCE IE JUI$EMEY[

~

I6 4.11.1.1.1 The radioactivity conten of each batch of radioactive liquid waste shall be determined p+- t . 2 a.a by sampling and analysis in accordince' with Table 4.11-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentiation at the point of release is maintained within the limits of Specification 3.11.1.1. ,

4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11-1. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Specification 3.11.1.1.

l 4.11.1.1.3 The radioactivity concentration of liquids discharged from l continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1. The results of the analyses shall be l used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of ;

Specification 3.11.1.1. -

l l

FARLEY-UNIT 1 3/4 11-1 Amendment No.

D

. i-noET t

, ~ ~

UM1 L TABLE 4.11-1.

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i

Minimum Minimum . Detectable Liquid Release Sampling Analysis Type of Activity Concentration, g Type Frequency Frequency Analysis (MDC)(pCi/ml) . ;

A. Batch Waste P P

~7 Release d Each Batch Each Batch Principa} Gamma 5x10 Tanks Emitters

-6

. I-131 1x10

~ -5 ,

P M Dissolved and 1x10 Entrained Gases j One. Batch /M '

(Gamma emitters)

P M H-3 . lx10 -5 ,

b Each Batch Composite

- Gross Alpha 1x10

-6 P-32 1x10

-8 P Q Sr-89, Sr-90 5x10

b Each Batch Composite

-6 l Fe-55 1x10 5x10

-7 B. Steam W Cec= # Ce .+~ i .,k PrincipaEmitters} Gamma , t GeneratopO Blowdown D ComfoS eh \-

,6 yg /c I-131 1x10 M M Dissolved and 1x10 ,

Grab Sample Entrained Gases l (Gamma Emitters)

-5 M H-3 1x10

-0 ..ti nnd Compositeh i

-7 D Gross Alpha 1x10 b"b I"h l P-32 1x10

-6

-8 O Q g Sr-89, Sr-90 5x10 l Gw Jnr# Composite -6 Fe-55 1x10 y g/e C. Turbine D W Princip1 9 amma G 5 x 10 ~7 b

l Builging Grab Sample Composite Emitters 1 x 10 -5 Sump l

- H-3 FARLEY-UNIT 1 3/4 11-2 Amendment No.

N

' e TABLE 4.11-1 (Continued) l TABLE NOTATION

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

For a particular measurement system (which may include radiochemical separation): 1 4.66 s b MDC =

E V 2.22 Y exp (-Mt)

Where:

MDC is the Minimum Detectable Concentration as defined above (as picocurie per unit mass or volume),

shis the standard deviation of the background counting rate or of tne 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 is the number of transformations per minute per picocurie, ;

Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the,particular radionuclide, and!

\

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

The value of sg used in the calculation of the MDC for a detection system shall bE based on the actual observed variance of the background ! ,

counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the MDC for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. \

Typical values of E, V, Y, and at shall be used in the calculation.

The background count rate is calculated from the background counts that are determined to be within + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

FARLEY-UNIT 1 3/4 11-3 Amendment No.

m m

.

TABLE 4.11-1 (Continued) ,

TABLE NOTATION L

b. A composite sample is one in which the quantit'y of liquid sampled is proportional to the quantity of liquid waste discharged and in which ,

the method of sampling employed results in a specimen which is representative of the liquids released.

c. To be representative the quantit and concentrations of radioactive m rials in li effl' ts, pies shall be collected continuously

)[ in p analyse ortio o the rate 1 samples n fo low of the effluent stream. Prior to the composite shall be throughly composite sample to be representative of the mixe no r for uent rele

d. A batch release is the discharge of liquid wastes of a discrete l vol ume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling. ;

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

f. The principal gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58,

'Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. '

Other peaks 'which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the MDC for the analyses shall be reported as "less

than" the nuclide's MDC and shall not be reported as being present at the MDC level for that nuclide. The "less than" values shall not be used in the required dose calculations. ,

. h ; hd M

- 'y: :d prhr '7 a " - '::x. l y , S nyky n d an.Jyz;s wlII b* P d5YI :

O lF th eH4ent w:ll be dd.su G Q 4 +4.

\

en viran 4 , i b i Qtviab fton f Le. AA D C rqutre~* ds of-fg/g

% II -I s hil be e apr+el p +r sp a.; g, S 9. l. i h /; e a.- e f- y 0 % ~,ouy, FARLEY-UNIT 1 3/4 11-4 Amendment No.

2

' ~ "

RADIDACTIVE EFFLUENTS

!1Q [.a i

(jilk I h DOSE

~

LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, 4 cent the site (see Figure 5.1-4) shall be limited: /97" ,

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

b. During any calendar year to less than or equal to 3 mrem to the

. total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by 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 cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commit- ;

ment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. .

b. The provi'sions of specifications 3.0.3 and 3.0.4 are not applicable. -

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents i shall be determined in accordance with the ODCM at least once per 31 days.

l l

FARLEY-UNIT 1 . 3/4 11-5 Amendment No.

RADI0 ACTIVE EFFLUENTS -

LIQUID WASTE TREATNENT THIS PAGE OPEN PENDING RECElPT O ORL. mil 6N iROM THE APPLICANT LIMITING CONDITION FOR OPERATION h a.v < m:t- o n e. O PETtA S t-E m e as af i

--- t e

dean +As les.s+4 e. ..cfru:ty s4 k e u ; 4 m s*f r te. fan 4aa, l 3.11.1.3 The liquid radwaste treatment system shan L-- Z. i ,_. : Ine appro- l priate portions of the system shall be used to reduce the radioactive materials ;

in liquid wastes prior to their discharge when the projected doses due to the i liquid effluent from the site (see Figure 5.1-4) when averaged over 21 __, ,'P4e * a-f would exceed 4,6 mrem to the total body or 6 mrem to any organ..ks- !'

0,1 % . 0.h (*R APPLICABILITY: At all times.

ACTION: ,

no optem.ble Me.ss of redu ci~p r'sh'arefisliy

a. With 'J.: ' q M c.i.. L t- r+-^a+ ey_e+== inan= " M for more than l

31 days or with radioactive liquid waste being discharged without .(

treatment and in excess of the above limits, in lieu of any other :

report required by S'pecification 6.9.1, prepare and submit to the !

Commission within 30 days pursuant to Specification 6.9.2 a Special ,

. Report which includes the following information: l

, 1. Identification of the inoperable equipment or subsystems and '

the reason for inoperability, Action (s) taken to restore the inoperable equipment to

2. ,

OPERABLE status, and 3

3. Summary description of action (s) taken to prevent a recurrence. !

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

SURVEILLANCE REOUIREMENTS ;

to unr es*frlcl* d W **-S i' 4.11.1.3.1 Doses due to liquid releaseshhall be projected at least once per 31 days, in accordance with the ODCM.

A + /e a s-/ ,, e. e e w s e 4

4.11.1.3.2 M 11guid radwaste treatment spahem shall be demonstrated OPERABLE l

- " - ^-

by operating the -"'" - '- ~ '

equipment for at least 1I ;

om ,, n.-- has been i i

minutes atprocess utilized to least once per 92 days radioactive liquid unless effluents the liq,..;

during . oy\he previous 92 days. '

I 2

g fv'fMee-f I t- fo-c. YF - VYY s W f G(~ I ,

FARLEY-UNIT 1 ,

3/4 T1-6 Amendment No.

0

~

.s RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDirION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

ESM tFJb 70 SaublFY

a. Outside temporary tank, excluding liners cent:f #ng ;clidified jfjd radioactive wastes.

APPLIC/.8ILITY: At all times.

ACTIrjN:

a. With the quantity of radioactive material in any of the above listed tanks 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 the limit.

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

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be deu mined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

FARLEY-UNIT 1 3/4 11-7 Amendment No.

t I

RADI0 ACTIVE EFFLUENTS

$5 3/4.11.2 GASEOUS EFFLUENTS lge ~

DOSE RATE .

LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose' rate due to radioactive materials released in gaseous effluents from the site (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem /yr to the total

=, body and less than or equal to 3000 mrem /yr to the skin, and

b. For all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY: At all times.

ACTION: ISI

=.With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). N'** *

g

a r e

~T' % . e r ir

Qcat s of 1.o.1 c snh1 a 4 se **f <et=,cukte v*~le o~e ~ ~ M i~ t u n e 4-; ss cinny^s *.x c~+r ^ ~

r,ecessq? ,'9t: ye :~;*,4 f^C" *sC SURfE LANCE REQUIREMENTS Mc re/csse. e a_Y d' ,

4.11. 2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance'with the methods and procedures of the ODCH.

4.11.2.1.2 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.

FARLEY-UNIT 1 3/4 11-8 Amendment Nc.

'l TABLE 4.11-2 -

A RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

.7, T

E Minimum l Minimum, Detectable M Sampling Analysis Type of Concentration, )

- Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)

P P Principal Gamma Emitters 9

-4 -

A. Vaste Gas Decay Each Tank Each Tank 1x10 Tank Grab Sample P P D b -4 Principal Gamma Emitters 9 lx10 -

B. Containment Purge Each Purge Each Purge Grab -6 Sample H-3 1x10 M ,c,e gb -4 Principal Gamma Emitters 9

. ~

C. Condenser Steam lx10

.le t Air Ejector, Grab Plant Vent Stack Sample 1x10

-6 11- 3 f d -12 I D. Plant Vent Stack, Continuous W I-131 1x10 7 Containment. Piirge Charcoal -IU O

Samp..le. _ -.1 .133 lx10 Z Continuous W Principal Gamma Emitters 9 1x10 Particulate (I-131, Others) q sample Continuous f

M Gross Alpha 1x10

~lI Composite Particulate Sample Continuous f

Q Sr-89, Sr-90 lx10'II Composite y Particulate

g Sample I

lx10

-6 a Continuous Noble Gas Noble Gases

" Monitor Gross Beta & Gamma

? -

wo,w- , - -

r , ~ ww e re

wat 8*

TABLE 4.11-2 (Continued)

TABLE NOTATION

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

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

4* 8 b

MOC =

E V 2.22 Y exp (-Aat)

Where:

MDC is the Minimum Detectable Concentration as defined above (as picocurie per unit mass or volume), ,

ssis the standard deviation of the background counting rate or of tMe 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 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

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

The value of ss used in the calculation of the MDC for a detection system shall b5 based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the MDC for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples.

Typical values of E, V, Y, and at shall be used in the calculation.

The background count rate is calculated from the background counts ,

that are determined to be within + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

FARLEY-UNIT 1 3/4 11-10 Amendment No.

e

I . a --

b 5 #F / l AC f,hUfT/00/AWll5lNAAy7mMi&W DA /s >o.

TABLE 4.11-2 (Continued)

TABLE NOTATION er [

y C ,. > ,s 2 e 7

7 , e e w t

b , or a h p. Analyses THERMAL POWER shall also be change exceeding within a one hour period.

performed 15 percent of RATED THERMALfollowing POWER shutdo :

gu ..

c. Tritium grab samples shall be takenht least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when Q the refuelino canal is flooded 5":Ltt "% ,p ,, f,,the]

E w : u :: m b w : = T 'o -

Samples snaii ce cnangeu at seast.onceper7daysfandanalysesshall

d.

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). Sampling and analyses shall also be performed at least l 3

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 shutdownfr., >td I #>

startup>or thermal power level change exceeding 15% of RATED THERMAL to > ls9, c.wer / POWER in one hour. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, ~

the corresponding MDC'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 i fuel is in the spent fuel pool.

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

- calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 l and 3.11.2.3. !

g. The principal gamma emitters for which the MDC specification applies >

exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, l Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, i Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for l particulate emissions. This list does not mean that only these !

nuclides are to be detected and reported. Other peaks which are l measureable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the l MDC for the analyses shall be reported as "less than" the nuclide's i MDC and shall not be reported as being present at the MDC level for ;

that nuclide. The "less than" values shall not be used in the i required dose calculations.

h o< a+, o n s Fr. n moc ecc n e s en+, a n s te 4.11- 2 si,all L, e e af, o,+ e J p . ,. sp e e;e,M e G. 9. t. 2 in her o+ ,

I a.n y oth e r~ r e js e rf, i l

FARLEY-UNIT 1 3/4 11-11 Amendment No.

l '

l

RADIOACTIVE EFFLUENTS y=q =

" DOSE - NOBLE GASES -" ** I b>

LIMITING CONDITION FOR OPERATION 3.11.'2.2 The air dose due to noble gases released in gaseous effluents, from eachreactorunit,f)f7'<mf the site (see Figure 5.1-3) shall be limited to the ;{g7 following: s

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

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

APPLICABILITY: At all times. -

ACTION I

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, 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 cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce t'e releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent thre~e calendar quarters, so that the cumulative dose during these four calendar quarters is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

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

SURVEILLANCE RE0VIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

FARLEY-UNIT 1 3/4 11-12 Amendment No.

RADI0 ACTIVE EFFLUENTS DOSE - RADI0I0 DINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND' RADIONUCLIDES -

OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines and radioactive materials in particulate form, and radionuclides (other than' noble gases) with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, JDunt the site (see Figure 5.1-3) shall be limited to the following:

47' jf[? a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

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

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radiciodines, radioact-ive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, 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 cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of c radiciodines and radioactive materials in particulate form, and radionuclides (other than nobles gases) with half-lives greater than 8 days in gaseous ef fluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from '

such releases during these four calendar quarters is within (15) mrem to any organ.

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

SURVEILLANCE RE0VIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance l with the ODCM at least once per 31 days.

l- ,

l i l

l l

l FARLEY-UNIT 1 ,

3/4 11-13 Amendment No.

l l

.-.9

RADI0 ACTIVE EFFLUENTS THIS PAGEOPEN PENDING RECEIPT OF

INFORMATiON ? ROM THE APPLICAHT GASEOUS RADWASTE TREATMENT

/ c oastdly 4 ..

ofw oae w Ae es c.-presso sA y =a 4 . ca.y A r :

l s#c-

-- LIMITING CONDITION FOR OPERATION

~

u se.>+ ene tee.s ee steeo. o f- w it.* e v 6 .; Id en 3.11.2.4 llE GASEGUS RA0 WASTE TREATMENT SYSTE and the ENTILATION EXHAUS ceasivih TREATMENT SYSTEMf shall Le OPERABLE. The appropriate portions of the GASEOUS

~

of +"* DWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in

",j .[ aseous waste prior to their discharge when the projected gaseous effluent air l ("4. , g oses due to,,pgoy effluen$,peleas gfrom the site (see Figure S.1-3), when veraged over ;. ajf,' T iu% exceed mrad for gamma radiation and 9-4

' MM;n or beta radiation. The appropriate portions of the VENTILATION EXHAUST ;,1 \ mrad

' g y 'T TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous E'(rp waste prior to their discharge wh'en the projected doses due to gaseous M

f.,.f,4 ef. fluent releases from the site (see Figure 5.1-3) when averaged over 31 d:7 would exceed %! Parem to any organ?)4- + M c O* d*"

ee

a. p m o,9 t u w + c r~

d+ APPLICABILITY: At all times.

9,ril'**) ,,1/,,. fis e Fs,el )%e t VEptn. prion Exn Aus7 gA av 5f ACTION: TB**maur m M - -

9.;/ fr* f * .o;I y bv;lha e ud f5* a. With the GASEOUS RADWAST TREATMENT SYSTEM and/or the% ENTILATION EXHAUST TREATNENT SYSTEM inoperable for more than 31 days or with L gaseous waste being ' discharged without treatment and in exce.is of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission withi- 30 days, pursuant to Specification 6.9.2, a Special Report whicn includes the folluwing information:

f 1. Identification of the inoperable equipment or subsystems and j g/ the reason for inoperability, i k 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence,

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

SURVEILLANCE REOUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.

At le st one -trea% e A ste esn oF p.,,;t.,y g ,,;Mt. , #

'"5 4.ll.2.4.2dTheGASEOUSRADWASTETREATMENTSYSTEMeMVENTILATIONEXHAUST) j

d f^e REATHENT SYSTEMsshall be demonstrated OPERASLE by operating theVGASEQUS str e- o f feel poo l RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM jequipment for at least II minutes, at least once per 92 days unless the appro-e#

7tSW ast# priate system has been EEilized to process radioactive gaseous effluents sy# ,during the previous 92 days.

L- FARLEY-UNIT 1 3/4 11-14 Amencment No.

k Thes e dos os a.r e p er ren. dor o n .4,

RADIOACTIVE EFFLUENTS b EXPLOSIVE GAS MIXTURE LIMITIMG CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume. ,

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system

. greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the waste gas hbidup system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% within 1 ' r gg,

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

SURVEILLANCE REOUIREMENTS DURING dby7/M/OFwe$72wg 7p 7)%lc.gf31f*.Af 4.11.2.5 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by 6.m:o w ij monitoring the waste gases in the recombiner discharge with the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3-14 of Specification 3.3.3.%

FARLEY-UNIT 1 3/4 11-15 Amendment No.

O RADI0 ACTIVE EFFLUENTS l' j ?

{~ '

GAS STORAGE TANKS LIMITING CO.'!DITION FOR OPERATION ;

3.11.2.6 The quantity of radioactivity contained in each waste gas storage '

tank shall be limited to less than or equal to 70,500 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

. ACTION: . .

a. With the quantity of radioactive material in any waste 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 !

I contents to within the limit.

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

SURVEILLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each waste gas t storage tank shall be, determined to be within the above limit at least once per ^; L. when radioactive materials are being added to the tanked.

~osd :

. g ; a.A, is l<ss H~ c c>i sso co-:e s of -

r> e b l :

g ;s

, -s4 3.s l0 s& p AA s 64/ /> <

bf M

~

$ Nbdee lid, i at fea s+ cx-c e p+ 2 V 4&<s ~ k-n4o a.eh n 2 i. d ,, ,- .e b .a; , adcd./

fo /4 h4 nl h L h v <~ 6 y

[() 000 {c/ h f.S c) MQ b N y 4$ &

FARLEY-UNIT 1 3/4 11-16 Amendment No.

. ;

. 5 L -<

'RMI0 ACTIVE EFFLUENTS e.us* solid.hgjM}{Ar 3/4.11.3 OCLIC ""I!C.aCT:'iC .,,, 72

~2. S l ,

LIMITING CONDITION FOR OPERATION l $ 6l'0 f:C *0 50 ^ -

3.11.3 The wMd radwasteAsystem shall be Gr'ERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to ship' ment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid e site radioactive wastes h a dsoa5 from tp$'c. d.*0^-

A 50/Idl

b. With the - '" "- - -tem inoperable for more than 31 days, 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 includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABL,E status,

3. A description of the alternative used for SOLIDIFCATION and packaging of radioactive wastes, and s-

4. Summary description of action (s) taken to prevent a recurrence.

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

SURVEILLANCE REQUIREMENTS

. rw&ua.sle ul:dAc h

t system shall be demonstrated OPERABLE at least 4.11.3.1 The "' "

once per 92 days by:

s.l.'d:Hca+I+

a. Operating the se44 radwasteAsystem at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or

b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

FARLEY-UNIT 1 3/4 11-17 Amendment No.

2

RADI0 ACTIVE EFFLUENTS f

SURVEILLANCE REQUIREMENTS (Continued) 4.11.3.2 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICA-TION of at least one .epresentative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g. , M1-t.e, sludges, spee&

se64**, evaporator bottoms, boric acid solutions, ;nd ;;di i. euliaie avi u b vii= r.

AND 659W/Md ON S'sKUT/0W3). %

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICA-TION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can ce determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION

. of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.

FARLEY-UNIT 1 3/4 11-18 Amendment No.

l

, RADI0 ACTIVE EFFLUENTS t 3/4.11.4 TOTAL DOSE 7 ,

LIMITING CONDITION FOR OPERATION

~ 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 4 e consecutive ;.;c.t.t.

APPLICABILITY: At all times. ,

ACTION:

i I

. a. With the calculated doses from the release of radioactive materials '

in liquid or gaseous effluents exceeding twice the limits of Specifica-ti ons 3.11.1. 2. a , 3.11.1. 2. b , 3.11. 2. 2. a . 3.11. 2. 2. b , 3.11. 2. 3. a , or ;

3.ll.2.3.b, in lieu of any other report required by Specification 's.9.1, prepare and submit a Special Report to the Director, Nuclear Reaccor l Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C 20555, within 30 days, which defines the corrective action to be taken ,

to reduce subsequent releases to prevent recurrence of exceeding the l limits of Specification 3.11.4. This Special Report shall include an :

l 27 analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources includin al gfluent , ;

. pathways and direct radiation) for a #s con (ecutiveIperiod that i includes the relaase(s) covered by this report. If the estimated .

dose (s) exceeds we limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and , :

including the specified information of 6 190.11(b). Submittal of . i the report is considered a timely request, and a variance is granted '

l L

until staff action on the request is comolete. The variance only relates to the limits of 40 CFR 190, and does not analy in any'way 1 to the requirements for dose limitation of 10 CFR Part 20, as l addressed in other sections of this technical specification. l

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

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations _ Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, p 4.11.2.2, and 4.11.2.3, and in accordance with the ODCH.

Fh{lLEy . . . . . . - - -

" " ' ' 'mu Z ^ ZYnu - UNIT 1 3/4 11-19

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING j.c 3/4.12.1 MONITORING PROGRAM

~

LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted

~

as specified in Table 3.12-1.

APPLICABILITY: At all times. ,

I ACTION:

a. With the radiological environmental monitoring program not being

conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar qui'ter, prepare and submit to the Commission within 45 days from the end of the affected calendar quarter a Report pursuant to Specification 6.9.1.13. When more than one of the radionuclides in Table 3.12-2 are detected in the sampl,ing medium, this report shall be submitted if:

concentration (1) concentration (2) + * * *> 1.0 limit level (1) limit level (2) -

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in.the Annual Radiological Environmental Operating Report.

c. With milk or. forage samples unavailable from one or more of the sample locations required by Table 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 cause of the unavailability of samples and identifies locations for. obtaining replacement sampin. The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environ-mental monitoring program as replacement locations.

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ,

j FARLEY-UNIT 1 3/4 12-1 Amendment No.

l i

.~

l RADIOLOGICAL ENVIRONMENTAL MONITORING y:Lu a SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected l pursuant to Table 3.12-1 from the locations given in the table and figure $in gg i the 00CM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1. i i

l L

r l

l FARLEY-UNIT 1 3/4 12-2 Amendment No.

i ; i .

Tills PAGE 0?EN PEmitlS RECElPT OF lilf0RMAildil .-ROM fiiE APPLICAtlT Taste 3.12-i ,

f.e i S *i IIl U 1 p RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I E Number of Samples H Exposure Pathway and Sampling and Type and Frequency

- and/or Sample Sample Locations

Collection Frequency of Analysis

1. AIRBORNE

a. Particulates Continuous operation of Particulate sampler.

Indicator 3 sampler with sample col- Analyze for gross beta Control 2 lection as required by radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months dust loading but at least following filter change.

b. Radioiodine once per 7 days Perform gamma isotopic Indicator 3 analysis on each sample <

Control 2 when gross beta activity

, is,> 10 times the yearly <

g mean of control samples.

Perform gamma isotopic y analysis on composite w

jg (by location) sample ,

at least once per ,

/[, 92 days.

Radiciodine canister.

Analyze at least once per 7 days for I-131.

9

$ 2. DIRECT RADIATION llec2 tion: ' '0) At leest uncu e s .- 31 days. Com.e desc. f.t Icast

& I 2 isi=ter: er ' ' c=c per 31-tys.

$ O(, ][ Iastruinent Icr ccr5 e gg4bFv7

[ Urucurly = acuring- At least once per 92 days. Gamma dose. AAt least F Jg/)f/g7DM 1 y cp>diosJZc- (y2d-00t 'r0?2nci25 MS ,

once per 92 days.

??a 6 du c o u i- b,e 6si m s iit:u uy 6y p e u s tI6St'*

Ap Mb/dN leedt iOf't. r*tdi5-5eleC W AO (COM WIID 3

[0NTA04 AP ORi 13I SO t

TABLE 3.12-1 (Continued) .

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM J q . .) -

3 Number of Samples 3 Type and Frequency

-i Exposure Pathway and Sampling and H and/or Sample Sample Locations

Collection Frequency of Analysis

3. WATERBORNE

a. Surface Composite ** sample collected Gamma isotopic analysis Indicator 1 over a period of 5, 31 days. of each composite sample.

Control 1 Tritium analysis of com-posite sample at least once per 92 days.

b. Ground At least once per 92 days. Gamma isotopic and

, Indicator 1 tritium analyses of each

,g Control 1 sample, y d. Sediment At least once per 184 days. Gamma isotopic analysis

Indicator 1 of each sample. ,

N 8

5 8

. - - . - _ - - - , , _ . _ ~ _ , . . - - - .

,, TABLE 3.12-1 (Continued)

?> i r RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM UHill I gi Number of Samples q Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis

4. INGESTION

a. Milk At least once per 1 ' days Gamma isotopic and Indicator *** when animals are on pasture; I-131 analysis Control 1 at least once per 31 days of each sample.

at other times.

b. Fish One sample in season, or at Gamma isotopic analysis Indicator 2 least once per 184 days *if on edible portions.

sg Control -

not seasonal. One sample of

= each of the following' species:

S# 1. Game Fish .

. 2. Bottom feeding Fish

c. Forage Grab sample cut from Gamma isotopic analysis, Indicator 2 green forage at least which includes I-131 Control 1 once per 31 days analysis, of each sample.

F k ^ Sample locations are shown in tables and figures in the ODCM.

g ** Composite samples shall be collected by collectir' an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

g ***No applicable indicator milk sampling locations from June, 1979 Milk Animal Survey.

.O

,Q . - - , . . _ _ - . -- ._ ,- _ - ._-_ -.

TABLE 3.12-2 . .

g jo REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES i 0 Reporting Levels

-' Water Airborne Particulate Fish Milk Forage Analysis ~ (pCi/1)' or Gases (pCi/m3 ) (pCi/Kg, wet) (pCf/1) (pCi/Kg, wet)

H-3 2 x 10 4( }

3 4 Hn-54 1 x 10 3 x 10 2 4 Fe-59 4 x 10 1 x 10 4

Co-58 1 x 10 3 3 x 10 3 x 10 2 1 x 10 4

.{ Co-60

% Zn-65 3 x 10 2 2 x 10 4 En 2(b) .

Zr-Nb-95 4 x 10 I-131 2 0.9 3 1 x 10 2 3

Cs-134 30 10 1 x 10 3 60 1 x 10 3

Cs-137 50 20 2 x 10 3 70 2 x 10 Ba-La-140 2 x 10 2 3 x 10 2 N (a) For drinking water samples. This is 40 CFR Part 141 value.

g g (b) Total for parent and daughter.

E n

O i e

%~.

.s

l l - - .

}

L_.i

~

TABLE 4.12-1 -

~-

MAXIMUM VALUES FOR Tile MINIMUM DETECTABLE CONCENTRATION (MDC)a,c h .

'2 E Airborne Particulate 5 Water or Ga3 Fish Hilk Forage Sediment Analysis (pCi/1) (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry)

[

gross beta 4 1 X 10 -2 H-3 2000 Hn-54 15 130 Fe-59 30 260 Co-58,60 15 130 M Zn-65 30 260 Z r- 30 4 .

Nb-95 15 ,

I-131 lb 7 X 10 -2 1 60 5 X 10

-2 130 15 60 150 Cs-134 15

-2 180 Cs-137 18 6 X 10 150 18 60 Ba-140 60 60

[

o

" 15 La-140 15

.o 9

_ m = - - ,. -----..m. . - - - r.... r - , , , -

7 - , - w ..-_- - - -,w ,

TABLE 4.12-1 (Continued)

I TABLE NOTATION ,

a. The MDC is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observatio1 represents a "real" signal.

For a particular measurement system (which may include radiochemical

separation):

4" $

D MDC =

E -

V -

2.22 -

Y -

exp(-Aot)

Where:

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

sh is the standard deviation of the background counting rate or of tne 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 is the number of transformation per minute per picacurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide,

and at is the elapsed time between sample collection (or end of the' sample collection period) and time of counting (for environmental samples, not plant effluent samples).

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

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

O FARLEY-UNIT 1 ,

3/4 12-8 Amendment No.

O

l TABLE 4.12-1 (Continued) . ;

TABLE NOTATION L MM

% b. 4ttT for drinking water. ;

c. Other peaks which are measurable and identifiable, together with the f radionuclides in Table 4.12-1, shall be identified and reported.

. ;

i i

1 i

+

t i

FARLEY-UNIT 1 3/4 12-9 Amendment No. j

RADIOLOGICAL ENVIRONMENTAL MONITORING

3/4.12.2 LAND USE CENSUS LIMITING CONDITION F0;l OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times.

ACTION:

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

. calculated dose or dose commitment greater than the values currently being 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 uso census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 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 this land use census was conducted.

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

SURVEILLANCE REQUIREMENTS 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) by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, using that information which will provide the best results.

FARLEY-UNIT 1 3/4 12-10 Amendment No.

RADIOLOGICAL ENVIRONMENTAL MONITORING g- ,, ,

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM

24 g LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. ,

APPLICABILITY: At all times.

1 ACTION:

. a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

b. The provisions of Specifications 3.0.3 and 3.0.4 a're not applicable.

Ss?VEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required q Interlaboratory Comparison Program nf ' ;;;;. mm.. a o. ... ...e ;;;M shall be included in the Annual Radiological Environmental Operating Report.

l

! FARLEY-UNIT 1 3/4 12-11 Amendment No.

l l

INSTRUMENTATION j BASES 3/4.3.3.10 RADIOACTIVE 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 Of:::dur:: in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION

~

5 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_prc::dur;; in the ODCM to ensure that the alarm / trip will occur prior jgggrgdggtoexceedingthelimitsof10CFRPart20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

I i

i FARLEY-UNIT 1 8 3/4 3-5 Amendment No. !

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EU LUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR

- 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. ,

The ACTION statements provide the required operating flexibility and at the i same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." C; ,fec fccsh.etec. Lc. i t h, drinko y -stcr ;upplic: "i2 ::r b; p;tcut.all., ;f fected by pie..t veci ativc.5, t6 e is i ccavocile :::umne th;.t th; sper tier f the f: i'ity 'd net rc: ale ni iod.unuclid; :;ncei.t Livus ni u.c fini;h;d dr# " ng ,;;ter-that art-

^ exc;;s of the ceamircmcat; cf 10 CF' 1 *1 The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appro-priate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revisien 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing i Appendix I," April 1977.

l This specification applies to the release of liquid effluents from each l

reactor at the site, for ; nit; ith chcr:d c;d~;t: t r : ; t - ~ . m. ap ic...s , th: l liquid ffluent: 'rer th :h:r d cyster cr prepectiened among the crit: i th;cing th;t ;,st;;

l l

l i

i i

FARLEY-UNIT 1 B 3/4 11-1 Amendment No. l l

n I

RADI'0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements.of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 -

and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the liquid ;

radwaste treatm9nt system were specified as a suitable fraction of the dose I design objectives :: forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside l the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). ;

For individuals who may at times be within the site boundary, the occupancy of >

the individual will be sufficiently low to compensate for any increase in the ,

atmospheric diffusion factor above that for the site boundary. The specified release r te 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 :

eoual to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an i infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /

l year for the nearest cow to the plant.

FARLEY-UNIT 1 B 3/4 11-2 Amendment No.

I e m

RADIDACTIVE EFFLUENTS

~

BASES

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

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 Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous

. effluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III.A of Q andix I that conformance with the guides of Appendix I be shown by alculational p ;;;d res based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underesi.imated. The dose calculations established in the 00CM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous' effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calcu-lation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

3/4.11.2.3 DOSE - RADI0 IODINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM .

AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calcula-tional procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses FARLEY-UNIT 1 B 3/4 11-3 Amendment '!o.

RADIOACTIVE EFFLUENTS '* 8 BASES to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluat- ,

ing Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi-tions. The release rate specifications for radioiodines, radioactive materials

.in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were:

. 1). individual inhalation of airborne radionuclides, 2) deposition of radio-nuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption cf the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

7]&FJUfMJMY BNNAUWWY ENhfv57 7XAFTkasTCH7&l 3/4.11.2.4 GASEOUS RADWASTE TREATMENT

. Fort Put TheOPERABILITYoftheGASEOUSRADWASTETREATMENTSYSTEhiandtheAVENTILA-TION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of tnese systems be used, when specified, provides reasonable assurance that the relesses of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 1I.0 of Appendix I to 10 CFR Part 50. The .

specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the waste maintained below the flammability limity of oxygen.# gas holdup Automatic controlsystem is feature,r

/s are included in the system to prevent the oxygen concentratiorpr from reaching these flammability limit /. The w automatic control featueef include isolation N of the source of oxygen to reduce the concentration below the flam:rability limit /. Maintaining the concentration of oxygen below the.M flammability limit / 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.

FARLEY-UNIT 1 B 3/4 11-4 Amendment No.

s

RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".

3/4.11.3 SCL: SC:: fit '/C WASTE SOZ/b/NM TheOPERABILITYofthewLk!radwas[ [e en res that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid /

solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which sho 1 licitation of dose to a member of the public g for 2 'consecuti u.....; o wi in the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

FARLEY-UNIT 1 B 3/4 11.-5 Amendment No.

3

S 3 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING jjj i

]

BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential -

radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring prog.am by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and mooelin; of the environmental exposure pathways.

The in.tially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabi;ities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The JAd}'T~ jf[)

for drinking water meet the requirements of 40 CFR 141. / #234? 3I 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

FARLEY-UNIT 1 B 3/4 12-1 Amendment No.

O

'* 9F

' ;

} '

- 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2. '

SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.3 The site boundary for gaseous effluents shall be as shown in Figure 5.1-3.

SITE BOUNDARY FOR LIQUID EFFLUENTS 3.1.4 The site boundary for liquid effluents shall be as shown in Figure 5.1-4.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dcme roof and having the following design features: .

a. Nominal inside diameter = 130 feet.

b. Nominal inside height = 183 feet. !

c. Minimum thickness of concrete walls = 3.75 feet. ,

t

d. Minimum thickness of concrete roof = 3.25 feet.

e. Minimum thickness of concrete floor pad = 9 feet.

f. Nominal thickness of steel liner = 0.25 inches.

6

g. Net free volume = 2x10 cubic feet.

t P

FARLEY-UNIT 1 5-1 Amendment No.

3

m w IJ C

8

a. ~

PROPERTY LINE (SITE BOUNDARY FOR GASEOUS EFFLUENTS) 68,000 g

l METEOROLOGICAL TOWER \

\ '

N 257,000 --

I ELEVATION b APPROX 150 FT .-BOTH UNITS, 96, 7,. l RELEASE POINT I #

UNIT NO. 2. CONTAINMENT ELEVATION APPROX 300 FT.

I

' AND AUXILIARY SUILDING d240 g7 4270p UNIT.2 CONTAINMENT VENT y i

6 m.31 C CO INMENT VENT 'g O

/ MNIT NO.1 A '

CONTAINMENT AND

'l , AUXILIARY _.

[

f JNFORMATION CENTER BUILDING '-

f (NOT COMPLETED ZERO RIVER

( OCCUPATION)

INTAK E i SERVICE WATER INTAKE STRUCTURE 9

L__. i RESERVOIR l l

~~ ~ ~~ ~~

PROPER 3Y LINE NOTE:SEE FSAR FIGURE 2.1-4 FCR TCPCGRAPHICAL MAP OF SITE Figure 5.1-3 Plant far;ey Site Map Gaseous E!il ents FARLEY-UNIT 1 5-3a Amendment No.

o

O DRAFI

. N w ,- PROP _ERTY LINE (S!TE

- -- -- SOUNDAh -- . FOR LIQUID EFFLUENTS)

-m

\ N N 268,000 Q 7,y METEOROLOGICAL TOWER Ns i t N 267.000 6

$1 g 95 8 i UNIT NO. 2 - CONTAINMENT

/ AND AUXILIARY BUILDING WASTE LINE

/ UNIT NO. 2 d'

i 8 f

]N /--WASTE LINE UNIT NO.1 g/

/ 7 5'

/ -N UNIT NO.1 -

1 5

x i CONTAINMENT AN'O i/ '^

f INFORMATION CENTER O RIVER f -

U (NOT COMPLETED) '

5 INTAKE OIFFUSIC STRUCTURE SERVICE WATER PIPE INTC INTAKE STRUCTURE RIVER N260500 i

I I L7 WASTE DISCHARGE [

L -- . POINT I RESERVOIR s

s' +

PROPERTY LINE

.- __l Figure 5.'-4 . Plan- Tarley Site . Map l Ix=1usien Area a..d *,iquid Ifflue. s FARLEY-UNIT 1 5-3b Amendment No.

SECTION 6.0 ADMINISTRATIVE CONTROLS

lin t r" bnhT i ADMINISTRATIVE CONTROLS

. J. The plant Security Plan,

k. The Emergency Plan.

1. Facility operations to detect potential nuclear safety hazards. ,

m. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Operations Review Board.

n. Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Plant Manager and to the Nuclear Operations Review Board (NORB).

anA

o. Review of changes to the PROCESS CONTROL PROGRAMA 0FFSITE DOSE CALCULATION MANUAL,1- f - -f "'"

AUTHORITY 6.5.1.7 The PORC shall:

a. Recommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (e) and (j) and (k) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a), (c) and (d) above constitutes an unreviewed safety question.

c. Make recommendations to the Plant Manager in, writing that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed

__ safety question.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President-Power Supply and Chairman of the Nuclear Operations Review Board.

FARLEY-UNIT 1 6-7 Amendment No.

ADMINISTRATIVE CONTROLS DP#T 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB4 FUNCTION 6.5.2.1 The NORB shall function to provide independent review and audit of designated activities in the areas of: -

a. Nuclear power plant operations

b. Nuclear engineering

c. Chemistry and radiochemistry

d. Metallurgy

e. Instrumentation and control

f. Radiological safety

g. Mechnical and electrical engineering

h. Quality assurance practices COMPOSITION 6.5.2.2 The NORB shall be composed of at least five persons including; Chairman: Senior Vice President Vice Chairnan: Vice President-Production Alternate Vice Chairman: Vice-President-Power Supply Services Secretary: Manager-Operations Quality Assurance Member: Manager-Nuclear Generation and other appointed personnel having an academic degree in an engineering or physical sciencefield and a minimt.a of five years technical experience, of which a minimum of three years shall be in one or more of the areas given in 6.5.2.1.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NORB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NORS activities at any one time.

FARLEY-UNIT 1 6-8 Amendment No. ,7",

DRAFT ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NORB Chairman to provide expert advice to the NORB.

MEETING FREQUENCY 6.5.2.5 The NROB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum shall consist of the Chairman or Vice Chairman or Alternate Vice Chairman plus enough voting members to constitute a majority of the NORB.

No more than a minority of the quorum shall have line responsibility for operation of the facility. For the purpose of a quorum those considered to have line responsibility will include the Manager - Nuclear Generation, Plant Manager and personnel reporting to the Plant Manager.

REVIEW 6.5.2.7 The NORB shall review:

a. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

b. Proposed tests or experiments which involve an unreviewed safety question as defined in Saction 50.59, 10 CFR.

c. Violations of codes, regulations, ordert, Technical Specifications, license requirements, or of internal procedunes or instructions having nuclear safety significance or abnormal degradation of systems

__ designed to contain radioactive material.

d. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

e. All written reports concerning events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notication to the Commission.

l l f. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

FARLEY-UNIT 1 6-9 AmendmentNo./,

~

a

. N, ADMINISTRATIVE CONTROLS

<. g. Reports and meetings minutes of the PORC.

h. Proposed changes to Technical Specifications or this Operating

~

License.

i. The safety evaluations for proposed 1) procedures 2) changes' to -

procedures, equipment or systems and 3) test or experiments completed ,

under the provision of Section 50.59 10 CFR, to verify that such actions did no constitute and unreviewed safety question.

AUDITS I ~-

6.5.2.8 The following audits shall be conducted under the direction of APCO's Manager - Operations Quality Assurance:

a. The conformance of facility operation to provisions contained within '

the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance', training and qualifications of the entire facility '

staff at least once per 12 months. ,

c. The results of actions taken to correct deficiencies occurring in ,

facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months,

d. The performance of activities required by the operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e. The Facility Emergency Plan at least once per 24 months.

f. The Facility Security Plan at least once per 24 months.

~~

g. Any other area of facility operation considered appropriate by the NORB or the Senior Vice President. .

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program inspection an audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

l l

l FARLEY"lNIT 1 6-10 Amendment No. 4, o

ADMINISTRATIVE CONTROLS

k. At each scheduled NORB meeting the Manager - Operations Quality Assurance shall make a summary report of these activities.

1. The radiological environmental monitoring program and the results thereof at least once per 12 months. ,

m. The OFFSITE 00SE CALCULATION MANUAL and implementing procedures at least once per 24 months. -

n. The PROCESS CONTROL PROGRAM and implementing procedures for solidifica-tion of radioactive wastes at least once per 24 months.

e: $ t y ? :, $bb 197~

tin:t == p:r!2 : th:.

AUTHORITY .

6.5.2.9 The NORB shall report to and advise the Senior Vice President on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.9.

RECORDS 6.5.2.10 Records of NORB activities shall be prepared, approved and distributed I - as indicated below:

a. Minutes of each NORB meeting shall be prepared, approved an~d forwarded to the Senior Vice President within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President within 14 days followirg completion of the review. ,

_ c. Audit reports enccmpassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.

l FARLEY-UNIT 1 6-11 A endment No.

i

ADMINISTRATION CONTROLS 1 RAFT 6.5.3 TECHNICAL REVI(4 AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Technical Specification 6.8 and other procedures which affect plant nuclear safety, and changes (other than editorial or typographical changes) thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change. Procedures other than Administrative Procedures will be approved by either the Technical Superintendent, the~0pera-tions Superintendent or the Assistant Plant Manager as applicable.

The Plant Manager will approve administrative procedures, security implementing procedures and emergency plan implementing procedures.

Temporary changes to procedures which clearly do not change the intent of the approved procedures will be approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to

. approve the procedure shall approve the change.

b. Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications. Proposed modifica-tions to plant nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager.

c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved. Each such test or experiment shall be reviewed by an individual / group other than the individual /

group which prepared the proposed test or experiment. Proposed test and experiments shall be approved before implementation by the Plant Manager,

d. Occurrences reportable pursuant to the Technical Specification 6.0 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Plant Manager and forwarded to the Manager of Nuclear Generation; and to the Chairman of the Nuclear Operations Review Board.

FARLEY-UNIT 1 6-12 Amendment No.

I

)

gpAg l . .

ADM NISTRATIVE CONTROLS

e. Individuals responsible for reviews performed in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall be members -

'of the plant supervisory staff previously designated by the Plant l

(' Manager. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. ,1f deemed necessary, such review shall be performed by the review per-sonnel of the appropriate discipline.

f. Each review will include a determination of whether or not an unreviewed safety question is involved. Pursuant to 10 CFR 50.59 NRC approval of items involving unreviewed safety question will be obtained prior to Plant Manager approval for implementation.

RECORDS 6.5.3.2 Records of the above activities shall be provided to the Plant Manager, PORC and/or NORB as necessary for required reviews.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by the PORC and sub-mitted to the NOR8 and the Manager of Nuclear Generator.

FARLEY-UNIT 1 6-13 Amendment No.

( . . _ . . . _ _ _ _ . . . _. .. . _ _ . _ _ _ . _ _ _.

., .an

/

[]

., a,F , :

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission, the Manager of Nuclear Generation and to the Senior Vice President within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the NOR8 and the Manager of Nuclear Generator within 14 days of the violation.

6.8 PROCEDURES 2 _.

6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972. .

b. Refueling operations. ,

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

,%e; . cad:abyt=\ e.npamenh) myp't.y;.auroyat

'='

!M u?" "; Tl!! J ! ";!1 ;

3"Ti~ ""'. e n c :12:E 7 A,4 ' -' i N!!!.3

. . . . .,~3........ . '..r.....

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

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes I

thereto, including temporary changes shall be reviewed prior to implementation as set forth in 6.5 above.

i FARLEY-UNIT 1 6-14 Amendment No. 4 l

9

ADMINISTRATIVE CONTROLS 6.9 R6 PORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES ,

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions 1 - based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of startup test program, and resumption or commencement of commercial power openation), supplementary reports shall be submitted at least every three months until all three events have been completed. -

ANNUAL REPORTS E 6.9.1.4 Annual reports covering the operation of the unit as described below during the previous calendar year shall be submitted prior to March 1, of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

I k

1/ A single suomittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

f FARLEY-UNIT 1 6-15 Amendment No. 5,

\

1

I

.. 1

~

,DME-. ,

ADMINISTRATIVE CONTROLS l

':I 6.9.1.5 Ryorts required on an annual basis shall include:

a. A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr i and their psociated man rem exposure according to work and job functions,- e.g. , reactor operations and surveillance, inservice -

inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received

- from external sources shall be assigned to specific major work functions.

3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT _/

6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the

- radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. ,

The annual radiological environmental operating reoorts shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

y Inis tabulation supplements the requirements of S 20.407 of 10 CF'R Part 20.

-3/ A single submittal may be mada for a multiple unit station. TL _.. . . M

hnid x-t! c th x x tix: that :r: a n:r t: 11 xit: :t th: :tati; v 3 he r : , ' ; #t: 'it" ::p: :t: : c t: :yrt -

r, t": 9# tt:1 :P:?' .

p::i'y t' :!::::: ef :dia :t've :t: *:? 're 22:52#t.

FARLEY-UNIT 1 6-16 Amendment No. 5, 2

p 7"?

~

ADMINISTRATIVE CONTROLS f)dn['I The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.

3 ,

SEMIANNUAL RADI0 ACTIVE EFFLUEN~ RELEASE REPORT _/

6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the, data of initial criticality.

6. 9.1. 9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendik B thereof.

The radioactive effluent release report to be submitted 60 days af ter January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the 2 - form of an hour-by-hour listing of wind speed, wind direction, a'mospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. "i: n: rep:-t ch:1' :? x

' :lud: = nnnmut of the r:dic.ti r dnx 'rr r:dicxtiv 'iquid =d ; n s u; ge<3,mm+ + ,, a m e, . ,e g ic q..m .,.%;. w 4u;;;ge 4e4% .sg ,4 3

2xump ti:n g

bo r d: y 7?;;rn 5.'-3 r d 5.'-1) dur'r; th: r:;;rt peri:d.

and . h'ng th: = x ni = =t: (i.:., :pni'i: =ti ity, rpxtr tir =d lec ti: ) :h:l' b: ' =lud:d '- th:x c:p;rt:. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Oose Calculation Manual (00CM).

(

3/ A single sucmittal may be made for a multiple unit station. The submittal should combine those sections tnat are common to all units at the station; however, for units with separata radwaste systems, the submittal shall specify the .eleases rf radioactive material from each unit.

l FARLEY-UNIT 1 6-17 Amendment No.

p = ="w !

g ,,

y ADMINISTRATIVE CONTROLS $L .

i J2___L ,. ,___ L - _ L_?LL _J PR )m,._ e$b__ , ~ _ . _ _ . ,

T.. L. _ - me.--

. ..._22

!.. m. .m...

__t

. m.em,e . mr .t.

L

.s ..........w .. __,w _ . . . - - - - _ . ,

! cf ;;;h y;;r ;h;11 al;; include an ;;;;;;. ;nt ;' r;di;ticr de::: ! th: ' ": 15 ,

crt exp ::d :::b r: cf the publ?: 'r:: r:::t:r re!::::: :-d et"e- "e -by u 2-irm j

, fuel cycl: ::ur::: (including d;;;; fr;; pri;;r3 ;f flu;nt p;th..;y --d di. --- ,

":dicti:n) f;r th; pcr.!;u; 12 ;;r.;;;wt!.m ;; nth; te ;he- cen';..~..;m -.e.. !

i on r

~ ..-,, .,mm w, r_ , ______ _, n_2 _,,__ n__.__.:__ e. _;._;_ ,__ u.. ,_-_ n_..__

, . m... . . .. ......w, . . _ _ . _ _ . . . . . . . . . . . . . . . . . . _ _ . _ . .-. . - . - _ . . . _ . ,

C?:rati:r

,- - ; - _ J

".;;;pt;bl; ;;th;d; f;r ;;lculating th; d;;; ;;r.t. !h tie.. '. ;;

__ ___ _ - ,,, _m . _ _ _, - - . _ ,__._,_m__. r. :2_ , ,nn n_. ,

' Mw . w w..w gue-.we w. . . ws...e w. w y..wi. s.s ssw g w . w ww . g ===== .- ; - - - -

The radioactive effluent release reports shall include the following information !

for each type of solid waste shipped offsite during the report period: :

I

a. Container volume, !

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

I

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

i

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

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

- 1

f. Solidification agent (e.g., cement, urea formaldehyde). .

w w e w vw w . w 4 w . .e . - ._ -

t_",,,: .cit: t: rrc:tricted ;r::: Of r;di;;;ti.; ;tcrial; in ;;;s;-. mad 1;,..u

__ ._ __ _ - . , _ , _ _ , . w,,4,

,, a w.i ,, ...

3--. ... ., _-_

The radioactive effluent release reports shall include,any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period. :

MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Of fice of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.

- :dditicr, ; ;;;rt ;f ;n3 ;;j;r ; ;ng:; t; th; :di::: tic: :;t; t ;;;. ;..!

. ...___ _m.,, .__ .. m_ . .; :u .m_ .__.m,. ____m- ,____m <-_ mm_ -- >

=*r y-. ..w

,,.s w...s w1.w . . - = . - . . . ---- - - . . - . . . . . . . - - g r_.-- y - - -. v.a= . . .

. x ? _ _ __ f_ _J _ _J _____A _J L. mL_ MN9F

.........m m........ ..w. . .. . . . . . . ..._ _...r.._ ., . . . _ -..-.

FARLEY-UNIT 1 6-18 Amendment No.

~

MAFT ACMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES 6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. "

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

by telephone and confirmed by telegraph, mailgram, or facsimile transmission '

to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. The written followup report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective ,

function by the time a monitored parameter reaches the setoint specified as the limiting safety system setting in the technical e- specifications or failure to complete the required protective function. ,

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting i condition for operation established in the technical specifications. ,

c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% delta k/k; a calculated reac-tivity balance indicating a SHUTCOWN MARGIN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% delta k/k; or occurrence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional require-ments of system (s) used to cope with accidents analyzed in the SAR.

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, th fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.

FARLEY-UNIT 1 6-19 Amendment No.

3

e e

p. ,.

. ADMINISTRATIVE CONTROLS 0$h

g. Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by technical specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses,

i. Performance of structures, systems, or components, that requires

~~

remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that >

require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

j. Offsite releases of radioactive materials in liquid and gaseous effluents which exceed the limits of Specification 3.11.1.1 or 3.11.2.1.

k. Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive materials in the listed tanks. The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

THIRTY DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall the subject of written

__ reports to the Director of the Regional Office within thrity days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event,

a. Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfill-ment of the functional requirements of affected systems,

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

FARLEY-UNIT 1 6-20 Amendment No. 5.

t

-

me b '"

ADMINISTRATIVE CONTROLS

c. Observed inadequacies is the implementation of administrative or ,

procedural control swhich threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d. Abnormal degradation of systems other than those specified in '

6.9.1.8.c above designed to contain radioactive material resulting - >

from the fission process.

e. An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in

_. gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:

1. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

f. Measured levels of radioactivity in an environmental sampling medium '

determined to exceed the reporting level values of Table 3.12-2 when i averaged over any calendar quarter sampling period.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for -!

each report. ,

I l

i l

l 1

(

l FARLEY-UNIT 1 6-21 Amendment No. ;

1 l l

_ __-.d

'. . c' yr l'11 $

ADMINISTRATIVE CONTROLS -

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation coveri.ng time interval.at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. ALL REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to Operating Procedures.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record. ,

o -- ,

6.10.2 The following records shall be retained for the duration of the Facility l Operating License:

a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

a

b. Records of new and irradiated fuel inventory, fuel transfers and ,

__ assambly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f. Records of reactor tests and experiments.

1 g. Records of training and qualification for current members of the :

plant staff.

FARLEY-UNIT 1 6-22 Amendment No. J, 3, 5

. ADMINISTRATIVE CONTROLS

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Harual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR ~

50.59.

k. Records of meetings of the PORC and the NOR8.

1. Records of secondary water sampling and water quality.

m. Records of analyses required by the radiological environmental monitoring prograta.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be pre, pared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HICH RADIATION AREA

__. 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

~

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been~ established and personnel have been made knowledgeable of them.

l

" Health Physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

FARLEY-UNIT 1 6-23 Amendment No.

i kA ADMINISTRATIVE CONTROLS

c. An individual qualified in radiat,an protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at ',

the frequency specified in the radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or the Chemistry and Health Physics Supervisor.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP-

1. Shall be submitted to the Commission in the semi-annual Radioactive Ef fluent Release Report for the period in which the change (s) was made. This submittal shall contain:

a. Suf ficiently detailed information to totally support the rationale

' ~~ for the change without benefit of additional or supplemental information;

b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

2.

tfA ia **M'"* O Shall become effective upon review and eccc;'tre: t th: "C'O.

~.-

sghb (..s.1.1

! 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) l 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the 00CM:

1. Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective. This submittal shall contain:

FARLEY-UNIT 1 6-24 Amendment No.

)

Chl 1351 ADMINISTRATIVE CONTROLS

a. Sufficiently detailed information to totally support the rationale for the .:nange without benefit of additional or supplemental

. information. Information submitted should consist o'f a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

c c 6%

2. Shall become effective upon review and ;qpovd

pt;r.;; 53 th;'mFCCO.

ce .rdan e yS.4ca n to.G 3.\

4.I; . MAJOR CHA:4SE3 TO RADICACTIVE WASTE TREAT;4E;4T SYSTE.45 ' Liquid, Goaevua '

and solid) 6.15.1 icensee initiated major changes to the radioactive waste sys ms (liquid, seous and solid):

1. Shal be reported to the Commission in the Monthly 0 rating Report

~'~

for th eriod in which the evaluation was reviewe by the PORC.

The discu ion of each change shall contain:

a. A summar f the evaluation that led t he determination that the change uld be made in accordan with 10 CFR 50.59;

b. Sufficient detal d information totally support the reason for the change wit. ut benefi of additional or supplemental information;

c. A detailed description e equipment, components and processes involved and the int aces 'th other plant systems;

d. An evaluation of e change which ows the predicted releases of radioactive .aterials in liquid a gaseous effluents and/or quantity of lid waste that differ fr those previously predicted 'n the license application and mendments thereto;

e. An ev uation of the change which shows the e cted maximum exp ures to individual in the unrestricted area nd to the eral population that differ from those previous estimated in the license application and amendments thereto; FARLEY-UNIT 1 6-25 Amendment No.

i e

y

%e

~.

1 0'.p ,: "T bh f ADMINISTRATIVE CONTROLS

. comparison of the predicted releases of radioactive materi ,

in

uid and gaseous effluents and in solid waste, to

actual ases for the period prior to when the ges are to be made;

g. An estimate of the expo t nt operating personne'l as a result of the change; 'a

h. Documentati the fact that the chan as reviewed and foun eptable by the PORC.

2. all become effective upon review and acceptance by the Portu.

i

+

9 P

B FARLEY-UNIT 1 6-26 Amendment No.

l

?

'j

'l

ML19305D721

Text

Navigation menu

Search