ML17227A698

Proposed Tech Specs Utilizing Guidance of GL 89-01, Implementation of Programmatic Controls for RETS & NUREG-1301, ODCM Guidance:Srec for Pwrs.

ML17227A698
Person / Time
Site:	Saint Lucie
Issue date:	01/22/1993
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17227A699	List: ML17227A698 ML17227A700 ML17309A692
References
RTR-NUREG-1301 GL-89-01, GL-89-1, NUDOCS 9302010143
Download: ML17227A698 (215)

Text

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo Technical S ecifications Generic Letter 89-01 ical'ffluent ATTACHMENT 1 ST. LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES AND INSERTS IV VIIIa XV 1-4 Insert ¹1 1-5 Insert ¹2 3/4 3-22 3/4 3-22a 3/4 3-45 through 3/4 3-53 Insert ¹3 3/4 3-54 through 3/4 3-56 B 3/4 3-4 3/4 11-1 through 3/4 11-13 3/4 11-16 3/4 11-17 B 3/4 11-1 through B 3/4 11-5 3/4 12-1 through 3/4 12-12 B 3/4 12-1 B 3/4 12-2 6-15 Insert ¹4 (2 pages) 6-17 Insert ¹5 6-18 Insert ¹6 6-19 6-21 6-23 Insert ¹7 Insert ¹8 6-24 9302010143 930122 PDR ADOCK 05000335 p PDR

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE 3/4 2-1 3/4.2.2 DELETED 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR- F T 3/4 2-9 r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.2.4 AZIMUTHAL POWER TILT - T ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2 11 3/4.2. 5 ONB PARAMETERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2 13 3/4. 3 I NSTRIlMEN TATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION ................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ...................................... 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION 3/4 3-21 Radiation Monitoring ................................. 3/4 3-21 Incor e Detectors 3/4 3-25 Seismic Instrumentation .............................. 3/4 3-27 Meteorological Instrumentation ....................... 3/4 3-30 Remote Shutdown Instrumentation ...................... 3/4 3-33 Fire Detection Instrumentation .............. 37'4 3-37 Accident Monitoring Instrumentation ......... 3/4 3-41 Sl)C Monitoring gq.s Instrumentation ...................................... 3/4 3-50 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION 3/4 4-1 3/4.4.2 SAFETY VALVES -'HUTDOWN ............................. 3/4 4-2 3/4.4.3 SAFETY VALVES - OPFRATING ............................ 3/4 4-3 ST. LUCIE - UNIT 1 IV Amendment No. g7, P7, $ $ , $ 7,p p

INDEX LIMITING CONDITIONS FOR OPERATION AHO SURVEILLANCE RE UIREMENTS ION PAGE 3/4.11 IOACTIVE EFFLUENTS 3/4.11.1 LIg FFLUENTS ..... ....... ...................... 3/

3/4.11.2 GASEOUS 'EF S ............,.....,........... .. 3/4 11-7 3/4.11 .3. SOLID RADIOACTIVE ........... 3/4,11 -1 6 3/4.11.4 TOTAL DOSE . 3/4 11-17 3/4.12 RADIOLOGICAL ENVIRO L'MONITORING 3/4.12.1 MONITORI G RAM ~ o ~ ~ ~

/]1

/ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ..... 3/4 12-1'/4.12.2 USE CENSUS 4 12-11

.3 INTERLABORATORY COMPARISON PROGRAM . 3/4 QFLETC 3/1. II Re)i'oa.chive Effluen4 K)R. I). z.5 Ex plosive. (sAs Nilf~re 31cI II .1.( Iona 5 foe a.ge 1anks ST. LUCIE - UNIT 1 VIIIe Amendment No. 5 g

INOEX I

l ADMINI STRAT I VE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTION. 6-12 6.7 SAFETY LIMIT VIOLATION.. 6-12

,6.B PROCEDURES AND PROGRAMS............... 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS.. 6-15 S tartup Report............................. 6-15 Annual Reports......................... 6-16 Monthly Operating Reports............. 6-16

~annual Radioactive Effluent Release Report............,. 6-17 Annual Radiological Environmental Operating Report.......... 6-18 6.9.2 SPECIAL REPORTS.................... 6-19 6.10 RECORD RETENTION............................................. 6-20 6.11 RADIATION PROTECTION PROGRAM.......;.......................... 6-21 6.12 HIGH RADIATION AREA. 6-22 6.13 PROCESS CONTROL PROGRAM...................................... 6-23 6.14 OFFSITE DOSE CALCULATION MANUAL.............................. 6-23 r

+$ 1 ST. LUCIE - UNIT 1 XV Amendment Nc. 77,37,$ 9,69

DEFINITIONS IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or

c. Reactor Coolant System leakage through a steam generator to the secondary system.

LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE 1.16 The LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE is that. operating condition when (1) the cold leg temperature is < 304'F during heatup on 281'F during cooldown and (2) the Reactor CooTant System has. pressure boundary integrity. The Reactor Coolant Svstem does not have pressure boundary integr'it@

when the Reactor Coolant System is open to containment and the minimum area of the Reactor Coolant System opening, is greater than 1.75 square inches.

MEMBER S OF THE PUBLIC 1.17 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupation-ally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recrea-tional, occupational or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL ODCM 1.18 REPLACE w<T'A 'XHsMT ST. LUG I E - UNIT 1 1-4 Amendment No.N,$ 9,8, M. '104

INSERT g1 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in. the calculation of gaseous and liquid effIuent monitoring Alarm/Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the information that hould be included in the Annual Radiological Environmental Operating and MH nual Radioactive Effluent Release Reports required by Specifications 6.9. 1.'7 and 6.9.1.8.

~ ~ ~

DEFINITIONS OPERABLE - OPERABILITY 1,19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train,'omponent or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive .

combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

PROCESS CONTROL PROGRAM PCP 1.23 RepLAcc was x~~~<>+2 PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other. operating condition, in such a manner that replacement air or gas is required tg purify the confinement.

ST. LUCIE - UNIT 1 1-5 Amendment No. g7, 69

V I INSERT g2 The PROCES~CONTROL PROGRAH (PCP) shall contain the current formulas, sampling, analyses,, test, and determinations to be made to ensure that process-ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

TABLE 3.3-6 nnOIATION MONITORING IHSTRuMEHTATIOH MINIMUM I

CIlANNELS APPL I CMLE ALARM MEASUREMEHT INSTRUMENT OPERABLE MODES SETPOIHT 'ANGE ACTION

l. AREA MONITORS

a. fuel Storage Pool Area < 15 mR/hr 10 -10 mR/hr 13

b. Containment (CIS) < 90 mR/hr 1 - 10 mR/hr

c. Containment Area - Ili 1,2; 354 < 10 R/hr 1 - l0 R/hr Range

2. PROCESS MONITORS

a. Containment

i. Gaseous Activity RCS Leakage Oetection 1, 2, 3 5 4 Hot Applicable 10 - 10 pCi/cc 14 ii. Particulate Activi ty 6

RCS Leakage Oetection 1, 2, 3 8 4 Hot Applicable 1 - 10 cpm/hr 14

b. Fuel Storage Pool Area Ventilation System

i. Gaseous Activity -7 - 5 10 10 pCi/cc 12 i i. Parti cul ate Acti vi ty 1- 10 cpm 12

• With fuel in the storage pool or building.

• • With irradiated fuel in the storage pool or whenever there is fuel movement within the pool or crane operation with loads over .the storage pool.

• • 'The Alarm Setpoints are determined and set in accordance wi th requirements of THE QFFSIT~ QosC

TABLE 3. 3-6 ( Con ti nued)

RADIATION t"10H ITOR I HG INSTRUMEHTATIOH MINIMUM CHANNELS APPLICABLE ALARtl MEASUREMENT INSTRUMENT OPERABLE MonES SETPOIHT RANGE ACTION

2. PROCESS MONITORS (Continued)

c. Noble Gas Effluent Monitors

i. Radwaste Building Exhaust System (Plant Vent Exhaust

• • • Moni tor) 1,2,3&4 10 10 5

pCi/cc 15 ii. Steam Generator Blowdown Treatment Faci l i ty Oui 1 ding Exhaust System .1,2,384 *** 10 7

10 2 Cl /CC 15 iii. Steam Safety Valve Discharge )/Header 1, 2, 3 & 4 '** 10 - 10 pCi/cc iv. ECCS Exhaust 1/Train 1, 2, 3 & 4 *** 10 - 10 pCi/cc

""'Tlii Alarm Setpoints are determined and set in accordance with the requirements of Tire OFFsirc l)os s

<pLc,uge r tow NI +<+<<

J . ~ .. ~ t4 ~ h.

RUMENTATION RAD TIVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITING DITION FOR OPERATION 3,3.3.9 The r 'oactive liquid effluent monitoring instrum ation channel s shown in Table -12 shall be OPERABLE with their alarm/ p setpoints set to ensure that th imits of Specification 3.11.1.1 are t exceeded.. The alarm/trip setpoint f these channels shall be determ' in accordance with the methodology and ameters in the OFFSITE DOSE C LATION MANUAL (ODCM) .

APPLICABILITY: At all ti e .

ACTION:

a. With a radioactive liq eff nt monitoring instrumentation alarm/trip setpo 'hannel s conservative than required by the above specification, diately suspend the release of radioactive liquid efflu , nitored by the affected channel or declare the channel per b e.

b. With less than the iImum numbe f radioactive liquid effluent monitoring.)nstr, tiop channe, . PERABLE, take the ACTION shown in Tab) e3 2..: If .the, inop 1e'instruments are not returned to op- tg,status,withiri.3 s,explain.- in the. next Semiannual" 0 active Effluen't"Rel'eas 'ort=why the inopera-bili .y was corrected in a timely man e .

C. The prov ons of Specifications 3.0.3 and . 4 are not applicable.

SURVEILLANC UIREMENTS 4.3.3.9 ch radioactive liquid effluent monitoring instrument t n channel shall demonstrated OPERABLE by performance of the CHANNEL CHE , OURCE CHEC CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations he fr encies shown in Table 4.3-8.

ST. LUCIE - UNIT 1 3/4 3-45 Amendment No. J/9,69 '

rnnl.E.:1.:1-12 ftnt) tohCTlvl.'l(rtt'll) l,f'I'I.UI'.Nf I'tot)I'lolllttrC INS fftUIOCHfRTION I

n I 1 I H I l 1UI I m CIIRHf'ILI.S INSTIIUtlL'Hf Ol'EIIRl1LL nr Tlotl rltoss itnoto I~ONlxotts I ttovtotHG ni.nltH nHo AU1OHATIC TEIII OI. IIEI.LASL.

cl. Li quirt Ita~twcls1.c E el I.i>>c

b. SLeam GeneraLo> Illowtown: ll L l.inc'.

1/S(i I:Lolt itnfE ttEASUftEHEHT I)EvlcES

a. I.iq<<ld ItadwasLc Lff1<<e>>t l.ine ll. Oi scllal (Jc Calla) r:. SLeam Generator t)lowctown Ef l ll. I.ines CD D

CL CD D

TABj - 3 "-12 ~/Con- irucd~

TABLE HOTS  :" <

With -:ihe nu;ber oi cnanneis ".--".".ABL= fess tnar. re '. rec OJ i Iie

tiniimum "nannei5 GP BABLE~ requirement, e;-', en J ea5es i7i av continue ior uo to 14 days provided hat prior " 1 il 1 t ct ii 1 ri g el ease:

a.. At leasi two independent sai-.,ples ar nalvzed in accordance ith Specifica-ion 4. 11. l. 1.1~ an A ast wo technically qual d miembers of the,"cc i 1 i ty 5ta i '. nC pencently vel i v 1 re i ease ate cal cul ations and d harge line val vin ne performs, ore verifies);

Other wise, suis d release i radioactive efiluents via this I pathway..

P ACT:ON Mith the n mber of 1 1 s OPK!?ABLE less than recuired by the Minimum Charnels GP= E requirement, effluent releases via vill5 Pctiiwcy filav C 1 n ioi uP to 0 dcvs P ovlded g. cb

~

samples are anal d for SS radlocC iVltV (b ta Or gaiina) a limit of dat on of at st 2 x '0-'icrocuries/gran:

At 1e the

- onc per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ondary coolant is g

'n=

the spec'.'fic ectivity "=

er han 0.01 microcuries/

gr OSE "GUIVALEHT I-131.

b. *i lees once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w,",en i speci, lc ac iivltJ of the secordary coolant is less ti - or equal to 0.0'1 microcur ies/gram GOSC 7/UIIALF"t 131..

ACTiOH 3 " system design flow iiinihum of req ired runrin umps shell be utilized for NPC calculations ior d-,schar"~ ="al flow and maximum system design flow shall be util zec = ti?C calculat'ons for effluent line flow.

ST. LUCIE Ui/IT I 3/4 3-47 Amendment Wo. 5 9

ttAOIOACl lVE LI IJIO Et.t:I.I)1:H'I'IONI'IOJIIH(i Itt."'fIII!t!4'I(fAT[OIISIJBVI:tI.I.AN(:I:. III'.(IIII(AIC CIIANlll I, CIIANNLL SOUIICE . IAHN['.L I'UHC I I OI IAI.

I HSl II()I1EIIT CIIL'CK CIIEC CAL I I) IPA f I OH IESI

(;IIOSS t)CTA Ot< (At~tIA ftAOt . V HOHtrotlS I'IIOV1I) IHG ALAAII AHO AUTOMAT: NRT IOH

()F III'.I.EASE

a. I.i~tnt~i ttartwasl.e Effluent Line II(2) (~( I )

I). SLealll Cienerator O)owilown Ef Line tt(2) (l( I)

Z. I 1.(3W I(A I I'. IPCASUtIEHEHT .ES Liilui~l I te Ef f I uent Line H.A.

I).' Cieneralor Olowdown Ef fluenL Line H.A.

I, t

TAGl E 4.3-8 Continued

'f TABLE NOTATIONS (1) Th NNEL FUNCTIONAL TEST shall also demonstrate automatic .

isola this pathway and control room alarm nciation occur if any o following conditions exists:

l. Instrumen icates measured level a ve the alarm/trip setpoint.

2. Circui,t failure.

3. Instrument indicates a al e failure.

4. Instrument contr s ot set in ate mode.

(2) The initial tion shall CHAN be'rmed ALIBRATION using one for radio or more o

'ty measurement instrumenta-reference standards trace-able to th ional Bureau of Standards or usl andards that have been calibra gainst standards certified by the NBS. s'e standards should permi ibrating the system over its intended range nergy and rate ca 'ties that are typical of normal plant operation. subsequent EL CALIBRATION, button sources that have been related e initial libration may be used.

ST. LUC IE - UNIT 1 3/4 3-49 Amendment No. 5 9

MONITORING INSTRUMENTATION Q)4PLo5) v6'AS LIMITING CONOITION FOR OPERATION

3. 3. 3.10 The monitor ing instrumentation channel s shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to

~i i i* i .>>.2.

APPLICABILITY: As shown in Table 3.3-13.

ACTION: EXPLOSIVE &AS

a. Wi th monitoring in'strumentation channel alarm/trip setpoint less conservative than required by the above Specification, 4

~ declare the channel inoperable. ggpLQ5jp

b. With less than the minimum number of monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. If the inoperable instruments are not returned to operable status within 30 days, why the inopera-bility was not corrected in a timely manner.

C. The provisions of S 'tion . . .

s~bmA

'0. e p(g(gag Kn0 a. s)pclcL( I c$ ><+

+c+pe. 4dM~I ssl+6 v Ah~ 3o day s +> CVf ~"<<

SURVEILLANCE RE UIREMENTS

+<pro~ 4.3.3.10 Each gP~ monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, MURED

, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

P gL<f6 ST. LUCIE - UNIT 1 3/4 3-50 Amendment No./fB'~ 69

'\ ~

~ p 1 I I ~ ~

~ P

~

l i' 4 P

~ )

0

blONI I OII IH(i INS fIIUIREHfA f1 ON 111N I IIUlI CIIAHNLIS I NS fAUIIEHT Dl'EILAllLE RP V L I CRll I I. I 'fY AC I ION HASTE GAS OECAY TANKS LXI'LOSIVE GAS H()NITOIIIHG SYSTEH

a. OxyrOeo llor>i Lor s

a IIRI) IOAC'I I VI: (lASI Otter I'I'I I ltl Ill'l()tlll()lt lit( I ttS fltltl11:tt(RTION I IINIHI)II (:IIR)ltll:I.S lt I I HT Ol'I.IIRI)I. I'. Rf'I'I. I CRI) I I. I fY I'Itl:I. S IOIIRGL. VLtlTILAlION SYS fl;I'I Hol>)e Gas Acti; loni tnr (Low Itanfle) li. I online Soml) 1 cr I'arLicnlaLe Sampler tt. I'low llaLC I'ion) tor Sam)ale) Flow ItaLc Honi Loi Ci. Sl'I.AH (sf.'Nl:ftATOII I)I.OWI)OWN 1)IIII.I)IHG VCHT

-SYS I'Lt1 ttob1e (ias RcLiviLy lloniLor I). I o(lille Sam)I I cr

c. I'arLiclllALc Sam))l

~I. I:low llaLc f (L NR

c. S lm ) r 'w ItaLe lloni Lor

TABLE 3.3-13 Continued TABL E NOTATION

~"

Ah Ouring waste gas system operation.

ACTION 1 Rept<~"

~~e gpss T

ION 2 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases vi ss pathway may continue for up to 30 days provided the flow is stimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 3 - Wi e number of channels OPERABLE less than re 'd by the Minim annels OPERABLE requirement, effluen eases via this pathway ontinue for up to 30 days provi grab samples are taken at lea ce per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these ples are analyzed for Isotopic a 'ty within 24 hours.

ACTION 4 Maximum system flows 1 be uti in the determination of the instantaneous releas it alarm setpoint.

ACTION 5 - With the number of channel E one less than required by the Minimum Channels OPERAB equir operation of this system may continue for up 0 days prov> amples of 02 are analyzed by the lab gas par ioner at leas ~ .onc 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 6 - With the num of channels OPERABLE less tha uir ed by the Minimum Ch els OPERABLE requirement, effluent ses via the affecte thway may continue for up to'0 days pro samples are inuously collected with auxiliary sampling equ t as re ed in Table 4.11-2.

ST. LUG IE - UNIT 1 3/4 3-53 Amendment No. 5 9

INSERT g3

'With the number of channels OPERABLE one less than r equired by the tiinimum Channels OPERABLE r equir ement, operation of this system may continue for up to 30 days provided samples of 02 are analyzed by the lab gas partitioner at 1eas .once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

fl

HOHITOIIIHCi INSTIIUHI:NIATION SUAVCILLANCE ftL UIIIBIL'HTS I

n CIIANNCL thOI)l:S I tl hlll I CII m CIIAHHfL SOIIIICL CIIAHHLL FUHCI IOHAL SIIIIVf;II I.ht<CL IHSTIIIIIIEHT CIIL'CK Clif.CK CAL I I)I)ATIOH TL'ST ill:gU I III I)

MKSEE OAS DEEKY ThNKS EXPLOS)VE (ihS R)HI10IIIHCi SYSTL'H

a. Oxygen tloniLor 0 gO

~ +& QOL)

I). Oxygen Honi t,or (al ternate) 0

'9 Q(W~L)

Q

k 1k

) l

~ ~

j g k

1RIII.E l. 1-9 (Coot. (i<(ie(I)

BR(I(OR(TIYI; ('h!il (lllS I I:I'I III III'l()Ill'l(Ill(ll(ll(l."ll(III((i(lb'IIOII '.I(ll(YCII I RIICI: III ()I(Ill((I( I(IS CIIRflilt:t. Ilt)l)i.".s I II 'IIIII Cll CI IRNNI'.I. SOUIICE CIIAIIHEI. I:IIIIC1 IOIiht. SIIIIVI I t.t.hllC I HS'I lt IIIII.IIf CIIECII CIII:.CK CAL I I) lth'I'IOH TES1'tl'QU II .

~J. FIII:I. STOIIAGL hit TILATIOW SYS II'.II Hnt)le Cias RcL'iviLy Hoi>> It(3)

b. l oit i ne Sampler N. A. H. h. H.h.

c. I'arLicll)aLe Salllpler N. A. H.R.

(I. Sat Ill) I er Flow ltaLe Honi Lor N. A.

S'll:RH CiEIIEIthTOIt DI.OHI)OLCH l)UILO1f]Ci VI:HT

a. ttohle Gas hcliviLy IIooiLor It(S) Q(2) li. Ioitirie Sampler N.R. H. h..

c. I arLicatlaLe Sam ~

r H. R. H.R.

<I. Sam))I(.r .

o aL'e Ho))iLor H. h.

TABLE 4.3-9 Continued TABLE NOTATIOH (g) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l. One volume percent oxygen, balance nitrogen, and 2; Four volume percent oxygen, balance nitrogen.

ST. LUG I E - UNIT 1 3/4 3-56 Amendment No. 5 9

~ ~

I

INSTRUl1ENTATION BASES Pgpl oS>VC ivloN n'omit &

3/4.3.3.10 INSTRUNENTATIOP The i ns trumenta tion i s prov id ed to moni tor t i'I 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 Oesign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE - UNIT 1 8 3/4 3-4 Amendment No. 5 9

'k

<. 11 RAD IOACT I="FFLU-"HTS 1.1 LrOUIO "".-FLU HTS C HC Ri"ATIOH L 'T:HG 0 7<OH FOR OP:RATIOH 3.11.1.1 The entration of radioac ive material released fram sita (se Figure 5.1- ) hall be limited to the concentrations soecifi in 10 CFR Part 20, Appendix, Table ii, Column 2 for radionuclides other ~ an dissalved cr entrained noble a s. For dissolved or entrained noble g s, the concentration shall imited to 2 x 10-~ microcuries/ml o activity.

APPLICABILiTY: At all 'm s, ACilOH: I kith he concentration of radi a ive material re ed <rcm the site exce cing the a-cve limits, immediately r . re the conce r tion to within the above 11m1ts.

I L F R OUIR M HTS 4.11.1.1,1 The r adioactivity con i of each b tch of radioactive liquid was e shall be deter,ined prior to r el e by samoli nd analysis in accordance with Table 4. 11-1. The result f pre-release a a ses shall be used with the calcula iona <<methods in the CM to assure that i concentration at the point o> release is maintained w' the limits of Soeci<i tion 3. 1. 1. 1. Also, results o< the previous p -release analyses shall b sed with the calcu-lational methods in the CM to assure that the cancen " tions at the point of release 'were main ain i thi'n the limits of Specificati n 3. 11. 1. 1.

4. 11. 1. 1.2 Post-r ase analyses of samples composited frc atch releases shall be perform in accordance with Table 4. 11"1.

4. 11. 1. 1.3 T r adioactivity concentratian af liquids discharge rcm con inuous ease points shall be determined by collection and a sis of samples i cordance with Table 4. 11-1. The results af the analys shall be used 1 h the calculational methods in he OOCM to assure tha- th cancan tions at the point of release are maintained wi hin the limit Soec'ti<on 3. 11. 1. 1.

ST. LUCIE - UNIT 1 3/4 ll-l Pmendrrent No. 5 9 f

j I

4

TABLE 4.11-1 RAOIOACi.V L.OU'0 'wAS iE SAMPL ilG AiNQ Ai'iAL 5i 5 PR"GRAM Lower Minimum or 0o tion Liquid Rel ea Sampling Aralysis Tvpe o Activity LO)

Tyoe Frequency Frequency Analysis Ci/ml )

A. Batch Maste P ~

P Release a h Batch Each Batch Principal Gamma axlO Tanks Emitters I-131 lxl0 P Oissolved a d lxlO One Bate Entrain ases (Gamma c it ers)

P M b

H-3 1xl0 Each Batch <<osl te ss Aloha lxl0 P Sr 89, Sr-90 BxlO Each Batch Col>>posi e Fe-55 1 x 1'0 B. Continuoy 4 incipal Gamma 5x10 Releases " Daily Cor i te "m'tters e 1x10 O 4/M Oisso e and 1 x)0 Grab Samp Oai ly Comoosite Entrain (Gamma E. 'rs) d -ases M H-3 lx10 Oail Composite Grass Alpha 1xl0

-8 Sr"89, Sr" 90 X Oaily Comoosite Fe" 55 1xl C. Set 1'n Pr ncipal Gamma 5x'0 Bas~in Grab Sample c Emi tte. 5 T 131 0 ST. LUCIE - VHIT 1 Amendment Ho. 5 9

TABLE 4. 11 1 (Continued)

TABLE NOTATION The LL is defined, for purposes of these specifica ions, as he liest conc t tion of radioactive material in a sample that will yie a net count, ab ve system background, ihat wi 11 be detected with 95,. obabi li ty with on probability of falsely concluding that a blank ervation represent a "real" signal.

For a partic la measurement system, which may include r ochemical seoaration:

4.66 sb E ~

V ~

2. 22 ' Y - exp(-Mt)

Mhere:

LLO is the "a priori'o er limit of ection as defined above, as picocuries per unit ma volume, sb is the s andard deviatl n of background coun ing rate or of the coun ing rate of a blank s le as appropriate, as counts per minute, E .is the counting efficie , as o nts per disintegration, V is the sample size i its of ma volume, 2.22 is the number disintegrations p r inute per picocurie, Y is the fractio radiochemical yield, e applicable, A, is he radi tive decay cons ant for the p r icular radionuclide, and At for e 'nmental samples is .the elapsed time t een sample collect'o , or end of the sample collection period, a time of counti Ty 1 values of E, V, Y, and At should be used in the a culation.

ST. LUCIE - UHjT 1 3/4 11-3 Amendment Ho. 5 9

TA""L"- 4. 11-1 (Cont;nued)

TABLE NOTATION comocsiie sampl is one in which the quantity of liquid samol

"" ortional to ." q ar,:i-.y of liquid was-'e discharoed ard th m hod of <<ampling emolcyed resulis in a specimen

'ich s .s en ativ of the liquids released.

whic'epre c- A batch re e e is ihe discharge of liquid was es of a discrete for analyses, each bat all isolat d,'

volume.

and hen Prs ihor" 'ixed sampling to a'ssure represen at'o sampling.

be A continuous releas i the discharge of li 'asies .of a nondiscre'e volume, e.g., from a v 1 e of a sysiem " a has an inpu" flow during the ccniinuous re'. ease.

e. The principal gamma eml ers i r the LLO specification appl'.es exclusively are the following ra uclides: Mn-54, Fe-59, Co-58, Co-60, Zn"55, Mo-99, Cs-134, C " "~41, and Ce-144. This'isi does not me n thai only ihe elide e to be deiecied and reported.

Other peaks which are mea r le and id t iable, together wiih he above nucl ides, shall a e identified a d eported.

f. Grab samples to be a' when there is confirme imary to secondary sysiem leakage i i ied by the air ej'ector rn'onit 'icating > 2x background.

g. If Com p one oolin g Water aciiviiy is>>m10 pi/ml, C p a weekiy gross ac iy on ihe in.ake Cooling Mater System ouilet to ure the

ac iv t'evel is < a 2x~0 pCi/ml LLO limii. if ICY is >2x1 Ci/ml, per.o m analysis in accordance wiih a Plani Con inuous Release on 's e.

ST. LUCIE - UNIT 1 3/4 11-4 Amendment iso. 5 9

0 V

L i'~ G CO'<0:TsQH FOR OPERATION

3. 11. 1.2 e dose or dose commitment to a MEMBER OF THE PUBLIC from radioactiv terials in liquid effluents released, from each react un ., to UHRESTRICTEO EAS (see Figure 5. l-l) shall be limited:

a. Ourin ny calendar quarter to less than or equal to mrems to the tot body and to less than or equal to 5 mrems any organ, and

b. Ouring any ndar year to less than or equal 3 mrems to the total body an o less than or equal to 10 m s to any all tim organ.'PPLICABILITY; At s ACiiGN:

- With: the'alculated .dos om the r ase of radioactive materials "

in 1:iquid'ffluents excee i any : the above limits, prepare and submit to. the Commission. w, n:-. :days--'pursuant=to- Specification 6.9.2,.-a.'Special Report whic ntifies the cause(s) for exceeding the limit(s) and'efines the ective actions to be taken to reduce the releases and rad c 'aterials in liquid effluents during the r emainder of t curre t calendar quarter and during the subsequent three calend uar ters, that the cumulative dose or dose commitment to an ividual fro ese releases is within 3 mrems to the total dy and 10 mrems any organ.

b. The provisions Specifications 3.0.3 an .0.4 are not applicable.

SURVEILLANCE RE UIR .. TS

4. 1 l. l. 2 Oos al cul ations. Cumulative dose contributions o 1 i quid effluen s fo ne current calendar quarter and the current cal r year shall be dete.mi in accordance with the methodology and parameters the CDCM at least on er 31 days.

0 ST. LUCIE - UtiIT 1 3/4 11-5 Amendment ."lo. 4'9, 69

E lg

'O'OACT 'l= =FFLUIENTS L C TD 4'ASTr TReAT cubi LI."i i.'ONOITI'ON FOR OPERAT:GN

3. 11. 1.3 e liquid radwas c treatment sys .em shall be OPERABLE. The priate porti of the system shall be used to reduce the radioactive .a er als in liquid wast s rior to their discharge when the projected doses d e .o the liquid ef,luent m the si e to UNRESTRICTED AREAS (see Figure 5. when averaged over 31 , would exceed 0.06 mrem ta the total body o .2 mrem to any argan.

APPLICABILITY: At al t mes, ACTION:

a. With the liquid ra a te treatment system in able for more than 31 days or with radi ive liquid waste b discharged without treatment and in exces the above limi , prepare and submit to the Commission within, 3 s;pursuant; pecification. 6.9.2 a Special Report which incl 'the'ol ng'.-information'.

l. Identifica ion of the i r ble equipment or subsystems ana thc reason for inoperabi

2. Action(s) akcn to r re t inoperablc equipment to OPERABLE status, and

3. Summary descrip n of action(s) a en to preven. a recurrence.

b. The provisions of ecifications 3. 0. 3 an . 0. 4 are not applicable.

SURVEILLANCE REQUIREH~

4.11.1.3.1 Dos ue to liquid releases to UNRESTRICTED AREA hall be projected at 1 t once per 31 days, in accordance with the 00 nless he liquid radwa . treatment system is being used.

4. 11. 1.3. The liquid radwas c treatment system shall be demonstra c CP R'B'y aper 'ng the liquid radwastc treatment system equipment for at 1 30 mi cs at least once per 92 days unless the liquid r adwcstc system h s been uti d ta process rad oac='.ve liquid effluen s Curing the previous 92 ~'.

ST. LUCIE - UNIT 1 3/4 11-6 Amendment No. ~/5~ 69

e

"~CTHE EFFLUENTS 3/". CAS OUS =, FLUc<TS OGSE RA)-

LIMITIYG CON TON FOR OPERATION 3.11.2.1 The dose te in UNRESTRICTEO AREAS due to radioa ' materials released in gaseous luents from the site (see Figure 5.. - ) shall be limited o the followi

a. For noble gases: Less than or equal to 50 rems/yr to the total body,and less tha r equal to 3000 mrem / r to the skin, and

b. For iodine"131, iodi culate form with hal'f-to .1500 mrems/yr to any

's

~33, tritium, greate an.

i d all radionuclides an 8 days: Less ~ban in parti-or equal APPLICABIL:TY: At al 1 times.

ACi:QN:

With the dose rate(s) exceedin e above lii s, immedIatel'y decrease the release rate to within the ab limit(s).

URV= L NCE REOUTREMEN

4. 11.2. 1. 1 The rate due to noble gases in gaseous e

- ents shall be determined to b ithin the above limits in accordance with t e methodology and parameter n the OOCM.

4. 11. 2. 1. he dose rate due to iodine-131, iodine"133, tritium, d all radionu 'des in particulate form with half-lives greaterthan 8 in gaseo effluents shall be determined ~o be within the above limits acc ance with he methodology and parameters in the OOCM by obtaini r - esentative samples and performing analyses in accordance wi th the pling and analysis program spedified in Table 4. 11-2.

ST. LUCIE - UNIT 1 3/4 11-7 Amendment No. 5 9

TABLE 4.

RADIOACTIVE GASEOUS WASTE SAHPLING AND ANALYSIS PROGRAH Hinimum Lower Sampl ing Analysis Type of Lim'etect n LD) o Gas eou ease Type Fr equency Frequency Activity Analysis I 1) ~

I P

A. Waste Gas Each Tank Each Tank Principal Gamma Emitters. 1 xl 0

'Tank Grab Sam le P P b b B. Containment Purge Purge Each Purge Principal Gamm tters e 1 xl 0 Gr Sam H-3 1 xl 0 C. (1) Plant Vent 4/H 4/H Prin Gamma Emitters lxl0 (2) Fuel Building Grab Vent Sample (3) Steam Generator Blowdown H-3 1 xl 0 Buildin Vent d c D. All Release Types Continuous 4/H I-131 1xl0 as listed in A,B, Cha C above.

d c Continuous 4/H Prin 1 Gamma Emitters 1 xl 0 Particulate ( I-131, ers)

Sam le d

C nuous H Gross Alpha 1 xl 0-11 Composite Particulate Sam le d

Continuous Sr-89, Sr-90, lxl0 O Composite Particulate Sam le d

Continuous Noble Gas Noble Gases lxl0 Honitor Gross Beta or Gamma

TA8L" 4. 11-2 (Continued)

TA8LE NGTATiON h LLO is defined, for purposes of hese speci;ica ions, as the sma t c c ntration of radioactive material in a sample that will yield n t cou t, aoove system background, that will be detected with 95~ pr ility with n 5.o probability of falsely concluding that a blank obs zion repres t a

" real" signal. chemical For a part'c lar measurement system, which may include rad o separation:

4.66 sb ZLD =

2. 22 ~

Y ~

exp(-Ut)

Mhere:

LLD is the "a priori wer limit of ction as defined above, as picocuries per unit ma s r volume, sb is he standard deviat n of ackground counting rate or of counting rate of a blank s

'he e as appropriate, as counts per minute, is the courting effici c as ts per disin egration,

'iis E ,

V is the sampIe size of mas o volume, 2.22 is the number o disintegrations pe nute per picocurie, Y i s the frac'. 1 radi ochemi cal yi el d, wh plicable, A, is the ra l ctive decay constant for the par i lar radionuclide, and tt for e ironmental samples is the elapsed time bet sample coll on,, or end of the sample collection period, an ime'f co ng ical va'lues of E, V, Y, and ht should be used in the cal u tion.

ST. LUCIE - UNIT 1 3/4 11-9 Amendment i'lo. 5 9

I V,

0

TABLE 4.11-2 Continued TABLE NOTATION

b. pling and analysis shall also be performed fol.lowing shutdow artup, o THERMAL POWER change exceeding 15$ of RATED THERMAL POWE w hin 1 h unless (1) analysis shows that the DOSE EQUIVALENT I- concentra-tion e primary coolant has not increased more than a tor of 3; and (2) the e gas activity monitor shows that effluent vity has not increased ore than a factor of 3.

c. 'amples shall b anged at least 4 times a mont d analyses shall be completed within urs after changing (or a removal from sampler).

Sampling shall also erformed at least on er 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each down, startup or RfPAL, POWER change exceeding 15% of RATED THERMAL POW within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing I-131 concentration in the prs

'1) hour and an lyses shall be completed ss shows that the DOSE EQUIVALENT ant has incr'eased more than a factor of 3; and (2) the noble g tivity monitor shows that effluent activity has increased by more a factor of 3. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, th rres ing LLDs may be increased by a factor of 10.

d. The ratio of the sampl ow rate to the sam stream flow rate shall be known for the tim riod covered by each do or dose rate calculation made in accordance Specifications 3.11.2-.1, .2.2 and 3.11.2.3.

principal t'e followingfor

e. The a emitters which the LLD specifs ion applies exclusively radionuclides: Kr-87, Kr- , Xe-133, Xe-133m, 35, and .Xe-138 for gaseous emissions and Mn-5 e-59, Co-58, Co-60, emiss .

5, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for pa This list does not mean that only these nuclides ar

'late be det ed and reported. Other peaks which are measureable and iden t ther with the above nuclides, shall also be identified and repor able, ST. LUG IE - UNIT 1 3/4 11-10 Amendment No. 5 9

":O'CTiV= ii'ENTS 0" . NC""L= "'SES i". ON -OR OV-SATION

3. 11. 2. 2 The > dose due to noble gases released in gaseous eff u ts, from each reac or un't, to areas at and beyond the SITE BOUNDARY (se F'gure 5.~-1) s'hall be limited o the ollowing:

a. During any endar quarter: Less than or equa t 5 mrads for gamma radiat'nd less than or equal to 10 a for beta radiation and,

b. During any calend ear: Less than or q 1 to 10 mrads for gamma radiation and less h or equal to 20 r ds for beta radiation.

APPLIC'BILITY: At all times.

ACTION

a. Mith the. calculated air dos radioactive. noble gases in gaseous effluents,- exceeding,.any o =t e. a o limits, prepare and submit to the Coin)is'sf'on~withiQp ."3 ',-d sou u 'nt to-:-.Specifi'cation 6.9';:. a.

Specia1'Report which e i'fies"the s'e'(s) for exceeding the limit(s) and define t corrective a ns to be taken to reduce the releases and e roposed correctiv tions to be taken to assure that subs q nt releases will be ompliance with the above limits.

b. The prov's's of Specifications 3.0.3 and 3.0 ~ re not applicable ~

SURV ILLANC < IREMENTS

. 11. .2 Dose Calculations. Cumulative dose con.ributions for the quar:er and current calendar year shall be determined in acc ren'al d . -nce h he methodolgy and parameters in the ODCN at least once per 31 day ST. LUG IE - UNIT 1 3/4 11-11 Amendment No. 54 ~ 69

'.CACTiVE EFFLUENTS OCS iCOjNE-1.1. iQOi.NE-i33, TRi71UH, ANO RAO.QN"CLiC AS jN PART, L 7 L

" "- "NO TiGN FGR GP~RATiQN 3.11.2.3 Th se to a HEHSER OF THE PUBLIC from iodine-131, iodi tri:ium, and a adionuclides in particulate form with half-live reater than 8 Cays in gaseou fluents released, from each reactor unit to eas .at and beyond the SiTE B N RY, (see Figure 5.1-1) shall be limited . the follow'ng:

a. During any ndar quarter: Less than or equal 7.5 mrems to any organ and,

b. During any calen r ear: Less than or eq to 15 mrems to any or gan.

APPL.'CAPiLITY: At all times.

ACT10N:

Mith the calculated dose from tritium, and.radionuclides in than,.8'jdays.'.",*in gaseous prepare "and submit to'h'".

eff 's release of iodine -131, iodine-133, cul'ate form with half-lives greater ceding.any of the above, limits, iss$ o,",. thi'ni:;30-'days;", pursuant to Specification 6.9.2, exceedi'ng the limit an a S al: Repo'r t t i'deritifies'the'cause(s) for fines the co e tive actions that have been taken to reduce the r ases and the pro d corrective actions to be taken to assure tha ubsequent releases w'1 be in compliance with the above limits.

b. The provisi of Specifications 3.0.3 and 3.0. a not applicable.

SURVEiLLANCE REQ MENTS 4.11. 2. 3 ulative dose contributions for the current calendar quar and current endar year for iodine-131, iodine-133, tritium, and radionuc i s in par late form with 'half-lives greater than 8 days shall be determin in ac dance with the methodology and parameters in the ODCM at least onc per days.

ST. LUCIE - UNIT 1 3/4 11-12 Amendment No.p),69

m RADIOACTIVE EFFLUENTS G EOUS RAOWASTE TREATMENT L I NG CONDITION FOR OPERATION 3.11. 4 The GASEOUS RAOWASTE TREAT11ENT SYSTEM and the VENTH.ATI'ON EXHA TREATM T YSTEti shall be OPERABLE. The appropriate portions of the G JS RADWASTE R TMENT SYSTEM shall be used to reduce radioactive materia in gaseous wa te rior to their discharge when the projected gaseous ef ent air doses due t ga eous effluent'eleases from the site to UNRESTRICT AREAS (see Figure 1- , when averaged over 31 days, would exceed 0.2 ad for gamma radiatio a 0.4 mrad for beta radiation. The appropria portions of the VENTILATIOtt XH UST TREATt1EttT SYSTEM shall be used to r ed radioactive materials in gas s aste prior to their discharge when th oj'ected doses due to gaseous eff1 en releases from the site (see Figure -1) when averaged over 31 day wo ld exceed 0.3 mrem to any organ.

APPLICABILITY: At all 'me .

ACTION:

a. 11th, the'ASEOUS'A A E. TREATNENT S M and/or the VENTILATION

- more"than'31I EXHAUST'REATMENT'SY E "inoperable."- days oi %i:th.>.

gaseous';wasti.-being.di ch ged'-wit t. treatment and fn excess oT=

the. above.=lilsits*;: prepa ',.a O,'so . to: the Cossaissibn within 30 days, pursuant to. Specifi at n,9'.2-; a. Special'eport which includes- the.;;fol Towing'!=inrf 'n'.

Identification of th nop ab e equipment or subsystems and the reason for the operab

2. Action(s) taken restore the no rable equipment to OPERABLE status, and

3. Summary de ption of action(s) ta n prevent a recurrence.

b. The provisio of Specifications 3.0.3 and 0. are not applicable.

SURVEILLANCE RE UIR ITS 4.11.2.4.1 Dos due to gaseous releases from the site to U. E RICTED AREAS shall be proj d at least once per 31 days, in accordance w> h e ODCH unless the OUS RADWASTE TREATMENT SYSTEM is being used.

4.11.2.4. he GASEOUS RADWASTE TREATMENT SYSTEt1 and VENTILATION HA ST TREATHE YSTEt1 shall be demonstrated OPERABLE by oper ating thy GA OU RAD-WASTE ATMENT SYSTEH equipment and VENTILATION EXHAUST TREATMENT SY TEt1 equip-ment at least 30 minutes, at least once per 92 days unless the app pr> te sys has been utilized to process radioactive gaseous effluents during the pr ious 92 days.

ST. LUCIE - UNIT 1 3/4 11-13 Amendment No. 4'Ss 69

J RADIOACTIVE EFFLUEHTS 11.3'OL~D 8"DIOACTIVE PASTE L 'MIT NDITIQN FOR OP RATION

3. ll. 3 Ra tive bead resins shall be Cexatered, as appropriate, in - r-transpor<<'

dance with.th requirements du in the disposal si-e.

OCESS CONTROL PROGRAM ransit, and to meet shipping and disposal site requirements when re 'd at APPLICABILITY'tal t'es.

ACT ON:

Mith dewatering not e ting disposal stt d shipping and transpor tation requirements, s end shipment i he inadequa ely Cewa~ered bead resin and correct e ROC~SS C OL PROGRAM, the procedures and/or the dewatering sys m as n sary to prevent recurr ence.

b. Mith dewatering not performe accordance with the PROCESS CONTROL PROGRAM, (1) i f the dewater csin has not already been shipped for disposal, verify eac l.

nta ln ensure that it meets burial around and shipping r ,u'ment s an take appropr-'a e adminis-trative action to p v nt recurrence. 0 C. The provisions f pecifications 3.0.3 an 3..4 are not applicable, SURVEILLANCE REQU HTS 4.3.1.3 Pr o . to disposal, each container of radioac ive bead re 'n shall be tested r free standing liquids in accordance with the PROCESS CO R PROGRAM to as that it mee s shipping, transportation, and disposal site c 'rements.

ST. LUCIE - 'UNIT 1 3/4 11-16 Amendment Ho.5 9

1 OACTIVE EFFLUENTS 3/4. 1 4 TOTAL DOSE LIMITI ONDITION FOR OPERATION 3.V..4 Th a nual (calendar year) dose or dose commitment to any MEMBER OF T PUBLIC due t eleases of radioactivity and to radiation from uranium fuel cycle sources h ll be limited to less than or equal to 25 mrems to the t body or any org n, except the thyroid, which shall be limited to less th or equal to 75 mrem APPLICABILITY: At times.

ACTION:

a. With the calcula e doses from the release of radio ive materials in liquid or gase effluents exceeding twice the mits of Specifi-cation 3.11.1.2a, 1 .1.2b, 3.11.2.2a, 3.11.2.2 3.11.2.3a or 3.11.2.3b, calculati shall be made includin rect radiation contributions from th r actor units and from tside storage tanks to determine whether the a limits of Specif'ion 3.11.4 have been exceeded'..=If'such t's th c se prepare'an . ubq$ t 'to the Comtssgon within 30 days, pursuant t ecificatio .9.2, a Special'Rexsport-;.that defines the corrective acti o be tak to reduce subsequent releases to prevent recurrence of exce d g th ove limits and includes the schedule for achieving conforma c w the above limits.. This Special Report, as defined in 10 CFR Par 05c, shall include an analysis that estimates the radiation expo (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources ing all effluent pathways and direct radiation, for the cale r ye r that includes the release(s) covered by this report. It 1 also cribe levels of radiation and concentrations of radioacti material v lved, and the cause of the exposure levels of concen ions. If th timated dose(s) exceeds the above limits, and of 40 CFR Part 190 has if e release condit o resulting in violation already been corr d, the'pec.'al Report shall include a reque for a variance in acco ce with the provi-sions of 40 CFR Par 0. Submittal of the rep is considered a timely request, an variance is granted until s a f action on the request is compl

b. The provisio of Specifications 3.0.3 and 3.0.4 are n t pplicable.

SURVEILLANCE RE UI NTS 4.11.4.1 Cumul ve dose contributions from liquid and gaseous effluen s hall be determined accordance with Surveillance Requirements 4.11 ~1.2. 4.1 2.

and 4.11.2.3 nd in accordance with the methodology and parameters in the 0 CM.

4.11.4.2 mulative dose contributions from direct radiation from the reacto units a from radwaste storage tanks shall be determined in accordance with the m dology and parameters in the ODCM. This Surveillance Requirement shal be r ired only in the event the above Action a. requires the applicable al ations.

T. LUCI E - UNIT 1 3/4 11-17 Amendment No. 5'9,69

1 3/4.11 RADIOACTIVE EFFLUENTS BASES 3 . 1.1.1 CONCENTRATION specification is provided to ensure that the concentration of io-active rials released in liquid waste effluents from the site to STRICTED AREAS wil e less than the concent'ration levels specified in 10 CF P rt 20, Appendix B, ble II, Column 2. This limitation provides additio 1 assurance that the lev of radioactive materials in bodies of water .ou i e the site will result in e osures within (1) the Section II.A. design j ctives of Appendix" I, 10 Part 50, to an individual, and (2) the 1 ,i of 10 CFR 20.106(e) to the lation. The concentration limit for i olved or entrained noble gases is base on the assumption that.xe-135 is h controlling radio-isotope and its tlPC i ir (submersion) was converted o n equivalent concentra-tion in water using th thods described in Intern i al Commission on Radio-logical Protection (ICRP blication 2.

3/4,11.1.2 DOSE This specification is prov'o imp nt the requirements of Sections II.A. III.A and IV.A of art 50. The Limiting Condition-for Appendix Operation implements the guides se

, 10 C

'n Section II.A of Appendix I. The ACTION statements provide the requir perating flexibility and at the same time implement the guides set fort i ction IV.A of Appendix I to assure that the releases of radioactive a eria n liquid effluents will be kept "as low as is reasonably achie b e." Th se calculation methodology and parameters in the ODCN impl n the requir ts in Section II,I.A of Appendix I that conformance with th g des of Appendi be shown by calculational procedures based on mode d data, such that h actual exposure of a HEllBER OF THE PUBLIC through p priate pathways is un ly to be substantially underestimated. The q tions specified in the.00 i for calculating the doses due to the actual r se rates of radioactive mater'a s in liquid effluents are consistent wi e methodology provided in Regula y Guide 1.159, "

"Calculation of ual Doses to lian from Routine Releas f Reactor Effluents for the Purpo e f Evaluating Compliance with 10 CFR Part Appendix I,"

March 1976 d egulatory Guide 1.113, "Estimating Aquatic i ersion of Effluents r Accidental and Routine Reactor Peleases for t urpose of Impleme i g Appendix I," April 1977.

T s specification applies to the release of liquid effluents om each r c r at the site. For units with shared radwaste treatment syst the i id effluents from the shared system are proportioned among the un t aring that system.

ST. LUG IE - UNIT 1 B 3/4 ll-l Amendment No. 5 9

~c gl< ~ LU~N 5 l% p

(

11.. ~ rOU D MASTE TREAT) EHT The 0 ~ILx f the liouid radwaste treatment system ensures will be a ab r use whenever liquid effluents requ ir - nt th'vsiem prior to relea e ~o i vir ent. The .requirement iha . e - opriate por ions of this system be wh ~ eciried prov'" a~ ance -hat ihe releases or l adloactive materials is reasonably achievable". This spec>> ')o liq e = en -ill be kept "as low as Dlements the requirements of

.10 CFR Par 50;36a, Cene", al Desi Par. 50 and the design ob ve

'overning

'n rl 'on in Seciion .

or e.',dix A o 10 CFR oi " end'.x I to 10 CFR Part 50. The specif i ihe use of app "iai ortions of the licuid' rad - ie atment system were specified as a suiic e ~ tion of the dos jectives set forth in Section~iI.A o Appencix, r

?-"- = r liquid erfluents. I) 3/".. 11. 2 CASEOUS EFFLUEHTS h'pecification is provided to ensure ihai ihe dose't any time - nd bevond ITE BOUNDARY from gaseous effluents f",om all units on he will be w h the annual dose limits of 10 CFR Part 20 to UNR STRI AREAS.

The arnual e imits are the doses associated with ihe concent 'ons of 10 CFR Pari 20, p ndix B, Table II, Column . These limits ide rea onable assura e hat radioactive material discharged i seous erfluents will rot resuli in t osure of a MEHBER OF THE 2UBLI i an UNRFSTRICTED AREA, eiiher within or u de ihe SITE BOUNDARY, tc - 1 averaoe concentra-tiors exceeding the limit s cified in Appendix B - ie II of 10 CFR Part 20 (10 CFR Part 20.106(b)). Fo BERS OF. THE PUB ho mav a times be wi ihin the SITE BOUNDARY, the occupan o that HERB~ THE PUBLIC will usually be suf=.icieni'ly low to.compensate fo a inc- ~ in the atmospheric diffusion facto above that for the SITE BOUN . e speci f i ed re i ease rate 1 '.mi is restrict, at all .iimes, ihe correspon -mrna and beta dose rates above background to a HEHSER OF THE PUBL - o be ond the SITE BOUNDARY io >ess ihan or equal to 500 mrems/year e tota or "o less than or equal to 3000. mrems/year io ihe skin.-

ihe corresponding ti e release ra.

d dose rate above bo

'ts also resirict, ai ound to a child via the all'imes, inhalaiion paihway to le an or equal io 1 00 mr ar.

The required. ion capabilities for radioac ive e. 'als in gaseous was e sa-ples ar ul ated in terms of ihe lo~er limits of 'et iion (LLDs).

Deiailed disc s n of the LLD, and other de ec ion limits can e und in HASL Proce r Hanual, HASL-300 (revised annually), Currie, L. . mits or Guai '.- ve Deteciii on and guanti iative Determination - npplicai' i Rao io e 5 iry," Anal . Chem. 40, 586-93 (: 6B), and Hartwell, J. K., o ie ion L ~ i fcr Raoioanalyti cal Counting Technicues," Atlan ic Riciifield Hanf a r ary Repori ARH-SA-2 5 (June 1075).

ST. LUCIE - UNIT I B 3/4 l~-2 Amendment Ho. g g

RADIOACTIVE EFFLUENTS BASES This specification applies to the release of gaseous effluents from all r tors at the site. For units with shared radwaste treatment systems, t gas o s effluents from the shared system are proportioned among the units shar that system.

3/4.11. DOSE - NOBLE GASES This s e ification is provided to implement the requirements Sections II.G, III.A a IV.A of Appendix I, 10 CFR Part 50. The Limiti Condition for Operation impl ts the guides set forth in Section II,B of A endix I. The ACTION statement ovide the required operating flexibility d at the same*

time implement th g ides set forth in Section IV.A of App >x I to assure that the releases o dioactive material in gaseous effl ts to UNPESTRICTED AREAS will be kept "a w as is reasonably achievable." he Surveillance Requirements implement h requirements in Section III of Appendix I that conformance with the gui e of Appendix I be shown b alculational procedures based on models and data s c that the actual expos of a MEMBER OF THE PUBLIC through appropriate ways is unlikely t e substantially under-estimated. The dose calculat'o methodology an rameters established in the ODCM for calculating the doses u to .the actu release rates of radioactive noble gases in gaseous effluents consist with the methodology provided in Regulatory Guide 1.109, "Calcu t n of ual Doses to Man from Routine Releases of Reactor Effluents for t ur e of Evaluating Compliance wi th 10 CFR Part 50, Appendix I", March 19 6, for Estimating Atmospheric Transpor a t d Regul'atory Guide l.ill, "Methods ispersion of Gaseous Effluents in Routine Releases from Light-Water Coo e ctors", Revision 1, July 1977.

The OQCH equations provided for det inin e air doses at and beyond the SITE BOUNDARY are based upon the orical v age atmospheric conditions or real atmospheric conditions.

This specification appli to the release o g eous effluents from each reactor at the site. For u s with shared radwas eatment systems, the gaseous effluents from the ared system are proport on d. among the units that system. 'haring 3/4.11.2. 3 DOSE - IO -131, IODINE-133, TRITIUM AND 0 NUCLIDES IN PART I CU FORM

~

r This specifi ion is provided to implement the requireme ts of Sections II.C, III.A and .A of Appendix I, 10 CFR Part 50. The Limiti ~ nditions for Operation e the guides set forth in Section II.C of Appendi I. The ACTION stat ts provide the required operating flexibility and a th same time impl the'guides set forth in Section IV.A of Appendix I to s re that the AREAS metho w'e eases of radioactive materials in gaseous effluents to UNR S ICTED kept "as low. as is reasonably achievable." The ODCH calc a onal pecified in the Surveillance Requirements implement the requirem t in S ion III.A of Appendix I that conformance with the guides of Appendix I LUCIE - UNIT I B 3/4 11-3 Amendment No. 5 9

RADIOACTIVE EFFLUENTS BASES a

unl 'o1 exposure be of a MEMBER OF THE PUBLIC-through appropriate pathways substantially underestimated; The ODCM" calculational ogy a 'd. arameters'or calculating the doses due to the actual rele of the u gect materials are consistent with the methodology prov' in odol-ates Regulator, 5 ide 1.109, "Calculation of Annual'oses to Man fro o R ctor Effluents for the Purpose of Evaluating Co p ance with tine'eleases 10 CFR Part, ppendix I", March 1976, and Regulatory Gutd l. 11, "Methods for Estimating t spheric Transport and Dispersion of Gas u Effluents in.

Routine Rel eases r Light-Mater-Cooled Reactors", Revi o 1, July 1977.

These equations al rovide for determining the actua d ses based upon the historical average a o heric or real meteorologica c ditions. The release rate specifications fo dine-131, Iodine-133, tri i , and radionuclides in particulate form with ha f ives greater than 8 d y are dependent upon the existing radionuclide path a g to man, in the a e at and beyond the SITE BOUNDARY. The pathways tha w4 e examined in h development of these calcula-tions were: (1) individual i a tion of a b ne radionuclides, (2) deposi-tion of radionuclides onto gree 1 fy ve t ion with subsequent consumption by man, (3) deposition onto grass a a w re milk animals and meat producing animals graze with consumption of t il and meat by man, and (4) deposition"..

on the ground with subsequent exposu . man.

This specification applies e re ea e of gaseous effluents from each reactor at the site. for unit w' share ra waste treatment systems, the gaseous effluents from the s r system are r ortioned among the units sharing that system.

3 4.11.2.4 GASEOUS RAD S TREATMENT

. The OPERABILIT o the GASEOUS RADWASTE TREATMEN Y EM and the VENTILA-TION EXHAUST TREA E SYSTEM-ensures that the systems w 1 e'available f'r use whenever. ga ou effluents.requir.e treatment prior environment. e equirement that the appropriate portions to'l f se to the ese systems be used; whe s cified, provides reasonable assurance tha- th r leases of radioactiv m erials in gaseous effluents will be kept "as low s s e" This specification implements the requirements f reason-'bly ach v Part 5 .36, General Design Criterion 60 of Appendix A to 10 CFR the'i objectives given in Section II.D of Appendix I to. 10 CFR P Pa,t 0 CFR and 0..

Th sp ffied limits'overning the use of appropriate portions of the s t s w e pecified as. a suitable fraction of the dose design ob'jectives set f r~ ~ h ~ \

3/4.11;2.5 EXPLOSIVE GAS MIXTURE

-.This. specification iq. provided. to ensur e that the concentration of poten-'..

tially'xplosive: gas mixtures contained'in the waste gas holdup system is main-tained below the flammability" limits af hydrogen and. oxygen. Maintaining the.

concentration. of hydrogen and'xygen below. their flammabil'ity limits provides assurance that the'eleases of radioactive. materials willLbe controlled in .':

conformance with the requirements to: TO'CFR'art 50'...', '

r ST .

~

LUCIE. -'NEl,'T: ., '

3/4 11-4, 7

~,

of: General Design Criterion 60: of A'ppendix A

\

Amendment No 5 9 h

RAOIOACTIVE 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."

T s specification implements the requirements of 10 CFR Part 50.36a Gener sign Criterion 60 of Appendix A to 10 CFR Par t 50. The proces ram-eters i 1 ed in establishing the PROCESS CONTROL PROGRAM may include not limit t waste type, waste pH, waste/liquid/solidification age t are atalyst ratios, was o content, waste principal chemical constituents, 1

mixing and curing times.

3/4.11.4 TOTAL 00 190 This that specificatio have been i rovided to meet the dose incor ra ed into 10 CFR Part 20 b li ions of 40 CFR Part FR.18525. The speci-fication requires the prepa at n and submittal of ecial Report whenever the calculated doses from plant g e ted radioactive luents and direct radiation exceed 25 mrems to the total bo any organ, ept the thyroid, which shall be limited to less tha'n or equal mrems. r sites-containing up to four reactors,.it is highly unlikely tha t re ant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 0 Part 190 if the individual reactors remain within twice the dose design ob' es of Appendix I, and if direct radiation doses from the reactor uni n ou ide storage tanks are kept small.

The Special Report, will describe a r se o c 'on that should result in the limitation of the annual dose to MBER OF

" BLIC to within the'0 CFR Part 190 limits. For the purp of the Specia R ort, it may be assumed that the. dose. commitment to the M R OF THE PUBLIC fr o er uranium fuel 'cycle sources is negligible, wit e exception that dose nt ibutions from other nuclear fuel cycle facil' pleted'~ s at the same site or withi a adius of 8 km must be considered. If th e to any-MEMBER OF THE PUBLIC s e imated to exceed the requirements of FR Part 190, the Special Report wit a equest for a variance (provide e release conditions resulting in violat n f 40 CFR Part 190 have not air y been corrected), in accordance with the pr is ons of 40 CFR Part 19 . and 10 CFR Part 20.405c, is considered to be a im y request and fulfill e requirements of 40 CFR Part 190 until NPC staff'act' 's com-variance relates only to the limits of 40 CFR Part 190, a es not app n any way to the other requirements for dose limitation of 10 F Part as addressed in Specifications 3.11.1.1 and 3.11.2.1; An individ 1 s not sidered a MEMBER OF THE PUBLIC during'any period in which he/she is 4

ST. LUCIE - UNIT 1 B 3/4 11-5 Amendment No. 5 9

.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4 1 .1 MONITORING PROGRAM LIMIT CONDITION FOR OPERATION 3.12.1 T e adiological environmental monitor ing program shall be condu as specified > able 3.12-1.

APPLICABILITY. At all times.

ACTION:

a. With the a iological environmental monitoring progr not being con-ducted as ified in Table 3.12-1, prepare and s t to the Commission, n the Annual Radiological Environmen a Operating Report required by S e ification 6.9.1,8, a descripti f the reasons for not conducting program as required and the ans for preventing a recurrence.

With the confirmed 'Vel: of 'radioactivit .the result of:-plant,.

effluentsdn-'an-envi 'ntal sampling d'um at a specified location exceeding-the reporti - evels-of- Tabl 12%.when ayeyaged over. any, calendar quarter;, prepa e and submit o'he, Commission wit5in,30~days, purssint-to'-Specificatio = .9;Z,--a-cause(V)'.i'ol 'exceeding:th~

to-'be--taken to reduce radio c iv

'it(s -'-

ial=Repopt-.that..idegtifieZ-.the nd-defines the-corrective-'actions fluents so that the potential annual dose to a MEMBER OF T limits of Specifications 3.11 than one of the radionuclide sampling medium, this repo

'le ha IC is less than the calendar year

, 3.11.2.2, and 3.11.2.3.

e 3.12-2 are detected in the submitted if:

When more concentration 1 + concen r tion 2 + ... > 1.0 r eporting 1 evel reportin vel 2 When radionuclides er than those in e 3.12-2 are detected and are the result of nt effluents, this r rt shall be submitted if the potential an dose to a MEMBER OF T UBLIC is equal to or greater than t alendar year limits of Sp ications 3.11.1.2, 3.11.2.2 and . .2.3. This report shall inc u e the methodology for calculating cumulative potential dose cont tions for the calendar y from radionuclides detected in env r nmental samples and can b etermined in accordance with the meth logy and parameters in the . This r eport is not required if the m red level of radioa vity was not the result of plant effluents; h wever, in such an e , the condition shall be reported and describ in the Annual Ra o ogical Environmental Operating Report.

C ~ i h milk or broadleaf vegetation samples unavailable fro e or more the sample locations required by Table 3.12-1, identify o ations

~A c irmatory reanalysis of the original, a duplicate, or a new sample a be

'd able, as appropriate. The results of the confirmatory analysis shal o pleted at the earliest time consistent with the analysis but in any case thin 30 days.

ST. LUCIE - UNIT 1 3/4 12-1 Amendment No. ~g)~))

j J

0 IOLOG ICAL ENV IRONNENTAL MONITORING L T G CONDITION FOR OPERATION Continued ACTIONl: o i need) for ob 'n' replacement samples and add them to t r iological environme oni toring program wi thin 30 days. h specific 1 oca-tions from w 'mples were unavailable may e deleted from the monitoring o am. Pursuant to,Speci on 5.9.1.10, identify the cause of the u v lability of samp d identi'fy 'the new locat'ion(s)'.for, obta n "replacemen es.": in'- the next Semiannual Radioa'ctive=E'ffl."uent Re "s ".'Repo -"'also>include-'n" the report a rev'ised figure(s) and table o OOCH reflecting the new location(s).

d. The provisions of Speci c ons . . and 3.0.4 are not applicable, SURVEILLANCE RE U 4.12.1 Th r ological environmental monitoring samples shall b lected pursuan able 3.12-1 from the specific locations given in the ta nd figu in the OOCH, and shall be analyzed pursuant to the requiremen T .12-1 and the detection capabilities required by Table 4.12-1.

ST. LUCIE - UNIT 1 3/4 12-2 Amendment No, f/9',"g '

C e

TAI3LE 3.12-1 I

IIRDIOI.OGICRL ENVIIIOHIIEN1AI. HONITOfllNG PIIOGIIAH n

fR I

Number of itepresentative Exposure Path Samples an>>>'.

S p1 L Collection Fre uency of Anal sis D I IIECT. RADIATION Z7 llonitoring Locations CoALinuous monitoring Gannna ex t raLe-with samp)~ collection quart quarterly

2. A I IIDOIIHE Iladioiodine and 5 Locations Continuous sampl Ratlioiodine Fil ter:

Particulates operation wit sa le 1-131 analysis weekly.

collect,ion ee , or re fr >e y if Part. IclllaLc Fi 1 tcr:

ed y dust loading Gross bcL< radioactiviLy analysis > 2d hours following. a filLcr change

. h) analys>s Gamma 1sotop))

of composite" (by locaLion) qual Lcrly

3. WATEIIDOIIHE

a. Surface h) cat.ion Weekly Ga n isotopic h) h Lri titan 3 anal week ly Galllma i soL h) h Lr i t. Ium 1 Location Non thly O analyses mont b Sc ment. from 2 Loca ti ons Semi an~u~a 1 ly Gamma isoLoliich) al Is shoreline semiannually

'N TAOLE 3. 12-1 Conl.i t>tted IInnlOLOGi chL EHVInOHIIEHTAI. I IOH I TOII IHG>>IIOGIInH')

Hitmber of Acprcsct> La L'i ve tI)

>> c>>athway Samples anil Salllfll t lt(J all(l Typi n rcq<<cttcy a ll( ale b) c) Col lcctiott Frequency 1 sis I

1HGEST

a. Fislt and Invertebrates

1. Crustacea 2 Locations ital ly Cialimla i so Lop i c Ii) ana lyses semiannually

. Ii)

2. Fi sh 2 Locati oils ital ly Gamma isotopic ana1yses semiannually

b. Food Products 4J

l. Oroad 1 Locations 1) Honthly wl>en ttlllia 1 so top 'I c I>)

all(l vcg I avai1 able nalyscs montlt ly tO i I I I

I

A I

p' C'

TABLE 3, 12-1 (continued)

TABL'E NOTATiON Dev'a ions are permitted from tale required samrplino schedule iis specir s are btainable due to hazardous corditions, eascnal unavai'.abilit mal i un r. on of automati c sampl i ng equipment or other 1 egi T imate re s.

If spec ns are unobtainable due to sampling eouiment rrsal suncti n correctiv ction shall be taken prior to the end of the next s- . ing period. A 1 deviations from the sampling schedule shall be do ented in the Annua adiolooical Environmental Opera'ting Report pur ~nt '

Speci ication 9.11.1.

b. Specific paramet of distance and direction sector >ro he centerline of one reactor, a additional description where perti i, shall be provided for each s le location in Table 3.12-1 in able-and iioure(s) in the ODCM.

C. At times, it may not be ssible or prac icable continue t'o obtain samples of the media of ice at the most desi location or time. In these instances suitable a t rnative media an ocations may be chosen for the particular pathway in q tion and aporo r ate substitutions made within 30 days in the radiolo 1 al envi ron al monitorino, program.

'he ollowing definition of freq e cies all apply to Table 3.12-1 only:

~Weekl - Hot less than once per cal r week. A maximum in erval of 11 days is allowed between the coll 'on of any two consecu-.ive samples.

2 of not less than 7 days betwee ample co ctions. A maximum interval of 24 days is allowed between co ction of a two consecutive samples.

~Monthl - Hot less than on per calendar non h with an interval of not less than 10 days betwee ample collections.

~0uarterl - Hot less n once per calendar quart

-2 p1

• 2 . 1

' 2 J 2 and (July 1 - De er 31).. An interval of not less i 30 days will be provided bet n sample col,lections.

The frequenc f analyses is to be consistent with the sam collection frequency.

e. One or instruments, such as a pressurized ion chamber, fo 'asuring and re o ding dose rate continuously may be used in place of, or >

addi to, integrating dosimeters. For purposes of this table, the luminescent dosimeter (TLO) is considered to be one phosphor; . o or phosphors in a packet are considered as two or more dosimeters.

IE - UNIT 1 3/4 12-'5 Amendment No. 5 9

TABLE 3.12-1 Continued TABLE NOTATION efers .to normal collection frequency.. Nore fr equent sample coll on i ermitted when conditions warrant.

g. Air. n particulate sample filters are analyzed for gros ta hours or more after sampling to allow for r thoron radio-'ctivi n and daughter c . In addition to the requirement for mrna isotopic on a composite m e a gamma isotopic ss also requir or each sample having a gross e radioactivity which is > l. i/ms and which is also > 10 times t t f the most recent contr sample.

h. Gamma isotopic analysi ns the ident ation and quantification of gamma-emitting radionucli s hat ma attributable to the effluents from the facility.

i. Atlantic Ocean, in the vicini t public beaches along the eastern shore of Hutchinson Island the . ucie Plant (grab sample).

j. Atlantic Ocean, at a ion beyond infl n from plant effluents (grab sample);

k. Discharges fro e St. Lucie Plant do not influe e rinking water or ground wate hways.

1. Sample broad leaf vegetation grown nearest each of tw fferent off ocations of highest predicted annual average groun el 0/g.

a ne sample of similar broad leaf vegetation at an availabl ation 30 km distant in the least prevalent wind direction based upon istorical data in the ODCN.

ST. LUCIE - UNIT 1 3/4 12-6 Amendment No. 5 9

TABLE 3. 12-2 I

AEPOllTING LEVELS FOft llRI)IORCTIVITY CONCENTllAI IONS IN ENVIBONHENTRL SRtll'l.ES.

n Pl Reporting Levels t Airborne Particulate Fish 'Mi 1 k .

od Products Anal ys i s (p or. Gases (pCi/ma) (pCi/kg, wet) (pCi/a) (pCi/kg, wet)

II"3 30,000" Hn-50 1,000 30,000 I'e-59 400 '10,000 Co-50 1,000 30,0 Co-60 0 0 ln-65 300 20,000 lr-Nb-95""" '00 I-131 0.9 100 Cs-131 30 1,000 60 1,000 Cs-137 50 2,000 70 2,000 B

Oa-La-140""" 200 =

3 lD Since no drinkinr er pathway exists, a value of 30 000 pCi/X is used. For drinkii i ter samples, vain<<of 20,00 l/R is used. This is 40 CFfl Part ill

~

value.

a Applies t d 'nking water.

O AAA Rn eq rium mixlure of the parent and daughter isolopes which corresponds Lo the reporting va <<. f th ) enL isotope.

0 Thl3LE 0; 12-1 I

OETECTION Ch>>hflILITIES f'nn ENVllloNltENThL Shel t.f; hNhLYSIS n

Pl LOWEft LIllIT 0F OEfECrloN (LLa)

Mater Airborne Par ticul'ate Fish Hilk F o~ roduc Ls Sediment hna'lys i (pCi/R) or Gas (pCi/ma) (pCi/kg,wet) (pCi/g) i/kg,weL) (pCi/kg,(try) gross beta . 0. 01 II-3 30008 ltn-51 . 15 130 Fe-59 30 Co-50,60 130 Zn-65 30 m lr-Nb-95 15 1-131 .07 60 Cs-131 15 0. 05 130 15 60 150 Cs-13/ 0. 06 150 10 100 lla- La-110 15e A)

A Since inking water paLhway exists, a valuate of 3000 pCi/k may be used. For drinking waLer sanqite, a aine of 200 . /X is used.

E, 1

'I

TAB L 4.,12-1 (Continued)

TABLE NOTATION Ths i st does not mean that only these nucl i des are to be cons ide 0 he eaks that are identifiable, together with those of the abo nucl i shall also be analyzed and repor.ed in the Annual Rad ogical Enviro n tal Operating Report pursuant to Specification 6.9.~

b Required de tion capabilities for thermoluminescent dos i ers used for environme i-1 measurements are given in Regulatory Gu' 4.~3.

The LLD is defin, for purposes of these specificati as the smel.lest ccncentra ion of r oactive material in a sample th will yield a net count, above sys .em kground, that will .be detec with 95~ probability with o'nly 5 probabil 't of falsely c'oncluding h- a blank observation represents a "real" si For a particular measureme system, which ma nclude radiochemical separation:

4,66 sb LLD =

E ~

V ~

2.22 ~

Y ~

p(-Mt)

Mhere:

LLD is the "a priori" lower mit o etection as defined'above, as picocuries per unit ma or volume s is the s andard devi ion of the back und counting rate or of t5e counting r ate of lank sample as ap riate, as counts per minute, E is the counting >iciency, as counts per di > tegration, V is the sampl ize in units of mass or volume, 2.22 is the mber of disintegrations per minute per 'coeur ie, Y is the actional radiochemical yield, when applicabl l

I, is t radioactive decay constant for the particular rad uclihe, and or environmental samples is the elapsed time between sample lection', or end of the sample collection period, and time of ounting Typical values of E, V, Y, and +t should be used in he calcula~ion.

ST. LUC IE - UNIT I 3/4 12-9 Amendment No. 5 9

TABLE 4.12-1 Continued TABLE NOTATION it 'it d be recognized that the LLD is defined as an a ~riori (b the fa representing the capability of a measurement and not as an a ment. Analyses riori (after the fact) limit for a part'easure-be performed .in such a manner e stated LLOs will be achieved un utine conditions. Occa y background fluctuations, unavoidab s. 1 sample 'sizes presence of interfering nuclides, or other uncontro circu es may render these LLOs unachievable; In such cases, t ting factors shall be identified and described in the Annual Radi o 'vironmental Operating Report pursuant to Specification 6 d

LLO for drinking samples. If no drinking wa hway exists, the LLO of gamma ic analysis may be used.

An rium mixture of the parent and daughter isotopes which onds o pCi/'a of the parent isotope.

ST. LUCI E - UNIT 1 3/4 12-10 Amendment No. 5 3

RADIOLOGICAL ENVIRONMENTAL MONITORING

.12.2 LAND USE CENSUS LIi NG CONOITION FOR OPERATION 3.12.2 . land use census shall be conducted and shall identify within a distance o 8 km (5 miles) the location in each of the 16 meteorological sectors o e nearest milk animal, the nearest residence and the neare garden* of ater than 50 m~(500 ft~) producing broad leaf vegetatio .

APPLICABILITY: t all times.

ACTION: culatedd a ~

With a lan e census identifying a location(s) t a yields a cal-cur rently dos dose, commitment..greater. than, the being calcula e -in-S'pecification 4.11.2'.3,,ig, fg t.

ues--

new.'loca-tion(s) 'in the t. Semiannual Radioactiye~Ef 'nt-Rel'ease-"'Report.

pursuant to Spec'cation 6.9.1'. 7:

b. With a land use cen identifying a loc t on(s) that yields a cal-culated dose or dose o itment (via t arne exposure pathway) 20%

greater than at a loca i from whic s mples are. currently being obtained in accordance Specifi on 3.12:1, add the new loca-tion(s) to the radiologic 1 envir ntal monitoring program within 30 days. The sampling loc n excluding the control station location, having the lowest a ated dose or dose coenitment(s),

via the same exposure pathway y be deleted from this monitoring program after October 31 of e ar in which this land use census was conducted. Pursuant pec ation 6.9.1.7 , identify the new location(s) in the n x Semian u 1 Radioactive Effluent Release Report and also includ the repo t revised figure(s) and table for the ODCM reflecti the new loca o (s).

The provisions of cifications 3.0.3 a 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENT 4.12.2 The land us c nsus shall be conducted during the wing season at least once per 12 hs using that information that will o ide the best results, such as a door-to-door survey, aerial survey, or consulting local agricultu e author ities. The results of the land use c s s shall be included in t nnual Radiological Environmental Operating Re r pursuant to Specifica i n 6.9.1.8.

• Broad 1 a vegetation sampling may be performed at the site boundar each of tw fferent direction sectors with the highest predicted D/gs in 1 eu of the den census. Specifications for broad leaf vegetation sampling able

3. .4b shall be followed, including analysis of control samples.

T. LUG IE - UNIT 1 3/4 12-11 Amendment No. SH $ )

I DIOLOGICAL. ENVIRONMENTAL MONITORING 3 4. 2.3 INTERLABORATORY COMPARISON PROGRAM L IMITI ONDI T ION FOR OPERATION 3.12.3 An es shall be performed on radioactive materials supplied a r t of an Interl atory Comparison Program that has been approved by the Commission.*

APPLICABILITY: At 1 times.

ACT[0<I:

a ~ >lith analyses not 'ng performed as required ove, report the corrective actions o the Commission in the ual Radiological Envir onmental Operate Report pursuant to ecification 6.9.1.8.

b. The provisions of Speci c tions 3.0.3 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.3 A summary of the results obtai as t of the above required Inter-laboratory Comparison Program shall nclude i the Annual Radiological Environmental Operating Report purs t to Speci tion 6.9.1.8.

• This condi n is satisfied by participation in the Environmental Radioa t'vity Laborator ntercompar ison Studies Program conducted by the Environmental Protect'gency (EPA).

S .'CIE - UNIT 1 3/4 12-12 Amendment No. 5 g,

3/4.12 RADIOLOGICAL ENVIRONMENTAL t)ONITORING BASES

4. 2.1 MONITORING PROGRAM e adiological environmental monitoring program required by this specifi ti provides representative measurements of radiation and of rad ctive mat i s in those exposure pathways and for those radionuclides lead to the h t potential radiation exposures of MEMBERS OF THE P C resulting from e tation operation. This monitoring program impl tsSection IV.B.2 of p dix I to 10 CFR Par t 50 and thereby suppl ts the radiological effluen m itoring program by verifying that th surable concentrations of radi c ve materials and levels of radia are not higher than expected on the basi o the effluent measurements he modeling of the environmental exposure t ays. The initially sp 'ed monitoring program will be effective for t ast the first 3 s of commercial ope'ra-tion. Following this period, pr r changes may initiated based on opera-tional experience.

The required 'detection capabilitie environmental sample analyses are tabulated in terms of the lower limits t tion (LLDs). The LLDs required by Table 4.12-1 are considered optim or ro t> environmental measurements in industrial laboratories. It s d be recog 'z that the LLD is defined as an a ~riori (befor e the fact mit representi t capability of a measure-ment system and not as an a eriori (after the fa ) imit for a particular measurement.

Detailed discuss of the LLD, and other detection li 'ts, can be found .

in HASL Procedures ual, HASL-300 (revised annually), Currie, L , Limits for Qualitative ection and Quantitative Determination - Appli ts ,to Radiochemistr Limits for

'nal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "0 'ection oanalytical Counting Techniques," Atlantic Richfield Ha fo Company r t ARH-SA-215 (June 1975).

ST. LUCIE - UNIT 1 B 3/4 12-1 Amendment No. 5 '3

s

.12 RADIOLOGICAL ENV IRONMENTAL MONITORING BAS 3/4.12.2 , USE CENSUS This speci tion is provided to ensure that changes in the us areas ht and beyond the BOUNDARY are identified and that modificati to the radiolog'cal environ 1 monigvring programare made if requir y the results of this census. e belt'nformation from the door-t - or survey, from aerial sur vey or fro suiting with local agricultu authorities shall be used. This census i sfies the requirements ection IV.B.3 of Appendix I to 10 CFR Part 50. e tricting the census gardens of greater than 50 mz provides assurance tha 'ificant exp e pathways'via leafy vegetables will be identified and m 1 r ed sine garden of this size is the minimum required to produce the quanta 6 k ar of leafy vegetables assumed in Regulatory Guide 1.109 for consumptio child. To determine this minimum garden size, the following assum ere made: 1) 20% of the garden was used for growing broad leaf veget n (i. , similar to lettuce and cabbage), and 2) a vegetation yield 2 kg/mz.

3/4.12.3 INTERLAOORATORY C RISON PROGRAM The requirement f art'icipation in an approved Interla tory Comparison Program is provided ensure that independent checks on the pr i 'on and accuracy of the m rements of radioactive material in environmen ample atrices are p rmed as part of'he quality assurance program for v on-ental moni ng in order=- to d'emonstrate that the results are reasonab lid for the p ses of Section IV.B.2 of Appendix I to 10 CFR Part 50.

T. LUCI E - UNIT 1 B 3/4 12-2 Amendment Wo. 5 g

AOMINISTRATIVE CONTROLS (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Backu Method for Oeterminin Subcoolin Mar in A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring.

e. Post-accident Sam lin A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include .the following:

(i) Training of personnel, (ii) Procedures for sampling and analysis, and 5E~~ (iii) Provisions for maintenance of sampling and analysis q.( o~~ equipment.

6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 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 NRC."

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 inv'olving 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.

ST. LUCIE - UNIT 1 6-15 Amendment No.+, 86

l lv '8 I

Radioactive Effluent Controls Pro ram A program shall be provided conforqing with 10 CFR 50.36a for, the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably The program (1) shall be contained in the ODCM, 'chievable.

(2) shall be implemented by operating procedures, and (3) shall in-clude remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point 'determination in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. 106 and with the methodology and parameters in the ODCM,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50,

.5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would ceased 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-.

nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

INSERT g4 (Continued)

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

I

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters .in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE 80UNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance pro-gram for environmental monitoring.

ADMINISTRATIVE CONTROLS IANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.2 6 da after January and July 1 of each year . The period of 1 the first re t all begin with the date of initial criticality.

The Rad> ac ve Effluent Release Reports shall include a summary of quantities of adioactive liquid and gaseous effluents and solid e released from the un> a outlined in Regulatory Guide 1.21, "Measuring, uating, and Reporting Radar ac vity in Solid Wastes and Releases of Radio ve Materials in Liquid and Ga eo Effluents from Light-Water-Cooled Nu e Power Plants,"

Revision 1, June 1 74, with data summarized on a quarter sis following the format of Appendix th eof.

The Radioactive Effluent e ase Report to be subm d within 60 days aft~

January 1 of each year sha elude an annual s ry of hourly meteorological data collected over the prev u ear. This n 1 summaiy may be either-in pgpagcp the form of an hour-by-hour li i on magn i tape of wind speed, wind direc-tion, atmospheric stability, an r ipit i (if measured), or in the form of

] TH'2nSe< joint frequency distributions of w' e , wind direction, and atmosphere stability.>> This same report shall de an assessment of the radiation.

W 5' doses due to the radioactive liquid n g eous effluents released from the unit or station during the previo ale a ear. This same report shall also include an assessment of the ra son dos om radioactive liquid and gaseous effluents to MEMBERS E PUBLIC d their activities inside the SITE BOUNDARY (Figure 5.l-l ring the report e od. All assumptions used in making these assessments ., specific activit sure time and location, shall be included in t s r eports. The meteorolo ca conditions concurrent with the time of rel s of radioactive materials in as ous effluents, as determined by samp n frequency and measurement, shal be used for determining the gaseous path y oses. The assessment of radiation se shall be performed in accordance the methodology and parameters in the 0 S DOSE CALCULA-TION MANUAL ).

very 2 e s using the previous 6 months release history for iso p 'nd

'iistor c meteorological data determine the controlling age group r oth Iiq d nd gaseous pathways. If changed from current, submit change CM to 1 t new tables for these groups and use the new groups in subsequen d e

" A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.-

ST. LUG I E - UNIT 1 6-17 Amendment No. $ /p, 6g

INSERT ff 5

()zL f~

I'2 61 The Zesrtknnual yyyy f 1 yl~

Radioacti ation of the unit during the previ e Eff)cent Release Report covering the oper-us ~ months of operation shall be submitted f yy . 16 6 611 elude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the OOCH and PCP and (2) in con-formance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

AOM I N I ST RAT I V E CONTROL 5 The R i ctive Effluent Release Report to be submitted 60 days'-after Ja ar 1 of ea ar shall also include an assessment of radiation doses to e likely mo osed MEM3ER OF THE PUBLIC from reactor releases for e evious calendar yea . cceptable methods for calculating the dose conti't n from liquid and ga ou effluents are given in Regulatory Guide 1.10 , M ch 1976.

The Radioactive E lu t Release Reports shall include the oil wing informa-tion for each class f lid waste (as defined by 10 CFR ar 6l) shipped off-site during the report e iod:

a. Volume,

b. Total curie quantity s cify wheth d ermined by measurement or estimate),

c. Principal radionuclides (s c y ether determined by measurement or estimate),

d. Type of waste (e.g.. d at ed s n resin, compacted dry waste, evaporator bottoms),

e. Type of containe (e g., LSA, Type A, p 8, Large guantity), and 0 The

.f.

of unplanned re materials in s Solidificat Radioactive E as s

u n ent or absorbent (e.g.,

t Release Reports shall include a is from the site to UNRESTRICTED AREAS o and liquid effluents made during the re c en urea formaldehyde).

and description r ioactive.

t' period.

The Radi ct' Effluent Release Reports shall include any change m e during the re rt' period to the PROCESS CONTROL PROGRAM (PCP) and ta th 0 SITE 00SE AL LATION MANUAL (OOCM), as well as a listing of new locations o dose c cul tions and/or environmental monitoring identified by the land use e us ANNOAL RADIOLOGICAL ENVIRONIIENTAL OPERATING REPORT*Q~~ ~ADO:

• Rare<< 6.9.1.8

~gSs~<

~ >TH A single submittal may be made for a multiple unit station.

gOO'T. -

LUCIE UNIT 1 6-18 Amendment No. gg/, 6g

1 4

I

'4 I ~ IP 0

INSERT g6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCH and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ADMINI STRATI VE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) s di with operational controls and with previous environmental s lane re rts, and an assessment of the observed impacts of the p pera-tion on he nvironment. The reports shall also include the r of land use census r uired by Specification 3.12.2.

The Annual Radi og 1 Environmental Operating Repor 11 include the results of analysi o ll radiological environme mples and of all environmental radiat m surements taken dur e period pursuant to the locations specified in le and Figure n e ODCM, as well as sumoarized and tabulated results of t e alyses asurements in the format of the table in the Radiological Ass m t an Technical Position, Revision 1, November 1979. " In the event tha 'ndivfdual results are not available for inclusion with the report, the po s ll be submitted noting and explaining the reasons for the missing su s. e ssing data shall be submitted as soon as possible in a su tary repo The .reports shall so elude the following: s ary description of the radiological en 'ro ntal monitoring program; at ea two legible maps*

covering all am ng locations keyed to a table gfv tances and direc-tions fro th enterline of one reactor; the resul ts o th Interlaboratory Compar on ogram required by Specification 3.12.3; disc io of all devia-ti fr the sampling schedule of Table 3.12.1; and discus n all 6.9.1. 9 At least once every 5 years, an estimate of the actual population within 10 miles of the plant shall be prepared and submitted to the NRC; 6.9.1.1O At least once every 10 years, an estimate of the actual population within 50 miles of the plant shall be prepared and submitted to the NRC.

SPECIAL REPORTS 6.9.2 Soecial reports shall be submitted to the NRC withtn the time period specified for each report. ~e D aie~s ST. LUCIE - UNIT 1 6-19 Amendment No. $ g, h9. 86

AOMIN I STRAT I VE CONTROLS

g. Records of training and qualification for current member s of the unit staff.

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

i. Records of guali ty Assurance activities required by the qA Manual.

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 FRG and the CNRB.

1. Records of the service lives of all safety related snubbers including the date at which the service life commences and associated installation and maintenance records.

Records of secondary water sampling and water quality.

n. Annual Radiological Environmental Operating Reports and records of analyses transmitted .to the licensee which are used to prepare the Annual Radiological Environ'mental Monitoring Report.

o. Meteorological data, summarized and reported in a format consistent with the recommendation of Regulatory Guides 1.21 and 1.23.

p. Records of audits performed under the requirements of Specifications 6.5.2.8 and 6.8.4.

6.11 RAOIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consjstent with the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

Records of reviews performed for changes made to the OFFSITE OOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

- 83 ST. LUCIE UNIT 1 6-21 Amendment No. gf,$ 9,

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM PCP i see initiated changes to the PCP:

Sha submitted to the Commission in the Semiannual ive Efflue ease Report for the period in which the s) was made. Thi s ittal shall contain:

a. Sufficient d iled information ly support the Pter~ c.r= rationale for ange witho fit of additional or g+5GC1 supplemental info t

b. A determination th h e did not reduce the overall conformance of ewatere e resin to existing criteria for radio astes; and

c. Do ation of the fact that the c as been reviewed a found acceptable by the FRG.

all become effective upon review and acceptance b h RG.

6.14 OFFSITE DOSE CALCULATION MANUAL ODCM icensee initiated changes to the ODCM:

a be submitted to the Commission in the Semiannual Radi e Ef e Release Report for the period in which the cha was made e e ive. This submittal shall contain:

a. Suffic detailed information to tot upport the rationale he change without ben 'dditional or REPLAcL. supplemental tion. Inform submitted should consist of a pa of those of the ODCM to be changed'ith each um and provided with an approval and date box, er with appropriate analyses or evaluations just t change(s);

b. A determinat at the chang 1 not reduce the accuracy or relia of dose calculatio setpoint determina-tions C. mentation of the fact that the change een reviewed and found acceptable by the FRG.

Shall become effective upon review and acceptance by th ST LUCIE - UNIT 1 6-23 Amendment No. $ 9,h9, 86

J, ~

I'

~

'I 4

K I4,o g

Changes to the PCP:

Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.? q. This documentation shall contain:

fo Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

6) A determination that the change willmaintain the overall conformance of the solidified waste product to existing requirements of Federal,.State, or other applicable regulations.

2. Shall become effective after review and acceptance by the Facility Review Group and the approval of the PlantPCanager.

Gene,ca<

INSERT g8 Changes to the ODCM:

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2q. This documentation shall contain:

a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s) and

$) A determination that the change willmaintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the Facility Review Group and the approvtd of the PlantPanager.

6 cqeral pgtgzg Shall be submitted to the Commission in the form of complete, legible copy of the entire ODCM as a part of or concturent with the Semiganual Radioactive Effluent Release Report for the period of the report jn which any change to the ODCM was a

made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADIOACTIVE LI UID, GASEOUS AND SOLID WASTE TREATMENT SY T S~

6.15. icensee initiated major changes to the radioactive waste systems (1 iqui aseous and solid):

ll be reported to the Commission in the Semiannual Radio ive E

re shal

'dent Release Report for the period in which the evalu 'on was by the Facility Review Group. The discussion ntain:

each

a. A ary of the evaluation that led to the de ination that the h nge could be made in accordance with FR 50.59;

b. Suffice n detailed information to totall upport the reason for the ge without benefit of additi 1 or supplemental informatio ;

C. A detailed de c iption of the equi t, components and processes invo and the interf s with other'plant systems.

evaluation of change wh'hows the predicted releases

d. An of radioactive mate s ls in 1'd and gaseous effluents and/or quantity of solid wa tha iffer from those previously predicted in the licen e ication and amendments thereto;

e. An evaluation of the c e which shows the expected maximum exposures to individu i e UNRESTRICTED AREA and to the general population t dif r from those previously estimated in the license app 'tion an endments thereto;

f. A comparison of e predicted re es of radioactive materials in liquid and seous effluents an solid waste to the actual releases for e period prior to wh he changes are to be made

g. An esti of the exposure to plant o ting personnel as a result f the change; and

h. Doc tation of the fact that the change w reviewed and fo acceptable by the FRG.

2. Shal ecome effective upon review and acceptance by FRG.

• Lice s may choose to submit the information called for in this Spec'ca-tio s part of the annual FSAR update.

T. LUCIE - UNIT 1 6-24 Amendment No. 69

Il St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 ATTACHMENT 2 ST. LUCIE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES AND INSERTS V

X XIX XX 1-4 Insert ¹1 1-5 Insert ¹2 3/4 3-25 3/4 3-26 3/4 3-48 through 3/4 3-56 Insert ¹3 3/4 3-57 through 3/4 3-59 B 3/4 3-3 B 3/4 3-4 3/4 11-1 through 3/4 11-13 3/4 11-16 3/4 11-17 B 3/4 11-1 through B 3/4 11-5 3/4 12-1 through 3/4 12-12 B 3/4 12-1 B 3/4 12-2 6-15 Insert ¹4 (2 pages) 6-18 Insert ¹5 6-19 Insert ¹6 6-20 6-21 6-23 Insert ¹7 Insert ¹8 6-24

INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE................. 3/4 2"1 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTORS F 3/4 2-7 xg 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FT . 3/4 2=9 3/4.2.4 AZIMUTHAL POWER TILT.... 3/4 2-13 3/4.2.5 DNB PARAMETERS................... 3/4 2-14 3/4. 3 INSTRUMENTATION 3/4. 3. 1 REACTOR PROTECTIVE INSTRUMENTATION....... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION. 3/4 3-11 3/4. 3. 3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION.. 3/4 3-24 INCORE DETECTORS. 3/4 3-30 SEISMIC INSTRUMENTATION. 3/4 3-32 METEOROLOGICAL INSTRUMENTATION........... 3/4 3-35 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION. 3/4 3-38 ACCIDENT MONITORING INSTRUMENTATION. 3/4 3-41 DELE'Tp FIRE DETECTION INSTRUMENTATION.......... 3/4 3"44

~LOOSE-PART OETECTION INSTRUMENTATION... 3/4 3"47 e

Q X PLOSIV O'AS MONITORING INSTRUMENTATION........... 3/4 3-53 3/4.3. 4 TURBINE OVERSPEED PROTECTION. 3/4 3-60 3/4.4 REACTOR COOLANT SYSTEM .

3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION. 3/4 4-1 HOT STANDBY. 3/4 4-2 HOT SHUTDOWN.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4-3 COLD SHUTDOWN (LOOPS FILLED).... ~ ~ 3/4 4-5 COLO SHUTDOWN (LOOPS NOT FILLED).. 3/4 4-6 ST. LUCIE - UNIT 2

INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE 3/4 11-14 GAS STORAGE TANKS. 3/4 11"15 ST. LUCIE - UNIT 2

INDEX ADHINISTRAT I VE CONTROLS SECTION PAGE 6.5.2 COHPANY NUCLEAR REVIEW BOARD............... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 9 F UNCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-9 C OMPOS IT ION e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 A LTERNATES.................................................. 6-10 C ONSULTANTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 HEETING FREQUENCY........................................... 6-10 Q UO RUM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 REV I EM e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ 6-11 AUD ITS ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-11 AUTHOR IT Y e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ 6-12 R ECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-12 6.6 REPORTABLE EVENT ACTION....................................... 6-13 6.7 SAFETY LIMIT VIOLATION....................................... 6-13 6.8 PROCEDURES AND PROGRAMS....................................... 6-13 6.9 REPORTING RE UIREHENTS. ~ ~ ~ ~ ~ -. ~ . ~ ... ..~ ~ ~ ~ ~ ~ - ~ ~ .. .~ ~ ~ ~ ~ ~ ~ - ~ ~ . ~ 6-16 6.9.1 ROUTINE REPORTS........................................... .. 6-16 STARTUP REPORT.............................-..-......... ~ . .. 6-16 ANNUAL REPORTS.............................................. 6-16 MONTHLY OPERATING REPORTS......................... e ~ ~ e ~ ~ ~ ~ ~ ~ 6~1 7

~ SB8'ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.... ~ ~ oe ~ ~ ~ oo ~ 6 18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ~ ~ e ~ ~ ~ ~ ~ ~ ~ 6 1 9 6.9.2 SPECIAL REPORTS...................................... 6-20 6.10 RECORD RETENTION....................... .. .. ................ 6-20 6.11 RADIATION PROTECTION PROGRAM.................................. 6-21 ST. LUC IE - UNIT 2 XIX Amendment No.

INDEX ADMINI STRATI VE CONTROLS SEC TIPN PAGE 6.12 HIGH RADIATION AREA........................................... 6-22 6.13 PROCESS CONTROL PROGRAM....................................... 6-23 6.14 OFFSITE DOSE CALCULATION MANUAL............................... 6-23

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~

~ I ST. LUCIE -. UNIT 2 XX Amendment No.

DEFINITIONS LOW TEMPERATURE OVERPRESSURE PROTECTION RANGE - RCS 1.16 The LOM TEMPERATURE OVERPRESSURE PROTECTION RANGE is that operating condition when fl) the RCS cold leg temperature is less than or equal to that specified in Table 3.4-3, and (2) the Reactor Coolant System is not vented to containment by an opening of at least 3.58 square inches.

MEMBER S OF THE PUBLIC 1.17 MEMBER(S) OF THE PUBLIC shall include all persons who are not .

occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors. Also excluded from this category are persons who enter the site to service /PLAQUE'l equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not ciate i h plant. g I TI4 OFFSITE DOSE CALCULATION MANUAL OOCM:

1. 18 QM men MI-Ho OPERABLE - OPERABILITY

1. 19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its .

function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50. 59, or (3) otherwise approved by the Commission.

'ST. LUCIE - UNIT 2 Amendment No. 150 fQ 46

II 1 t l

0

INSERT g1 The OFFSITE OOSE CALCULATION MANUAL (OOCH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alare/Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. The OOCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental- Operating and -See~

annual Radioactive Effluent Release Reports required by Specifications 6.9. 1. 7 and 6.9.1.8.

o'"

DEFINITIONS PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generato~ tube leakage) through a non-isolable fault in a R c C t m component body, pipe wall or vessel wall.

pgpigg~

PROCESS CONTROL PROGRAM PCP ~QUEST- ~ P

1. 23 PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of dischargng air or'gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time inter~al from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING INTEGRITY 1.2B SHIELD BUILDING INTEGRITY shall exist when:

a. Each door is closed except when the access opening is being used for normal transit entry and exit;

b. The shield building ventilation system is in compliance with Specification 3.6.6. 1, and

c. The sealing mechanism associated with each penetration ge.g., welds, bellows or 0-rings) is OPERABLE.

ST. LUCIE - UNIT 2 1-5 Amendment No. 8. I3

I CI

INSERT g2 The PROCES~CONTROL PROGRAH (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that process-ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

TABLE 3.3-6 RADIATION HONITORING INSTRUHENTATION HINIHUH CHANNELS APPLICABLE ALARH/TRIP HEASUREHENT INSTRUMENT OPERABLE HODES SETPOINT RANGE ACTION

l. AREA HONITORS

a. Fuel Storage Pool Area

i. Criticality and < 20 mR/hr 10 - 10 mR/hr 22 Venti lation System Isolation Honitor

b. Containaent Isolation 3 6 < 90 mR/hr' 1 - 10 7

mR/hr 25

c. Control Room Isolation 1 per ALL HODES 2x background 10 - 10 pCi/cc 26 intake

d. Containment Area - Hi Range 1, 2, 3 4 4 Not Applicable 1.

- 10 7

R/hr 27

2. PROCESS HONITORS

a. Fuel Storage Pool Area Ventilation System

i. Gaseous Activity 10 - 10 pCi/cc 24' ii. Particulate Activity - 10 6

cpm 24

b. Containment Gaseous Activity RCS Leakage Detection 1, 2, 3 8 4 Not Applicable 10 - 10 pCi/cc 23 ii. Particulate Activity RCS Leakage Detection 1, 2, 3 8 4 Not Applicable 1 - 10 6

cpm 23

""With irradiated fuel in the storage pool or whenever there is fuel movement within the pool or crane operation with loads over the storage pool.

"""The Alarm/Trip Setpoints are determined and set in accordance with the requirements of .

~gp OVALS ATE'oSE Ca.luau.la,Cia~ Rahu.a, )

TABLE 3.3-6 (Continued)

RADIATION HONITORING INSTRUHENTATION HINIHUH CHANNELS APPLICABLE ALARH/TRIP HEASUREHENT INSTRUHENT OPERABLE - HOQES SETPOINT RANGE ACTION PROCESS HONITORS (Continued)

c. Noble Gas Effluent Honitors

i. Reactor Auxiliary Building Exhaust System (Plant Vent Low Range Honitor) 1, 2, 3, & 4 10 " 10 pCi/cc 27 ii. Reactor Auxiliary Building Exhaust Sys-tea (Plant Vent High Range Honitor) 1 1, 2, 3, & 4 10 " 10 pCi/cc 27 iii. Steam Generator Blowdown Treatment Facility Building Exhaust System 1 1, 2, 3, & 4 *M 10 - 10 pCi/cc 27 iv..Steaa Safety Valve 3 Dischargef 1/steam 1, 2, 3, & 4 10 10 pCi/cc 27 header

v. Ataospheric Steaa Dump Valve Ois-

-1 " 3 charget 1/steam 1, 2, 3, 8,4 10 10 pCi/cc 27 header

~lii ii 5

vi. ECCS Exhaust 1, 2, 3, & 4 IN A* 10 10 pCl/cc 27

~ ~

i i i d ii the requirements of The steam safety valve discharge monitor and the atmosphe0ic steam dump valve discharge monitor are the same monitor.

~HE'F'PS~T'6'Oo&E QACCu.<AIrlO< HA<~~~

STRUMENTATION RA CTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITIN NOITION FOR OPERATION 3.3.3.9 The ioactive liquid effluent monitor ing instrumentation nnels shown in Table ensure that the trip setpoints of

'ts

-12 shall be OPERABLE with their alarm/trip setp ts set to of Specification 3. 11. l. 1 are not exceede . The alarm/

e channels shall be determined in accord e with the methodology and para ers in the OFFSITE 00SE CALCULATION L (ODCM).

APPLICABILITY: At al 1 s.

ACTION:

a. Mith a radioactive 1 id effluent moni ing instrumentation channel alarm/trip set 'nt less cons ative than required by the above specification, i iately s nd the release of radioactive liquid effluents monitore the fected channel or declare the channel inoperable.

Mith less than the minimum of radioactive liquid effluent monitoring instrumentatio ann OPERABLE, take the ACTION shown in Table 3.3-12. If th noperab operable status withi 0 days, exp 'n

'nstruments are not returned to the next Semiannual Radioactive Effluen elease Report w the inoperability was not corrected in a ti manner.

C. The provision Specifications 3.0.3 an 0.4 are not appiicab1e.

SURVEILLANCE RE EMENTS 4.3.3.9 h radioactive liquid effluent monitoring instrumentat' channel shall b emonstrated OPERABLE by performance of the CHANNEL'CHECK, 3 URCE CHEC HANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at e fre ncies shown in Table 4.3-8.

ST. LUCIE - UNIT 2 3/4 3-48 Amendment No. 13

0 TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHA NSTRUMENT E ACTION

1. GROSS RADIOACTIVI ORS PROVIDING ALARM AND AUTOMATIC TERM INATIO EASE

a. Liquid Radwaste Effluent Ls 28

b. Steam Generator Blowdown Effl 1/SG 29

2. FLOW RATE MEASUREMENT DEV

a. Liquid Radw e luent Line 30

b. Dis Canal 30 team Generator Blowdown Effluent Lines 30

TAB E 3.3-12 Continued TABLE NOTATION ACTION 28- i the number of channels OPERABLE less than required by nl um Channels OPERABLE requirement, effluent releases co i e for up to 14 days provided that prior to init ng a rele e.

a. At ea t two independent samples are analyze 'n accordance with ification 4. 11. 1. 1. 1, and

b. At least tw technically qualified mern of the Facility Staff inde en ently verify the relea ate calculations and dischar ne valving (one per ms, one verifies);

Otherwise, suspend r le se of radio ve effluents via this pathway.

ACTION 29- With the number of channe LE less than required by the

~

Minimum Channels OPERABLE 'ment, effluent releases via this pathway may continue up to 30 days provided grab samples are analyzed for ss a 'oactivity (beta or gamma) at a limit of detection o least 10-7 microcuries/gram:

a. -

At least once e 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when e specific activity of the secondar olant is greater h 0.01 microcuries/

gram DOSE VALENT I-131.

b. At lea nce per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> .when the sp s ic activity of t econdary coolant is less than o e al to

0. icrocuries/gram DOSE EQUIVALENT I-1 ACTION 30- Min system design flow of required running pum hall b u lized for MPC calculations for discharge cana f w n maximum system design flow shall be utilized for C lculations for effluent line flow.

ST. LUCIE - UNIT 2 3/4 3"50

TABLE 4.3-8 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I

n M

m ANNEL CHANNEL SOURCE CHA FUNCTIONAL C

INSTRUMENT CHECK CHECK ON TEST

1. GROSS BETA OR GAMMA RADIOAC NITORS PROVIDING ALARM AND AUTOMATIC ON OF RELEASE

a. Liquid Radwaste Effluent Line R(2) q(l)

b. Steam Generator Blowdown Ef n ne R(2) 0(l)

2. FLOM RATE MEASUREME

a. Liqu a e Effluent Line N.A.

am Generator Blowdown Effluent Line N.A.

TABLE 4.3-8 Continued)

TABLE NOTATION (1) The C FUNCTIONAL TEST shall also demonstrate that autom c isolatio is pathway and control room alarm annunciat ur if any of the 1 ing conditions exists:

l. Instrument > ic es measured levels above t a rm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a n 1 fa'e.

4. Instrument controls not i p ate mode.

(2) The initial CHANNEL CA A N for radar ct'ty measurement instrumentation sha be erformed using on or ore of the reference standards tracea e t he National Bureau of an rds or using standards th NBS.

intend pl The o

av een calibrated against stan st ards should permit calibrating the s ra e of energy and rate capabilities that are ation. &or .subsequent CHANNEL CALIBRATION, but

'l ds ertified by the over its of normal rces that ve en related to the initial calibration may be used.

ST. LUCIE " UNIT 2 3/4 3"52

4 0

INSTRUMENTATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION EsPnosivG les

3. 3. 3. 10 The 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. 2.g are not exceeded.

APPLICABILITY: As shown in Table 3.3-13 ACTION: Q.n gN laS >VC $ 0.5

a. With monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specification, declare the channel inoperable.

b. Wi'th less than the minimum number of monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3 '-13. If the inoperable instruments are not returned to operable status within 30 days, why the inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3 0.3 and 3.0.4 are not a licab PCq>mr@. awk Su 4~if a, SPCciat VCPov 4

+< +he. commission uvl4h)w 5< day> +< +

I ~ ~ 0 ~ g I I ~ ~ ~ 0

e. I '

I 5 g ~ ~ ~ ~ 4 II a ~ I ~" ~ ~ II TABLE 3.3" 13 MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION WASTE GAS DECAY TANKS EKPLDSIVE GAS MONITORING SYSTEM

a. 'Oxygen Monitors P~

l 5 II 'I t TABLE 3. 3-13 Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION HINIHUH CMANNELS MENT OPERABLE APPLICABILITY

5. FUEL STORAG A VENTILATION SYSTEM

a. 'oble Gas A s ty Monitor (Low Range) 37

b. Iodine Sampler 40

c. Particulate Sampler 40

d. Flow Rate Monitor 38

e. Sampler Flow Rate Monitor 36

6. LAUNDRY AREA VENTILATION SYSTEM

a. Noble Gas Activity Monitor 37

b. Iodine Sampler 40

c. Particulate Sampler 40

d. Flow Rate 38

e. Sampler Flow Rate Monitor 36

7. STEAM GENERATOR BLOWDOWN BUI VENT SYSTEH

a. Noble Gas Activ y onitor 37

b. Iodine Sam e 40 C. Parti 1 e Sampler 40

d. Rate Honitor NA Sampler Flow Rate Honitor 36

TABLE 3.3-13 Continued TABLE NOTATION 9" During waste gas system operation. Q& ACTION 35-Mi hannels OPERABLE requirement, the contents o tank(s released to the environment for u days provided th r to initiating the releas ~PLACE +'~ a0 At least two in e nt sampl he tank's contents are analyzed, and ggggaT '

b. At least two tec qua members of the Facility Staff indepe verify the re rate calculations and dis valve lineup (one perfo e verifies).

0th , suspend release of radioactive effluents his AC N With the number of channels OPERABLE less than requi the Minimum Channels OPERABLE requirement, effluent r es via this pathway may continue for to 30 days provi e flow rate estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ACTION 37- Wi t number of channels OPERABLE han required by the Minim C nels OPERABLE requirem effluent releases via this pat ay continue for u 0 days provided grab samples are k at least o e er 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed f s topic c ity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ACTION 38- Maximum system flow be utilized in the determination of the instantaneou ea m itor alarm setpoint. ACTION 39- With the n of channnels LE one less than required by the Min hannels OPERABLE re i ent, operation of this syst continue for up to 30 da p vided samples of 02 a alyzed by the lab gas partitione east once per ours. ACTION With the number of channels OPERABLE less than q ed by the Minimum Channels OPERABLE requirement, effluent re a s via the affected pathway may continue for up to 30 days p v ed samples are continuously collected with auxiliary sample ST. LUCIE " UNIT 2 3/4 3-56 INSERT g3 'With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 30 days provided samples of 0~ are analyzed by the lab gas par titioner at 1 eas .once per 24 hourK. pypgo~>" TABLE 4.3-9 HONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS I C M CHANNEL NODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRlNENT CHECK CHECK CALIBRATIDH t %II I RED HASTE OAS DECAY TAHKS EXPLOSIVE GAS HONITORING SYSTEH A

a. Oxygen Honitor D D()L) <<g 0

b. Oxygen Honitor (alternate) D DI)L)

EAR I Ql 0 I ~ K'a + I 4f l Q 1 ~ 1 h Wt II' II TAHLE 4. 3-9 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I foal CHANNEL MODES HICH CHANNEL SOURCE CHANNEL FUNCTIONAL S LLANCE INSTRUMENT CIIECK CHECK CALIBRATION TEST UIRED

5. FUEL STORAGE AR NTILATION SYSTEM

a. Noble Gas Activity s r R(3) 2)

b. Iodine Sampler N.A. N.A. N.A.

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

d. Sampler Flow Rate Monitor N.A. N.A.

6. LAUNDRY AREA VENTILATION SYSTEM

a. Noble Gas Activity Monitor R(3) C(2)

b. I'odine Sampler N.A. N~ A. N.A

c. Particulate Sampler N.A. N.A

d. Sampler Flow Rate Monitor N.A. N.A.

7. STEAM GENERATOR BLOWDOW LDING VENT

a. Noble Gas A Monitor -R(3)

b. Iodine ler N.A. N.A. N.A

c. P culate Sampler N.A. N.A. N.A.

Sampler flow Rate Monitor N.A. N.A. TABLE 4.3-9 (Continued) TABLE NOTATION he@-4he 14m ~ 0" During waste gas holdup system operation. ntpel~eem-a-l~~nnun 'mental-4n-shAWbe-performed-us-i~g-on d eu44-p d-pa4e-capa ea4hs-. (g) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen; balance nitrogen.

ST. LUCIE - UNIT 2 3/4 3-59 l il ~I II INSTRUMENTATION BASES 3/4. 3. 3. 6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." 3/4. 3. 3. 7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fir es will reduce the potential for damage to safety- elated equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is requii ed to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. 3/4. 3. 3. 8 LOOSE" PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capabili,ty is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.I ~ EVQHRC ~V-'h>m&s-d 9CH-to-casu ST. LUCIE - UNIT 2 B 3/4 3-3 INSTRUMENTATION P gPiOSlVC &AS BASES 3/4. 3. 3. 10 91AfRSA BR MONITORING INSTRUMENTATION Th~ instrumentation is provided to monitor PPWeahTl~h ct the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY,and use of this instrumentation is consistent with the requiremdnts of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. I 3/4. 3.4 TURBINE OVERSPEEO PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE '- and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures. ST. LUCIE - UNIT 2 8 g/4 3-4 Amendment No.25 /4.11 RADIOACTIVE EFFLUEHTS 11.1 LI UID EFFLUEHTS COH RATION LIMITING C DITION FOR OPERATION 3.11.1.1 The o entration of radioactive material released from th (see Figure 5. 1 ) shall be limited to the concentrations specific Part 20, Appendix 8, Table II, Column 2 for radionuclides other t '0 te dissolved CFR or entrained noble a s. For dissolved or entrained noble gas s, the concentration shall e imited to 2 x 10"~ microcuries/ml tot activity. APPLICABILITY: At al 1 'm ACTION: With the concentration of radar a ive material rel ed from the site exceeding the above limits, immediately r t e the concen ion to within the above limits. SURVEILLANCE RE UIREMEHTS

4. ll. 1. 1. l The radioactivity co t of each ba ch of radioactive liquid determined prior to re d analysis in accordance waste'hall be se by sampli with Table 4. 11-1. The resul of pre-release a 1 ses shall be used with the calculational methods in th CM to assure that e oncentration at the point of release is maintained in the limits of, Speci 'c tion 3. 11. 1. 1. Also, results of the previous t-release analyses shall b ed with the calcu-lational methods in t DCM to assure that the concen a 'ons at the point of release were maintai within the limits of Specificati . 11. 1. 1.

4. 11. 1. 1.2 Post ease analyses of samples composited fro b tch releases shall be perfo in accordance with Table 4. 11-1.

4.11. 1. 1.3 e radioactivity concentration of liquids discharge om continuo elease points shall be determined by collection and an 1 is of samples > accordance wiht Table 4. 11-1. The results of the analys all be us ith the calculational methods in the ODCM to assure that the con rations at the point of release are maintained within the limit o S fication 3.11.1.1. ST. LUCIE UNIT 2 3/4 11-1 TABLE 4. 11-1 RADIOACTIVE LI UID WASTE SAHPLING AND ANALYSIS PROGRAH Lower Limi Hinimum of Detec n Liquid 1 ase Sampling Analysis, Type of Activity (LL Type Frequency Frequency Analysis (p ml ) A. Batch Wa t p p -7 Release Each Batch Each Batch Principal Gamma Tanks Emi tters I-131 1xl 0 Dissolved a 1xl0 One a ch/H Entrained es (Gamma E ers) p H 3 1 xl 0 Each Batch Composite b Gr Alpha 1xlO p Q r"89, Sr-90 SxlO Each Batch Co ite b Fe-55 1 xl 0 B. Continuous Releases Daily / Principal Gamma Sxl0 Com te Emitters -131 1xl 0 D 4/M D's olved and 1 x10 Grab Samp Composite En 'ned Gases Dai ly (Gam a Emitters) M H-3 1xl0 Dai Composite Gross Alph 1xl0 Q Sr-89, Sr-90 0 Dai ly Composite Fe-55 10 C. Settl Basi W Grab Sample I-131'xl Principal Emitters Gamma 5 7 lxlO ST. LUCIE - UNIT 2 3/4 11-2 TABLE 4.11-1 (Continued TABLE NOTATION a ~ The is defined, for purposes of these specifications, as the smalle conce t tion of radioactive material in a sample that will yield a n count, b ve system background, that will be detected with 95.o proba ' i >ty with onl 'robability of falsely concluding that a blank observ represents 'real" signal. For a particu r easurement system, which may include radioc cal separation: 4.66 sb LLD = E ~ V ~ . 22 ~ Y . exp(-Mt) Where: LLD is the "a priori" lo r limit of dete n as defined above, as picocuries per unit mass o lume, sb is the standard deviation o e 'ground counting rate or of the counting rate of a blank sam s appropriate, as counts per minute, E is the counting efficiency coun er disintegration, V is the sample size in u of mass or me, 2.22 is the number of integrations per mi t per picocurie, Y is the fractional r diochemical yield, when ap 1> able, A, is the radioa decay constant for the particu r adionuclide, and ht for env'ental samples is the elapsed time between a le collecti or end of the sample collection period, and ti countin Typ values of E, V, Y, and at should be used in the calculat'o ST. LUCIE - UNIT 2 3/4 11"3 F TABLE 4. 11-1 (Continued) TABLE NOTATION

b. A o osite sample is one in which the quantity of liquid samples pro r 'onal to the quantity of liquid waste discharged and in w the me o of sampling employed results in a specimen which i represen t of the 1 i qui ds released.

c. A batch relea 'he discharge of liquid wastes of a crete volume. Prior t mpling for analyses, each batch 1 be isolated, and then thoroughl m ed to assure representative pling.

d. A continuous release is discharge of liqu astes of a nondiscrete volume, e.g., from a volu a system th as an input flow during the continuous release.

e. The principal gamma emitters for he LLO specification applies exclusively are the following rad' ides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs ,

- 1, and Ce-144. This list does not mean that only thes clides a o be detected and reported. Other peaks which are meas le and ident> ~ le, together with the above nuclides, shall al e identified and rted.

f. Grab samples to be n when there is confirmed p ry to secondary system leakage in ted by the air ejector monitor 'ting > 2x background.

-5

g. If Compone ooling Water activity is >lxl0 pCi/ml, perfo weekly gross a >ty on the Intake Cooling Water System outlet to en the acti level is ( a 2x10 pCi/ml LLD limit. If ICW is >2x10 ml, p m analysis in accordance with a Plant Continuous Release on th e.-

ST. LUCIE - UNIT 2 3/4 11"4 OACTIVE EFFLUENTS 005 LIMITING 0 IT'ION FOR OPERATION

3. 11. 1.2 The s or dose commitment to a MEMBER OF THE PUBLIC from radioactive mate UNRESTRICTED AREA s in liquid efbluents released, from e Figure 5. 1-1) shall be limited:

each react it, to (

a. During any ndar quarter to less than or equal to . mrems to the total bo d to less than or equal to 5 mrem t any organ, and

b. During any calenda ar to less than or equ 3 mrems to the total body and to le s than or equal to 10 r s t'o'ny organ.

APPLICABILITY: At al 1 times. ACTION: 'Mith the calculated dose from elease of radioactive materials in liquid effluents exceeding the above 1.imitZ prepareand. submi toto,".,thmCearii's's$ aawi' "g3, - ~sgpYirsiiant'~t'o~$ port>w . c .,ident . "s, the,-,~cause('i)>fot<exceeding pecification;,9;":~i'-Spic61jRe -"th.l,:$m)f(i;),,aijdMe'fi'Ee ".0; "~o~rrec e~ clan'a-. to",:"'be~taken -to.:- rcducefthIe"-ret.'eases;a ',.'.: coact: vi. ma ji;,. 1'spfn~liqufd=;effIl,uents. o'jCfii=-cubi't'.eii&ca1'4ti -quarter/and, during the 'ur'ingghe@rema)jlde'r subsequeiit three- dar'quarters', so tH'a 'e'cutttulaAtfve dose" o'r dose coomitm o an individual from the e eleases is within 3 mrems to the o al body and 10 mrems to any r n.

b. The provi i s of Specifications 3.0.3 and 3.0.4 a ot applicable.

SURVEILLANCE REMENTS 4.11.1 ose Calculations. Cumulative dose contributions from liqui eff1 n for the current calendar quarter and the current calendar year h 1 be e rmined in accordance with the methodology and parameters in the ODC a 1 a once per 31 days. ST. LUCIE - UNIT 2 3/4 11-5 Amendment No. I3 RA CTIVE EFFLUEHTS LI UI TE TREATMENT LIMITING C TION FOR OPERATION

3. 11. 1.3 The ls u'd radyaste treatment system shall be OPERABLE. The pro-priate portions o e system shall be used to reduce the radioactiv terials in liquid wastes pr o to their discharge when the projected doses to the liquid effluent from h site to UNRESTRICTED AREAS (see Figure 5 ) when averaged over 31 days, ld exceed 0.06 mrem to the total body 0.2 mrem to any organ.

APPLICABILITY: At all time . ACTION:

a. With the -liquid, radwast eatment syst operable for more than 3I dajrs-,or with-':radioact liqu!d was-t treatment.and-f'n excess- o t 'above:-

'og, disc-harged without .ts.,'- prepari and subpft to'a. the Coamfssion within 30.'d ursu'b'Specification 6.9:P. a'."~~=. Report;which fnctudes. 'wing information: 'pecial

1. Identfffcatfon of the fn 1 equipment or subsystems and the reason for fnopera ty,

2. Action(s) taken to ore the in able equfpment to OPERABLE status, and

3. Suiliary descrf n of action(s) taken t prevent a recurrence.

b. The provisions o pecificatfons 3.0.3 and 3.0. re not applicable.

SURVEILLANCE RE UIRE S 4.11.1.3.1 Do due to liquid releases to UNRESTRICTED AREAS sha 1 e projected at e st once per 31 days, fn accordance with the ODCM un s the liquid radw treatment system is being used.

4. 11. 1.3 The -liquid radwaste treatment system shall be demonstrated 0 BLE by ope ng the liquid radwaste treatment system equipment for at least 30 m es at least once per 92 days unless the liquid radwaste system has e uti f ed to process radioactive liquid effluents during the prevfous 92 days.

ST. LUCIE " UNIT 2 3/4 11-6 Amendment Ho. 'I 0 A IOACTIVE EFFLUENTS 3/ 1 2 GASEOUS EFFLUENTS DOSE R T LIMITING C D. ION FOR OPERATION 3.11.2.1 The do te in UNRESTRICTED AREAS due to radioac v materials released in gaseou e fluents from the site (see Figure 5. 1 shall be limited to the folio i

a. For noble gas  : Less than or equal to 500 mr ms/yr to the total body and less t a or equal to 3000 mrems yr o the skin, and

b. For iodine-l3l, io i -133, tritium, d 11 radionuclides in parti-culate form with ha - ives greater h 8 days: Less than or equal to 1500 mrems/yr to a rgan.

APPLICABiLITY: At all times. ACTION: Mith the dose rate(s) exceeding e above li its, immediately decrease the release rate to within the abo mit(s). SURVEILLANCE RE UIREMENT

4. 11. 2. l. 1 The do e ate due to noble gases in gaseo ffluents shall be determined to be i in the above limits in accordance i the methodology and parameters n he ODCt1.

4.11.2.1.2 T dose rate due to iodine-l3l,.iodine-133, trs i , and all radionuc d in particulate form with half-lives greater tha 8 ays in gaseou e luents shall be determined to be within the above li it in accor a e with the methodology and parameters'n the ODCM by ob i ng re e ntative samples and performing analyses in accordance with e s mp ing and analysis program specified in Table 4.11-2. ST. LUG IE - UNIT 2 3/4 u.-7 tABLE 4.11-2 RADIOACTIVE GASEOUS MASTE SAh)PLING AND ANALYSIS PROGRAh'I I Hinimum Lower Limit of foal Sampling Analysis Type of Detection ( ) Gase Release T e Fre uenc Fre uenc Activit Anal sis Ci/ P P Maste Storage 4 M A. a Each Tank Each Tank Principal Gamma Emitters Tank Grab Sam le b BE Containment Purg Each Purge Each Purge Principal Gamma Emitters lxl0 ab e ll-3 lx10 C. (1) Plant Vent 4/H itters Principal Gam lxl0 (2) Fuel Building Grab Vent Sample (3) Laundry Area H-3 lxlO Vent (4) Steam Generator I Bio@down CO Buildin Vent D.'ll Release Types ~ Continuous 4/h1 -131 lx10 as listed in A, B, Chare C above. Sa d Continuous /H Princip mrna Emitters lx10 articulate (I-131, 0 e Sam le 11 Con s hl Gross Alpha 10 Composite Particulate Sam le Continuous d Sr-89, Sr-90 lxlO Composite Particulate Sample Continuous d Noble Gas Noble Gases lx10 Honitor Gross Beta or Gamma k C TABLE 4. 11-2 Continued) TABLE NOTATION a ~ T D is defined, for purposes of these specifications, as the small t con en ration of radioactive material in a sample that will yield a n t count ove system background, that will be detected with 95M prob i >ty with o Fo probability of falsely concluding that a blank obser t' represen "real" signal. For a partic 1 measurement system, which may include radio e real separation: 4 66 sb ~ LLD = E ~ V . 22 ~ Y . exp(-Ut) Mhere: LLD is the "a priori" w limit of de c on as defined above, as picocuries per unit mass r olume, sb is the standard deviation oi th b kground counting rate or of the counting rate of a blank s , as appropriate, as counts per minute, E is the counting efficien , s cou ts er disintegration, V is the sample size in 'ts of mass o v ume, 2.22 is the number o sintegrations per m u e per picocurie, Y is the fractio 1 radiochemical yield, when p 'cable, is the radi a ive decay constant for the partic la radionuclide, and bt for v'nmental samples is the elapsed time betwee pie collec , or end of the sample collection period, and t's of coun T p al values of E, V, Y, and bt should be used in the calcul i ST. LUCIE - UNIT 2 3/4 11-9 TABLE 4. 11-2 Continued O b. S lin and analysis shall also TABLE NOTATION be performed following shutdown, star up or a E POWER change exceeding 15K of RATED THERMAL POWER with' hour les (1) analysis shows that the DOSE E(UIVALENT I-131 concentra 'on the primary coolant has not increased more th actor of 3; and ( the oble gas activity monitor shows that effl n activity has not increa d b more than a factor of 3. C. Samples shall be ch e t least- 4 times a month an an yses shall be completed within 48 ho s ter changing (or after e al from sampler). Sampling shall also be p fo d at least once hours for at least 7 days following each shut n, tartup or TH POWER change exceeding 15K of RATED THERMAL POWER in ho and a y s shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing if (1) ana sis ho t t the DOSE EQUIVALENT I-131 concentr ati on in the primary cool a h i reased more than a factor o f 3; and (2) the noble gas activity moni s that effluent activity has increased by more than a factor o 3. en amples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the correspondin L may in eased by a factor of 10. ratio of the sample fl r e to the samp 'he

d. s am flow rate shall be known for the time p io covered by each dos or se rate calculatioa made in accordance wi S cifications 3.11.2.1, 3..2. and 3.11.2.3.'he principal g a itters for which the LLD specifica on plies exclusively ar t following radionucl ides: Kr-87, Kr-88, Xe- 3, Xe-133m, Xe- 5 and Xe-138 for gaseous emissions and Mn-54, -5 Co-58, Co 0, n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 partic at are b missions.. This list does not mean that only these n detected and reported. Other peaks which are measureable li d

i ti able, together with the above nuclides, shall also be identifi nd eported. ST. LUCIE - UNIT 2 3/4 11-10 Amendment No. IOACTIVE EFFLUENTS 00 NOBLE GASES LIMITIH C OITEON FOR OPERATION 3.11.2.2 The each reactor un i dose due a areas to noble gases released in gaseous efflu at and beyond the SITE BOUNDARY (see F'g t, from e S. l-l) shall be limited e following:

a. Ouring any a ndar quarter: Less than or equal t mrads for gamma radiat n nd less than or equal to 10 mra or beta radiation and,

b. Ouring any calend q ar: Less than or eq 1 o 10 mrads for gamma radiation and less 4 a or equal to 20 mr d for beta radiation.

APPLICABILITY: At all times. ACTION

a. Ki thethe, col cu1ated,a) r, dose: .

radioacti,ve~nobl e gases.in~aaseroauas . efflnentki'XC'etejling-a'ny~O'fà 'xiii'ii-"t artgerPnale'a'ri'd Saii east.;t'OW~Vk<$ 'he,Cereissjon'ii.thitn~30~ y g~pu 'u ante'o)Spider/ t; ..its.tfi -c se(s)5fordixce'citing.-;"th =:-"..-.. f~igiBon,'9;2~ta~~'-~~'peci'ilgR'eapor't;,whiech..-,)d liriiit(s'f an'd defities e orrective qt ns to be taken to reduce the releases and th posed correctA tions to be taken to assure that subse e releases will be mpliance with the above, limits.

b. The provis of Specifications 3.0.3 and 3.0. a not applicable.

SURVEILLANCE R EMENTS 4.11.2.2 0 se Calculations. Cumulative dose contributions for the r nt calend uarter and current calendar year shall be determined in acco a e with methodolgy and parameters in the OOCM at least once per 31 days ST. LUCIE - UNIT 2 3/4 11-11 Amendment No '3 RA CTIVE EFFLUENTS DOSE DINE-131 IODINE-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM LIMITING ITION FOR OPERATION

3. l1.2.3 The to a MEMBER OF THE PUSLIC from iodine-131, iodine-13, tritium, and all a ionuclides in particulate form with half-lives gr r than 8 days in gaseous uents released, from each reactor unit to area and beyond the SITE SOUN , (see Figure 5. 1-1) shall be limited t'o t ollowing:

a. During any ca n r quarter: Less than or equal to . mrems to any organ and,

b. During any calendar r: Less than or equal t mrems to any or gan.

APPLICASILITY: At al l times. ACTION:

a. Mf:th;,the'".ca ascii fated'duose~from-5 ~ ase";:ofa iod one'-73l,:-fodf qe 133;~~.

trit'tuar;:.a'kaid:;-.radtaau51~1daa ~ii~iIar ='x Tate fdm-iftti~.half,=;Itv'SACN'gruaattSIII: th'hn-"8-days,,<@~gaseous=.,effluen, 'ng.:anyyf -4he~ra5ove.".:1imits-;.~ prepareZaW'O'.FsSumtp~to"tfi~e":. t,'o Sperc<'fieiig)on<6".9.Z,...a-Spec" 'Peppy: f ioiin,;30<day~spuriuant~'to~M:,-. - . 1'dh'nfl'f'ies th'e'"'ca'ose(s:)" for" excee'ding<the liiiiict and d" "e's taken to reduce the rel t tenor'r ve'ctions that have been s and the propo corrective actions to be taken to assure that equent releases wi in compliance with the above limits.

b. The provisions o Specifications 3.0.3 and 3'.0.4 ar ot applicable.

SURVEILLANCE RE UI TS

4. 11.2.3 C tive dose contributions for the current calendar quarter current ca ar year for iodine-131, iodine-133, tritium, and radionucli in parti te form with half-lives greater than 8 days shall be determined in acc nce with the methodology and parameters in the ODCM at least once per ays.

ST. LUCIE - UNIT 2 3/4 11-12 Amendment No. I o 0 RA OACTIVE EFFLUENTS G EO RAOWASTE TREATMENT LIMITI NDITION FOR OPERATION

3. 11 '.4 he ASEOUS RAOWASTE TREATMENT SYSTEM and the VENTILATION EXHAU TREATMENT S TE shall be OPERABLE. The appropriate portions of the GAS

. RADWASTE TREA E SYSTEM shall be used to reduce radioactive material i gaseous waste io to their discharge when the projected gaseous eff u t air doses due to gas ou effluent releases from the site to UNRESTRICTE EAS (see Figure 5. 1-1), wh a eraged over 31 days, would exceed 0. 2 mrad fr gamma radiation and 0.4 m ad or beta radiation. The appropriate port'o of the VENTILATION EXHAUST EA ENT SYSTEH shall be used to reduce r i active . materials in gaseous w st prior to their discharge when the r ected doses due to gaseous effluent el ases from the site (see Figure . 1 ) when averaged over 31 days would excee 0. mrem to any organ. APPLICABILITY: At all times ACTION: N thethe."NSEOUS.RADMAS jind/or')the'. VEN'ILATTION~--;~<. a. EXHAUST~TREATMENT~SYSTEM:: 'p =T, THENT~SY rabl'e~. r, re.-.than l~ days.-or."Nt~-~ gaseou~%aste'-";5'eing~dischare'd- fttt u thea'tYiientWnd~fj'eke'csi+o~ the-.- above;imit's;~prep'ari.'an 'from the release of r'a o ctive materials in.<<'liquid.. or'ase u 'ftf1uiqts'xceeding.',twi'ce,',,limits of Specifica-tion,3,.1'.1 ..1~2'-',.'3;,:, 1:."2b,"-;, =3'-g:2'; 2a;, 3'-.':1;1': ~3'; ll.2. 3a....or; 3".11,',2""..3b.,&ilcula't o '~h'a~1[ be.",-iade.,zfncfif ':-dp'rifctSga'diation~. COntr'ibuQOn'S~:f,'rOIrth;r, aCtOr unfteS-..;acne."""'fr'"Ocu't'i'<'Cfe~,StOnr~aiieYtan'kS~~~ to.='deters)'ne,whether-.=;=th . ove".-'limjts=of'i;Qcatioii3;.-1J.4~have .be~n=-'excidtde'd,, Tenace,- e:ca~s~:r ,e'.b'j+,abum3&¹~he~ CoteateafoÃ'iifth!h,'-30"-dier;, anent to ,',cM(ca Monad:-:6'-,"2~a~, Spec'$a'1$ Rcpojtjthat dcfiii.'s~; h corr vi.:.act'i'on~~at@he"-taken=to reduce~subseq'gent, rel'eas'es~tco: above+1-imi'ts aned~i'nc1"ader'::4he=s A "ve '.C ..dcurrenc'elf~'~exc'eedfrig; the-fo'r a'chieving conformance with the above limits. This Spe Report, a'efined in 10 CFR Part 20.405c, shall include an s that estimates the radiation exposure (dose) to a MEMBER 0 E IC from uranium fuel cycle sources, including all effl pathw and direct radiation, for " the calendar year that in u es the re a (s) covered by this report. It shall also d ibe levels o diation and concentra-tions of radioactive e ial involved, an e pause of the exposure levels or coy trations. If the mated dose(s) exceeds the above limits, a K f the release conditio suiting in viola-tion of 40 CFR Par 0 has not already been c cted, the Special Report shall incl d a request for a variance in ordance with the provisions of 4 R Part 190. Submittal of the rt is considered a timely requ and a variance is granted until s action on the request is c ete.

b. The provis of Specifications 3.0.3 and 3.0.4 are no plicable.

SURVEILLANCE RE U ENTS

4. 11.4. 1 Cum ive dose contributions from liquid and gaseous effluent all be determine accordance with Surveillance Requirements 4. 11. l.f, 4. 11.

and 4.11.2. and in accordance with the methodology and parameters in the

4. 11.4. umulative dose contributions from direct radiation from She reactor units from radwaste storage tanks shall be determined in accordanqe with the odology and parameters in the OOCM. This Surveillance Requirement sha e required only in the event the above Action a. requires the applicable c lations.

LUCIE - UNIT 2 3/4 11-17 Amendment No. 13 3/4. 11 RADIOACTIVE EFFLUENTS BASES

4. 11. 1. 1 CONCENTRATION T s specification is provided to ensure that the concentration of radio t ve materials released in liquid waste effluents from the site to UNRESTR AREAS will be less than the concentration levels specified 'n 10 CFR Pa t 0, Appendix B, Table II, Column 2. This limitation provi e addi"

'tional assb a e that the levels of radioactive materials in bodies f ater outside the t will result in exposures within (1) the Section I . design objectives of p dix I, 10 CFR Part 50, to a individual, and he limits of 10 CFR 20. 10 e) to the population. The concentration limi r dissolved or entrained noble es is based upon the assumption that X 5 is the control-ling radioisotope a s MPC in air (submersion) was conv d to an equivalent concentration in wate u ing the methods described in In r ational Commission on Radiological Protect' (ICRP) Publication 2. 3/4. 11. 1. 2 DOSE This specification is pro i d to impleme e requirements of Sections II.A, III.A and IV.A o A Rendix I, 0 FR Part 50. The Limiting Condition for Operation implement t% gui s et forth in Section II.A of Appendix I. The ACTION statements o i e required oper ating flexibility and at the same, time implement the et forth in Section IV.A of Appen-dix I to assure that the releases gu of d a 'tive material in liquid effluents c 'e ble." The dose calculation will be kept "as low as is reasonab methodology and parameters in the 0 imp m t the requirements in Sec-tion III.A of Appendix I that c f mance wi he guides of Appendix I be shown by calculational proced e based on mo 1 and data, such that the actual exposure of a MEMBER F HE PUBLIC throu propriate pathways is unlikely to be substantia y nderestimated. The q tions specified in, the ODCM for calculating th d es due to the actual re ea e rates of radioactive materials in liquid ef nts are consistent with the me hodology provided in Regulatory Guide l. 1 9 "Calculation of Annual Doses t M from Routine Releases of React fluents for the Purpose of Evaluat g ompliance with 10 CFR Part 50, p ndix I," March, 1976 and Regulatory Gu' l. 113, "Estimating Aquatic Disper io of Effluents from Accidental and Routine ea tor Releases for the Purp s of Implementing Appendix I," April 1977. Thi s ecification applies to the release of liquid effluent om each reacto a the site. For units with shared radwaste treatment syst s the liqu fluents from the shared system are proportioned among the u t sharing th stem. ST. LUCIE - UNIT 2 8 3/4 ll-l RADIOACTIVE EFFLOENTS BASES The B of the liquid radwaste treatment system ens this system will be a a or use whenever liquid effluents 'reatment prior to release to t v ment. The requiremen e appropriate portions of this system be w specific s assurance that the releases of radioactive materials i ents will be kept "as low as is reasonably achievable". This s lements the requirements of 10 CFR Part 50.36a, General sterion endix A to 10 CFR Part 50 and the desig e given in Section . endix I to 10 CFR Part 50. The s >mits governing the use of appro rtions of the liqui treatment system were specified as a suitab ion of the gn objectives set forth in Section II.A of Appendix I, 3/4. 11.2 GASEOUS EFFLUENTS hi specification is provided to ensure that the dose at. any time a a beyond e TE BOUNDARY from gaseous effluents from all units on the will be ws i the annual dose limits of 10 CFR Part 20 to UNRESTRI REAS. The annual'd its are the doses associated with the concertr i s of 10 CFR Part 20, p dix B, Table II, Column 1. These limits o de reasonable assuran t t radioactive material discharged i g eous effluents will not result in th e sure of a MEMBER OF THE PUBLI n UNRESTRICTED AREA, either within or o s e the SITE BOUNDARY, to average concentra-tions exceeding the limits e 'fied in Appendix B a e II of 10 CFR Part 20 o may at times be within (10 CFR Part 20. 106(b)). For the SITE BOUNDARY, the occupancy f at MEMB sufficiently low to compensate factor above that for the SITE BOUNDA for 'r RS OF THE PUB s in THE the PUBLIC will usually be atmospheric specified release rate limits diffusion restrict, at all times, the correspon 'n a a and beta dose rates above background to a MEMBER OF THE PUBL or o the SITE BOUNDARY to less than or equal to 500 mrems/year e total b . to less than or equal to 3000 mrems/year to the skin. e release rate m s also restrict, at all times, the corresponding t r d dose rate above bac r gnd to a child via the inhalation pathway to 1 an or equal to 1500 mrems ar The required ion capabilities for radioactive mat i s in gaseous waste samples a ' ulated in terms of the lower limits of det t n (LLDs). Detailed dis s of the LLD, and other detection limits can be in HASL Proc r Manual, HASL-300 (revised annually), Currie, L. A., 'ts for gu t ive Detection and quantitative Determination Application - Radi sstry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Dete L' for Radioanalytical Counting Techniques," Atlantic Richfield Hanford ST. LUCIE - UNIT 2 B 3/4 11-2 OACTIVE EFFLUENTS BASE This cification applies to the release of gaseous effluents from all reactors a t e site. For units with shared radwaste treatment systems, th gaseous eff1 e s from the shared system are proportioned among the units sharing that s em. 3/ . 11.2:2 DOSE OBLE GASES This specifica o is provided to implement the requirements Sections II.B, III.A n IV.A of Appendix I, 10 CFR Part 50. Th imiting Condition for Operatio I plements the guides set forth in Sec II.B of Appendix I. The ACTION t tements provide the required opera i g flexibility and at the same time .impl t the guides set forth in Sect ' IV.A of Appendix I to assure that e releases of radioactive mat in gaseous effluents to UNRESTRICTED AR will be kept "as low as 'easonably achievable." The Surveillanc quirements implement requirements in Section III.A of Appendix I tha onformance with the ides of Appendix I be shown by calculational procedure sed on models a ata such that the actual exposure of a MEMBER OF TH P BLIC through ropriate pathways is unlikely to be substantially under e t ated. Th ose calculation methodology and parameters established in the OD or calc ting the doses due to the actual release rates of radioactive no 1 gas in gaseous effluents are consistent with the methodology provide s ulatory Guide 1.109, "Calcula-tion of Annual Doses to Man from Routine ases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 art 50, Appendix I," March, 1976 and Regulatory Guide 1. 11'1, "Methods fo s m ting Atmospheric Transport and Dispersion of Gaseous Effluents in Ro e Re e es from Light-Water Cooled Reactors," Revision 1, July 1977. T ODCM eq t ons provided for determining the air doses at and beyond the SI OUNDARY ar sed upon the historical average atmospheric conditions or r al atmospheri nditions. This specification applie o the release of ga e s effluents from each reactor at the site. For un with shared radwaste e tment systems, the gaseous effluents from the red system are proportion d mong the units sharing that system. 3/4.11. 2. 3 DOSE - IOD "131 IODINE-133 TRITIUM AND RAD GLIDES IN PARTICU FORM This specifi ion is provided to implement the requirement Sections II.C, .A and IV.A of Appendix I, 10 CFR Part 50. The > iting Conditions for eration are the guides set forth in";Section;'II.,C o 'endix I. The ACTION s ements provide the required operating flexibility and a the same time i ement the guides set forth in Section,IV.A of Appendix t assure th the releases of radioactive materials in gaseous effluents o UNRESTR D AREAS will be kept "as low as is reasonably achievable." T ODCM c ulational methods specified in the Surveillance Requirements impl nt the requirements in Section III.A of Appendix I that conformance wit he guides of Appendix I be shown by calculational procedures based on m s and data, such that the actual exposure of a MEMBER OF THE PUBLIC ST. LUCIE - UNIT 2 B 3/4 11-3 RADIOACTIVE EFFLUENTS BASES The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with e methodology provided in Regulatory Guide 1. 109, "Calculation of Annual os to Man from Routine Releases of Reactor Effluents for the Purpose o E lu ing Compliance with 10 CFR Part 50, Appendix I," March, 1976 an Regu to Guide l. 111, "Methods for Estimating Atmospheric Transpor an - oled Disper on f Gaseous Effluents in Routine Releases from Light-Wa .Reactors,' ision 1, July 1977. These equations also provide or etermining the actual se based upon the historical average atmospheri or eal meteor-ological condi io . The release rate specifications. for di -131, iodine-133 tritium, and ra n ides in particulate form with half i s greater than 8 days are depende u n the existing radionuclide p w s to man, in the areas at and beyond t TE BOUNDARY. The pathway t were examined in the development of these ca ul ions were: (1) ind id inhalation of airborne radionuclides, (2) deposit n f radionuclides n green leafy vegetation with subsequent consumption by ma depositi o o grassy areas where and meat producing anim ls raze t consumption of the milk and meat milk:".':-'nimals by man, and (4) deposition on the ro w subsequent exposure of man. This specification applies to h e ase of gaseous effluents from each reactor at the site. For units it sha d dwaste treatment systems, the ortioned among the units gaseous effluents from the sh e ystem a p sharing that system. 3/4. 11.2.4 GASEOUS R A TREATMENT The OPERABI f the GASEOUS RADWASTE TREATMENT S M and the VENTILATION EX S Y REATMENT SYSTEM ensures that the sys s ill be available for use whe e gaseous effluents require treatment prior t r ease to the environme . he requirement that the appropriate portions of he systems be use w n specified, provides reasonable assurance that the r e es of radi ct e materials in gaseous effluents will be kept "as low as ason-ab ievable". This specification implements the requirements of 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, a e design objectives given in Section II.D of Appendix I to 10 CFR Part 5 he specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth - '4 l "$'+i. 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. ST. LUG IE - UNIT 2 B 3/4 11-4 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, "Maste Gas System Failure." This specification implements the requiremegts of 10 CFR Part 50.36a a eral Design Criterion 60 of Appendix A to 10 CFR Part 50. The process a m-e included in establishing the PROCESS CONTROL PROGRAM may include, are limited to waste type, waste pH, waste/liquid/solidification / catal atios, waste oil content, waste principal chemical const u ts, and mixing uring times. 3/4. 11. 4 TO L OSE This specifi t n is provided to meet the dose li ions of 40 CFR Part 190 that have e incorporated into 10 CFR Par y 46 FR 18525. The specification requires h preparation and submitt a Special Report whenever the calculated s from plant generat dioactive effluents and direct radiation exceed 25 . s to the total or any organ, except the thyroid, which shall be limit less tha o equal to 75 mrems. For sites containing up to four reactors, 't 's hig y nlikely that the resultant dose to a MEMBER OF THE PUBLIC wi 11 excee t limits of 40 CFR Part 190 if the individual reactors remain within tw e e dose design objectives of Appendix I, and if direct radiation doses from e tor units and outside storage tanks are kept small.. The Special Rep t ill s ibe a course of action that should result in the limitation of th nual dose o MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. the purposes f he Special Report, it 'may 5e assumed that the dose corn nt to the MEMBER PUBLIC from other uranium fuel cycle sources is n ible, with the excepti at dose contributions from other nuclear fu cle facilities at the same i or within a radius of 8 km must be co s red. If- the dose to any HEMBER E PUBLIC is estimated to exc he requirements of 40 CFR Part 190, e ecial Report with a reques a variance (provided the release conditio suiting in violation o 4 CFR Part 190 have~not already been corrected), 'n ccordance with the o sions of 40 CFR Part'"190.11 and 10 CFR Part 20 405 ,,consid .e to be a timely request and fulfills the requirements of R Part until NRC staff action is completed. The variance only rela s o th 1 its of 40 CFR Part 190, and does not apply in any way to the othe ' cerements for dose limitation of 10 CFR Part 20, as addressed in Speci ons 3. 11. l. 1 and 3. 11.2. 1.'n individual is not considered a HEHBER OF TH PUBLIC during any period in which he/she is engaged in carrying out any ST. LUCIE - UNIT 2 B 3/4 11-5 t 3/4. LIMITI 3.12.1 as 12 1 specifi APPLICABILIT 1 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM ONDITION FOR OPERATION e radiological environmental monitoring program shall 'n Table 3.12-1. At al 1 times. be conduc e ACTION: With th diological environmental monitor ng program o being conducte a specified in Table 3.12-1, .prepare and s t to the Coamfssion, the Annual RadioTogical Knvironmenta1 0 rating Report required by'ification 6.9.1; 8, a description he reasons for not conductin e program as required and the pl n for preventing a recurrence. With the confirme level of radioactivity as t result of plant effluents"irV an 'en 'mental-sampl-ing -medi t a specified location exceeding- the-report -levels=of-Table 3. 2 'her'i -.quarter,-pre  :-and suumit-to .Comiiss)on within 30 "days averaged-over-ali'alendat pur'suant-to Speci'ficati n " 6.9.2,' Spe cause(s),for,exceed$ ng-,t i Report" that identif'les-'he 1'im'K(s) a d., eAnes the co'rrecti've'et'io6s to be taken to reduce radi a tive ef 1 ents so that the potential annual dose to a MEMBER OF THE PUB is e than the calendar year limits of Specifications 3.11.1.2, 3.11 , nd 3.11.2.3. When more than one of the radionuclides in Table 3.1 re detected in the sampling medium, this report shall be submitte concentration 1 concen tion 2 reporting eve 1 reportsn evel 2 When radionuclides o than those in e 3. 12-2 are detected and are the result of a effluents, this r t the potential ann 1 dose to A MEMBER OF TH UBLIC is equal to or shall be submitted if greater than th c endar year limits of Spe 'cations 3. 11. 1.2,

3. 11. 2. 2 and 3 1. 2. 3. This report shall incl the methodology for calculat' he cumulative potential dose c ibutions for the calendar ye r rom radionuclides detected in envi o mental samples and can be de ned in accordance with the methodolo and parameters in the ODC his report is not required if the measur level of radio-activi as not the result of plant effluents; howev in such an even , e condition shall be reported and described in e Annual Rad 1 gical Environmental Operating Report.

C. W't milk or broadleaf vegetation samples unavailable from e or more f he sample locations required by Table 3. 12-1, identify 1 tions r obtaining replacement samples and add them to the radiolo environmental monitoring program within 30 days. The specific 'l A o irmatory reanalysis of the original, a duplicate, or a new sample ma s able, as appropriate. The results of the confirmatory analysis shall b c pleted at the ear liest time consistent with the analysis but in any case thin 30 days. ST. LUCIE - UNIT 2 3/4 12-3. Amendment No. Q, 45 LOGICAL ENVIRONHEKTAL HONITORING ACTION: o inued) locat rom which samples were unavailable may then 6e e from the 'ring program. Pursuant to Specificatio . .10, identify th a e of the unavailability of sample n 'ntify the new locatio s for obtaining replacement pl in the next '(s) '3 Semiannual Radioac v Effluent Release Re al so include in the report a revised and tabl o e ODCH reflect:ing the new location(s). I

d. The provisions of Specifica and 3.0.4 are not applicabIe.

SURVEILLANCE RE UIREHENTS

4. 12.1 The io real environmental monitoring samples sh e collected pursuant e 3. 12-1 from the specific locations given in t figur s) 'he T

ODCH, and shall be analyzed pursuant to the requs 2-1 and the detection capabilities required by Table 4. 12-1. le and ts of T e . ST. LUCIE - UNIT 2 3/4 12-2 Amendment No 13 TABLE 3.12-1 RADIOLOGICAL ENVIROHt1EHTAL NOHITORIHG PROGRAN Number of Representative Exposure Path Samples and Sampling and Type and r uency d) and/or Sam le Sam le Locations b) c) Collection Fre uenc of An s

1. DIRECT RADIATION 7 Monitoring Locations Continuous monitoring C mi exposure rate-with sampJ~ collection rterly.

quarterly ,

2. AIRBORNE Radioiodine and 5 Locations Continuo pier Radioiodine Filter:

Particulates oper a o Iith sample I-131 analysis weekly co e on w~eek1, or frequently if r 'd by dust loading Particulate Fil ter: Gross beta radioactivity analysis > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a filter change Gamma i so topi h) ana 1ys i s o f compos i te ~ (by 1 ocati on) quarterly

3. WATERBORNE

a. Sur face h 1 Location Meekly G m isotopic h) 8 tritium ana e weekly 1 Location Honthly Gamma iso i h) 8 tritium analyses mon 1

b. Sediment from 2 Locations Semiannually Gamma isotopic h) a 1 is shoreline semiannually

TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL t10HITORING PROGRAH Number of Representative Exposure Pathway- Frequency d) ~/ amples and Locations Sampling and Collection Fre uenc , e and of Anal sis

4. IHGEST I OH

a. Fish and Invertebrates

. h)

1. Crustacea 2 Locations Semi u Gamma isotopic analyses semiannually

. h)

2. Fi sh 2L io Semiannually Gamma isotopic analyses semiannually

b. Food Pr cts ad leaf 3 Locations 1) Monthly when Gamma isotop vegetation available I-131 analyses mo

TABLE 3. 12-1 (continued) TABLE NOTATION Oevia i ns are permitted from the required sampling schedule if speci .e are un inable due to hazardous conditions, seasonal unavailabili malfunc 'o of automatic sampling equipment or other legitimate re s s. If specim n are unobtainable due to sampling equipment 'ion shall be taken prior to the end of the next s m ing malfunct'orrective period. Al d viations from the sampling schedule shall be d ented in the Annual iological Environmental Operating Report p s ant to Specification 11. l. Specific paramete f distance and direction sector fr he centerline of one reactor, an a ditional description where pert e t, shall be provided for each sa location in Table 3. 12-1 in a able and figure(s) in the OOCH. At times, it may not be ible or practicable o continue to obtain. samples of the media of ch i e at the most des r d location or time. In these instances suitable al e ative media a ocations may be chosen for the particular pathway in qu t on and appr p iate substitutions made within 30 days in t,he radiolog c enviro 1 tal monitoring program. The following definition of freq n ie all apply to Table 3. 12-1 only: >~leekl - Not less than once per cal r week. A maximum interval of 11 days is allowed between the co i of any two consecutive samples. of not less than 7 days betw n sample co 1 tions. A maximum interval of 24 days is allowed between o ection of a wo consecutive samples. ~Monthl - Not less than n e per calendar mon ith an interval oi'ot less than 10 days betw sample collections. ~carter 1 Not les an once per calendar quart s 0 e ample each between calendar date anuary 1 - June 30) and (July 1 mber 31). An interval of not less a 30 days will be provided b t een sample collections. The frequ c of analyses is to be consistent with the sa 1 collection frequenc . One o re instruments, such as a pressurized ion chamber, fo asuring and ording dose rate continuously may be used in p'lace of, o a i on to, integrating dosimeters. For purposes of this table, a moluminescent dosimeter (TLD) is considered to be one phosphor i o or re phosphors in a packet are considered as two or more dosimeters. LUCIE - UNIT 2 3/4 12-5 TABLE 3. 12-1 (continued) TABLE NOTATION

f. Re ~r s to normal col lection frequency. Nore frequent sample col l e i p mitted when conditions warrant.

g. Airbo o rticulate sample filters are analyzed for gross e radioact i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow f don and thoron dau te decay. In addition to the requirement o a gamma isotopic on a o osite sample a gamma isotopic is s required for each sample having a ro beta radioactivity which is .0 pCi/ms and which is also > 1 i s that of the most rece. >trol sample.

h. Gamma isotopic analysis e s the identifi t n and quantification of gamma-emitting radionucli s at may b a ributable to the effluents from the facility.

i. Atlantic Ocean, in the vicinity public beaches along the eastern shore of Hutchinson Island ne t t. Lucie Plant (grab sample).

Atlantic Ocean, at a loca o eyond in e e from plant effluents (grab sample). J Discharges from t 5 . Lucie Plant do.not inf1 c drinking water or ground water pa w s.

1. Samples of o leaf vegetation grown nearest each of o ifferent offsite c sons of highest predicted annual average gro d evel 0/g, and o s pie of similar broad leaf vegetation at an avai la le ocation 15-

' distant in the least prevalent wind direction based u n ical data in the ODCt1. ST. LUCIE - UNIT 2 3/4 12-6 TABLE 3. 12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels at Airborne Particulate Fish Hi 1 k oo roducts Analysis (p or Gases (pCi/ms) (pCi/kg, wet), (pCi/i) i/kg, wet) tl-3 30,000" tin-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,00 Co-60 300 Zn-65 300 20,000 Zr-Hb-95*"" 400 I-131 0.9 100 Cs-134 30 1,000 60 1,000 Cs-137 50 20 2,000 2,000 Ba-La-140*<< 200 30 Since no drink g er pathway exists, a value of 30,000 pCi/2 is used. For drinkin a r samples, a value of 20 0 i/2 is used. This is 40 CFR Part 141 value. Applies o inking water. An qu librium mixture of the parent and daughter isotopes which corresponds to the reporting val o >e arent isotope. TABLE 4.12-1 DETECTIOH CAPABILITIES FOR EHVIROHNENTAL SAMPLE ANALYSIS LOWER LIt1IT OF DETECTIOH (LLO) Wa Airborne Particulate Fish Hilk Food Produ s Sediment -Analysis (pCi/ or Gas (pCi/ms) (pCi/kg,wet) (pCi/2) (pCi/k et (pCi/kg,dry) gross beta 0. 01 H-3 3000" Hn-54 15 130 Fe-59 30 260 Co-58,60 15 Zn-65 30 Zr-Nb-95 15 I-131 ld 60 Cs-134 15 .05 130 15 60 150 Cs-137 18 0. 06 150 180 Ba- La-140 15 Since dr ing water pathway exists, a value of 3000 pCi/R may be used. For drinking water samp, value of 200 Ci is used. I.'J TABLE 4.12-1 (Continued) TABLE NOTATION a T 0th 'ist r does not mean that only these nuclides are to be considered eaks that are identifiable, together with those of the above nucl , shall also be analyzed and reported in the Annual Radiol g al Enviro, tal Operating Report pursuant to Specification 6.9. 1. 1 . b Required t ction capabilities for thermoluminescent dosimet r used for environ al measurements are given in Regulatory Guid 4 13. c The LLD is defi e for purposes of'these specifications s the smallest concentration of a ioactive material in a sample that i 1 yield a net count, above syste ckground, that will be detected 'ih 95% probability with only 5% probab> represents a "real" s'. 1 of falsely concluding that lank observation For a particular measure o system, which may ude radiochemical separation: ~

4. 66 LLD =

E ~ V ~ 2.'2 ~ e hht) blhere: LLD is the "a priori" lower t detection as defined above, as picocuries per unit mass o volu e, s is the standard devi i n of the ba k ound counting rate or of tlute counting rate af a nk sample as p opriate', as counts per minute, E is the counting f ciency, as counts per i ntegration, V is the sample s' in units of mass or volume, 2.22 is the u er of disintegrations per minute.p r icocurie, Y is the r tional radiochemical yield, when applica 1 A, is t e adioactive decay constant for the particular r ds nuclide, and f r environmental samples is the elapsed time between sam e o ection, or end of the sample collection period, and time o c unting Typical values of E, V, Y, and bt should be used in the calculatio ST. LUCIE - UNIT 2 3/4 12-9 TABLE 4. 12-1 (Continued) TABLE NOTATION the fa not as an 't It o be recognized that the LLD is defined as an a riori e e representing the capability of a measuremen s o eriori (after the fact) limit for a par em and r measure-ment. Analys s 1 be performed in such a manner he stated LLDs will be achieved de outine conditions. Occ o y background fluctuations, unavoi le mall sample size presence of interfering nuclides, or other uncon o le circu a s may render these LLDs unachievable. In such case , t ' co i ing factors shall be identified and described in the Annual Ra Environmental Operating Report pursuant to Specification 6. LLD for drinking w ples. If no drin ter pathway exists, the LLD of gamma is p analysis may be used. 'b 7 An e mixture of the parent and daughter isotop w h c es ds to 15 pCi/2 of the parent isotope. ST. LUCIE - UNIT 2 3/4 12" 10 OLOGICAL ENVIRONMENTAL MONITORING 3/4. 1 .2 LAND USE CENSUS LIMITI ONOITION FOR OPERATION

3. 12. 2 A use census shall be conducted and shall identify within distance of (5 miles) the location in each of the 16 meteorologi sectors of ath arest milk animal, the nearest residence and the n r st garden" of grea e than 50 m (500 ft ) producing broad leaf veget 'on.

APPLICABILITY: A 1 1 times. ACT EON:

a. With a land census identifying a location(s) t at yields a calculated dos r dose comoitment greater tha e values currently being calculate Specification 4.11.2.3, ti fy the new location(s) in the next Semia n al Radioactive Effluce ease Report, pursuant to Specification 6.9.

b. With a land use cens 'dentifying a 1 ion(s) that yields a calculated dose or do ommitment (v'a he same exposure pathway) 20K greater than at a 1 ion from ch samples are currently being obtained in accorda c with p cification 3. 12. 1, add the new location(s) to the io o cal environmental monitoring program within 30 days. Th s ing location(s), excluding the control station location, hav the lowest calculated dose or dose commitment(s), via the same e s re pathway, may be deleted from this monitoring program a Oc o r 31 of the year in which this land use census was con c d. s ant to Specification 6.9.1.7;.

identify the new locat') include in P the in t n t Semiannual eport Radioactive revised figure(s) Ei'fluent and Release Report and a o a table for the OOCM e ecting the new o tion(s).

c. The provisions f pecifications 3.0.3 an 3.0.4 are not applicable.

SURVEILLANCE RE UIREME

4. 12. 2 The land e ehsus shall be conducted during the r wing season at least once per 1 nths using that information that wi 11 p o de the best results, such a door-to-door survey, aerial survey, or y consulting local agricu u authorities. The results of the land use ce s shall be included in -Annual Radiological Environmental Operating Rep t ursuant to Specifica o 6.9. 1.8. l "Broa 1 af vegetation sampling may be performed at the site bounda i each of w different direction sectors with the highest predicted. 0/gs in 1 u o e garden census. Specifications for broad leaf vegetation sampli a e 3. 12-1.4b shall be followed, including analysis of control samples.,

ST. LUCIE - UNIT 2 3/4 12-11 Amendment No. f8,45 0IOLOGICAL ENVIRONMENTAL MONITORING 3 1 3 INTERLABORATORY COMPARISON PROGRAM LIMITING C ION FOR OPERATION 3.12.3 Analyses sh e performed on radioactive materials p ied as part 'of an Interlaboratory rison Program that has been app by the Commission." APPLICABILITY: At al 1 times. ACTION: a0 With analyses not being perf s required above, report the corrective actions to th o is 'o in the Annual Radiological Environmental Operati ort purs n to Specification 6.9. 1.8. ,b. The provisions o ifications 3.0.3 a 0.4 are not applicable. SURVEILLANCE RE U

4. 12. 3

~ ~ ary of the results obtained as part of the above requ e ' Inte ab atory Comparison Program shall be included in the Annual Ra ical ir mental Operating Report pursuant to Specification 6.9. 1.8. ST. LUG IE - UNIT 2 3/4 12-12 12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4. 12. 1 MO T ING PROGRAM The radiolog a environmental monitoring program required by specification provi qs epresentative measurements of radiation d radio" active materials in t1 s exposure pathways and for those radi u ides that lead to the highest pot t' radiation exposures of MEMBER F HE PUBLIC . resulting from the statio o ration. This monitor ing pr r implementsSection IV.B.2 of Appendix t 10 CFR Part 50 and ther y upplements the radiological effluent monitor g rogram by verifyin t the measurable concentrations of radioactive m e ials and leveTs f adiation are not higher than expected on the basis of the luent meas em ts and the modeling of the environmental exposure pathways. e ini al specified monitoring program will be effective for at leas t r 3 years of commercial operation. Following this period, prog nges may be initiated based on operational experience. The required detection capab )t s'for v onmental sample analyses are tabulated in terms of the lower i s of detec o (LLDs). The LLDs required by Table 4. 12"1 are consider o imum for routin e ironmental measurements in industrial laboratories I should be recognize t t the LLD is defined as an a priori (before t f ct) limit representing t ability of a measurement system an o as an a gosteriori (after the f t) limit for a particular measurem t. Detailed sc sion of the LLD, and other detection limit an be found in Proc ur Manual, HASL-300 (revised annually), Currie, , "Limits HASL for Quali i'etection and Quantitative Determination - Applica o " 'o Radioch is y," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., tection Limit fo Radioanalytical Counting Techniques," Atlantic Richfield Ha o Co an eport ARH-SA-215 (June 1975). ST. LUCIE "=UNIT 2 B 3/4 12-1 4.12 RADIOLOGICAL ENYIRONMENTAL MONITORING BAS 3/4. 12.2 LA E CENSUS This specif> t' iS provided to ensure that changes in the u areas at and 'beyond the OUNDARY are identified and that modifica to the if requ'y S E radiological environme a monitoring program are made the resUlts of this census. h best information from the door- door survey, from aerial survey or from o ulting with local agricul authorities shall be used. This census t> fies the requirement Section IY. B. 3 of Appendix I to 10 CFR Part 50. s icting the cens o gardens of greater than 50 m~ provides assurance tha s nificant e re pathways via leafy vegetables will be identified and m i red s a garden of this size is the minimum required to produce the quant year of leafy vegetables assumed in Regulatory Guide 1. 109 for co tion by a child. To determine this minimum garden size, the followi m ions were made: 1) 20K of the garden was used for growing broad veget io (i.e., similar to lettuce and cabbage), and 2) a vegetatio eld of 2 k 3/4. 12/3 IHTERLABORATO PARISON PROGRAM The requireme r participation in an approved Inte ab atory Comparison Program is prov e o ensure that independent checks on the e sion and accuracy of e easurements of radioactive material in environ n 1 sample matrices rformed as part of the quality assurance program f e viron-mental 'ring in order to demonstrate that the results are reaso b vali f the purposes of Section IV. B. 2 of Appendix I to 10 CFR Part ST. LUCIE - UNIT 2 B 3/4 12-2 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) C. Secondar Water Chemistr A program for monitoring of secondary water chemistry.to inhibit steam generator tube degradation. This program shall include: (i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all off-control point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the. interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Backu Method for Determinin Subcoolin Mar in A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring.

e. Post-accident Sam lin A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel, (ii) Procedures for sampling and analysis, and (iii) Provisions for maintenance of sampling and analysis equipment. 4 ~~ XH5KE<

g. g.q.$ +~X ( .8.1. g.

ST. LUCIE - UNIT 2 6-15 Amendment No.25 INSERT g4 Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50,36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably The program (1) shall be contained in the DOCH, 'chievable. (2) shall be implemented by operating procedures, and (3) shall in-clude remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the OOCH,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. 106 and with the methodology and parameters in the OOCH,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameter s in the OOCH at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would exuded 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,

8) Limitations on the annual and quarter ly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-.

nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

INSERT g4 (Continued) Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity -in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the OOCM,

2) A Land Use Census to ensure that changes in the use of areas at and'eyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and

3) I artscipation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance pro-gram for environmental monitoring.

ADMINISTRATIVE CONTROLS 48QANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT e~c '6.9.1. 7 wit in 60 days after January 1 and July 1 of each year. The period of t rst eport shall begin with the date of initial criticality. The di ctive Effluent Release Reports shaf1 include a sunxnary of quanti es f radioactive liquid and'aseous effluents and solid e released from the ni as outlined in Regulatory Guide 1.'21, "Measuring, luating, and Reporting dio qtivity in Solid Wastes and Releases of Radio ve Materials in Liquid an as% us Effluents form Light-Water Cooled Nuc Power Plants," Revision I, Jun 19 , with data summarized on a quarterl sis following the format of Appendi B ereof. The Radioactive Effl nt elease Report to be submi within 60 days after January 1 of each year a include an annual s of hourly meteorological data collected over the p v us year. This an summary may be either in PgptA< the form of an hour by-hout is ing on magnet pe of wind speed, wind direction, atmospheric stabil orm of joint frequency distrib io ~ , nd preci of tion (if measured), or in the speed, wind direction, and atmos" heric stability."" This same re rt ~ ~ ~ ~ include an assessment of the ~~~gL radiation doses due to the radioact ~ ~ quid and gaseous effluents released ~ from the unit or station during the io s calendar year. This same report shall also include an assessment f he d tion doses from radioactive liquid and gaseous effluents to BERS OF UBLIC due to their activities inside the SITE BOUNDARY (Fi 5. l-l) duri t report period. All used in making these s essments, i.e., s c ic activity, exposure time assump-'ions and location, shall be i ded in these reports. T meteorological condi-tions concurrent with ime of release of radioa i materials in gaseous effluents, as determ by sampling frequency and me ur ent, shall be used for determining th shall be perform seous pathway doses. The assessme 'n accordance with the methodology and t radiation doses r eters in the OFFSITE DOSE TION MANUAL (OOCM). Every 2 ye sing the previous 6 months release history for i t es and histor ic teorolgical data determine the controlling age group o oth liquid n gaseous pathways. If changed from current submit change gCM to r efl ew tables for these groups and use the, new groups in subseque '5 se ca u tions. Radioactive Effluent Release Report to be submitted 60 days after Janua each year shall al'so include an assessment of radiation doses to the likel ~H&-PU e-peeviou A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material'from each unit. IPtt I ST. LUCIE " UNIT 2 6-18 Amendment No. 78. 18 INSERT g5 gtLe c Q>z f J yl~ The Semiannual Radioact've Efkuant Release Report covering the oper-ation of the unit during the prev'ous P months of operation shall be submitted ~ ihi SOdy f hy . Th p L F11 elude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the..unit. The material provided shall be (1) consistent with the objectives outlined in the OOCH and PCP and (2) in con-formance with 10 CFR 50.36a and Section IV.B. 1 of Appendix I to 10 CFR Part 50. ADMINISTRATIVE CONTROLS ca r year. Acceptable methods for calculating the dose contribution fro iiqui a gaseous effluents are given in Regulatory Guide 1. 109,.March The Radioac 'ffluent Release Reports shall include the followin ormation for each class solid waste (as defined by 10 CFR Part 61) shi offsite during the repor iod:

a. Volume, b, Total curie quan 'specify whether de 'ned by measurement or estimate),

C. Principal radionuclides cify e er determined by measurement or estimate),

d. Type of waste (e. g., dewat t resin, compacted dry ~aste, evaporator bottoms)

e. Type of container , LSA, Type A, B, Large guantity), and Solidification or absorbent (e.g., t, urea formaldehyde).

The Radioactive Ef Release Reports shall include a and description of unplanned re s from the site to'UNRESTRICTED AREAS o ioactive materials in us and liquid effluents made during the repo period. The Ra the 've Effluent Release Reports shall include any changes m ting period to the PROCESS CONTROL PROGRAM (PCP) and to the 0 uring 0 ALCULATION MANUAL (OOCM), as well as a listing of new locations for c culations and/or environmental monitoring identified by the land use cens ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT"Q+~ A>c'. + 6 8 A single submittal may be made for a multiple unit station. AD 'T. LUCIE - UNIT 2 6- 19 Amendment No. I3 ~ ~ ~ 4 U~ J ~U ( P~ ( INSERT g6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the OOCH and (2) Sections IV.8.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. ADMINISTRATIVE CONTROLS ANNUAL RAOIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) N su rize d tabulated results of these analyses and mea~ e s in the format the e in the Radiological Assessment Br cii nical Position, Revision 1, embe 79. In the event that so dual results are not available for in ion h the ~eport, th p shall be submitted noting and'xplaining the re s he miss ts. The missing data shall be submitted as soon as poss in entary report. 6 The reports shall also i d e w a summary description of the radiological enviro onitoring pro  ; least two legible maps" covering all s ocations keyed to a tab i distances and direc-tions from e erline of one reactor; the resu Interlaboratory Compa n gram, required by Specification 3. 12.3; d ss of all a s from the sampling schedule of Table 3.12-1; and ds s of all h4eh-4he-LLO-req~d-by Ta 'o4-a 6.9.1. 9 At least once every 5 years, an estimate of the actual population within 10 miles of the plant shall be prepared and submitted to the NRC. t 6.9. 1. 10 At least once every 10 years, an estimate of the actual population within 50 miles of the plant shall be prepared and submitted to the NRC. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC within the time period specified for each report.

6. 10 RECORO RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least 5 years: Records and logs of unit operation covering time interval at each power level.

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

C, All REPORTABLE EVENTS. Records of surveillance activities; inspections and calibrations required by these Technical Specifications. Records of changes made to the procedures required by Specification 6.8.1. ST. LUCIE - UNIT 2 6- 20 Amendment No. t =0 AOMINISTRATI VE CONTROLS 'RECORO RETENTION (Continued) 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.

.6.10.2 The following records shall be retained for the duration of the unit Operating License:

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

Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories. C. Records of reactor tests and experiments.

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

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

Records of transient or operational cycles for those unit components identified in Table 5.7-1. Records of training and qualification for current members of the unit staff.

h. Records of inservice inspections performed pursuant to these Technical Specifications.

i. Records of quality assurance activities required by the gA Manual.

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 FRG and the CNRB.

l. Records of the service lives of all snubbers including the date at which the service life comences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality.

n. Annual Radiological Environmental Operating Reports; and records of analyses 'transmitted to the licensee which are used to prepare the Annual Radiological Environmental Monitoring Report.

o. Meteorological data, summarized and reported in a format consistent with the recommendations of Regulatory Guides 1.21 and 1.23.

p. Records of audits performed under the requirements of Specifications 6.5.2.8 and 6.8.4.

6. 11 RAOIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent, with the requirements of 10 CFR part 20 and shall be approved, maintained, and adhered to for.all operations involving personnel radiation exposure.

ST. LUCIE - UNIT Z 6-21 Amendment No. of reviews performed for changes to the 22'ecords aade OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRN. AOMINIST ViVe- CONTROLS

6. 13 PROC '-"CONTROI PROGRAM PCP CB e initiated changes to the PCP:

Sh be submitted to the Commission in the Semiannual Radioac ue Release Report for the period in which the chan made. h ubmittal shall contain:

a. Sufficie ailed information to t upor t the rationale

/@PL" for the chan ws ut benefit of nal or supplemental I information; gg,

b. A determination tha e an did not reduce the overall conformance of atere a sin to existing criteria for radio v s tes; and C. ation of the fact that. the chang s en reviewed and nd acceptable by the FRG.

Shall become effective upon review and acceptance by the

6. 14 OFFSITE OOSE CALCULATION MANUAL OOCM I

ice e initiated changes to the OOCM: 1 be submitted to the Commission in the Semiannual Radioa 'v t Release 'Report for the period in which the change s mad ff ive. This submittal shall contain: a.. Suffic t detailed information to total port the ~ationale r change without benef o additional or supple-mental inform on. Information s d should consist of a package of those es the OJ) be changed with each page ushered and provide it n oval and date box, together HSgat appropriate analys luations )ustifying the change(s); '~i)th b~4":determination t e change ll t reduce the accuracy, or "-,< "Wliability d calculations or tp t determinations; and

c. 0 ation of the fact that the change has iewed and o d acceptable by the FRG.

all become effective upon review and acceptance by the FRG. 1 ST. LUCIE - UNIT 2 6-23 Amendment No.'~ ~ ~k* ~ ~ II I It ~ 11 ~>> ~ 4 I I ~ ~ 1 ~ INSERT g7 Changes to the PCP: Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.? q. This documentation shall contain: a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

6) A determination that the change willmaintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2. Shall become effective after review and acceptance by the Facility Review Group and the approval of the PlantPanager.

gene,ca( INSERT PS Changes to the ODCM: Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2q. This documentation shall contain: n) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes(s) and $) A determination that the change willmaintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the Facility Review Group and the approval of the plan rpfanager. /

&eqera L 'QC+ Shall be submitted to the Commission in the fo o a complete, legible copy of the entire ODCM as a part of or concurrent with the SaaiAnnual Radioactive Effluent Release Report for the period of the report jn which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented. M ISTRATIVE CONTROLS

6. 15 R CHANGES TO RADIOACTIVE LI UIO GASEOUS AND SOLIO WASTE TREATME Y MS

6. 15. 1 Lic ee initiated major changes to the radioactive waste sys (liquid, gase and solid):

l. Shall 'reported to the Commission in the Semiannual oactive Effluen elease Report for the period in which the uation was reviewed the Facility Review Group. The discuss'o of each shall contain:

a. A summar f the evaluation that led to t e etermination that the chang ould be made in accordance 10 CFR 50.59.

b. Sufficient d t iled,information to t ly support the reason for the chang 'thout benefit of 'tional or supplemental information;

c. A detailed descrip i n of the ipment, components and processes involved and the in aces i other plant systems;

d. An evaluation of the c e hich shows the predicted releases of radioactive material liquid and gaseous effluents and/or quantity of solid was differ from those previously predicted in the li n e ap 'cation and amendments thereto;

e. An evaluation of change w 'hows the expected maximum exposures to i i idual in the STRICTEO AREA and to the general popul n that differ f those previously estimated in the lice application and arne d nts thereto;

f. A compar s of the predicted release f radioactive materials, in liq and gaseous effluents and in id waste, to the actual rele e for the period prior to when th anges are to be made;

g. A e timate of the exposure to plant operat'n personnel as a e lt of the change; and

,. h ocumentation of the fact that the change was r v wed and found acceptable by the FRG. 2 hall become effective upon review and acceptance by the Licensees may chose to submit the information called for in this Specificati as part of the annual FSAR update. ST. LUCIE - UNIT 2 6 24 Amendment No. ~3 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 ATTACHMENT 3 SAFETY ANALYSIS Introduction In Generic Letter 89-01, the Nuclear Regulatory Commission (NRC) staff stated that it had examined the contents of the Radiological Effluent Technical Specifications (RETS) in relation to the Interim Policy Statement on Technical Specification Improvements. The NRC staff concluded that programmatic controls could be implemented in the Administrative Controls Section of the Technical Specifications (TS) to satisfy existing regulatory requirements for RETS. It was also determined that the operational and surveillance requirements of the current Technical Specifications could be relocated to the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP), as appropriate. The purpose of these Proposed License Amendments (PLAs) is to simplify the RETS while meeting the regulatory requirements for radioactive effluents and radioactive effluent monitoring. These PLAs implement the recommendations made in Generic Letter 89-01 and NUREG 1301. Discussion These PLAs for St. Lucie Units 1 and 2 are intended to accomplish the following:

1. Incorporate programmatic controls in the Administrative Controls section of the TS that satisfy the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50.

2. Relocate the procedural details in current specifications involving radioactive ef fluent monitoring instrumentation, the control of liquid and gaseous effluents, equipment requirements for liquid and gaseous effluents, radiological environmental monitoring and radiological reporting details to the ODCM.

3. Relocate the definition of solidification and existing procedural details in the current. specifications on solid radioactive wastes to the PCP.

4. Simplify the associated reporting requirements.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01

5. Simplify the administrative controls for changes to the ODCM and PCP.

6. Include record retention requirements for changes to the ODCM and PCP.

7. Update the definitions of the ODCM and the PCP to be consistent with the changes discussed above.

Descri tion of Pro osed Chan es Definition 1.18, "Offsite Dose Calculation Manual (ODCM)" have been revised to reflect the change in scope of the ODCM. Definition 1.23, "Process Control Program (PCP)" has been revised to reflect the change in scope of the PCP. Table 3.3-6, "Radiation Monitoring Instrumentation" footnote ***is revised to reference the ODCM. The existing footnote makes references to TS 3.3.3.10 which has been deleted by these PLAs. TS 3/4.3.3.9, "Instrumentation: Radioactive Liquid Effluent Monitoring Instrumentation," Table 3.3-12, "Radioactive Liquid Effluent Monitoring Instrumentation,<< and Table 4.3-8, "Radioactive Liquid Monitoring Instrumentation Surveillance Requirements," have been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls sections as TS 6'.8.4.f, Item 1. TS 3/4.3.3.10, "Instrumentation: Radioactive Gaseous Effluent Monitoring Instrumentation," Table 3.3-13, "Radioactive Gaseous Effluent Monitoring Instrumentation," and Table 4.3-9, "Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements," have been changed to delete all references to gaseous effluent monitoring requirements while retaining all requirements relative to explosive gas monitoring. The operational and surveillance requirements and the related NUREG 1301 Bases sections for the gaseous effluent monitors have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Item 1. The existing St. Lucie TS requirements associated with the "Explosive Gas Monitoring Instrumentation" of Table 3.3-13 have been retained. GL 89-01 supplied Enclosure 4 which provided model specifications for retaining existing requirements for explosive gas monitoring instrumentation requirements that applied on a plant-specific basis. The model specifications do not apply to St. Lucie. St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 The St. Lucie Unit 2 Updated Final Safety Analysis Report (UFSAR) Section 11.3 "Gaseous Waste System" describes the Gaseous Waste Management System (GWMS). Section 11.3.1 m) of the system design bases describes the features to detect and preclude the formation of potentially explosive mixtures of hydrogen and oxygen. Section 11.3.2 "System description" describes the gas analyzer package that is provided to continuously monitor the oxygen concentrations in various plant components where potentially explosive mixtures could develop. The system design was reviewed as part of the Original License review. The NRC staff review and the acceptability of the design is documented in section 11 of the St. Lucie Unit 2 Safety Evaluation Report. Revision 0 and supplemented in section 11.5 of SSER Revision 3. The NRC review of the Unit 1 system is documented in the Safety Evaluation (dated August 18, 1983) and Technical Evaluation Report (EGG-PHYS-6241 dated April 26, 1983). This review was performed in support of Amendment 59 which added the Radiological Effluent Technical Specifications (RETS) to the Unit 1 Technical Specifications. These Safety Evaluations describe the FPL commitment to maintain a safe concentration of oxygen in the system since hydrogen is present in excess. TS 3/4.11.1.1, "Radioactive Effluents: Liquid Effluents Concentration," and Table 4.11-1, "Radioactive Liquid Waste Sampling and Analysis Program," have been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Items 2 and 3. TS 3/4.11.1.2, "Radioactive Effluents: Dose," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Items 4 and 5. TS 3/4.11.1.3, "Radioactive Effluents: Liquid Waste Treatment," has been deleted. The operational and surveillance requirements and the 'related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Item 6. TS 3/4.11.2.1, "Radioactive Effluents: Gaseous Effluents Dose Rate," and Table 4.11-2, "Radioactive Gaseous Waste Sampling and Analysis Program," have been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Items 3 and 7 ~ St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 TS 3/4.11.2.2, "Radioactive Effluents: Dose Noble Gases," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Items 5 and 8. TS 3/4.11.2.3, "Radioactive Effluents: Dose Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Items 5 and 9. TS 3/4.11.2.4, "Radioactive Effluents: Gaseous Radwaste Treatment," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Item 6. TS 3/4.11.3, "Radioactive Effluents: Solid Radioactive Waste," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the PCP. TS 3/4.11.4, "Radioactive Effluents: Total Dose," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.f, Item 10. TS 3/4.12.1, "Radiological Environmental Monitoring: Monitoring Program," Table 3.12-1, "Radiological Environmental Monitoring Program," Table 3.12-2, "Reporting Levels for Radioactivity Concentrations in Environmental Samples," and Table 4.12-1, "Detection Capabilities for Environmental Sample Analysis," have been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.g, Item 1. TS 3/4.12.2, "Radiological Environmental Monitoring: Land Use Census," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.g, Item 2. St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 TS 3/4.12.3, "Radiological Environmental Monitoring: Interlaboratory Comparison Program," has been deleted. The operational and surveillance requirements and the related NUREG 1301 Bases sections have been relocated to the ODCM. Programmatic controls have been added to the Administrative Controls section as TS 6.8.4.g, Item 3. TS 6.8, "Administrative Controls: Procedures and Programs," has been amended to provide new programmatic controls for the ODCM. The addition of Specifications 6.8.4.f, "Radioactive Effluent Controls Program" and 6.8.4.g, "Radiological Environmental Monitoring Program," provide for these programmatic controls. TS 6.9.1.7, "Semiannual Radioactive Effluent Release Report," has been changed to simplify the existing specification and relocate the existing reporting details to the ODCM or PCP as appropriate. In addition, this report and all references to have been changed to an Annual report consistent with the most it recent 10 CFR 50.36a rule change documented in federal register number 57 FR 39353 dated 8/31/92. TS 6.9.1.8, "Annual Radiological Environmental Operating Report," has been changed to simplify the existing specification and relocate the existing reporting details to the ODCM. TS 6.10, "Record Retention," has been changed to incorporate requirements for keeping records of changes made to the ODCM and PCP. TS 6.13, "Process Control Program," has been changed to simplify the requirements of this specification. TS 6.14, "Offsite Dose Calculation Manual," has been changed to simplify the requirements of this specification. TS 6.15, "Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems," has been deleted. The procedural details have been relocated to the ODCM or PCP as appropriate. Conclusion These PLAs are submitted using the guidance of Generic Letter 89-01 and NUREG 1301. The technical content of the specifications transferred to the ODCM and PCP is unchanged. New programmatic controls for radioactive effluent and radiological environmental monitoring have been added to the Technical Specifications. Therefore, FPL concludes that all aspects of the facility safety margin remain unchanged. St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Xm lementation of Pro rammatic Controls for Radiolo ical ,Effluent Technical S ecifications Generic Letter 89-01 ATTACHMENT 4 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission s regulations, 10 CFR 50.92, which state that no significant hazards considerations are involved operation of the facility if in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of new or different kind of accident from any accident previously evaluated; or (3)'nvolve a significant reduction in a margin of safety. Each standard is discussed as follows: (1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated. These Proposed License Amendments relocate the operational and surveillance requirements of the existing Technical Specifications to the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) as appropriate. Programmatic controls have been added to the Administrative Controls section of the Technical Specifications to ensure existing regulatory requirements for RETS are met. No physical change is being made to the facility and all aspects of the safety analysis remain unchanged. Therefore, the proposed amendments do not involve a significant increase in the probability or consequences of an accident previously evaluated. (2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated. These Proposed License Amendments are administrative in nature. No changes to operating limits or surveillance requirements have been made. No physical change is being made to the facility and all aspects of the safety analysis remain unchanged. The dose calculation methods which are being relocated by this change remain unchanged. Therefore, the proposed amendments do not create the possibility of a new or different kind of accident from any accident. previously evaluated. 0 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Im lementation of Pro rammatic Controls for Radiolo ical Effluent Technical S ecifications Generic Letter 89-01 (3) Use of the modified specification would not involve a significant reduction in a margin of safety. These Proposed License Amendments incorporate programmatic controls in the Administrative Controls section of the Technical Specifications that satisfy the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. All technical content is preserved. Therefore, the proposed amendments do not involve a significant reduction in a margin of safety. Based upon the above, we have determined that the amendment request does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant, reduction in a margin of safety, and therefore does not involve any significant hazards consideration. I 0