Text

Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program
	ML17353A617
Person / Time
Site:	Turkey Point
Issue date:	03/21/1996
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17353A616	List: ML17353A615; ML17353A617; ML17353A619;
References
	NUDOCS 9603280120
	Download: ML17353A617 (102)
	v • d • e

INDEX DEFINITIONS SECTION PAGE

l. 0 OEF IN IT IONS. 1-0 1.1 ACTION..

1.2 ACTUATION LOGIC TEST..

"1.3 ANALOG CHANNEL OPERATIONAL TEST ...

1.4 AXIAL FLUX DIFFERENCE .. a-l

'.5 CHANNEL CALIBRATION.

1.6 CHANNEL CHECK.

1.7 CONTAINMENT INTEGRITY. 1-2 1.8 CONTROLLED LEAKAGE . 1-2 1.9 CPRc y TcRATION 1-2

1. 10 DOSE EQUIVALENT I-131............................... 1-2 E" AVERAGE DISINTEGRATION ENERGY.

'.12 FREQUENCY 'NOTATION 1-3

1. 13 GAS DECAY TANK SYSTEM. 1-3 I1.14 IDENTIFIED LEAKAGE .. .. ~A@> 1-3

'.15 , . Q PEi. ETED) .. PQ o ~ ~ ~ ~ 1-3

1. 16

- OPERABILITY .

( pEJ EPEE) 1-3

l. 17 OPERABLE 1-4

1. 18 OPERATIONAL MODE - MODE

1. 1": PHYSICS TESTS.. ~ ~ ~ ~ ~ ~ ~ ~ 0 ~

l. 20 PRESSURE BOUNDARY LEAKAGE 1-4

l. 21 . (G aI.<-.~II). 1-4

l. 22 PURGE - PURGING........., 1-4

l. 23 QUADRANT POWER TILT RATIO... 1-5

l. 24 RATED THERMAL POWER... 1-5

1. 25 REPORTABLE EVENT... 1-5

l. 26 SHUTDOWN MARGIN............. 1-5

1. 27 SITE BOUNDARY ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ 1-5

'.

~,9E,Dsasoxss qi'ossi "poR Aoacx osoooaio F~

P TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS. )37AND 132

NG N 0 T ON AND SURV NC R 2XXLOH ~AG TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.................. ".......... -....... 3/4 3-36 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS..".................. 3/4 3-39 Movable Incore Detectors.................................. 3/4 3-40 Accident Monitoring Instrumentation..'..................... 3/4 3-41 TABLE 3.3-5 ACCIDENT MONITORING INSTRUMENTATION.................... 3/4 3-42 TABLE 4.3-4 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................'/4 APD 3-46 Fire Detection Instrumentation - Deleted.................. 4 3/4 '3-47 Radioactive Liquid Effluent Honitoring Instrumentation 0V <~ /4 3-5p TABLE 3.3-7 RADIOACTIVE LI(UID EFFLUENT MONITORING INSTRUMENTATION. 3/4 3-51 TABLE 4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......~".:..~ .... 3/4 3-53 w- p-i.~v'a EWPiOSiPC CAS Monitoring Instrumentation...

Rad~4ea -haft-uerbs 3/4 3-54 TABLE 3.3-8 SSQA ASEOUS-ESSLUE4T MONITORING INSTRUHENTATIQN...........................................

,pgI VC 3/4 3-55 TABLE 4.3-6 RA5kA M~FFNBH MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................. 3/4 3-58 TURKEY POINT - UNITS 3 EE 4 AMENDMENT NOS.159AND 153

IHOEX 0- LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3 4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE S afety Valves.................... ... ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ 3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION...................................... 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP...................... 3/4 7-2 Auxiliary y Feedwater System................................ 3/4 7-3 TABLE 3.7-3 AUXILIARY'FEEDWATER SYSTEM OPERABILITY................. 3/4 7-5 Condensate Storage Tank.............................. .... ~ 3/4 7-6 S peel flc Acti vl ty.......

a

~ ~ ~ ~ ~ - ~ ~ 3/4 7-8 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM............................. ~ ...... . ~ 3/4 7-9 Main Steam Line Isolation Valves.......................... 3/4 7-10 Standby Steam Generator Feedwater System........ 3/4 7-11 3/4.7.2 COMPONENT COOLING WATER SYSTEM................... ~ ~ ~ ~ - ~ ~ ~ ~ 3/4 7-12 3/4.7.3 INTAKE COOLING WATER SYSTEM.............-................. 3/4 7-14 3/4.7.4 ULTIMATE HEAT SINK............ -... ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ -- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-15 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................. 3/4 7-16 3/4.7.6 S NUBBERS............;..................................... 3/4 7-18 3/4.7.7 SEAL'ED SOURCE CONTAMINATION.............. ~... ~ . -. ~ ~ ~ ~ ~ ~ ~ ~ ~ 3 47-22 3/y.7.g $ gPXoSZvB +AS A>/<~~8 .

gas onymy W>~vs..., .

TURKEY POINT UNITS 3 L 4 AMENDMENT NOS. 164AND 158

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMEHTS SECTION PAGE 3/4. 9. 9 CONTAINMENT VENTILATION ISOLATION SYSTEM................. 3/4 9-10 3/4.9. 10 MATER LEYEL - REACTOR YESSEL 3/4 9-11 3/4.9. 11 MATER LEVEL - STORAGE POOL . 3/4 9-12 3/4.9. 12 HANDLING OF SPENT FUEL CASK. 3/4 9-13 3/4. 9. 13 RADIATION MONITORING. 3/4 9-14 3/4. 9. 14 SPENT FUEL STORAGE 3/4 9-15 TABLE 3.9. 1 SPENT FUEL BURHUP REQUIREMENTS FOR STORAGE IN REGION II OF THE SPENT FUEL PIT...: 3/4 9-16 f 3/4.10 SPECIAL TEST EXCEPTIONS r

3/4. 10. 1 SHUTDOWN MARGIN.... 3/4 10-1 3/4. 10. 2 GROUP HEIGHT, INSERTION, ANO POMER DISTRIBUTION LIMITS... 3/4 10-2 3/4. 10. 3 PHYSICS TESTS............... 3/4 10-3 3/4. 10.4 (This specification number is no'sed). 3/4 10"4 3/4.10,5 POSITION INDICATION SYSTEM - SHUTDOWN. 3/4 10-5 3 . AOIOACTIYE EFFLUEHTS 3/4.11.1 LIQUID EFFLU Concentration............... 3/4 11-1 TABLE 4.11-1 RAOIOACTIYE LIQUID MASTE SAMPLI ANALYSIS PROGRAM.. 3/4 11-2 Dose ~ ~ ~ ~ ~ ~ ~ 3/4 11-5 Liquid Radwaste Treatment System.....,................... 3/4 1-TURKEY POINT - UNITS 3 It; 4 X111 AMENDMEHT NOS. 137ANO 132

INDEX LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE RE UIREMEHTS SECTION PAGE

4. 11. 2 GASEOUS EFFLUENTS Dose Rate 3/4 11-7 TABLE 4. 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P RAM. 3/4 11-8 Dose Noble Gases. 3/4 11-12 Dose - I ine-131, Iodine-133, Tritium, and Radioactive Material in articulate Form. 3/4 11-13 Gaseous Radwas Treatment System. 3/4 11-14 Explosive Gas Mix re 3/4 11-15 Gas Decay Tanks...... 3/4 jj-j6 3/4. 11. 3 SOLID. RADIOACTIVE WASTES.... 3/4 11-17 3/4. 11. 4 TOTAL DOSE.. 3/4 11-18 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MOHI TOR ING PROGRAM. 3/4 12" 1 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGR 3/4 12-3 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIO IN ENVIRONMENTAL SAMPLES 3/4 12-7 TABLE 4.12-1 DETECTIOH CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 4 12-8 3/4. 12.2 LAND USE CENSUS...... 3/4 2-11 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM..........,............ 3/4 12" TURKEY POINT - UNITS 3 K 4 xiv AMENDMENT NOS.l37AND l32

0 INDEX SECTION 6.11 RADIATION PROTECTION PROGRAM.. 6-21

6. 12 HIGH RADIATION AREA.. 6-22

6. 13 PROCESS CONTROL PROGRAM (PCP}........ 6-23

6. 14 OFFSITE DOSE CALCULATION MANUAL ODCM). 6" 23 6.15 MAJOR GASEOUS, AND SOLID RADMASTE TREATMENT SYSTEMS 6-24 TURKEY POINT - UNITS 3 8 4 Xxl V AMENDMENT NOS.i3PAND ]32

DEFINITIONS FRE UENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1. 1.

GAS DECAY TANK SYST H

1. 13 A GAS DECAY TANK SYSTEH shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off gases from the Reactor Coolant System and providing for delay or holdup. for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFI D LEAKAGE

1. 14 IDENTIFIED LEAKAGE shall be:

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

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or C. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

1.15 1.16 TURKEY POINT - UNITS 3 5. 4 1-3 AHENDHENT NOS.l57AND

DEF IN ITION5 OPERABLE - OPERABILITY

1. 17 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE

1. 18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS

1. 19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 13.5 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.20 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) througn a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

1. 21

~ j aJJ PURGE " PURGING 1.22 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration other operating condition, in such a manner that replacement air or gas is

'r required to purify the confinement.

TURKEY POINT - UNITS 3 8 4 1"4 AMENDMENT NOS. 137AND 132

TABLE 3.3-3 (continued)

SA U C U 0 S U 0 0 (I) Either II M

I I

Ip VII I

11

~~

the particulate or gaseous channel in the 11

( F )

OPERABLE F

PII status PM, will satisfy this LCO.

'...

( )

Where F Act ow Oesign Purge Flow (35,000 CFH)

Setpoint may vary according to current plant conditions vided t elease rate does not exceed allowable limits provided in CATE 0$ fs: Ouse.C. Ce+ CP cu 4~ '~n

<DE u<<va..

Q<<VQ (3) Auxiliary feedwater manual initiation is included in Specification 3.7.1.2.

0 If no Allowable Value is specified, as indicated by [], the trip setpoint shall also be the allowable value.

TABLE 3.3-4 (Continued)

TABLE NOTATIONS During CORE ALTERATIONS or movement of irradiated fuel within the containment comply with Specification 3/4.9.13.

With irradiated fuel in the spent fuel pits.

¹ Unit 4 Spent Fuel Pool Area is monitored by Plant Vent radioactivity instrumentation.

Note 1 Either the particulate or gaseous channel in the OPERABLE status will satisfy this LCO.

Setpoint 3.2 x 104 Note 2 Containment Gaseous Monitor CPM,

( F )

Actual Pur e Flow esign urge ow vary according to current plant conditions provided Setpoint may that the release rate does

<lge BA s'o~ ~alculaho< Aag~g/

ceed roy'n ACTION STATEMENTS aud.

ACTION 26 - In MODES 1 thru 4: With both the Particulate and Gaseous Radioactivity Monitoring Systems inoperable, operation may continue for up to 7 days provided:

1) A Containment sump level monitoring system is OPERABLE,

2) Appropriate grab samples are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

3) A Reactor Coolant System water inventory balance is performed at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during steady. state operation except when operating in shutdown cooling mode, and

4) Containment Purge, Exhaust and Instrument Air Bleed Valves are maintained closed.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (ACTION 27 applies in MODES 5 and 6).

TURKEY POINT " UNITS 3 E 4 3/4 3-37 AMENDMENT NOS.137AND 132

STRUMENTAT ION 0 SRUE IO LIMIT G COND TIO FOR OPERATION 3/4.3.3.4 (Deleted)

TURKEY POINT - UNITS 3 K 4 3/4 3-47 AMENDMENT NOS.159AND 153

ABLE 3.3-IRE DETECTION INSTRlNENTS OR ESSENTIAL E VIP'Deleted)

TURKEY POINT - UNITS 3 5, 4 3/4 3-48 ANENDNENT NOS,1 59 AND 153

/I TABLE 3.3-6 Continued FIRE DETECTION INSTRUMENTS FOR ESSENTIAL E UIPNENT (Deleted)

URKEY POINT - UNITS 3 S 4 3/4 3-49 AMENDNENT NOS.159 AND 153

STRUMENTATION RAD ACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION

'LIMITI CONDITION FOR OPERATION 3.3.3.5 The adioactive liquid effluent monitoring instrumentation channels shown in Tabl 3.3-7 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the imits of Specificat'ion 3. 11. 1'. 1 are not exceeded. The Alarm/

Trip Setpoints o these channels shall be determined and adjusted in accordance with th methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all imes, except as indicated in Table 3.3-7.

ACTION:

a ~ With a radioactive 1> uid effluent monitoring instrumentation channel Alarm/Trip Setpoint le conservative than required by the above spe-cification, immediately uspend the release of radioactive liquid effluents monitored by th affected channel or declare the channel inoperable, or change the s tpoint so it is acceptably conservative.

b. Mith less than the minimum num r of radioactive liquid effluent monitoring instrumentation charm ls OPERABLE, take the ACTION shown in Table 3.3-7. Restore the inop able instrumentation to OPERABLE status within 30 days and, if unsuc essful, explain in the next Annual Radioactive Effluent Release port pursuant to Specifica-tion 6.9. 1.4 why this inoperability wa not corrected in a timely manner.

c. The provisions of Specification 3.0.3 are n t applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.5 Each radioactive liquid effluent monitoring instrum tation channel shall be demonstrated OPERABLE by performance of the CHANNEL ECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST t the frequencies shown in Table 4.3-5.

U~l<4 Vl.s Pap~

TURKEY POINT UNITS 3 S. 4 3/4 3-50 AMENDMENT NOS. 157 AND

0 r

TABLE 3.3-7

'0 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION Gross Ra ioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid dwaste Effluent Line 35

b. Steam Gene tor Blowdown Effluent Line 36

2. Flow Rate Measure ent Devices

a. Liquid Radwaste ffluent Line 37

b. Steam Generator Bl down Effluent Line 1""/Steam 37 generator "Applicable during liquid effluent releases.

""Applicable during blowdown operations.

TURKEY POINT - UNITS 3 8 4 3/4 3-51 AMENDMENT NOS. 137AND 1

TABLE 3.3-7 Continued)

TABLE NOTATION ACTION With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

At least two independent samples are analyzed in accordance with Specification 4. 11. l. l. 1, and

b. At least two technically qualified members of the facility aff independently verify the release rate calculations an discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36- With the numbe of channels OPERABLE less than required by the Minimum Channel OPERABLE requirement, effluent releases via this pathway may ontinue provided grab samples are analyzed for gross (beta or amma) radioactivity at a lower limit of

.detection of no more than 1 x 10-7 microcuries/ml or analyzed isotopically (Gamma) t a lower limit of detection of at least 5 x 10-7 microcuries/m

a. At least once per 12 ours when the specific activity of the secondary coolant 's greater than 0.01 microcuries/gram OOSE E(UI VALENT I "131,

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months hen the specific activity of the secondary coolant is les than or equal to 0.01 micro-curies/gram OOSE E(UIYALENT I 31.

ACTION 37- With the number of channels OPERABLE ss than required by the Minimum Channels OPERABLE requirement, ffluent releases via this pathway may continue provided the f w rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual r eases. Pump performance curves may be used to estimate low.

D~],4

~SPY TURKEY POINT - UNITS 3 6 4 3/4 3-52 AMENDMENT NOS137 ANO 132

TABLE 4.3-S RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS C) ANALOG M CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL I INSTRUHENT CHECK CHECK CALIBRATION TEST Gross Radioactivity Honitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluents Line R(2) 0(1) +

b. Steaa Generator Blowdown Effluent Line R(2) c(i)

2. Flow Rate Measureent Devices I

a. Liquid Radwaste Effluent Line D(3) N.A.

b. Steam Generator Blowdown Effluent Lines D(3) N.A.

TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control rooa alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip m

Setpoint.

C7 m (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are

'V made.

INSTRUMENTATION pgpgosx vB gAs MOH ITOR IHG INSTRUME ATION LIMITIHG CONDITIOH FOR OPERATION CR'as:vr 85 > 7.E 3.3.3.6 The monitoring inst umentation channels with their Alarm/T ip Setpoints set to shown in Table 3.3-8 shall exceeded.

i <<i ii i i i ii* i ~a+5-.i-.&

be OPERABLE APPLICABILITY: As shown in Table 3.3-8 ACTION:

a.n dp. los:ve, as

a. With monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, declare the channel inoperable or change the setpoint so it is acceptably conservative.

OssVC. JS

b. Mith less than the minimum number of monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful why this inoperability was not corrected in a timely manner.

c. The provisions of Specification 3.0.3 are not applicable.

p.~p~rr 9 9u4~. 9 ~p <.~l Royce+~- 4J~

SURVEILLANCE RE UIREMENTS

~~ ~;ss,~~ ~,ff,.~ Po Joys Ca c~plo'e eX Jas-'vc 8~

4.3.3.6 Each monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, 4QQK&

EBB'; CHANNEL CALIBRATIOH and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.

TURKEY POINT UNITS 3 K 4 3/4 3-54 AMENDMENT HOS. 157 AHD 151

TABLE 3. 3-8 PjCPgoS~F +AS MONITORING IHSTRUHEHTAT ION m

MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION I

AY TANK SYSTEM l/l a. Noble Gas Act.>v itor-Providing Alarm and Autom Termination of Release (Plant Vent Monitor)

b. Effluent System Flow Rate Measuring Device ne GJ WASTE GAS DISPOSAL SYSTEM (Explosive Gas Monitoring System)

Col U1 I

a. Ilydrogen and Oxygen Monitors

~ou(2~

3. ondenser Air Ejector Vent System

a. Noble tivity Monitor (SPIHG or 47 PRMS)

Iodine Sampler m

C. Particulate Sampler 48 ED m

d. Effluent System Flow Rate Measuring Device ID C/I e. Sampler Flow Rate Measuring Device 4D t

C7 GJ

0 TABLE 3. 3-8 Continued RADIOACTIVE GASEOUS EFFLUEHT MONITORING IHSTRUMEHTATIOH MIHIMUM CHAHHELS INSTRUMENT OPERABLE APPLICABILITY ACTION P t Vent Systei (Include Unit 4's Spent 1 Pool)

a. Noble Ga tivity Monitor (SPIHG 47 or PRMS)

b. Iodine Saipler

c. Parti cul ate Sampler 48

d. Effluent System Flow Rate Measuring 46 Oevice

e. Sampler Flow Rate Measuring Oevice

5. Unit 3 Spent Fuel Pit Building Vent

a. Noble Gas Activity Monitor

b. Iodine Sampler 48

c. Particulate Sampler

d. Sampler Flow Rate Measuring Device

TABLE 3.3-8 (Continued}

TABLE NOTATION Ourin GAS OECAY TANK SYSTEM operation.

Applies ur>ng 1, , an

¹¹ plies during MOOE 1, 2, 3 and 4 when primary to secondary leakage is d ected as indicated by condenser air ejector noble gas activity monitor.

ACTION 45 Mith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the nk(s) may be released to the environment provided that prior to itiating the release:

a. At east two independent samples of the tank's contents are lyzed, and

b. At least o technically qualified members of the facility staff indepe ently verify the release rate calculations and discharge lve lineup; Otherwise, suspend relea of radioactive effluents via this, pathway.

ACTION 46- Mith the number of channels OP BLE less than required by the Minimum Channels OPERABLE require t, effluent releases via this pathway may continue provided t flow rate is estimated at least once per 4 hours.

ACTION 47- Mith the number of channels OPERABLE less t n required by the Minimum Channels OPERABLE requirement, efflue releases via this pathway may continue provided grab samples e taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are anal ed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 " With the number of channels OPERABLE less than required b the Minimum Channels OPERABLE requirement, effluent releases vi the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4. 11-2 and analyzed at least weekly.

ACTION 49- lith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the GAS OECAY TANK SYSTEM may continue provided that grab samples are collected and analyzed for hydrogen and oxygen concentration at least a) once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during degassing operations, and b) once per day during other operations.

TURKEY POINT - UNITS 3 8c 4 3/4 3-57 AMEHOMEHT HOS. AND

0 cpA s 0

QJPl052 YB TABLE 4.3-6 MONITORING IHSTRUMEHTATIOH SURVEILLANCE RE UIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS

?:

INSTRUMENT CHECK cnecv, cncraRnxtoz TEST RE UIRED C/l DECAY TANK SYSTEM 4J go a. Noble Gas Act>v> or-Providing Alarm and Automat>

Term>nation of Release (Plant Vent Monitor)

h. Effluent System Flow Rate Measuring Device (Explosive "g

GAS DECAY TANK SYSTEM Gas Monitoring System)

a. Hydrogen and Oxygen Monitors 0 N.A.

Condenser Air Ejector Vent System

a. Noble a ity Monitor (SPIHG or PRMS) R(3) m t3 b. Iodine Sampler H. A. N.A.

m C. Particulate Sampler H.A.

C)

C/l Effluent System Flow Rate Measuring Device N.A.

I CD

TABLE 4.3-6 Continued RADIOACTIVE GASEOUS EFFLUENT MOHITORING IHSTRUMENTATIOH SURVEILLANCE RE UIREMENTS ANALOG CNANHEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST RE UIRED

3. Condenser Air Ejector t System (Continued)

e. Sawple Flow Rate Measuring Device H.A. N.A.

4. Plant Vent Systea (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor (SPIHG or PRHS) 3) Q(2)

b. Iodine Sampler H.A. H.A. H.A.

c. Particulate Saapler N.A. H.A. .A.

d. Effluent System Flow Rate Measuring Device N.A. H.A.

e. Sampler Flow Rate Measuring Device D H.A. H.A.

TABLE 4. 3-6 Continued RADIOACTIVE GASEOUS EFFLUEHT MONITORING IHSTRUMENTATIOH SURVEILLANCE RE UIREMEHTS CD ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS IHSTRUMEHT CHECK CHECK CALIBRATION TEST RE VIREO

5. Unit 3 Spent Fuel Pit Building Ven

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

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

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

d. Salpler Flow Rate Measuring

'evice 0 H.A. N.A.

I cia TABLE NOTATION CD g Durin GAS ies during TANK S ST HODE o

1, 2, 3 an aration.

App during MODE 1, 2, 3 and 4 when priltary to secondary leakage is detected as indicated by m condenser ecto'oble gas activity monitor.

C7 (1) The ANALOG CHANNEL OPE TEST shall also demonstrate that automatic isolation of this pathway and fll control room alarm annunciation if the instrument indicates measured levels above the Alarm/Trip Setpoint.

CD (2) The ANALOG CHANHEL OPERATIOHAL TEST shall also demon e that if the instrument indicates measured levels above the Alarm Setpoint, alari annunciation occurs e control room (for PRMS only) and in the computer rooa (for SPING only).

(3) The initial CHANNEL CALIBRATIOH shall bc performed using one or more of the r ce standards certified by the National Institute of Standards and Technology (NIST) or using standards that been obtained from suppliers that participate in measurement assurance activities with NIST. These stan a hall permit calibrating the system over its intended range of energy and measurement range. For subseque CHANNEL CALIBRATIOH, sources that have been related to the initial calibration shall be used.

TABLE 4. 3-6 (Continued)

I TABLE NOTATIONS Continued (g) The CHANHEL CALIBRATION shall include the use of standard gas samples containing a nominal.

a. One volume percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

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

a. One volume percent oxygen, balance nitrogen, and

b. Four volume percent oxygen, balance nitrogen.

TURKEY POINT - UNITS 3 8 4 3/4 3-61 AHEHOHENT NOS. 149 AND 144

0 4.11 RADIOACTIVE EFFLUENTS 3 11.1 LI UID EFFLUENTS CONC E RATION LIMITING CONDITION FOR OPERATION 3.11.1.1 T concentration of radioactive material released in liquid effluents to HRESTRICTED AREAS (see Figure 5.1-1) shall be limited to 10 times the conc ntrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for ra 'onuclides other than dissolved or entrained noble gases. For dissolved or ent ined noble gases, the concentration shall be limited to 2 x 10 'icroCurie/ml otal activity.

APPLICABILITY: At al times.

ACTIOH:

With the concentration of dioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen-tration to within the above 1 its.

SURVEILLANCE RE UIREMEHTS

4. 11. 1, 1. 1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program o Table 4. 11-1.

4. 11. 1. 1.2 The results of the radioactiv ty analyses shall be used in accordance with the methodology and parame rs in the ODCM to assure that the concentrations at the point of release are i ntained withi n the limits of Specification 3.11.1.1.

TURKEY POINT UNITS 3 5, 4 3/4 11-1 AMEHDMEHT HOS.157AND 15

TABLE 4.11-1 RAOIOACTIVE LI UIO MASTE SAMPLING ANO ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUI RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLO)( )

TYP FREQUENCY FREQUEHCY ANALYSIS (pCi/ml)

1. Batch ste P P Release Each Batch Each Batch Principal Gamma 5x10-~

Tanks Emitters( )

I"131 lxl0-6 P Oissolved and lxl0- s 0 Batch/M Entrained Gases (Gamma Emitters)

P M H-3 lxlO-s Each Bat h Composite (4 Gross Alpha 1xl0-~

P Sr-89, Sr-90 Sx10 s 4

Each Batch Co osite Fe-55 1x10-6

2. Continuous Principal Gamma 5x10-~

Releases( ) Emitters I-131 lx10-6

a. Steam M(8) 0 solved and lxl0-s Generato~7) Ent ained Gases Slowdown (Gam Emitters)

(8) M(8) H-3 1x10-s Composite Gross Alpha lxl0-'xl0-a W(8) Q(8) Sr-89, Sr-90 Composite Fe-55 1 0-6

b. Storm Principal Gamma 5x10 Orain Emitters ( )

I-131 1x10-6 TURKEY POINT - UNITS 3 8 4 3/4 11-2 AMEHOMEHT HOS.137 ANO 132

TABLE 4. 11-1 (continued}

TABLE NOTATIONS (1.) e LLD is the smallest concentration of radioactive material in a sample th t will be detected with 95K probability with only 5~ probability of fal ly concluding that a blank observation represents a "real" signal.

For a rticular measurement system, which may include radiochemical separatl n:

4.66 sb LLD = -Qt

~

V ~

( .2 x Y exp Where:

LLD = the "a priori" lower limit of detection as defined above for a blank sample (microCurie per unit mass or volume),

s b

= the sta ard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts pe minute),

the counting ficiency (counts per disintegration),

V the sample size units of mass or volume),

2.22 x 10' the number of disin egrations per minute per microCurie, Y = the fracti onal radi och mi ca 1 yi el d, when app1 i cail e, the radioactive decay co tant for the particular radionucl ide, and at = the elapsed time between the idpoint of sample collection and the time of counting (for lant effluents, not environmental samples).

The value of sb used in the calculation of the LL for a detection system shall be based on the actual observed variance of t background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and b,t should be used in the calculation.

A batch release is the discharge of liquid wastes of a disc te volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure r resenta-tive sampling.

TURKEY POINT - UNITS 3 8 4 3/4 11-3 AMENDMENT NOS.137AND 132

TABLE 4. 11-1 Continued)

TABLE NOTATIONS (Continued)

The principal gamma emitters for which the LLO specification exclusively plies are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Z 65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean tha only these nuclides are to be considered. Other gamma peaks that are iden fiable, together wi th those of the above nuclides, shall also be analyz d and reported in the Semiannual Radioactive Effluent Release Report rsuant to Specification 6.9. 1.4.

A composite ample is one in which the quantity of liquid sampled is proportional o the quantity of liquid waste discharged and in which the method of samp 'ng employed results in a specimen that is representative of the liquids leased.

(5) A continuous releas is the discharge of liquid wastes of a nondiscrete volume, e.g., from a olume of a system that has an input flow during the continuous release.

(6) Prior to analyses, all sam les taken for the composite shall be thoroughly mixed in order for the comp ite sample to be representative of the effluent release.

(7) Sampling and analysis of steam

'

nerator blowdown is not required during Mode 5 or 6.

(8) Sampling and analysis of steam gener tor blowdown on the applicable unit is only necessary for these species w n primary to secondary leakage is occurring as indicated by the condenser ir ejector noble gas activity monitor. (See Specification 3.3.3.6 in ble 3.3-8, Item 3a).

$2LP TURKEY POINT - UNITS 3 & 4 3/4 11-4 AMENOMENT NOS.137 AND 132

0IOACTIVE EFF LUEHTS OOS LIMITI CONDITION FOR OPERATION 3.11.1.2 e dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5. -1) shall be limited:

a. Ouring ny calendar quarter to less than or equal to 1.5 mrems to the who body and to less than or equal to 5 mrems to any organ, and b, Ouring any c lendar year to less than or equal to 3 mrems to the whole body an to less than or equal to 10 mrems to any organ.

APPLICABiLiTY: At all tim ACTION:

a 0 With the calculated do e from the release of radioactive materials in liquid effluents exc ding any of the above limits, prepare and submit to the Commiss'on within 30 days, pursuant to Specification 6.9.2, a Special Report th t identifies the cause(s) for exceeding the limit(s) and defines th corrective actions that have been 'taken to reduce the releases and th proposed corrective actions to be taken to assure that subsequen releases will be in compliance with the above limits.

b. The provisions of Specification 3. 3 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11. 1.2 Cumulative dose contributions from liquid ffluents for the current calendar quarter and the current calendar year shall determined in accordance with the methodology and parameters in the OOCM at leas once per 31 days.

TURKEY POINT - UNITS 3 8 4 3/4 11-5 AMEHOMEHT NOS3.37 AHO 132

DIOACTIVE EFFLUEHTS LI U RADMASTE TREATMEHT SYSTEM LIMITIHG CONDITION FOR OPERATION

3. 11. 1.3 T Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of t e system shall be used to reduce releases of radioactivity when the projected ses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figu 5. 1-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At a 1 times.

ACTION:

Mith radioactiv liquid waste being discharged without treatment and in excess of the bove limits and any portion of the Liquid Radwaste Treatment System n t in operation, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6. 9. 2, a Special Report that includes the fol owing information:

1. , Explanation of why iquid radwaste was being discharged without treatment, identific tion of any inoperable equipment or, subsystems, and the r son for the inoperability,

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

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

The provisions of Specification 3.0. are not applicable.

SURVEILLANCE RE UIREMEHTS 4.11.1.3.1 Doses due to liquid releases from each un't to UNRESTRICTED AREAS shall be projected at least once per 31 days in accord ce with the methodology and parameters in the ODCM when Liquid Radwaste Treatmen Systems are not being rul ly utilized.

4. 11. 1. 3. 2 The installed Liquid Radwaste Treatment System s all be considered OPERABLE by meeting Specifications 3. 11. 1. 1 and 3. . 1.2.

Bel~>~

Pa )e TURKEY POINT - UNITS 3 & 4 3/4 11-6 AMENDMENT HOSZ37 AND132

RA IOACTIVE EFFLUEHTS 3/4. 1 .2 GASEOUS EFFLUEHTS OOSE RA LIMITING CO ITIOH FOR OPERATION

3. 11.2. 1 The se rate due to radioactive materials released in gaseous effluents from t site to areas at and beyond the SITE 80UNOARY (see Figure

5. 1-1) shall be 11 ited to the following:

a. For noble ses: Less than or equal to 500 mrems/yr to the whole body and les than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-131, for Iodine-133, for tritium, and for all radio-nuclides in part> ulate form with half-lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ.

APPLICAS ILITY: At al 1 times.

ACTION:

Mith the dose rate(s) exceeding the a ove limits, immediately restore the release rate to within the above limit ).

4 SURVEILLANCE RE UIREMEHTS

4. 11.2. 1. 1 The dose rate due to noble gases gaseous effluents shall be determined to be within the above limits in ac rdance with the methodology and parameters in the OOCM.

4.11.2.1.2 The dose rate due to Iodine-131, Iodine 133, tritium, and all radionuclides in particulate form with half-lives gr ter than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 0 M by obtaining representative samples and performing analyses in accorda ce with the sampling and analysis program specified in Table 4. 11-2.

Dgl~4<

pa)e TURKEY POINT - UNITS 3 8 4 3/4 11-7 AMENOMEHT HOS.137 AHO 132

TAB~~ 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLIHG AND ANALYSIS PROGRAM MIN I MUM LOW R M OF SAMPLING ANALYSIS TYPE OF DETECTIOH ( )(1)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (tjci/

1. Gas Decay P P Tank (Batch) Each Tank Each Tank Principal Gamma Emit. ters Grab Sam le xlO-'xlO-~

6

2. Containment Purge P P or Venting (Batch) Grab Sample Each PURGE( Princi al Gamma Emitters ft-3 lxlO-6

3. Condenser Air M Principal Gamma E ters lxlO-~

Ejector s Grab Sample Gas Sampl e H-3 lxlO-6 Plant Vent. (In- M M Principal amma Emi tt.ers lxlO-~

cludes Unit 4 Grab Sam le Gas Sam le Spent Fuel Pit M 4 , 5 Building Vent. ) Grab Sample I-3 lxlO-G

5. Unit 3 Spent. Fuel M M Principal Gamma Emi t ters lxlO-~

Pi t Building Grab Sam le Gas S le Vent M Grab Sam le H-3 lxlO-6 3

6. All Release Types Cont.inuous W 1-131 lxlO-'2 as listed in 3., Charcoal 4., and 5. above Sam le 3

Co >nuous W Principal Gamma Emitters lxlo->>

Particulate Sam le Continuous M Gross Alpha lxlo->>

Composite Par-ticulate Sam l~

3 Continuous Sr-89, Sr-90 lxlo->>

Composi te Par-ticulate Samil~

3 Cont.inuous Hoble Gas Noble Gas Monitor ross Beta or Gamma lxlO-6

0 TABLE 4.11-2 (Continued)

TABLE NOTATIONS The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95K probability with only 5X probability of alsely concluding that a blank observation represents a "real" signal.

Fo a particular measurement system, which may include radiochemical sepa tion:

4. 66 sb LLD

~

V . (2. 22 x lOe) ~

Y [exp (-Mt)]

Mhere:

LLD t "a priori" lower limit of detection as defined above as blank sample (microCurie per unit mass or volume),

sb

= the st dard deviation of the background counting rate or

'of the c unting rate of a blank sample as appropriate (counts p minute),

the counting fficiency (counts per disintegration).,

C V the sample size units of mass or volume),

2.22 x 10' the number of disin grations per minute per microCurie, Y = the fractional radioch ical yield, when applicable, the radioactive decay con ant for the particular radionuclide, and at = the elapsed time between the m'oint of sample collection and the time of counting (for p nt effluents, not environmental samples)

The value of sb used in the calculation of the LLD r a detection system shall be based on the actual observed variance of the ackground counting rate or of the counting rate of the blank samples (as a ropriate) rather than on an unverified theoretically predicted variance. pical values of E, V, Y and b,t shall be used in the calculation.

0 l~k Pffft TURKEY POINT - UNITS 3 & 4 3/4 l.a-9 AMEHDMEHT HOS.137 AHD 132

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

The principal gamma emitters for which the LLD specification will apply e exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, X 133m, Xe-135, and Xe-138 in noble gas emissions and Mn-54, Fe-59, Co-, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for p rticulate emissions. This list does not mean that only these nuclid are to be detected and reported. Other gamma peaks that are measurab e and identifiable, together with the above nuclides, shall also be identi 'ed and reported pursuant to Specification 6.9. 1.4.

Huclides whi are below the LLD for the analyses should not be reported as being prese t at the LLD for that nuclide. When a radionuclide's calculated LLD > greater than its listed LLD limit, the calculated LLD should be assigne as the activity of the radionuclide; or, the activity of the radionuclide should be calculated using measured ratios with those radionuclides which e routinely identified and measured.

(3) The ratio of the sample low rate to the sampled stream flow rate shall be known for the time period overed by each dose or dose rate calculation made in accordance with Spe ifications 3. 11.2. 1, 3. 11.2.2, and 3. 11.2.3.

(4) When a Unit's refueling canal i flooded Tritium grab samples shall! be taken on that Unit only from the ollowing respective area(s) at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

For Unit 3 sample the plant vent and e Unit 3 spent fuel pool area ventilation exhaust.

For Unit 4 sample the plant vent only.

(5) When spent fuel is in the spent fuel pool, tri ium grab samples shall be taken from the following respective area at ast once per 7 days:

For Unit 3, sample the Unit 3 spent fuel pool area entilation exhaust For Unit 4, sample the plant vent.

I (6) Sampling and analysis shall also be performed following s tdown, startup, or a THERMAL POWER change exceeding 15K of RATED THERMAL PO R within a 1-hour period if (1) analysis shows that the DOSE E(UIVALENT -131 con-centration in the primary coolant has increased by more than a actor of 3; and (2) the noble gas activity monitor shows that effluent ac ivity has increased by more than a factor of 3.

TURKEY POINT - UNITS 3 8 4 3/4 11-10 AMEHDMEHT NOSj.37 AND 132

TABLE 4. 11-2 Continued)

TABLE NOTATIONS (Continued)

(7) mple collection media on the applicable Unit shall be changed at least on e per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after cha ing, or after removal from sampler. Sample collection media on the appl> able Unit shall also be changed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least days following each shutdown, startup, or THERMAL POMER change exceedin 15K of RATED THERMAL POMER within a 1-hour period and analyses shall be mpleted within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing if: (1) analysis shows that the 0 E E(UIVALENT I-131 concentration in the primary coolant has increased mo e than a factor of 3; and (2) the noble gas monitor shows that effluent ctivity has increased more than a factor of 3. Mhen samples collect d for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by factor of 10.

TURKEY POINT - UNITS 3 & 4 3/4 11-11 AMENDMEHT HOS.137 AHD 132

RADIOACTIVE EFFLUENTS DOSE NOBLE GASES LIMITIHG COHOITIOH FOR OPERATION

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

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

b. During any c endar year: Less than or equal to 10 mrads for gamma radiation and ess than or equal to 20 mrads for beta radiation.

APPLICABILITY: At al 1 tim ACTION with the calculated ai dose from radioactive noble gases in gaseous effluents exceeding any f the above limits, prepare and submit to the Commission within 30 ays, pursuant to Specification 6.9.2, a Special Report that identi ies the cause(s) for exceeding the, limit(s) and defines the corrective tions that have been taken to .reduce the releases and the propose corrective actions to be taken to assure that subsequent release will be in compliance with the above limits.

b. The provisions of Specification 3. 3 are not applicable.

SURVEILLANCE RE UIREMEHTS

4. 11.2.2 Cumulative dose contributions for the cur ent calendar quarter and current calendar year for noble gases shall be deter ned in accordance with the methodology and parameters in the ODCM at least on e per 31 days.

D~t~te P~~e.

TURKEY POINT - UNITS 3 8 4 3/4 11-12 AMENDMENT NOS.137 AND 132

RAOIOACTIVE EFFLUEHTS 00 E

- IOOIHE-131 IOOIHE-133 TRITIUM, AHO RAOIOACTIVE MATERIAL IH A ULA ORM LIMITI CONOITIOH FOR OPERATION 3.11.2.3 he dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, an all radionuclides in particulate form with half-lives greater than 8 days > gaseous effluents released, from each unit, to areas at and beyond the SI BOUNOARY (see Figure 5.1-1) shall be limited to the following:

a. Ouring ny calendar quarter: Less than or equal to 7.5 mrems to any organ an

b. Ouring any alendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all t) es.

ACTIOH:

Mith the calculated se from the release of Iodine-131, Iodine-133, tritium, and radionuc des in particulate form with half-lives greater than 8 days, in aseous effluents exceeding any of the. above limits, prepare and subm t to the Commission within 30 days, pursuant to Specification 6. 9. 2, a pecial Report that identifies the cause(s) for exceeding the limit(s) nd defines the corrective actions that have been taken to reduce the rel ses and the proposed corrective actions to be taken to assure that s 'quent releases will be in compliance with the above limits.

b. The provisions of Specification 3. .3 are not applicable.

SURVEILLANCE RE UIREHENTS

4. 11.2.3 Cumulative dose contributions for the cu ent calendar quarter and current calendar year for Iodine-131, Iodine-133, tr tium and radionuclides in particulate form with half-lives greater than 8 da shall be determined in accordance with the methodology and parameters in t OOCM at least once per 31 days.

TURKEY POINT - UNITS 3 & 4 3/4 11-13 AMEHOHEHT NOSZ37 ANO 132

RADIOACTIVE EFFLUEHTS GA US RAOWASTE TREATMEHT SYSTEM LIMITIH CONOITION FOR OPERATION

3. 11.2.4 T VENTILATION EXHAUST TREATMENT SYSTEM and the GAS OECAY TAHK SYSTEM shall e OPERABLE and appropriate portions of these systems shall be used to reduce eleases of radioactivity when the projected doses in 31 days due to gaseous fluent releases, from each unit, to areas at and beyond the SITE BOUNOARY (se Figure 5. 1-1) would exceed:

a. 0.2 mrad o air from gamma radiation, or

b. 0.4 mrad to ir from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At al 1 times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the abov limits, prepare and submit to the Commission within 30 days, ursuant to Specification 6.9.2, a .

Special Report that includes the following information:

1. Identification of any inop rable equipment or subsystems, and the reason for the inoperab'lity,

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

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

b. The provisions of Specification 3.0.3 are ot applicable.

SURVEILLANCE RE UIREMEHTS

4. 11.2.4. 1 Ooses due to gaseous releases from each unit t areas at and beyond the SITE BOUHOARY shall be projected at least once p 31 days in accordance with the methodology and parameters in the OOCM w n Gaseous Radwaste Treatment Systems are not being fully utilized.

4. 11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM an AS OECAY TANK SYSTEM shall be considered OPERABLE by meeting Specifications 3. ~ 2. 1 and either 3.11.2.2 or 3.11.2.3, TURKEY POINT - UNITS 3 8 4 3/4 11-14 AMEHOMEHT NOS137 AND 132

EXPLOSIVE GAS MIXTURE LIMITIHG CONDITION FOR OPERATION

~4.'~ The concentration of oxygen in the GAS DECAY TANK SYSTEM (as measured in the inservice gas decay tank) shall be limited to less than or equal to 2X by volume whenever the hydrogen concentration exceeds 4X by volume.

APPLICABILITY: At all times.

ACTION:

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

b. Mith the concentration of oxygen in the inservice gas decay tank greater than 4X by volume and the hydrogen concentration greater than 4X by volume, immediately suspend all additions of waste gases to the gas decay tanks and reduce the concentration of oxygen to less than or equal to 4X by volume, then take ACTION a., above.

C. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMEHTS . R-.2-.S- The concentrations of hydrogen and oxygen in the inservice gas decay tanks shall be determined to be within the above limits by continuously" monitoring the waste gases in the inservice gas decay tank with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-8 of Specification 3.3.3.6.

"When continuous monitoring capability is inoperable, Table 3.3-8 allows the use of grab samples.

3/q'-NV TURKEY POINT - UNITS 3 8 4 AMENDMENT NOS. 149 AHD 144

'

pj]+7 Sps7kA/S GAS DECAY TANKS LIMITING COHO IT ION FOR OPERATION

~g '~ ~ 7t The quantity of radioactivity contained be limited to less than or equal to 70,000 Curies in each gas decay tank shall of noble gases (considered as Xe-133 equivalent) .

'APPLICABILITY: At al 1 times.

ACTION:

a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9. 1.4.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREHEHTS T f f df f TT* T df k d k shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank and the Reactor Coolant System total activity exceeds the limit of Specification 3.4.8.

t TURKEY POINT UNITS 3 K 4 AMEHDMEHT HOS . 1 ~ 7AND 1 ~1

0 ADIOACTIVE EFFLUEHTS 3 . 11. 3 SOLID RADIOACTIVE WASTES LIMI NG CONDITION FOR OPERATION 3.11.3 SOLIDIFICATION or dewateting of radioactive wastes shall be performed in accor nce with the PROCESS CONTROL PROGRAM to meet shipping and transpor-tation re irements during transit, and the applicable licensing requirements of the cons nee when received at the shipping destination.

APPLICABILITY. At all times.

ACTION:

a. With SO DIFICATION or dewatering not meeting the applicable licensin requireme ts of the consignee and shipping and transportation require-ments, sus nd shipment of the inadequately processed wastes and correct the ROCESS CONTROL PROGRAM, the procedures, and/or the Solid Waste S tern as necessary to prevent recurrence.

With SOLIDIFICA ON or dewatering not performed in accordance with the PROCESS CONT L PROGRAM, test the improperly processed waste in each container to sure that it meets the applicable licensing requirements of the onsignee and shipping requirements and take appropriate administr tive action to prevent recurrence.

c. The provisions of Speci ication 3.0.3 are not applicable.

SURVEILLANCE RE UIREMEHTS 4.11.3.1 Dewatering shall be performe in accordance with the PCP.

4.11.3.2 SOLIDIFICATION (excluding dewa ring) of at least one representative test specimen from at least every tenth ba ch of each type of wet radioactive wastes (e. g., filter sludges, spent resins, vaporator bottoms, boric acid solutions, and sodium sulfate solutions) sha be verified in accordance with the PROCESS CONTROL PROGRAM:

If any test specimen fails to verify S IDIFICATIOH, the SOLIDIFICATION of the batch under test shall be suspen d until such time as additional test specimens can be obtained, alternati e SOLIDIFICATION parameters can be determined in accordance with the P CESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATIO . SOLIDIFICATION of the batch may then be resumed using the alter tive SOLIDIFICATION parameters determined by the PROCESS CONTROL P GRAM; If the initial test specimen from a batch of wast fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall ovide for the collection and testing of representative test speci ns from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIF ATIOH.

The PROCESS CONTROL PROGRAM shall be modified as require , as provided in Specification 6.13, to assure SOLIDIFICATION of subseq nt batches of waste; and c ~ With the installed equipment incapable of meeting Specificats n

3. 11.3 or declared inoperable, restore the equipment to OPERAB status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.

TURKEY POINT - UNITS 3 8 4 3/4 11-17 AMEHDMENT NOS.137 AHD 132

RADIOACTIVE EFFLUENTS 4.11.4 TOTAL DOSE LI TING CONDITION FOR OPERATION

3. 11.4 he annual (calendar year) dose or dose conmitment to any MEMBER OF THE PUBLIC d to releases of radioactivity and to radiation from uranium fuel cycle sour s shall be limited to less than or .equal to 25 mrems to the whole body or any rgan, except the thyroid, which shall be limited to less than or equal to 75 m ems.

APPLICABILITY: t all times.

ACTIOH:

a. With the calc lated doses from the release of radioactive materials in liquid or gase s effluents exceeding twice the limits of Specifi-cation 3. 11. 1.2a , 3. 11. 1.2b., 3. 11.2.2a., 3. 11.2.2b., 3. 11.2.3a., or

3. 11.2.3b., calcu tions shall be made including direct radiation contributions from he units to determine whether the above limits of

~)> Specification 3. 11.4 ave been exceeded.

and submit to the Co If such is the case, prepare ssion within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken pygmy. to reduce subsequent rel ses to prevent recurrence of exceeding the above limits and includes e schedule for achieving conformance with the above limits. This Spe 'al Report, as defined in 10 CFR 20.2203(a)(4), shall include analysis that estimates the radiation exposure (dose) to a MEMBER OF HE PUBLIC from uranium fuel cycle sources, including all effluent athways and direct radiation, for the calendar year that includes the r ease(s) covered by this report. It shall also describe levels of radia ion and concentrations of radio-active material involved, and the ca e of the exposure levels or concentrations. If the estimated dose s) exceeds the above limits, and if the release condition resulting violation of 40 CFR Part 190 has not already been corrected, the Specs l Report shall include a request for a variance in accordance with e provisions of 40 CFR Part 190. Submittal of the report is consi red a timely request, and a variance is granted until staff action on t e request is complete.

b. The provisions of Specification 3.0.3 are not ap licable.

SURVEILLANCE RE UIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous fluents shall be determined in accordance with Specifications 4. 11. 1.2, 4. 11.2.2 and

4. 11.2.3, and in accordance with the methodology and parameters in e ODCM.

4. 11.4.2 Cumulative dose contributions from direct radiation from the nits and the methodology used shall be indicated in the Annual Radioactive E luent Release Report. This requirement is applicable only under conditions set orth in ACTION a. o f Speci fi cat i on 3. 11.4.

TURKEY POINT UNITS 3 L 4 3/4 11-18 AMENDMEHT HOS.>>7 AHD >>l

/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/ 12. 1 MONITORING PROGRAM LIMIT G CONDITION FOR OPERATION

3. 12.1 T Radiological Environmental Monitoring Program shall be conducted as specific in Table 3.12-1.

APPLICABILITY. At all times.

ACTION:

a. With the adiological Environmental Monitoring Program not being conducted specified in Table 3. 12-1, prepare and submit to the Commiss> n, in the Annual Radiological Environmental Operating Report requir by Specification 6.9. 1.3, a description of the reasons for not conduc 'ng the program as required and the plans for preventing a recurrence.

With the level of nfirmed"" radioactivity as the result of plant effluents in an envi onmental sampling medium at a specified location exceeding the reporti levels of Table 3.12-2 when averaged over any calendar quarter, prepa e and submit to the Commission within 30 days, pursuant to Specificatio 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 redu radioactive effluents so that the potential annual dose" to a MBER OF THE PUBLIC is less than the calendar year limits of Speci cations 3, 11. 1.2, 3. 11.2.2, or

3. 11.2.3. When more than one o the radionuclides in Table 3. 12-2 Pap~ are detected in the sampling medi m, this report shall be submitted if:

concentration (1) concentra ion (2) report>ng eve 1 reporting ve 2

+ ...> 1.0 When radionuclides other than those in Ta le 3. 12-2 are detected and are the result of plant effluents, this re rt shall be submitted the potential annual dose" to a MEMBER OF T PUBLIC from all radio-if nuclides is equal to or greater than the cale ar year limits of Specification 3. 11. 1.2, 3. 11.2.2, or 3. 11.2.3. This report is not required if the measured level of radioactivity as not the result of plant effluents; however, in such an event, th condition shall be reported and described in the Annual Radiologica Environmental Operating Report required by Specification 6.9. 1.3.

"The methodology and parameters used to estimate the potential ann al dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

"~A confirmatory reanalysis of the original, a duplicate, or a new sam le may be desirable, as appropriate. The results of the confirmatory analyst shall be completed at the earliest time consistent with the analysis, but in y

case within 30 days.

TURKEY POINT - UNITS 3 & 4 3/4 12-1 AMEHDMEHT HOS.137 AHD 132

RAD IOLOG ICAL ENV I RONMENTAL MON I TOR ING LIMITING CONDITION FOR OPERATION ACTION Continued Wit ilk or broad leaf vegetation samples unavailable from one or more o the sample locations required by Table 3. 12-1, identify specific ocations for obtaining replacement samples and add them within 30 s to the Radiological Environmental Monitoring Program given in the CM. The specific locations from which samples were unavailable may hen be deleted from the monitoring program. Pursuan to Specification . 4, submit in the next Annual Radioactive Effluen Py~ Release Report docum tation for a change in the ODCM including a revised figure(s) and le for the ODCM reflecting the new location(s) with supporti information identifying the cause of the unavailability of samples a justifying the selection of the new location(s) for obtaining samp s.

The provisions of Specification 3. are not applicable.

SURVEILLANCE RE UIREMENTS

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.

TURKEY POINT - UNITS 3 8 4 3)4 12-2 AMENDMENT NOS. 178 AND 172

TABLE 3.12"1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM O NUMBER OF CD REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE ARD FREg($ )CY AND/OR SAMPLE SAMPLE LOCATIONS COLLECTIQN FRE UENCY OF ANALYSIS

1. Direct Radiation monitoring locations Continuous monitoring Gamma exposure rate with sample collection quarterly quarterly

2. Airborne Radioiodine and Five location Continuous sampler oper- Radioiodine Filter Particulates ation with sample collec- y kky.

tion weekly, or more frequently if required by dust loading. Particulate Filter ross eta ra >oactivity analysis > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change; Gamma isotopic analysis of composite (by locat>on) quarterly.

3. Waterborne m a. Surface Three locations Monthly Gambia isotopic CD nd tritium analyses monthly.

Ell CD CA C7 CkkR

% e.

TABLE 3. 12-1 RAD IOLOG ICAL EHVI ROHMEHTAL MON I TORIHG PROGRAM HUMBER OF REPRESEHTATIVE EXPOSURE PATHWAY SAMPLES AHD SAMPLIHG AHO TYPE AND F )CY AHO/OR SAMPLE SAMPLE LOCATIOHS COLLECTIOH FRE UEHCY OF AH SIS ($

3. Waterborne (Continued)

b. Sediment Three locations Semiannually. Gamma isotopic analysis from semiannually.

Shoreline

4. Ingestion

a. Fish and Inverte-brates

l. Crustacea Two locations Semiannually Gamma isotopic analysis semiannually

2. Fish Two locations Semiannually Gamma isotopic analysis semiannually

b. Food Products

l. Broad leaf Three locations (11) Monthly when available Gamma isotopic (B)

.

and I-131 vegeta on analyses monthly.

TABLE 3. 12-1 Continued TABLE NOTATIONS (1) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, sea-sonal unavailability, and malfunction of automatic sampling equipment or other legitimate easons. If specimens are unobtainable due to sampling equipment malfunct'on, corrective action shall be taken prior to the end of the next samplin period. All deviations from the sampling schedule shall be documented the Annual Radiological Environmental Operating Report pursuant to Sp ification 6. 9. l. 3.

(2) Specific parameters of 'stance and direction sector from the centerline of the plant vent stack a d additional description where pertinent, shall be provided for each and e ry sample location in Table 3. 12-1 in a table and figure(s) in the ODCM.

(3) At times, it may not be possib e or practicable to continue to obtain samples of the media of choice t the most desired location or time. In these instances suitable alterna 've media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological nvironmental Monitoring Program given in the ODCM.

(4) The following definition of frequencie shall apply to Table 3.12-1 only:

Weekl - not less than once per calendar eek. A maximum interval of 11 ays >s allowed between the collection of y two consecutive samples.

Semi-Monthl - Not less than 2 times per cale dar month with an interval o not ess than 7 days between sample collect'ons.' maximum interval of 24 days is allowed between collection of any two consecutive samples.

Monthl - Not less than once per calendar month ws h an interval of not ess t an 10 days between collection of any two con ecutive samples.

guuarterlr - Not less than once per calendar quarter.

Semiannuall - One sample each between calendar dates ( nuary 1 - June 30) an u y - December 31). An interval of not less than 3Q days will be provided between sample collections.

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

(5) One or more instruments, such as a pressurized'on chamber, for asuring and recording dose rate continuously may be used in place of, or addi-tion to, integrating dosimeters. For the purposes of this table, a thermo-luminescent dosimeter (TLD) is considered to be one phospho~; two or more phosphors in a packet are considered as two or more dosimeters.

s TURKEY POINT " UNITS 3 4 4 3/4 12-5 AMENDMENT NOS.137 AND 132

TABLE 3. 12-1 Continued)

TABLE NOTATIONS Continued)

(6) Ref s to normal coll. ection frequency. More frequent sample collection is p mitted when conditions warrant it.

(7) Airborn particulate sample filters are analyzed for gross beta radio-activity 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or more after sampling to allow for radon and thoron daughter cay. In addition to the requirement for a gamma isotopic on a composite ample, a gamma isotopic is also required for each sample having a gro beta radioactivity which is > 1.0 pCi/ms and which is also > 10 time that of the most recent control sample.

(8) Gamma isotopic a lysis means the identification and quantification of gamma-emitting ra 'onuclides that may be attributable to the effluents from the facility.

(9) Off-shore grab samples.

(10) Discharges from the Turke Point Plant do not influence drinking water or ground water pathways.

(11) Samples of broad leaf vegetat'on grown nearest each of two different off-site locations of highest pred'cted annual average ground level 0/g; and one sample of similar broad lea vegetation at an available location 15-30 km distant in the least pre alent wind direction based upon his-torical data in the ODCM.

Pygmy.

TURKEY POINT - UNITS 3 8 4 3/4 12-6 AMEHDMEHT HOSZ37 AND132

TABLE 3. 12-2 REPORTIHG LEVELS FOR RAOIOACTIVITY CONCENTRATIONS IH ENVIRONMENTAL SAHPLES REPORTING LEVELS MATER AIRBORNE PARTICULATE FISII HILK FOOD PROOUCTS ANALYSIS (pCi/1) OR GASES (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) l/l If-3 30,000" po Hn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 C

Co-60 300 ,000 I

Zn-65 300 20,000 Hb 954*4 400 1-131 0.9 100 Cs-134 30 1,000 60 1,000 m Cs-137 50 20 2,000 70 2,000 m Ba- La-140**" 200 300 Since no drink g water pathway exists, a value of 30,000 pCi/1 is used. For drinking water samples, a value CD CA of 20,000 p 1 is used. This is 40 CFR Part 141 value.

""Applies drinking water

~ 4h uilibrium mixture of the parent and daughter isotopes which corresponds to the reporting value of the

'>>An C) rent. isotope.

PJ,

TABLE 4. 12-1 m DETECTION CAPABILITIES fOR ENVIRONMENTAL SAHPLE ANALYSIS LOWER LIMIT OF DETECTION LLD)

I WATER AIRBORNE PARTICULATE FISH =

HI LK FOOD PR CTS SEDIMENT ANALYSIS (pCi/1) OR GASES (pCi/m~) (pCi/kg, wet) (pCi/1) (pCi g, wet) (pCi/kg, dry)

C/l 4J Gross Beta 4 0. 01 go ll-3 3000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 30 I

OO 2n-65 30 260 Zr-Nb-95 15("

1-131 1(4) .07 60 Cs-134 15 0. 05 130 15 60 150 m Cs-137 18 0. 06 150 18 180 C)

Ba- La-140 15(5)

Since no nking water patbway exists, a value of 3,000 pCi/1 is used. For drinking water sampIes a value of 2,0 pCi/1 is used.

TABLE 4. 12-1 Continued)

TABLE NOTATIONS

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

Other peaks that are identifiable, together with those of the above clides, shall also be analyzed and reported in the Annual Radiological En ironmental Operating Report pursuant to Specification 6.9. 1.3.

(2)Requi ed detection capabilities for thermoluminescent dosimeters used for en 'ronmental measurements are given in Regulatory Guide 4. 13.

(3)The LLO i defined, for purposes of these specifications, as the smallest concentrati of radioactive material in a sample that will yield a net count, above stem background, that will be detected with 95M probability with only 5X p bability of falsely concluding that a blank observation represents a "re 1" signal.

For a particular me surement system, which may include radiochemical separation:

4.66 (sb)

LLO E ~

V ~

.22 ~

Y [exp(-Mt)j Where:

LLO = the "a priori" lower 1 it of detection as defined above as ~

picoCuries per unit mas or volume, sb = the standard deviation of e background counting rate or of the counting rate of a blank sam le as appropriate (counts per minute),

E = the counting efficiency (counts er disintegration),

V the sample size (units of mass or olume),

2.22 = the number of disintegrations per min te per picoCurie, Y = the fractional radiochemical yield, when pplicable, the radioactive decay constant for the part ular radionuclide, and Dt = the elapsed time between environmental collect n, or end of the sample collection period, and time of counting ec).

Typical values of E, V, Y, and bt should be used in the ca culation.

TURKEY POINT - UNITS 3 & 4 3/4 12-9 AMENDMENT NOS.137 AND 132

TABLE 4. 12-1 Continued TABLE NOTATIONS Continued It should be recognized that the LLD is defined as an a priori (before the act) limit representing the capability of a measurement system and not as a a osteriori (after the fact) limit for a particular measurement.

An yses shall be performed in such a manner that the stated LLOs will be achi ved under routine conditions. Occasionally background fluctuations, unavo able small sample sizes, the presence of interfering nuclides, or other u controllable circumstances may render these LLDs unachievable.

In such ses, the contributing factors shall be identified and described in the Ann al Radiological Environmental Operating Report pursuant to Specificati 6.9. 1.3, (4)LLO for drinki water samples. If no drinking water pathway exists, the LLD of gamma is opic analysis may be used.

(5)An equilibrium mix re of the parent and daughter isotopes which corresponds to 15 pCi/1 of the p rent isotope.

pg) L TURKEY POINT " UNITS 3 & 4 3/4 12-10 AMEHOMEHT HOS.137AHO 132

RAD LOG'ICAL EHVIRONMENTAL MONITORING 3/4. 12. LAHD USE CENSUS LIMITIHG NDITION FOR OPERATION

3. 12.2 A Lan Use Census shall be conducted and shall identify within a distance of 8 (5 miles) the location in each of the 16 meteorological sectors of the arest milk animal, the nearest residence, and the nearest garden" of greate than 50 m (500 ft ) producing broad leaf vegetation.

APPLICABILITY: At al times.

ACTION:

Mith a Land Use ensus identifying a location(s) that yields a calculated dose o dose commitment greater than the values currently being calculated i Specification 4. 11. 2. 3, pursuant to Specifica-tion 6. 9. 1. 4, ident fy the new location(s) in the next Semiannual Radioactive Effluent elease Report.

b. Mith a Land Use Census 'dentifying a location(s) that yields a calculated dose or dose mmitment (via the same exposure pathway) 20M greater than at a loca ion from which samples are currently being obtained in accordanc with Specification 3. 12. 1, add the new location(s) within 30 days t the Radiological Environmental Moni-toring Program given in the 0 M. The sampling location(s), exclud-ing the control station,locatio , having the lowest calculated dose or dose commitment(s), via the s e exposure pathway, may be deleted from this monitoring program afte October 31 of the year in which this Land Use Census was conducted. Pursuant to Specification 6. 14, submit in the next Semiannual Radioa tive Effluent Release Report documentation for a change in the ODC including a revised figure(s) and table(s) for the ODCM reflecting t new location(s) with informa-tion supporting the change in sampling cations. 1 C. The provisions of Specification 3.0.3 are t applicable.

"Broad leaf vegetation sampling may be performed at the SITE BOUNDAR in each of two different direction sectors with the highest predicted 0/gs in lieu of the garden census. Specifications for broad leaf vegetation sampling 'n Table 3.12-1, Part 4.b., shall be followed, including analysis of contr 1 samples.

TURKEY POINT - UNITS 3 & 4 3/4 12-11 ~

AMENDMEHT NOS.137 AHD 132

RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILLANCE RE UIREMEHTS 12.2 The Land Use Census shall be conducted during the growing season at le t once per 12 months using that information that will provide the best res ts, such as by a door-to-door survey, aerial survey, or by consulting local griculture authorities. The results of the Land Use Census shall be include in the Annual Radiological Environmental Operating Report pursuant to Speci fic tion 6. 9. 1. 3.

TURKEY POINT - UNITS 3 8 4 3/4 12-12 AMENDMENT NOS,137 AHO 132

RAOI LOGICAL ENVIRONMENTAL MONITORING 3/4. 12. INTERLABORATORY COMPARISON PROGRAM LIMITIHG C HDITION FOR OPERATION 3.12.3 Analy es shall be performed on all radioactive materials, supplied as part of an Int rlaboratory Comparison Program that has been approved by the Commission", th t correspond to samples required by Tables 3. 12-1 and 3. 12-2.

APPLICABILITY: A al 1 times, ACTION:

a. With analyse not being performed as required above, report the corrective ac 'ons taken to prevent a recurrence to the Commission in the Annual diological Environmental Operating Report pursuant to Specification 6.9.1.3.

b. The provisions of ecification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMEHTS

4. 12.3 A summary of the results o tained as part of the above required :

Interlaboratory Comparison Program hall be included in the Annual Radiological Environmental Operating Report pursu t to Specification 6.9. 1.3.

"This condition is satisfied by participation in the Environmenta Radio-activity Laboratory Intercomparison Studies Program conducted by e Environmental Protection Agency (EPA).

TURKEY POINT - UNITS 3 8( 4 3/4 12-13 AMENDMENT NOS.137 AND 1 2

ADNIHISTRAT CONT 0 S PROCEDURES AX PROGRAMS Continued (3) Ident1f1cat1on of process sampl1ng po1nts, which shall 1nclude monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (4) Procedures for the recording and management of data, (5) .Procedures def1ning corrective act1ons for all off-control point chem1stry conditions, and (6) A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrat1ve events required to init1ate corrective act1on.

d. Post-Accident Sam lin A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and conta1nment atmosphere samples under accident cond1tions, The program shall include the following:

(1) Training of personnel, (2) Procedures for sampling and analysis, and (3) Provisions for maintenance of sampling and analysis equipment.

e. Diesel Fuel Oil Testin Pro rara A diesel fuel oil test1ng program to implement required testing of both new fuel oil and stored fuel oil shall be establ1shed. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with appl1cable AS'tandards. The purpose of the program is to establish the following:

Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API Gravity or an absolute specific gravity. within limits,

2. a flash point and k1nemat1c v1scosity within limits for Grade No. 2-D fuel oil per AS'975, and

3. a clear and br1ght appearance w1th proper color;

b. Other properties for Grade No. 2-D fuel oil per AS'975 are within l1m1ts w1thin 30 days follow1ng sampl1ng and addit1on to storage tanks; and Total particulate concentrat1on of the fuel oil is < 10 mg/liter when tested every 31 days in accordance with either ASTI D-2276 or ASTM D-5452.

AHENDHENT NOS.l69 AND 163 TURKEY POINT UNITS 3 K 4

INSERT 1 This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

2. Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to ten times the 10 CFR 20, Appendix B, Table 2, Column 2 limits;

3. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 4, Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I;

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

6. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

7. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary to 500 mrem per year to the whole body, 3000 mrem per year to the skin and 1500 mrem per year to any organ from iodine 131, iodine 133 tritium and all radionuclides in particulate form with half live greater than 8 days.

8. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR 550, Appendix I;

9. Limitations on the annual and quarterly doses 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 unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

10. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

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

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made by the results of this census, and if required

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

'

AOMIHISTRATIVE COHTROLS ANNUAL RAOIOLOGICAL ENVIRONMENTAL OPERATING REPORT"

.9. 1.3 Routine Annual Radiological Environmental Operating Reports covering t operation of the unit during the previous calendar year shall be sub tted prior to May 1 of the following year.

The nnual Radiological Environmental Operating Reports shall include summaries, 'nterpretations, and an analysis of trends of the results of the radiological nvironmental surveillance activities for the report period, including a co rison with preoperational studies, with operational controls, as appropriate, a with previous environmental surveillance reports, and an assessment of the o erved impacts of the plant operation on the environment.

The reports shall als include the results of the Land Use Census required by Specification 3. 12. 2.

The Annual Radiological nvironmental Operating Reports shall include the results of analysis of all diological environmental samples and of all environmental radiation measureme s taken during the period pursuant to the locations specified in the table an figures in the OFFSITE 00SE CALCULATIOH MANUAL, as well as summarized and tab ated results of these analyses and measurements in the format of the table the Radiological Assessment Branch Technical Position, Revision 1, Hovember 1 9. In the event that some indivi-dual results are not available for inclusion ith the report, the report shall be submitted noting and explaining the.r sons for the missing results.

The missing data shall be submitted as soon as po ible in a supplementary report.

The reports shall also include the following: a s ary description of the Radiological Environmental Monitoring Program; at leas two legible maps*"

covering all sampling locations keyed to a table giving dist ces and direc-tions from the centerline of one reactor; the results of licen e participa-tion in the Interlaboratory Comparison Program and the corrective ction taken if the specified program is not being performed as required b Specifi-cation 3. 12.3; reasons for not conducting the Radiological Environmen 1 Moni-toring Program as required by specification 3. 12. 1, and discussion of a deviations from the sampling schedule of Table 3. 12"1; discussion of envir mental sample measurements that exceed the reporting levels of Table 3. 12-2 but are not the result of plant effluents, pursuant to ACTION b. of Specifi-cation 3. 12. 1; and discussion of all analyses in which the LLO required by Table 4. 12-1 was not achievable.

3aSev~ ~

"A single submittal may be made for a multiple unit station.

TURKEY POINT - UHITS 3 8c 4 6-17 AMEHOMEHT HOS.153 AHO 148,

INSERT 2 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the Offsite Dose Calculation Manual (ODCM), and in (2) 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the

-locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

ADHINI STRATI V CONTROLS ANNUA RAD OACTIV EFF UEHT R L ASE R PORT*

g. 1.4 An Annual Radioactive Effluent Release Report covering the operation o he unit during the 'previous 12 months of operation shall be submitted by Apri 1 of each year.

The nual

'

Radioactive Effluent Release Report shall include a summary of the quanti of radioactive liquid and gaseous effluents and solid waste released from he unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, an eporting Radioactivity in Solid Wastes and Releases of Radio-active Materials Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant " Revision 1, June 1974, with data summarized on a quar-terly basis following e format of Appendix 8 thereof. For solid wastes, the format for Table 3 in Ap ndix 8 shall be supplemented with three additional categories: class of soli wastes (as defined by 10 CFR Part 61), type of container (e.g., strong tigh ackage, Type A, Type 8) and SOLIDIFICATION agent or absorbent (e.g., cemen The Annual Radioactive Effluent elease Report to be submitted by April 1 of each year shall include an annual ary of hourly meteorological data collected over the previous year. This nual summary may be either in the form of an hour-by-hour listing on magneti tape of wind speed, wind direction, atmospheric stability, and precip ation (if measured), or, in the form of joint frequency distributions of wind eed, wind direction, and atmospheric stability.** This same report shall 'lude an assessment of the radiation doses due to the radioactive liquid a gaseous effluents released from the unit or station during the previous alendar year. This same report shall also include an assessment of the rad> tion doses from radioactive liquid and gaseous effluents to MEMBERS OF TH UBLIC due to their activities inside the SITE BOUNDARY (Figure 5. 1-1) during th report period.

All assumptions used in making these assessments, i.e., speci activity, exposure time, and location, shall be included in these reports. The meteoro-logical conditions concurrent with the time of release of radioacts e mate-rials in gaseous effluents, as determined by sampling frequency and m sure-ment, shall be used for determining the gaseous pathway doses, Approxi te and conservative methods may be used in lieu of actual meteorological mea-surements. The assessment of radiation doses shall be performed in accordan with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL OOCM 3qSe>+

A single submittal may be made for a multiple unit stations 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.

'ssion with the Annual Radioactive Effluent Release Report, the licensee as aining this summary of required meteorological data on site in a file that sha e NRC upon request.

TURKEY POINT - UNITS 3 8, 4 6-18 AMENDMENT NOS.157 ANO 151

0 C

INSERT 3 The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the ob)ectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

0, ADMINISTRATIVE CONTROLS NNUAL RADIOACTIVE FFLUENT RELEASE REPORT (Continued) e Annual Radioactive Effluent Release Report to be submitted by April 1 of eac ear shall also include an assessment of radiation doses to the likely most expo d MEMBER OF THE PUBLIC from reactor releases from the previous calendar yea and other nearby uranium fuel cycle sources, including doses from primary e luent pathways and direct radiation, for the previous calendar year to show con mance with 40 CFR Part 190, "Environmental Radiation Protection Standar for Nuclear Power Operation." Acceptable methods for calculating the dose tribution from liquid and gaseous effluents are given in Regulatory Guide 1. 10 Revision 1, October'1977.

The Annual Radioactive E luent Release Report shall include a list and description of, unplanned releas from the site to UNRESTRICTED AREAS of radioactive materials in gaseous a liquid effluents made during the report-ing period.

The Annual Radioactive Effluent Relea Report shall include any changes made during the reporting period to the PROC S CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pu ant to Specifications 6. 13 and 6. 14, respectively, as well as any major chan to Liquid, Gaseous, or Solid Radwaste Treatment Systems pursuant to Specif> tion 6. 15. It shall also include a listing of new locations for dose calcu tions and/or environmental monitoring identified by the Land Use Cens pursuant to Specification 3. 12.2.

I The Annual Radioactive Effluent Release Report shall also i lude the following: an explanation as to why the inoperability of liquid o aseous effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.3.5 or 3.3.3.6, respectively; and descri ion of the events leading to liquid holdup tanks or gas storage tanks exceedin the limits of Specification 3. 11. 1.4 or 3. 11 '.6.

MONTHLY OPERATING REPORTS 6.9. 1.5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the HRC, no later than the 15th of each month following the calendar month covered by the report.

PEAKING FACTOR LIMIT REPORT 6.9. 1.6 The W(Z) function(s) for Base-Load Operation corresponding to a -:2%

band about the target flux difference and/or a +3% band about the target flux difference, the Load-Follow function F,(Z) and the augmented surveillance turnon power fraction, P shall be provided to the U,S. Nuclear Regulatory Commission, whenever P, is <1.0. In the event, the option of Baseload Operation (as defined in Section 4.2.2.3) will not be exercised, the submission of the W(Z) function is not required. Should these values (i.e., W(Z), F,(Z) and P,) change requiring a new submittal or an amended submittal to the Peaking TURKEY POINT UNITS 3 8 4 6-19 AMEHOMEHT HOS. l 57AHO

AOMINISTRATIVE CONTROLS RECORO RETENTION (Continued)

Records and drawing changes reflecting unit 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; Records of radiation exposure for all individuals entering radia-tion control areas; Records of gaseous and liquid radioactive material released to the environs; Records of transient or operational cycles for those unit components identified in Table 5.7-1;

9. Records of reactor tests and experiments;

h. Records of training and qualification for current members of the fac i i ty staf f; 1

Records of inservice inspections performed pursuant to these Technical Specifications; Records of quality assurance activities required for the duration of the unit Operating License by the guality Assurance Manual; Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; Records of meetings of the PNSC and the CHRB;

m. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.6 including the date at which the service life commences and associated installation and maintenance records; Records of secondary water sampling and water quality; and

o. Annual Radiological Environmental Operating Reports and records of analyses transmitted to the licensee which are used to prepare the Annual Radiological Environmental Operating Report.

p Records for Environmental gualification which are covered under the provisions of 10 CFR 50. 49.

6. 11 RAO IATIOH PROTECTION PROGRAM Wil$ 8>

6. 11. 1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, TURKEY POINT - UNITS 3 8 4 6-21 AMEHOMEHT HOS 153 AHO 1M)

XNSERT 4 Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.

AQHIN STRAT V CONTROLS HIGH RAD AT ON AREA Continued For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mrem/hr and less than 500 rads/hr that are located within large areas, such as PWR containment; where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6. 13 PROCESS CONTROL PROGRAM PCP 6.1 The PCP shall be reviewed by the PNSC prior to implementation.

6.13.2 Lic ee-initiated changes to the PCP:

Shall be mitted to the Commission in the Annual Radioactive Effluent Rel e Report for the period in which the change(s) was DzS<<+ made. This subm al shall contain:

(1) Sufficiently detaile 'nformation to totally support the rationale for the change 'thout benefit of additional or supplemental information; (2) A determination that the change did t reduce the overall conformance of the solidified waste pro t to existing'riteria for solid wastes; and (3) Documentation of the fact that the change has been iewed and found acceptable by the PNSC.

b. Shall become effective upon review and acceptance by the PNSC.

6.14 OFFSITE DOSE CALCULATION MANUAL ODCH

14. 1 The ODCH shall be approved by the Commission prior to implementation.

6.14.2 see-initiated changes to the ODCH:

a. Shall be s 'tted to the Commission in the Annual Radioactive Effluent Release ort for the period in which the change(s) was ittal shall contain:

3h$ ert made effective. This (1) Sufficiently detailed informa ale for the change without benefit

'o totally support the ration-dditional or supplemental information. Information submitted shou nsist of a package of those pages of the ODCH to be changed with page numbered, dated and containing the revision number, together appropriate analyses or evaluations justifying the change TURKEY POINT - UNITS 3 & 4 6-23 AMENDMENT NOS.I 67AND I "-I

INSERT 5 The Process Control Program (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

Licensee-initiated changes to the PCP:

a ~ Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3q.

This documentation shall contain:

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

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

b. Shall become effective after review and acceptance by the PNSC and the approval of the Plant General Manager.

INSERT 6 The ODCM shall contain the following:

a ~ The methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program; and

b. The radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Annual Radioactive Effluent Release Reports required by Specification 6.9.1.3 and Specification 6.9 '.4.

Licensee initiated changes to the ODCM:

a ~ Shall be documented and records of reviews performed shall be retained as required by specification 6.10.3q.

This documentation shall contain:

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

2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after the review and acceptance by the PNSC and approval of the Plant General Manager; and c ~ Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

I ,l ADMINISTRAT V CONTRO S OFFSIT DOS CA CULATIOH MANUAL ODCM (Continued)

(2) A determination that the change will not reduce the accuracy or reliability of dose calculations or Setpoint determinations; and (3) Documentation of the fact that the change has been reviewed and found acceptable by the PHSC.

b. hall become effective upon review and acceptance by the PNSC.

6.15 MAJOR C HGES TO LI UID GASEOUS AND SOLID RADMASTE TREATMENT SYSTEMS*

6. 15. 1 Licensee initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, nd solid):

a. Shall be r orted to the Commission in the Annual Radioactive Effluent Rel ase Report for the period in which the evaluation was reviewed by t PNSC. The discussion of each change shall contain:

(1) A summary of he evaluation that led to the determination that the change cou d be made in accordance with 10 CFR 50.59; (2) Sufficient detail d information to totally support the reason for the change without enefit of additional or supplemental information; C (3) A detailed description the equipment, components, and processes involved and th interfaces with other plant systems; (4) An evaluation of the change, which shows the predicted releases of radioactive materials in l'quid and gaseous effluents and/or quantity of solid waste that d> fer from those previously pre-dicted in the License applicatio and amendments thereto; (5) An evaluation of the change, which ows the expected maximum exposures to a MEMBER OF THE PUBLIC i the UNRESTRICTED AREA and to the general population that differ om those previously estimated in the License application an amendments thereto; (6) A comparison of the predicted releases of dioactive materials, in liquid and gaseous effluents and in soli waste, to the actual releases for the period prior to when the cha e is to be made; (7) An estimate of the exposure to plant operating p rsonnel as a result of the change; and (8) Documentation of the fact that the change was revie d and found acceptable by the PHSC.

b. Shall become effective upon review and acceptance by the PHS

Licensees may choose to submit the information called for in this Specifica-tion as part of the annual FSAR update.

TURKEY POINT - UNITS 3 8 4 AMENDMENT HOS.157 AND 151

4 L-96-18 Page 1 of 3 ATTACHMENT 4 Deleted the method for apportioning liquids based on RCS activity.

When releases are made, the dose limit per reactor is applied to the common release point. This ensures that the dose limit is not exceeded for any single unit. (see par. 1 on page 2-2 of Rev. 6 of the ODCM)

2. Added the elevations of the vents to the Basis section of Objectives/System Description in section 3. The dispersion models were also verified to be correct as stated in the ODCM.

3. Changed wording to clearly state that the calculations are for Trip and Alarm setpoints. Added words that state the calculation is used to verify that a limit is not exceeded but due to the range of the monitors, lower setpoints are used in accordance with approved plant procedures. This has been emphasized in section 2 and 3 of the ODCM rev. 6.

4. See no. 3 above.

5. Redefined the term F, to read 'estimated', based on pump curves and expected condenser fouling.

6. FECb was redefined such that using data from a previous qtr. for beta emitting isotopes and actual sample data for gamma isotopes is the only acceptable method. The value of 0.5 for Eb was deleted.

7. This method was revised to allow the use of a gross beta-gamma analysis in lieu of an isotopic analysis. Labeling unidentified nuclides from gross counting techniques is not required. When gross counting methods are used, the activity concentration limit for the most restrictive isotope is used to calculate the effluent concentration.

8. Defined the term S, for liquids to be: 0,7 from the Liquid Rad Waste System, 0.1 from each unit's S/G blowdown System, and 0.1 from unmonitored pathways (storm drains). These values are assigned, not calculated.

9. See no. 3 above.

10. Accounting for gas effluents from steam dumps, blowdown flash tanks, and other unmonitored steam losses are not required unless a primary to secondary leak is occurring. During periods of primary to secondary leakage, the most accurate means available are used to determine the quantity of gaseous effluent released, and these methods are described in approved plant procedures. One method is described on page 3-5 in rev. 6 of the ODCM.

L-96-18 Page 2 of 3 The use of Noble Gas release fractions has been deleted.

12. Equation for noble gas setpoints, based on concentration, was deleted in Rev. 5.

13. See no. 10 above.

14. Added to the basis that the REMP program verifies that ocean pathways are not significant.

15. Added a description to Sec. 4 to use TLD measurements from the REMP program for the total dose calculation.

Reworded this to read : "The operability of the LRW System is verified by meeting Control 2.2 and 2.3." The basis now includes information on how we meet this. By virtue of meeting these Controls, the Radwaste system is fulfilling its intended function.

2. Added to control 1.3 that the methods used for calculations for the annual report are indicated in each method. When alternate methods are indicated, their use is controlled by approved plant procedures, and is stated in each method when their use is normally practiced.

3. Defined the term S, for noble gases to be: 0.6 from the Plant Vent, 0.1 from each unit's SJAE Vent, O.l from the unit 3 Spent Fuel Vent, and 0.1 from unmonitored pathways. These values are assigned, not calculated.

4, This was addressed in Category A no. 6, and B no. 2.

5. This was addressed in Category A no. 2.

6. This was deleted; only historical (or reference) Met. data is used. Reference Met. data is periodically verified to ensure it' validity.

7. Clarified this statement and added the basis for this methodology to the basis section. Iodine and particulates are not considered in batch releases but are measured and accounted for as continuous releases to prevent over accounting for these releases.

8. The basis for the pathway dose transfer factors in appendix A are still being investigated. These tables were derived in the early 1970's and the basis for these are not readily available. Corporate H.P./Chemistry is working on deriving a basis and validating the current tables or deriving new tables with a validated basis. This action is planned to be complete by 1/1/98.

9. The effective dose transfer factors in Appendix. B have been evaluated using data from 1992, 1993, and 1994. Only minor changes

L-96-18 Page 3 of 3 were noted between these values and the values currently in the ODCM. The canal-groundwater transfer is not relevant to airborne releases. 'Scaling factors're not used to calculate effective dose transfer factors, however the use of effective dose transfer factors are clearly defined and stated in their applicable methods.

The method for calculating these factors is contained in Appendix 3C of rev. 6 of the ODCM (appendix. B of rev.4).

10. The primary method for performing dose projections is to use the previous months calculated dose, with an alternate method used only when a more accurate projection is necessary and sufficient data is available.

The validity of these values are periodically checked against actual Met. conditions for the previous few years. This was added to the Basis section for these values. The derivation of this factor is not included in this manual since this factor is not routinely calculated and the value is periodically verified.

12. See no. 11 above.

13. This diagram was corrected.

14. This is included in Rev. 6. Rev. 4 did not contain was included in the Technical Specifications.

this since it This was added to the system description.

2. See Category A no. 10 and 11.

3. See Category A no. 15. A mathematical expression is not needed to add the dose from direct radiation with the dose from effluent releases.

in Rev. 6. Rev. 4 did not include this since 4 ~

it wasis contained This included in the Technical Specifications.

5.

it wasis contained This included in Rev. 6. Rev. 4 did not include this since in the Technical Specifications.

This reference will be updated when the review of the Appendix. A bases are complete.

L-96-18 Page 1 of 3 ATTACHMENT 4 Deleted the method for apportioning liquids based on RCS activity.

When releases are made, the dose limit per reactor is applied to the common release point. This ensures that the dose limit is not exceeded for any single unit. (see par. 1 on page 2-2 of Rev. 6 of the ODCM)

2. Added the elevations of the vents to the Basi.s section of Objectives/System Description in section 3. The dispersion models were also verified to be correct as stated in the ODCM.

3. Changed wording to clearly state that the calculations are for Trip and Alarm setpoints. Added words that state the calculation is used to verify that a limit is not exceeded but due to the range of the monitors, lower setpoints are used in accordance with approved plant procedures. This has been emphasized in section 2 and 3 of the ODCM rev. 6.

4, See no. 3 above.

5. Redefined the term F2 to read 'estimated', based on pump curves and expected condenser fouling.

6. FECb was redefined such that using data from a previous qtr. for beta emitting isotopes and actual sample data for gamma isotopes is the only acceptable method. The value of 0.5 for Eb was deleted.

7. This method was revised to allow the use of a gross beta-gamma analysis in lieu of an isotopic analysis. Labeling unidentified nuclides from gross counting techniques is not required. When gross counting methods are used, the activity concentration limit for the most restrictive isotope is used to calculate the effluent concentration.

8. Defined the term S, for liquids to be: 0.7 from the Liquid Rad Waste System, 0.1 from each unit's S/G blowdown System, and 0.1 from unmonitored pathways (storm drains) . These values are assigned, not calculated.

9. See no. 3 above.

10. Accounting for gas effluents from steam dumps, blowdown flash tanks, and other unmonitored steam losses are not required unless a primary to secondary leak is occurring. During periods of primary to secondary leakage, the most accurate means available are used to determine the quantity of gaseous effluent released, and these methods are described in approved plant procedures. One method is described on page 3-5 in rev. 6 of the ODCM.

L-96-18 Page 2 of 3 The use of Noble Gas release fractions has been deleted.

12. Equation for noble gas setpoints, based on concentration, was deleted in Rev. 5.

13. See no. 10 above.

14. Added to the basis that the REMP program verifies that ocean pathways are not significant.

15. Added a description to Sec. 4 to use TLD measurements from the REMP program for the total dose calculation.

Reworde this to read : "The operability of the LRW System is verified by meeting Control 2.2 and 2.3." The basis now includes information on how we meet this. By virtue of meeting these Controls, the Radwaste system is fulfilling its intended function.

2. Added to control 1.3 that the methods used for calculations for the annual report are indicated in each method. When alternate methods are indicated, their use is controlled by approved plant procedures, and is stated in each method when their use is normally practiced.

3. Defined the term S, for noble gases to be: 0.6 from the Plant Vent, 0.1 from each unit's SJAE Vent, 0.1 from the unit 3 Spent Fuel Vent, and 0.1 from unmonitored pathways. These values are assigned, not calculated.

4. This was addressed in Category A no. 6, and B no. 2.

5. This was addressed in Category A no. 2.

6. This was deleted; only historical (or reference) Met. data is used. Reference Met. data is periodically verified to ensure it' validity.

7. Clarified this statement and added the basis for this methodology to the basis section. Iodine and particulates are not considered in batch releases but are measured and accounted for as continuous releases to prevent over accounting for these releases.

8. The basis for the pathway dose transfer factors in appendix A are still being investigated. These tables were derived in the early 1970's and the basis for these are not readily available. Corporate H.P./Chemistry is working on deriving a basis and validating the current tables or deriving new tables with a validated basis. This action is planned to be complete by 1/1/98.

9. The effective dose transfer factors in Appendix. B have been evaluated using data from 1992, 1993, and 1994. Only minor changes

L-96-18 Page 3 of 3 were noted between these values and the values currently in the ODCM. The canal-groundwater transfer is not relevant to airborne releases. 'Scaling factors're not used to calculate effective dose transfer factors, however the use of effective dose transfer factors are clearly defined and stated in their applicable methods.

The method for calculating these factors is contained in Appendix 3C of rev. 6 of the ODCM (appendix. B of rev.4).

10. The primary method for performing dose projections is to use the previous months calculated dose, with an alternate method used only when a more accurate projection is necessary and sufficient data is available.

11. The validity of these values are periodically checked against actual Met. conditions for the previous few years. This was added to the Basis section for these values. The derivation of this factor is not included in this manual since this factor is not routinely calculated and the value is periodically verified.

12. See no. 11 above.

13. This diagram was corrected.

1 4. This is included in Rev. 6. Rev. 4 did not contain was included in the Technical Specifications.

this since it This was added to the system description.

2. See Category A no. 10 and 11.

3. See Category A no. 15. A mathematical expression is not needed to add the dose from direct radiation with the dose from effluent releases.

4 This is included in Rev. 6. Rev. 4 did not include this since

~

it was contained in the Technical Specifications.

in Rev. 6. Rev. 4 did not include this since 5.

it wasis contained This included in the Technical Specifications.

1. This reference will be updated when the review of the Appendix. A bases are complete.

ENCLOSURE 1

ML17353A617

Text

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