ML17213B202

Revised Radiological Effluent Tech Specs

ML17213B202
Person / Time
Site:	Saint Lucie
Issue date:	03/29/1983
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17213B201	List: ML17213B200 ML17213B202
References
NUDOCS 8303310060
Download: ML17213B202 (96)

Text

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

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.) . Times shall include diesel .generator starting and sequence loading delays where applicable.

PHYSICS'TESTS 1.28 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.

UNRODDED INTEGRATED RADIAL PEAKING FACTOR - F r

1.29 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.

LOAD FOLLOW OPERATION 1.30 LOAD FOLLOW OPERATION snail be daily power level changes of more than 10~ of RATED THERMAL POWFR or daily insertion of CEAs below the Long Term Insertion Limit.

GASEOUS RADWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TMA~~ NT SYSTEM is any system designed and installed to reduce radioact'e gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of "educing the total radioactivity prior to release to the environment.

>>~R03310060 8~p>>>

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ST. LUCIE UNIT 1 Amendment No.

I DEFINITIONS i~KMBER(S) OF THE PUBLIC 1.32 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 equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.33 The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and shall include the Radiological Environmental Monitoring Sample point locations.

PROCESS CONTROL PROGRAM (PCP) 1.34 The PROCESS CONTROL PROGRAM shall contain the provisions, based on full sc'ale testing, to assure that dewatering of spent bead resins results in a waste form with the properties that. meet the requirements of 10 CFR Part 61 (as implemented by 10 CFR Part 20) and of the low level radioactive waste disposal site at the time of disposal.

PURGE PURGING 1.35 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 to purify the confinement.

SITE BOUNDARY 1.36 The SITE BOUNDARY shall be that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee.

SOURCE CHECK 1.37 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee. for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

ST. LUCIE UNIT 1 1-.6a Amendment No.

TABLE 1.2 FRE UENCY NOTATION NOTATION FRE UENCY At least once per 12 hours D At least once per 24 hours At least once per 7 days 4/n>* At least 4 per month at intervals of no greater than 9 days and a minimum of 48 per year At least once per 31 days At least once per 92 days At least once per 184 days At least once per 18 months S/U Prior to each reactor startup Completed prior to each release N.A. Not applicable

• For Radioactive Effluent Sampling

• • For Radioactive Batch Releases Only ST. LUCIE UNIT 1 1-8 Amendment No.

0 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUMENT OPERABLE f BODES SETPOINT RANGE ACTION

1. 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 16

c. Containment Area - Hi . 1, 2, 3 5 4 < 10 R/hr 1 - 10 7

R/hr 15 Range

2. PROCESS MONITORS

a. Containment

i. Gaseous Activity RCS Leakage Detection 1, 2, 3 8 4 Not Applicable 10 - 10 pCi/cc 14 ii. Particulate Activity

- 6 RCS Leakage Detection 1, 2, 3 8 4 Not Applicable 1 10 cpm/hr 14

b. Fuel Storage Pool Area Yen ti l ati on Sys tern

i. Gaseous Activity 10 - 10 pCi/cc 12 ii. Particulate Activity 1- 10 cpm 12

• lilith 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 with requirements of Specification 3.3.3. 10.

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE -

ALARM MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

2. PROCESS MONITORS (Continued)

c. Noble Gas Effluent Monitors Radwaste Building Exhaust System (Plant Vent Exhaust Monitor) 1,2,38I4 *** 10 10 pCi/cc 15 ii. Steam Generator Blowdown Treatment Faci 1 i ty Bui1 ding Exhaust System 1,2,38I4 10-7 10-2 Ci/cc 15 Steam Safety Valve Discharge 1/Header 1, 2, 3 8 4 *** 10 10 pCi/cc 15

• • • 5 1V. ECCS Exhaust- 1/Train 1, 2, 3 8 4 10 10 pCi/cc 15

• • • The Alarm Setpoints are determined and set in accordance with the requirements of Specification 3.3.3. 10.

k TABLE 3.3-6 Continued TABLE NOTATION ACTION 12 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

ACTION 13- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I ACTION 14- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Spec ifi cat ion 3.4.6.1.

ACTION 15 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

') Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 16 - With the number of channels OPERABLE less than required by the

~

Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ST. LUCIE - UNIT 1 3/4 3-23 Amen'dment No.

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVE ILLANCE INSTRUMENT CHECK CALIBRATION TEST RE UIRED

l. AREA MONITORS

a. Fuel Storage Pool Area

b. Contai nment { C IS)

Containment Area - High Range 1,2, 354

2. PROCESS MONITORS

a. Fuel Storage Pool Area-Venti lation System

i. Gaseous Activity Particulate Activity

b. Containment

i. Gaseous Activity RCS Leakage Detection 1, 2, 3 8 4 ii. Particulate Activity RCS Leakage Detection 1, 2, 3 & 4 "With fuel in the storage pool or building.

• • With irradiated fuel in the storage pool.

TABLE 4.3-3 (Continued)

RADIATION MONITORING INSTRUtlENTATION SURVEILLANCE RE UIREMENTS CHANNEL t10DES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE I NSTRUNENT- CHECK 'CALIBRATION TEST IS RE UIRED

2. PROCESS llONITORS (Continued)

c. Noble Gas Effluent Monitors ii.

Radwaste Building Exhaust System Plant Vent Monitor Steam Generator Blowdown Treatment Building Exhaust R',2,384 1,2,38(4 System Steam Safety Valve Discharge 1,2, 354 iv. ECCS Exhaust 1,2, 354

NSTRUMENTATION METEORO OC:CAL INSTRU!:ENTAT ON

'IM 'INC CGNO T 'N OR GP RA i ION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be GPERABL .

APPLICABILITY: At al 1 times.

ACTION:

With the number of OPERABLE meteorological monitoring channels less than required by Table 3.3-8, suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel(s) is restor'ed to OPERABLE status.

b. With one or more requi red meteorological monitoring channels inoperable, for more than 7 days, prepare and submit a Special Re'port to the Commission pursuant to Specification 6.9. 2 within the next 10 days outlining the cause of the malfunction and the plans Gr restoring the channel(s) to OPERABLE status.

c:. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.'URV" ANC- P OU~R 8 0 S

4. 3. 3. 4 Each of the above meteorological monitor ino instrumentation c~ annels shall be demonstrated OPERABLE by the performance of ihe CHANNEL CHECK ard CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

X The Meteorological Instrumentation system is shared between St. Lucie - Unit 1 and St. Luci e - Unit 2.

"*The emergency power source may be inoperable in Modes 5 or 6.

11 ST,. LUCIE - UiVIT I 3/4 3-30 Amendment No.

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMEHT MINIMUM MINIMUM CHANNELS INSTRUMENT 8( ELEVATION ACCURACY OPERABLE

1. MINDSPEED a) Nominal El ev (10 meter s) + 0. 5 "mph 1A b) Hominal El ev (57. 9 meters) + 0.5 "mph N. A.

2. MIND DIRECTION a) Hominal Elev (10 meters) 50 18 b) Hominal Elev (57.9 meters) 50 H. A.

3. ,AIR TEMPERATURE (Delta T) a) Hominal Elev (10 meters) 0 10Cx~ 1C

+ O.a'C<> C b) Nominal Elev (57.9 meters) c) Hominal Elev (33. 5 meters) + 0.1 C"" H. A.

Starting speed of anemometer shall be'< 1 mph..

bT measurement channels only.

A The 57.9-meter channel may be substituted for <he 10-meter wind speed for up to 30 days in the event the 10-meter channel is inoperable. Mind speed data from the 57.9-meter elevation should be adjusted using the wind speed power law:

S 10 meters = 57.9 meters ..

(0.1727) where:

S = wind speed in mph n = 0. 25 for Pasqui ll Vertical Stability Classes'A,B,C,D.

= 0.50 for Pasquill Vertical Stability Classes E,F,G:

n 1.727 x 10- = constant = 10 meters/57.9 meters B

The 57.9-meter channel may be substituted for the 10-meter wind direc 'on channel for up to 30.days in the event the 10-meter channel is inoperable.

C The 33.5-meter channel may be substituted for one of the 10-met r or 57.9-meter temperature channels >or up to 30 days if one of'he channels is inoperable. The data should always be normalized to 'C/100 meters to determine the ve. tical stability class.

ST. LUCIE - UNIT 1 3/4 3-31 Amendment No.

TA8LE 4. 3-5 METEOROLOC:CAL MONITORING IHSTRUMEHTAT:OH SURVEI'ANCE REQUIREM HTS CHANNEL CHANNEL INSTRUMENT CHECK CALI8 RAT ION

1. MIND SPEED a) Hominal Elev (10 meters) 0 SA b) Nominal Elev (57.9 meters) D* SA~

2. MIND DIRECTION a) Nominal Elev (10 meters) 0 SA b) Nominal Elev (57.9 meters) DA SA"

3. AIR TEMPERATURE (DELTA T) a) Nominal El ev (10 meter s) D SA b) Hominal Elev (57.9 meters) Do SA c) Nominal Elev (33.5 meters) 0* SA" "Required only if these channels are being substituted for one of the Minimum Channels Operable as per Table 3.3-8.

ST. LUCIE - UNIT I 3/4 3-32 Amendment No.

IN STRUMIENTATi ON R'0::O'CT:VE LIQUID EFFLUEHT MONITORING IHSTRUMENTAT:OH LIM:TING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA8LE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11. 1. 1 are not exceeded. The alarm/

trip setpoints of these channels shall be determined in accordance with the metnodolooy and parameters in the OFFSITE DOSE CALCULATiON MANUAL (ODCM).

APPLICABILiTY: At al l times.

ACTION:

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid eIfluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTiOH shown in Table 3. 3-12. If the inoperable instruments are not,returned to operable status within 30 days, exp'iain in the next Semiannual Radioactive Effluent Release 'Report why the inoperability was not corrected in a timely manner.

C. The provisions of Specifications 3. C.3, 3.0. 4 and 6.9. 1.9 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERA8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALiBRATiOH and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

ST. LUCIE - UNIT I 3/4 3-45 Amendment No.

TROLE 3. 3-12 RnoroncTrvE I.I UII) EI I.I.UEHT tIOHI IORIHG IHSfAUtlcHTRTIOH tlIHIt1UM CIIRNNCLS INSTRUtIEHT ot'EIIRBLE RCl I otl GItoss ItnoroncTrvr Tv t<OHITons I RovroINc RLRI<H RHn RUTOI'IRTIC TEIIIIIHRTIOH OF RELERSE Liquid tta<twaste Effluent. Line

h. Steam Generator Blowdown Eff'luenL Line 1/SG 2 I-LOW ttnTE vERSUREIIENl nEvrcES

a. Liquid Badwaste Effluent Line Nn 3

b. Oiscl>arge Canal

c. Steam Generator Dlowdown Cffluent Lines

TABLE 3. 3-12 (Continued)

TABLE NOTATION

'T:Ot< With ihe number of channels OPERABLE less than required by the ttinimum Channels OPERABLE requirement,. effluent r eleases may continue for up to 14 days provided thai prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4. 11. l. 1.1~.and

b. At least two technically qualified members of the Facility Staff independently verify. the release rate calculations and discharge line valving (one performs, one verifies);

Otherwise, suspend release of radioactive effluents via this pathway..

ACTION 2-- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 2 x 10-'icrocuries/gram:

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the soecific activity of the secondary coolant is greater than 0.01 mi,crocuries/

gram DOSE E(UIVALEHT I-131.

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

ACTIOH 3- Minimum system design flow of required running pumps shall be utilized for MPC calculations for discharge canal flow 2nd maximum system design flow shal 1 be utilized for MPC calculations for effluent line flow.

ST. LUCIE - UttIT 1 3/4 3-47 Amendment Ho.

Tnl3LE 4.3-0 RnDIOAC1IVE l.I UID EFrt.uEHT tloHI1ORIHG IwSTRl!t~Et<TATIow suRvrILl.nHcc Rr: UIRctlrHTS I

n cllnHthcL m CIIAHHEL SOURCE CIIANNEL ruHCTioNAL It<STRUHEHT CllECK CIIECI( CALIBRnTIoH Tl.:ST

1. CROSS OCTA OR GAtltln RADIOACTIVITY NONITORS PROVIDIHG ALARM AHD AUTotlATIC TERtlIHATIOH or Ra.cnsc

a. l.iqui<t Radwaste Effluent Line R(2) 0(1) li. Steam Generator Blowdown Eff1uent Line R(2) 0(1)

2. I.LOW HAll=. tlEASUREHEHT DEVICES

a. Liquid ttadwaste Effluent Line N.n.

b. Steam Generator Blowdown Effluent Line N. A.

TABLE 4. 3 8 (Continued)

TABLE NOTATION

( ) The CHANNEL FUHCTiONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Ins rument controls not set in operate mode.

(2) The initial CHANNEL CALIBRATiON for radioactivity .measurement instrumentation shall be performed using one or more of the reference standards traceable to -the Hational Bureau of Standards or using standards that have been calibrated against standards certified by the NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities that are typical of normal plant operation. For subseouent CHANNEL CALIBRATiOH, button sources that have beon related to the initial calibration'may be used.

ST. LUC IE - UNIT I 3/4 3-49 Amendment No.

INSTRUMENTATION RAG IOACT VE GAS FOUS FFLU NT >>O>V>TOR ING INSTRUYENTAT ON L M:T:NG CONG '.IO>V FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OP RABLE with their alarm/trip setooin s set to ensure that the limits of Specification 3. 11. 2. are not exceeded.

1 The alarm/trio setpoints of these channels shall be determined in accordance with tt e methodology and parameters in the ODCH.

APPLICABiLITY: As shown in Table 3.3-13 ACiION:

C~ With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Specifica ion, immediately suspend the release of radio-active gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. 'r/ith less than the minimum number of radioactive gaseous effluent 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, expla(n in the next Semiannual Radioactive Effluent Release .Report why 'he i "operability was not corrected in a timely manner.

C. The orovisions of Speci>ications 3.0.3, 3.0.4, and 6.9. 1.9 are not applicable.

SURV ILLANCE REQUIREMENTS e

4.3.3.11 Each radioactive oaseous e> fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

ST. LUCIE - UNIT 1 3/4 3-50 Amendment No.

TROLL 3. 3-13 RAOIOACTIVE GASEOUS EFFLUEHT MOHrlORIHG IHSTRUMENTATIOH MINIMUM CHANNELS INSTRUMENT OPERAOLE AP PL I CAB I I.ITY ACTION WSTE GAS OECAY TANKS

a. Noble Gas Activity Monitor - Providing Alarm and hutomati:c Termination of Release

2. HASTE GAS DECAY TANKS EXPLOSIVE GAS MONITORING SYSTEM

a. Oxygen Moni tors

3. COHOENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor PI.ANT VLHT SYSTEM

a. Noble Gas Activity Monitor (Low Range) .

b. Iodine Sampler

c. Pa> Liculate Sampler

d. Flow Rate Nh

e. Sampler Flow Rate Monitor

I l TRI)l.l: 3.:3-13 ((:onL innerl)

ARI) lOA(;CIVI: (;ASI:.OUS I:I'I I:Ul tll'IOI11 l()lt ltlC IHS fltUfll:tITRTIOH

'l I HI IIIIII (:I IRHHt'.LS I HSTIIUt ll:HT Ol'I.'IIRI)I.I'. AVI'I. I CRI) I I. I TY I:ULL STOIIRGI.. RAER VLHTILRTIOtt SYSTFti Hohle Gas RctiviLy tloniLor (Low Itange)

Ii. Io(line Sampler

c. I'arLic()1aLe Sampler il. I:low ItaLe tlonitor

e. Sampler Flow Ital.e tlonl Lol

6. S li:AII (;FHI.:nATOn I) I.O3tnOMH Out u) IHO VEHT

. SYS I'I't1 ttolile Gas RcLiviLy t1onitov I). Io(line Sampler

c. I arLi co'I a Le Sampl er

~l. F low ltaLe tloniLor

e. Sampler Flow llaLe HoniLor

TABLE 3. 3-13 (Continued)

TABLE NOTATION x <~

1] times During waste gas system ooeration.

"""At all times when air 'ejector exhaust is not directed to plant vent.

ACT OH ..-1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release:

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

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup (one performs, one verifies).

I Otherwise, suspend release of radioactive effluents via this pathway.

ACTION With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for to-30, days provided the flow rate is 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 . 3- the number of channels v'ith OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for Isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION -~ - Maximum system flows shall be utilized in the determination of the instantaneous release monitor alarm setpoint.

ACTiOH 6 - "

With the number of channnels 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 partitioner at least once per s; r 24.'our "ACTION .-6 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent r eleases via the affected pathway may continue for up to 30 days provided

,samples are continuously collected with auxiliary sampling equipment as required in Table 4. l~-2.

ST. LUCIE - UNIT 1 3/4 3-53 Amendment No.

TAI3LE 4.3-9 RADIOACTIVE GRSEous EFFLUEHT HONITORIwG IrlsTRUIIENTRTION suRVEILLnwCE RL'IREHENTS CIIRNHEL IIODI.'S IH 'IIIIICII CI IANNI..L SOURCE CIIRHHEL FuwcclownL SURVE I L I.At< C IHSTRUIIEI<T CIICCK CIICCK CRLII3RATION TEST 'UtBEI) I'ltl.

1. MnSTC GAS nECAY TANKS Noble Gas Activity Honitor-Providing Alarm and A>>tomatic Termination of Release R(3) Q(l)

z. wnsTE Gns occnY TANKS ExpLOSIVE GRS I'IOHI10RItlG SYSTEt'I

a. Oxygen lIonitor N.A.

b. Oxygen Honitor (alternate) H. R. Q(5)

'A

'A'A

3. Cotll)LtISEII EVACUATION SYSTEM

a. Noble Gas Activity Monitor H, It(3) Q(2) 'A"A'LRNT VEtlT SYSTEH

a. Hoble Gas Activity t1o>>itor R(3) q(z)

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

c. Partic>>late Sampler H.n. N. A.

d. Sampler Flow Rale Honi tor N:A.

1'RDI f: 0.3-9 (ConLfnuecl) ltRDIOR(TrVE GASLOUS El I'.lJFN'I'()Ital()ltft<( 1tlSIItlllll:tll'RlION SltltVI rl.l RHCI'. ftl:()I/fftCIII:.NIS..

C<<RNNf:L HODI:S l<<WIIIC<<

C I IRNHI=. L sou<<CE c<<RHNEI. I'UNCTIONAL 5 UltVL I I.l.AllC L 1HSTltlttIEN I CIIECI< c<<ECK chLfoithTroH TFST lt I.'(U I lt I'. 0

~J. r:ur:I. STOlthGE nrtER VL'HTrLA rrOH SYSTEII

a. tlob 1 e Gas Rc ti v i ty Honi tor It(3) . 0(~)

b. lo(line Sampler N.n.

c. I'arLiculate Sampler A. N.n. H. R.

h

d. Sampler Flow ltaLe Honitor H. R.

STI RH GENEItATOlt DI.O)IDOMN OUILDIHG Vl:N D'.

I'.

floble Gas Activily tfoniLor It(3) c(~)

b. I o<l I ne Sampler H. R. H.n.

c. I'ar L i cu1a te Samp1e> H. A. H. R. H. R.

(I. Samp1er F1ow Ital;e -lloni Lor N. h.

TABL" 4. 3-9 (Continued)

TABLE HO!AT!QH Ai all iime other ihan when the line is valved ou'nd locked.

"; Curing waste gas holdup system operation.

At all times when air ejector exhaus is not direcied to plant vent (1) The CHANNEL FUNCTiONAL TEST shall also demonstraie that automaiic isolation of ihis pathway and control room alarm annunciation occurs if any of the following conditions exis is:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale fai lure.

Instrument controls not set in operate 'mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any oi the following conditions exists:

l. instrument indicates measured levels above the alarm seipoint.

2. Circuit fai lure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

M (3) The initial C,",AHNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been calibrated against standards certified by the HBS. These standards should permit calibrating the system over its iniended range of energy and rate capabilities thai are typical of normal plant operation. For subsequent CHANNEL CALIBRATiOH, buiton sources that have been related to ihe ini iial calibration may be used, at intervals of at least once per 18 months.

(4) The CHANNEL CALIBRATION shall include the use of s iandard gas samples coniaining a nominal:

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

ST. LUG IE - UNIT 1 3/4 3-56 Amendment Ho.

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~ ~

~ ~

~ ~

~ ~

~ ~ II ~ ~

~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ 0

~ ~ ~ ~

~ ~ ~ ~

~ I 0 ~

- TABLE 4. 11-1 RADIOACTIVE L QUID MASTE SAMPLING AND ANALYSIS PROGRAM Lower Limi t Minimum of Detection Liquid Release Sampling Analysis Type of Acti vi ty (LLD)

Type Frequency Frequency Analysis (pCi/ml)

A. Batch Waste p p

-7 Release Each Batch Each Batch Principal Gamma Sx10 Tanks Emitters I-131 1xl0 p Dissolved and 1 xl 0 One Batch/M Entrained Gases (Gamma Emitters) p M H-3 1xl 0 b

Each Batch Composite Gross Alpha 1 xl 0 p Sr 89, Sr-90 5xl0 b

Each Batch Composite Fe-55 1xl0

-7 B. Continuo~~ 4/M Principale Gamma 5x10 Releases Daily Composite Emitters I"131 1xl 0 D 4/M Dissolved and 1xl 0 Grab Sample Composite Entrained Gases Dai ly (Gamma Emitters)

M H"3 lxl0 Daily Composite Gross Alpha 1xl 0 Q SI-89, Sr-90 5x10 Dai ly Composite Fe-55 1xl 0 C. Settl jng W Principale Gamma 5x10 Basin Grab Sample Emitters 1-131 1x10 ST. LUCIE - UNIT 1 3/4-11-2 Amendment No.

TABLE 4. 11-1 (Continued)

TABLE NOTATION The LLO is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95.o probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 sb LLO =

E ~

V ~

2.22 ~

Y - exp(-4t)

Mhere:

LLO .is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, sb is the standard deviation of the background counting rate or'of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A, is the radioactive decay constant for the particular radionuclide, and

~t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and ht should be used in the calculation.

ST. LUG IE UNIT 1 3/4 11-3 Amendment No.

TABLE 4. 11-1 (Continued)

TABLE NOTATION

b. A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. A batch release is the discharge, of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

d. A continuous release is the discharge of liquid ~astes of a nondiscrete volume, e. g., from a volume of a system that has an input flow during the continuous re.ease.

,e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and repor ted.

Grab samples to be taken when there is confirmed primary to secondary system leakage indicated by the air ejector monitor indicating > 2x background.

If Component -5 Cooling Mater activity is >lx10 pCi/ml, perform a weekly gross activity on the Intake Cooling Water System outlet to ensure the

,activity level is < a 2xl0 pCi/ml LLD limit. If ICW is >2x10 pCi/ml, perform analysis in accordance with a Plant Continuous Release on this Tabl e.

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

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION

3. 11. 1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5. 1-1) shall be limited:

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

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any At all times.

organ.'PPLICABILITY:

ACiIOH:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6. 9. 1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defi'nes the correc .ive actions to be taken to reduce the releases and radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrems to the total body and lO mrems to any organ.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 3l days.

ST. LUC IE - UNIT I 3/4 11-5 Amendment No,

RADIOACTIVE EFFLUEHTS LIQUID WASTE TREATMENT LIMITIHG CONDITION FOR OPERATION

3. 11. 1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid ef luent from the site to UNRESTRICTED AREAS (see Figure 5. 1-1) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0. 2 mrem to any organ.

APPLICABILITY: At al 1 times.

ACTION:

'a ~ With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.9. 1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9 ' a Special Report which includes the following information:

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

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

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

b. The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be pr'ojected at least once per 31 days, in accordance with the ODCM unless the liquid radwaste treatment system is being used.

4. 11. 1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABL by operating the 1'iquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

ST. LUCIE - Ut/ IT 1 3/4 11-6 Amendment No.

RADiOACTiVE EFFLUENTS 3/4. 11. 2 GASEOUS EFFLUENTS DOSE RATE LIMITiNG 'CONDITION FOR OPERATION 3.11.2.1 "The dose rate in UNRESTRICTED AREAS due to .radioactive materials released in gaseous effluents from the site (see Figure 5. l-l) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than -or equal to 3000 mrems/yr to the skin, and

b. For iodine-131, iodine-133, tritium, and all radionuclides in parti-culate form with hal'f-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTTON:

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

SURVEII LANCE REQUIREMENTS 4.11.2 1.1

~ The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4. 11.2. 1.2 The dose rate due to iodine-131, iodine-133, tritium,.and all radionuclides in particulate form with half,-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCH by obtaining representative samples and performing analyses in accordance with the .

sampling and analysis program spedified in Table 4. 11-2.

ST. LUG IE - UNIT I 3/4 11-7 Amendment No.

ThllLE n.11-2 F'I IIADIGRI.TIVE GASI.OUS MASTE Shtff)LING AHO AHALYSIS PIIOGIthtl

>>1m>>m l.owev LimiL of .

Sillllp1 I I)(J hnalys)s Type o f OQLection (I.l.l))

T I. re( u'enc AcL1viL Anal sis IC ilml )

P f)

h. i)as te Gas S tora(Je Each Tank Eacl) fa>>k I'v)>>clf)al Gajjljjla Em) tters e 1xl 0 I'a>>k GI al)

Sall) )1Q P

I) e l3. Cojjtainment Purge Each Purge Eaclj I'urge I'r i nc i pal Gamma Emi L t Q rs 1 x10.

Ciral)

Sajjj le II-3 lxl0 Q

C. (:I) I'1 ajjt Yenl. 0/H I'rincipal Gamma Emit.ters Ixl0 (2) I:ue1 Ou i 1 d i ll(J Grat)

Ve>>L Sample (3) SLeam General.ov II-3 lxlO Olowdown Oui 1di>>( Vejjt

0. Rll ftelease Types Contijjuous d n/I,I I-131 xlO- 12 as 1 isLed in R, 0, Cl jarcoal C al)ove. Sajjj le d 11 Co>>tI>>nous C/tf Pvi>>cipal Gamma EmiLtevs xlO I aj'L1c(ll at'e (1-131, OLI)evs)

Sam )le d

Cont1>>(Ious tl (iross Rll)lja 1xl0 Colllt)05 I Le PaI'L I c(l I il L'e Sample d v- iJO Con t1 fl(lo(ls (f S I'-09, S Ix lg Cojjjposi Le

('art Icj)1aLQ S aIIII)1 e COI)tfI)uous d ~

Hof)le t'Io>> I Lo'I'oble Cia.,

Gross Ciases OQLa ov Gajllljl<l Ix IO

TABLE 4. 11-2 Continued)

TABLE NOTATION

a. The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95~ probability with only 5Ã probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 sb LLD =

E ~

V ~

2. 22 ~

Y - exp(-4t)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the courting efficiency, as counts per disintegration, V is the sample size in units of mass or volume,

2. 22 is the number of disintegrations per minute per picocurie, Y is the frac'!ional radiochemical yield, when applicable, A, is the radioactive decay constant for the particular radionuclide, and ht for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and bt should be used in the calculation.

ST. LUCIE - UNIT I 3/4 11-9 Amendment No.

TABLE 4. 11-2 (Continued)

TABLE NOTATION Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POMER change exceeding 15M of RATED THERMAL POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the DOSE EQUiVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor sho~s that effluent activity has not increased by more than a factor of 3..

Samples shall be chanoed at least 4 times a month and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).

Sampling shall also be performed at least once per 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 shutdown, startup or THERMAL POMER change exceeding 15K of RATED THERMAL POMER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses 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) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has increased by more than a factor or 3. When samples collected fo'r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3. 11. 2. 1, 3. 11. 2. 2 and 3. 11. 2. 3.

The principal gamma emitters for which the LLD specification app) ies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138- for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-13I', Ce-141 and Ce-144 for particulate,emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported.

ST. LUCIE - UNIT I 3/4 11-10 Amendment No.

RAOIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONOITION FOR OPERATION

3. 11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNOARY (see Figure 5. 1-1) shall be limited to the following:

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

b. Ouring any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION

a. Mith the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report 'required by Specification 6.9. 1, prepare and'submit to the Commission within 30 days, pursuant to Specification 6.9..2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to r duce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.2 Oose Calculations. Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodolgy and parameters in the OOCM at least once per 31 days.

ST. LUCIE - UNIT I "

3/4 11-11 Amendment No.

RADIOACTIVE EFFLUENTS DOSF - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMIT:NG CONDITION FOR OPERATION

3. ll.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit to areas .at and beyond the SITE BOUNDARY, (see Figure 5. 1-1) shall be limited to the following:

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

b. During any calendar year: Less than or equal to 15 mrems to any or gan.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives, greater than 8 days, in gaseous effluents exceeding any of the above li'mits, in lieu of a Licensee Event Report, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with 'half-lives greater than 8 days shall be determined in accor dance with the methodology and parameters in the ODCM at least once per 31 days.

ST. LUCIE - UNIT 1 3/4 11-12 Amendment No.

RADIOACTIVE EFFLUENTS GASFOUS RADMASTE TREATMENT LIM!TING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADMASTE TREATMENT SYSTEM and the VENTILATIOH EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADMASTE TREATMEHT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site to UNRESTRICTED AREAS (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projec ed doses due to gaseous effluent releases from the site (see Figure 5. 1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY: At al 1 times.

ACTION:

Mith the GASEOUS RADMASTE TREATMENT SYSTEM and/or the VEHTILATIOH EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, .in lieu of any other report required by.Specifica-tion 6.9. 1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

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

2. Action(s) taken to restore the inoperable eouipment to OPERABLE status, and II

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

b. The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 11.2. 4. 1 Doses due to gaseous releases from the site to UNRESTRICTED AREAS shall be projected at, least once per 31 days, in accordance with the ODCM unless the GASEOUS RADMASTE TREATMENT SYSTEM, is being used.

4. 11.2.4.2 The GASEOUS RADMASTE TREATMEHT SYSTEM and VENTILATION EXHAUST TREATMEHT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VEHTILATIOH EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appro-priate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

ST. LUCIE - UNIT I 3/4 11-13 Amendment No.

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS l>IXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than or equal to ZX by volume whenever the hydrogen concentration exceeds 4~ by volume.

APPLICABILITY: At all times.

ACilOH:

With the concentration of oxygen in the waste gas decay tank greater than 2X by volume but less than or equal 4~ by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas decay tank greater than 4~ by volume and the hydrogen concentration grea er than 2" by volume, immediately suspend all additions of waste gases to the system and immediately commence reductior of the concentration. of oxygen to less than or equal to 2 by volume.

C. The provisions of Specifications 3. 0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas decay tank shall be de ermined to be within the above limits by continuously monitoring the waste gases in the on service waste gas decay tank with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

ST. LUCIE UNIT I 3/4 11-14 Amendment No.

RAOIOACTIVE EFFLUENTS CAS STORAGE TAHKS LIMITING CONDITION FOR OPERATION

3. 11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 285,000 curies noble oases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a ~ Mith the quantity of radioactive material in any gas storage tank exceeding the above -limit, immediately suspend all additions of radioactive material to the tank, and provide prompt notification t'o the Commission.

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

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank when reactor coolant system activity exceeds 100

- E ST. LUCIE UNIT I 3/4 11-15 Amendment No.

RADIOACTIVE EFFLUENTS 3/4. 1" . 3 SOLID RADIOACTIVE WASTE LIMITING CONDITION fOR OP ERAT ION Cl

3. ll.3 Radioactive bead resins shall be dewatered, as appropriate, in accor-dance with. the PROCESS, CONTROL PROGRAM'to meet shipping and transporta ion requirements during ransit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At al 1 times.

ACTION:

With dewatering not meeting disposal site and shipping and transpor" tation requirements, suspend shipment of the inadequately dewatered bead resin and correct the PROCESS CONTROL PROGRAM, the procedures and/or the dewatering system as necessary to prevent recurrence.

b. With dewatering not performed in accordance with the PROCESS COHTROL PROGRAM, (1) if the dewatered bead resin has not already been shipped for disposal, 'verify each container to ensure that it meets burial ground and shipping requirements and (2) take appropriate adminis-trative action to prevent recurrence.

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

SURVEILLAHCE REOUIREMENTS

4. 11.3 Prior to disposal, 'each container of radioactive bead resins shall be tested for free standing liquids in accordance with the PROCESS CONTROL PROGRAM to assure that it meets shipping, transportation, and disposal site requirements.

ST. LUCIE - UNIT 1 3/4 11-16" Amendment No,

RADiOACTIVE EFFLUENTS 3/4. 11. 4 TOTAL DOSE LIYiITING COHDiTiON FOR OPERATiON 3.i1.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLiC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than 'or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLiCABILITY: At al 1 times.

ACTION:

a. Mith the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-ti on 3. 11. 1. 2a., 3. 11 1. 2b., 3. 11. 2. 2a., 3. 11. 2. 2b., 3 11. 2. 3a.,

~ ~

calculations shall be made including direct radiation or'.11.2.3b.,

contributions from the reactor units and from outside storaoe tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to preven recur-rence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an'nalysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLiC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 3.9g has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted unti 1 staff acti, on on the request is complete.

The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE REQUIREHENTS

4. 11. 4. 1 Cumulative dose contributions from liquid and gaseous eifluents shall be determined in accordance with Surveillance Requirements 4. 11. 1. 2, 4. 11. 2. 2, and 4. 11. 2. 3, and in accordance with the methodolooy and p'arameters in the ODCM.

4. 11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from r adwaste storage tanks shall be de ermined in accordance with the methodology and parameters in the ODCH. This Surveillance Requirement shall be required only in the event the above Action a. requires the applicable calculations.

ST. LUCIE -'NIT 1 3/4 11-17 Amendment No.

1 I 0

e 3/4. 12 RADIOLOGICAL ENVI ROHMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specif ted in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

With the radiological environmental monitoring program not being conducted as specified in Table 3. 12-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report requi red by Specifica-tion 6. 9. 1. 11, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

With the confirmed" level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6. 9. 2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3. 11. 1. 2, 3. 11. 2. 2, and 3. 11. 2. 3. When. more than one of the radionuclides in Table 3. 12-2 are detected in the sampl'ing medium, this report shall be submitted if:

concentration (1) concentration (2) reporting level 1 reporting level (2 When radionuclides other than those in Table 3. 12-2 are detected and are the result of plant effluents, this report shall be submitted the potential annual dose to A MEMBER OF THE PUBLIC is equal to or if greater than the calendar year limits of Specifications 3. 11. 1.2,

3. 11. 2. 2'nd 3. 1 1. 2. 3. This report shall include the methodology for calculating .the cumulative potential dose con'tributions for the calendar year from radionuclides detected in environmental samples and can be determined in accordance with the methodology and parameters in the ODCM. This report is not required if the measured level of radio-activity" was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

C. With mi lk.or broadleaf vegetation samples unavailable from one or .more of the sample locations required by Table 3. 12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis but in any case within 30 days.

ST. LUCIE - UNIT I 3/4 12-1 Amendment No.

RADIOLOGICAL ENVIRONMENTAL MONITORING ACTION: (Continued) locations from which samples were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1. 10, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCH reflecting the new location(s).

d. The provisions of Specifications 3. 0.3 and 3. 0.4 are not applicable.

SURVEILLANCE RE UIREHENTS 4 12.

~ 1 The radiological environmental monitoring samples shall be collected pursuant to Table 3. 12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3. 12-1 and the detection capabilities required by Table 4. 12-1.

ST. LUCIE - UNIT' 3/4 12-2 Amendment Ho.

I TAI1LE 3. 12-1 RADIOI OGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency d) and/or Sam le ~o">> L Collection Fre uenc of Anal sis

l. DIRECT. RADIATIOH '7 Honitoring Locations Continuous monitoring Gamma exposure rate-with samp).~ collection quarterly..

quarterly

2. AIRBORNE Radioiodine and 5 Locations Continuous sampler Radioiodine Filter:

Particulates operation with sample I-131 analysis weekly.

coliectioo ~weeki , or, more frequently i f Particulate Filter:

required, by dust loading Gross beta rarlioacLivi Ly analysis > 2d hours following a filter change

. h) analysis Gamma isotopj~

of composite" (by locaLion) quarterly

3. WATERBORNE

a. Surf ace h) l Location >) Meekly Gamma isotopic h) 8 Lri tium analyses weekly l Location Hon thly Gamma isotopic h) 8 Lritium analyses monthly

b. Sediment from 2 Locations Semiannually Gamma isotopic h) analysis shoreline semiannually

TABLE 3.12-1 (Continued RADIOLOGICAL ENVIRONMENTAL t1OHITORIHG PROGRAH Number of I

Representative Exposure Pathway Samples and Sampling and Type and Frequency d)

I

~l/ b) c) Collection Fre uenc of Anal sis INGEST ION

a. Fish and Invertebrates

1. Crustacea . 2 Locations Semiannually Gamma, isotopic h) analyses semiannually

2. Fi sh 2 Locations - Semiannually Gamma isotopic h) analyses semiannually

b. Food Products

1. Broad leaf 3 Locations 1) Honthly when Gamma isotopic h) and

=

vegetation available I-131 analyses montlily I

1

.I

TABLE 3. 12-1 (continued)

TABL'E NOTATION

a. Deviations are permitted from the required sampling schedule i< specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction corrective action shall be taken prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6. 9.11.1.

b. Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each sample location in Table 3. 12-1 in a Table and figure(s) in the ODCN.

c ~ At times, it may not be poss'ible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days i n the radiological environm>ental monitoring program; 1 2

d. The following definition of frequencies shall apply to Table 3.12-1 only:

W~eekl

- <<ot less than once per calendar week. A maximum interval of ll days is allowed between the collection of any two consecutive samples.

2 1 1 ~1 of not less than 7 days between sample collections. A maximum interval of 24 days is allowed between collection of any two consecutive samples.

~

~Monthl - Not less than once per ca1endar nonth with an interval of not less than 10 days between sample collections.

~Ouarterl - Hot less than once per calendar quarter.

~ 1i 1>>11 1

and (July 1 - December 31).. An interval 1 22 of not less than 1.

30 days will 2

be provided between sample collections.

The frequency of analyses is to be consistent with the sample collection frequency.

e. One or more instruments, such as a pressurized ion chamber, for'measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

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

TABLE 3.12-1 (continued)

TABL'E NOTATION

f. Refers to normal collection frequency. Nor e frequent sample collection is permitted when conditions warrant.

Q. Airborne particulate sample filters are analyzed for gross beta radioactivity 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 for radon and thoron daughter decay. In addition to the requirement for a gamma isotopic on a composite sample a gamma isotopic is also required ior each sample having a gross beta radioactivity which is > 1.0 pCi/m and which is also > 10 times that of the most recent control sample.

h. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

Atlantic Ocean, in the vicinity of the public beaches along the eastern shore of Hutchinson Island near the St. Lucie Plant (arab sample).

Atlantic Ocean, at a location beyond influence from plant effluents (grab sample).

k. Discharges from the St. Lucie Plant do not influence drinking water or ground water pathways.

Samples of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/g, and one sample of similar broad leaf vegetation at an available location 13-30 km distant in the least prevalent wind direction based upon historical data in the ODCN.

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

TABLE 3:12-2 REPORTIHG LEVELS FOR RAOIOACTIVITY CONCENTRATIONS IH ENVIRONMENTAL SAtlPLES.

Reporting Levels Water Airborne Particulate Fish Hilk Food Products Analysis (pCi/R) or Gases (pCi/ma) (pCi/kg, wet) (pCi/u) (pCi/kg, weL)

II-3 30,000*

1,000 30,000 Hn-54'e-59 400 10,000 Co-.58 1,000 30,000 Co-60 300 10,000 Zn-G5 =

300 20,000 Zr Hf) 400 95AAA'-131 0.9 100 Cs-134 30 10 1,000 GO 1,000 Cs-137 50 20 2,000 70 2,000 Da-La-140~~* 200 300 Since no drinking water pathway exists, a value of 30,000 pCi/R is used. For drinking water samples, a value of 20,000 pCi/R is used. This is 40 CFR Part 141 value.

Applies to drinking water.

An equilibrium mixture of the parent and daughter isotopes. which corresponds to the reporting value of the parent isotope.

I DETECTIOH CAPRBILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS n

Pl LOWEa LIHIT OF OErECl ION (LLO)"'nalysis Mater Rirborne Particulate Fish Milk Food Products Sediment (pCi/R) or Gas (pCi/m3) (pCi/kg,wet) (pCi/k) (pCi/kg,wet) (pCi/kg,dry) gross beta . 0. 01 II-3 3000" tin-54 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 I

co Zr-Hb-95 15 1-131 ld 0. 07 60 Cs-131 Cs-137-

0. 05 130 15 60 150

~

0. 06 150 18 80 180 Ba- La-110 15 15 5

Since no drinking water pathway exists, a value of 3000 pCi/R may be used. For drinking water samples, a value of 2000 pCi/E is used.

O

TABLE 4. 12-1 (Continued)

TAB'LE NOTATION a

This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together wi ih those of the above shall also be analyzed and reported in the Annual Radiological 'uclides, Environmental Operating Report pursuant to Specification 6.9. 1. 11.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4. 13.

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will .be detected with 95K probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particularmeasurement system, which may include radiochemical separation:

4 66 sb LLD E ~

V ~

2. 22 ~

Y ~

exp(-Mt)

Mher e:

LLD is the "a priori" lower limit of detection as defiried ab'ove, as picocuries per unit mass, or volume, s is the standard deviation of the background counting rate or of tie counting rate of a blank sample as appropriate, as counts per minute, E is the counting ef~iciency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A, is the radioactive decay constant for the particular radionuclide, and Dt for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and Dt should be used in the calculation.

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

TABLE 4. 12-1 (Continued)

TABlE NOTATiON It shou1d be recognized that the LLD is defined as an a priori (before the fact) ment. Analyses shall be

(<<performed fin')suchll manner limit representing the capability of a measurement system and a

f that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1. 11.

LLD for drinking water samples. If no drinking water pathway exists, the.

LLD of gamma isotopic analysis may be used.

An equilibrium mixture of the parent and daughter isotopes which corresponds to 15 pCi/2 of the parent isotope.

ST. LUCIE - UNIT 1 3/4 12-10 Amendment No.

RnDIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION

3. 12. 2 A land use census shall be conducted and shall identify within a ance of 8 km (5 miles) the location in each of the 16 meteorological 'is sectors of the nearest.milk animal, the neares. residence apd the nearest garden" of greater than 50 m (500 ft ) producing broad leaf. veoetation.

APPLICABiLITY: At all times.

AEiIOM:

a. Mith a land use census identi fying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4. 11. 2.3, in lieu of a Licensee Event Report, identify the new location(s) in the next Semiannual Radioactive .

Effluent Release Report, pursuant to Specification 6.9. 1. 10.

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

calculated dose or dose commitment (via the same exposure pathway) 20Ã greater than at a location from which samples are currently being obtained in accordance with Specification 3. 12. 1, add the new location(s) to the 'radiological. environmental monitoring program within 30 days. The samplino location(s), excluding the control station location, having the lowest, calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this moni .oring program after October 31 of the year in which this land use census was conducted. In lieu of a Licensee Event Report and pursuant to Specification 6.9. 1. 10, identify the new loc'ation(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s) an'd table for the ODCM reflecting the new location(s).

c. The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 12. 2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Speci f i cati on 6. 9. 1. 11.

I

• Broad leaf vegetation sampling may be performed at the site boundary in eac'h of two different direction sectors with the highest predicted'/gs in lieu of the garden census.. Specifications for broad leaf vegetation sampling in Table 3. 12-1.4b shall be followed, including analysis of control samples.

ST. LUCIE - UNIT I 3/4 12-11 Amendment No.

RADIOLOGICAL EHVIRONt1ENTAL HONITORIHG 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that ha's been approved by the Commission."

APPLICABILITY: At al 1 times.

ACTION:

a. Mith analyses not being, performed as required above, report the corrective actions to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6. 9. l. 1'i.

b. The provisions of. Specifications 3. 0.3 and 3.0.4 are hot applicable.

SURVEILLANCE REQUIREHENTS

4. 12. 3 A summary of the results obtained as part of the'bove required Interlaboratory Comparison Program shall be included in the .Annual Radiological Environmental Operating. Report pursuant to Specification 6.9. l. 11.

This condition is satisfied by participation in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by the Environmental Protection Agency (EPA).

ST. LUCIE - UNIT I" 3/4 12-12 Amendment No.

0 INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION Continued by the individual channels; and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient infor-mation is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recom-mendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Follow-ing an Accident,"December 1980 and NUREG-0737, "Clarifications of TMI Action Plan Requirements," November 1980.

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum com-plement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3. 3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficent capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facili.ty.

3/4.3.3. 4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs", February 1972.

3/4.3.3. 5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

ST. LUCIE - UNIT 1' 3/4 3-2 Amendment No.

INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/

trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64,of Appendix A to 10 CFR Part 50.

3/4.3.3. 10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION j

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE - UNIT 1 B 3/4 3-4 ,Amendment No.

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RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID MASTE TREATMENT The OPERABILITY of the liquid radwaste treatmert system ensures that this system wi 11 be available for use whenever liquid effl vents require treatment prior to release to the environment. The .requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were -specified as a suitable fraction of .

the dose design objectives set forth in Section II.A of Appendix I,, 10 CFR Part 50, for liouid effluents'.

3/4. 11. 2 GASEOUS EFFLUENTS

~

3/4.11. 2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, tc annual average concentra-,

tions exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20. 106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SiTE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for. the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanfor d Company Report ARH-SA-215 (June 1975).

ST. LUCIE - UNIT I B 3/4 11-2 Amendment No.

f r

4

~ ll

RAQ:OAC IVE EFFLUENTS BASES This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwas e treatment systems, the gaseous ef> luents from the shared system are proportioned an>ong the units sharing that system.

3/4. 11.2.2 DOSE " NOBLE GASES 4

This specification is provided to implement the requirements of "Sections II.B, III.A and 'IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IY.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implemen the requirements in Section III.A of Appendix I that, conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a HEHBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodolooy and paran>eters established in the ODCH for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided i n Regulatory Guide 1. 109, "Calcula-tion of Annual Doses to Han from Routine Releases o> Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," March, 1976 and Regulatory Guide l. 111, "Methods tor Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Peleases from Light-Mater Cooled.

Reactors," Revision 1, July 1977. The ODCH equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions or real atmospheric conditions.

This specification applies to the release of gaseous effluents from each reac.or at the site. For units with shared radwaste treatment systems, the gaseous eff)uents from the shared system are proportioned among the units sharing that system.

3/4.11.2.3 DOSE - IODINE-131, IODINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IY. A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS wi 11 be kept "as low as is reasonably achievable." The ODCH calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A or Appendix I that conformance with the guides .of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC ST. LUG IE - UNIT I B 3/4 11-3 Amendment No.

RADIOACTIVE EFFLUEHTS BASiS

,through appropriate pathways is unlikely to be subs.antially. underestimated.

The ODCN calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologoy provided in Regulatory Guide 1. 109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents.for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," March 1976 and Regulatory Guide l. 111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Mater-Cooled Reactors,""Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric or real meteor-

.ological conditions. The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consump ion of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man..

This specification applies to the release of gaseous effluents from each reactor't the site,'or units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4. 11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the. GASEOUS RADWASTE TREATMENT SYSTEM and the VEHTILATIOH EXHAUST TREATMEHT SYSTEM ensures that the systems will be -available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reason-ably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

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

3/4.11.2.5 EXPLOSIVE GAS MIXTURE This. spe'cification is provided to ensure hat the concentration of potentially explosive gas mixtures contained in the waste gas holdup system i s main ained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammabili .y 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. LUCIE - UNIT 1 B 3/4 11-4 Amendment Ho.

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 Revie~ Plan 15. 7. 1, "Haste Gas System Failure."

3/4.11. 3 SOLID RADIOACTIVE MASTE Thi s speci fi cati on impl ements the requi rements of 10 CFR Part 50. 36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process param-eters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/soli dification agent/

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

3/4. 11. 4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant. generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC wi 11 exceed the dose limits of 40 CFR Part 190 if the individuai reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC. from other uranium fuel cycle sources is negligible,',with the exception ihat dose-contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requi rements of 40 CFR Part 190, the Special Report

'with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), i n accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until HRC staff action is completed. The variance only relates to the limits of 40 CFR 'Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifica-tions 3.11. 1. 1 and 3."1.2. 1. An individual is rot considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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

E i' 3/< "2 RADIOLOG r CAL ENVIRONMENTAL MONITOR T NG BASES 3/4. 12. 1 MONITORING PROGRAM The radiological environmental monitoring program reouired by this specification provides representative measurements of radiation and of radio-active materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix' to 10 CFR Part 50 and thereby supplements the radiological effluent monitorino program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher an expected on the basis of the effluent measurements and the modeling of

'l the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities ior environmental, sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4. 12-1 are .considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined par ti cul ar measurement.

i << <<

as an a priori (before the fact) 'limit representing the capability of a

> ii i i Detailed di scuss i on of the LLD, and other detecti on limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. Ae a "Limits for gualitative Detection and guantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586"93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH"SA-215 (June 1975).

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

3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY. are identi fied and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV. B,3 of Appendix I to 10 CFR Part. 50. Restricting the census to gardens of greater than 50 m provides assurance that significant exposure pathways via leafy vegetables will be identi fied and monitored since a garden of this size is the minimum required to produce the quantity 26 kg/year of leafy vegetables assumed in Regulatory Guide 1. 109 for consumption by a child. To determine thi s minimum garden size, the following assumptions were made: 1) 20~ of the garden was used for growing broad leat vegetation (i. e., similar to .lettuce and cabbage}, and 2) a vegetation yield of 2 kg/m .

3/4.12 .3 IHTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Prooram is provided to ensure that independent checks on the precision and

~

accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV. B. 2 of Append'ix I to 10 CFR Part 50.

ST. LUCIE - UNIT I B 3/4 12-2 Amendment No.

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1. 1 The exclusion area is shown on Figure 5. 1-1.

LOM POPULATION ZONE

5. 1.2 The low population zone is shown on Figure 5. 1-.1.

FLOOD CONTROL

5. 1.3 The flood control provisions (dunes and slope protection) shall be designed and maintained in accordance with the original design provisions contained in Section 2.4.2.2 of the FSAR.

5.2 CONTAINNENT CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder wi th a hemispherical dome and ellipisoidal bottom, surrounded by a reinforced .concrete shield building.

The radius of the shield building is at least 4 feet greater than the radius of circular cylinder portion of the containment vessel at any point.

5.2. 1. 1 CONTAINMENT VESSEL

a. Nominal inside diameter = 140 feet.

b. Nominal inside height = 232 feet.

c~ Net free volume = 2.5 x 10 cubic feet.

d. Nominal thickness of vessel walls = 2 inches.'.

Nominal thickness of vessel dome = 1 inch.

f. Nominal thickness of vessel bottom = 2 inches.

ST. LUCIE - UNIT 1 5-.1 Amendment No.

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In Ih CJ CI CI Fp a L's O U

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POPULATION ZONE tl ni) UN)T 2 NOTES:

1) L-L'.quid Radwas.e +~

Release Point "o of the

2) Due to the scale Figure the Exclusion Area Radius (0.97 mile) and the Low >opulation Zone (1 mile) are shown as -being the same size. I

3) The following are unrestricted ~

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a) All waterways (Herman Bay, Bio Mud Creek, Indian River) with the aL's (/)~~I'

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~l I c) State Road A1A 'Z-;.

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C FLORIDA POWDER E LIGr'T COI, P~hY ST. LUCIE PLA.HT I/2

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FIGURE 5.1-2 (Oeleted)

ST. LUCIE - UNIT 1 5-3 Amendment No.

ADMINISTRATIVE CONTROLS 0

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Power Resources Nuclear, the Vice President of Power Resources and to the Chairman of the Company Nuclear Review Board.

f. Review of those REPORTABLE OCCURRENCES requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifica-'ion to the Commission.

9. Review of facility opertions to detect potential safety hazards.

h. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Company Nuclear Review Board.

1. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

J ~ Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

k. Review of every unplanned onsi te release of radioactive material.

to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to .

the Vice President Nuclear Energy and to the Company Nuclear Review Board.

Review of, changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADMASTE TREATMENT SYSTEMS.

AUTHORITY 6.5.1.7 Th'e Facility Review Group shall:

a ~ Recommend to the'lant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5. 1.6(a) through (e) above constitutes an unreviewed safety question.

co Provide written notification within 24 hours to the Vice President of Power Resources and the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1. 1 above.

ST., LUCIE - UNIT I 6-7 Amendment No.

Il ADMINISTRATIVE CONlCOLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CNRB. These audits shall encompass:

a. The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire facility staff at least once per 12 months.

c. The results of all actions taken to correct deficiencies 'occuring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

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

e. Any other area of unit operation considered appropriate by the CNRB or the Executive Vice President.

f. The fire protection programmatic controls including the implementing-procedures at least once per 24 months by qualified licensee gA'ersonnel.

g. The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection specialist or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.

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

i. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

j. The PROCESS CONTROL PROGRAM and implementing procedures for dewatering of radioactive bead resin at least once per 24 months.

AUTHORITY 6.5.2.9 The CNRB shall report to and advise the Ex'ecutive Vice President on those areas of responsibi lity specified in Sections 6.5.2.7 and 6.5.2.8.

ST. LUCIE - UNIT 1 6-11 Amendment No.

ADMINISTRATIVE CONTROLS

6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

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

b. The'afety Limit violation shall be reportd to the Commission, President of Power Resources and to the CNR8 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

the'Vice

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

d. The Safety Limit Violation Report shall be submitted to the Commission, the CNRB and the Director of Power Resources within 10 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained.

covering the activities referenced below:

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

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. guality Control Program for effluent monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974.

j. guality Control Program for environmental monitoring using the guidance in Regulatory Guide 4. 1, Revision 1, April 1975.

6.8.2 Each procedure of Specification 6.8.la through i. above, and changes thereto, shall be reviewed by the FRG and shall be approved by the Plant Manager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

ST. LUCIE - UNIT 1 6-13 Amendment No.

ADNINISTRATI VE CONTROLS Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1/ hk/k; a calculated reactivi ty balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifications; short-term reacti vi ty increases that correspond to a reactor period of less than 5 seconds or, if subcri tical, an unplanned reactivity inser-tion of more than 0.5% hk/k; or occurrence of any planned CI 1 ti ca 1 i ty,

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

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

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

Errors dis'covered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conser-vative than assumed in the analyses.

Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during uni't life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

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

k. Exceeding the limits in Specification -3. 11.2.6 for the storage of radioactive materisls in the listed tanks. The written followup report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified l imi ts.

ST. LUCIE - UNIT 1 6-17 Amendment No.

ADMIN I STRATI VE CONTROLS THIRTY DAY h'RITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a m'inimum, a completed copy of a licensee event report form. Information provided on- the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

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

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

c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of. degree of reduncancy provided in reactor protection systems or engineered safety feature systems.

d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.

e. An unplanned offsite release of (1) more than 1 curie of radioactive material in liquid effluents, (2) more than 150 curies of noble gas in gaseous effluents, or (3) more than 0.05 curie of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:

,l. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3." Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

ST. LUCIE - UNIT 1 6-18 Amendment No.

l l ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTiVE EFFLUENT RELEASE REPORT~

6.9. 1. 10 Routine Radioactive Effluent Release Reports covering the operation oi the unit during the previous 6 months of operation shall be submi ited within 60 days after January 1 and July i. of each year. The period of the first report shall begin with the date of initial criticality.

The Radioac ive Effluent Release Reports shall include a summary of the quantities of radioac~ive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.2~, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents form Light-Water-Cooled Nuclear Power Plants,"

Revision i., June 1974, with data summarized on a quarterly basis following the format, of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmos-pheric stability. *" This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released irom the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SiTE BOUNDARY (Figure 5. 1-1) during the report period. All assump-tions used in making these assessments, i. e., specific activity, exposure time and location, shall be included in these reports.. The meteorological condi-tions concurrent with the tim'e of release of radioactive materials in gaseous eifluents, as determi ned by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSiTE DOSE CSiLCULATION MANUAL (ODCM).

Every 2 years using the previous 6 months release history for isotopes and historical meteorolgical data determine the controlling age group for both liquid and gaseous pathways. If changed >rom current submit change to ODCM to reflect new tables= for these groups and use the new groups in subsequen" dose calculations.

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases .for the previous X

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.

• • In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on si te in a file that shall be provided to the NRC upon request.

ST. LUCIE - UNIT 1 6-18a Amendment No.

0 AD1>iINIS. RATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) year. Acceptable methods for calculating the dose contribution from

'alendar liquid and gaseous effluents are given in Regulatory Guide 1.109, March 1976.

The Radioactive Effluent Release Reports shall -;nclude the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

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

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

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

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

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release .Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE

'OSE CALCULATION MANAUL (ODCM), as well as a listing of new locations .for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT"

6. 9. k. 11 Routine Radiological Environmental Operating Reports covering the operation of the unit during the'previous calendar year shall be submitted prior to Hay 1 of .each year. The initial report shall be submitted prior to Nay 1 of the year iollowing initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and information based on trend analysis of the results of the radiological environmental surveillance activities for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3. 12.2.

The Annual Radiological Environmental Operating Reports shall include he results oi analysis of all radiological environmental samples and o all envirormental radiation measurements taken during the period pursuant to the A single submittal may be made for a multiple unit station.

ST. LUCIE - UNIT 1 6-18b Amendment No.

1 ADMINISTRATIVE CON OLS ANNUAL RADIOLOGICAl ENVIRONMENTAL OPERATING REPORT (Continued) 4 locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reaons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps*

covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results the Comparison Program, required by Specification 3.12.3:

'nterlaboratory discussion of all deviations from the sampling schedule of Table 3.12. 1, and discussion of all analyses in which the LLD required by Table 4. 12-1 was not achievable.

6.9.1. 12 At least once every 5 years, an estimate of the actual population within 10 mi les of the plant shall be prepared and submitted to the Regional Administrator of the Regional Office of the NRC.

6.9. 1. 13 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 Regional Administrator of the Regional office of the NRC.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a~ Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4..

c ~ Inservice Inspection Program Reviews, Specifications 4.4.10. 1 and 4.4.10.2.

d ~ ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e. Sealed Source leakage in excess of limits, Specification 4.7.9.1.3.

f. Seismic event analysis, Specification 4.3.3.3.2.

9 ~ Beach survey results, Specification 4.7.6.1.1.

h. Core Barrel Movement, Specifications 3.4.11 and 4.4.11.

l ~ Fire Detection Instrumentation, Specification 3.3.3.7.

J ~ Fire Suppression Systems, Specification 3.7.11.1.

k. Radiological Effluent, Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.4, and 3.12.1.

• One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

ST. LUCIE - UNIT 1 6-18c Amendment No.

P ADMINI STRATI VE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall b'e retained for at least five years:

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

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

c. All REPORTABLE OCCURRENCES submitted to the Commision.

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

e. Records of reactor tests and experiements.

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

i. 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 Facility Operating License:

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

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility radiation and contamination surveys.

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

ST. LUCIE - UNIT 1 6-19 Amendment No.

ADMINISTRATIVE CONTROLS

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

f. Records of transient or operational cycles for those facility components identified in Table 5.9-1.

g. Records of training and qualification for current members of the plant staff.

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

Records of Quality Assurance .activities required by the QA Manual.

j. Records of reviews performed for changes made to procedures or pursuant to equipment or reviews of tests and experiements 10 CFR 50.59.

k. Records of meetings of the FRG and the CNRB.

1. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

m. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-2a and 3.7-2b including the date at which the service life conmences and associated installation and maintenance records.

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 recommendation of Regulatory Guides 1.21 and 1.23.

6.11 RADIATION PROTECTION PROGRAM =

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

ST. LUCIE - UNIT 1 6-20 Amendment No.

ADNIHISTRATI VE CONTROLS

5. 12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or "alarm signa)" required by para-graph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which'he intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RMP)". Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

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

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

C. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing posi'tive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in ihe RMP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with. radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics super-vision. Doors shall remain locked except during periods of access by personnel under an approved RMP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that, a major portion of the body could receive in one'our a dose in excess of 1000 mrem"" that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reason-ably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of. the stay time specification of the RMP, direct 'or remote (s'uch as use of closed circuit TY cameras) continuous surveillance may be made by personnel qualified in radiation protecti'on procedures to provide posi ive exposure control over he ac.ivities within the area.

"Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RMP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radia ion areas.

""Heasuremen made at 18 inches from source of radioactivity.

ST. LUCIE - UNIT I 6-20a Amendment No.

AJ AOMINISTRAT IVE CONT S 6.16 BACKUP METHOD FOR OETERMINIHG SUBCOOLING MARGIN 6.16.1 The licensee shall implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:

l. Training of personnel, and

2. Procedures for monitoring.

6.17 PROCESS CONTROL PROGRAM PCP 6.17.1 The PCP shall be approved by the FRG prior to implementation.

6.17.2 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

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

b. A determination that the change did not reduce the overall conformance of the dewatered bead resin to existing criteria for radioactive wastes; and

c. Oocumentation of the fact that the change has been reviewed and found acceptable by the FRG.

2. Shall become effective upon review and acceptance by the FRG.

ST. LUCIE - UNIT 1 6-22 Amendment No.

ADYiINISTRATIVE CONTR LS 6.18 OFFSITE DOSE CALCULATION MANUAL ODCN 6.18.1 The ODCM shall be approved by the Commission prior to implementation.

6. 18.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information'. Information submitted should consist of a package of those pages of the ODCN to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

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

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

2. Shall become effective upon review and acceptance by the FRG.

ST. LUG IE - UNIT 1 6-23 Amendment No.

I S

C