Text

Proposed Ts,Relocating Radiological Effluent TS from TS to Chapter 16 of FSAR
	ML20097G155
Person / Time
Site:	Catawba
Issue date:	06/08/1992
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20097G154	List: ML20097G150; ML20097G155;
References
	NUDOCS 9206160325
	Download: ML20097G155 (155)
	v • d • e

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ATTACHMENT 1 ,

PROPOSED CATAWBA TECHNICAL SPECIFICATIONS CHANGES -

I 9206160325 920600 PDR ADOCK 05000413 P PDR

i DEFINITIONS e SECTION PAGE-

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- 1.33 m 4vaiawn.4vn............................................... 1-5 1.34 SOURCE CHECK................................................. 6-1.35 STAGGERED TEST BASIS......................................... 1-6 1.36 THERMAL P0WER................................................ 6 1.37 TRIP ACTUATING DEVICE OPERATIONAL TEST....................... 6 1,38 UNIDENTIFIED LEAKAGE......................................... 1 1. '9 UNRESTRICTED AREA............................................ 1-6 1.40 VENTILATION-EXHAUST TREATMENT SYSTEM......................... 1-6 1,41 VENTING...................................................... 1-7 ,

1.42 WASTE GAS HOLDUP SYSTEM...................................... 1-7 TABLE 1.1 FREQUENCY N0TATION......'................................ 1-8 TABLE 1.2 OPERATIONAL M0 DES....................................... 1 e

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CATAWBA - UNITS 1 & 2 II Amendment No. (Unit $ 1).

Amendment No. (Unit 2)-

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r LIMITING C0h0lTIONS FOR OPERATION AND-SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION. . . . . . . . . . . . . - 3/4 3-60 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS,......................................... 3/4 3-61 -

Remote Shutdown System................................... 3/4 3-62 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING-INSTRUMENTATION............_ 3/4_3-63 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................. 3/4 3-64 Accident Monitoring Instrumentation......................, 3/4 3-65.

TABLE 3.3-10 ACCIDENT-MONITORING INSTRUMENTATION.................. 3/4 3 TABLE 4. 3 - ACCIDENT: MONITORING INSTRUMENTATION SURVEILLANCE - -

REQUIREMENTS................ ............................. 3/4 3-68 Chlorine Detection Systems................ ....._,........ -3/4 3 TABLE 3.3-11 -(Deleted)

Loose-Part Detection-System.........-..................... 3/4 3-79 9: die::tive Liquid Ef f h:nt " ritering In:trd=nt:tica. . . 3 /4 _ 3-60--

-TA8t! 3.3-12 MDIO^.CTIVE -LIQUIC EFFLUENT "^HP.Of,INC INST"UMENTATION 3/4 3 01 mo., ,& ,.n , m ....- ,,-,,,- ---...~.,.. ....--.m.

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Instrumentation..

INSTRUMENTA ION...... -

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3/4 3- W -

H TABLE 4. 3-+ grt.or. 10A . IVC GASww.w. musn. n0NITORING g3 INSTRUMENTATION SURVEILLANCE-REQUIREMENTS................- 3/413 Boron Diluti_on Mitigation. System. ....................... 3/4:3-4N-3/4.3.4 TURBINE OVERSPEED PROTECTION..........................-.... 3/4.3 8 3/4.4 REACTOR COOLANT SYSTEM-3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION- _

Startup and Power Operation.....'......... ................. 3/4 4 Hot Standby................._............................. 3/4L 4 c -!

Hot Shutdown............................................... ~

3/4 4-3 Col d Shutdown - Loops Fi11 ed. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-5 Cold Shutdown '- Loops Not Filled. . . . . . . . . . . . . .-. . . . . . . . . . . 3/4 4-_ 6_. _

~0ATAWBA - UNITS 1 & 2- VI~ Amendment No. --(Unit 1)

Amendment No; (Unit 2)

l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level......................................... 3/4 9-10 Low Water Level.......................................... 3/4 9-11 3/4.9.9 WAT ER LEVE L - RE ACTOR VE55 E L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-12 3/4.9.10 WATER LEVEL - STORAGE POOL ............................. 3/4 9-13 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM. . . . . . . . . . . . . . . . . 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUT 00WN MARGIN.,.................. ..................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS... 3/4 10-2 3/4.10.3 PHYSICS TEST 5............................................ 3/4 10-3 3/a.10.4 R EACTO R COO LANT LOO P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN... . . ..... ........ 3/4 10-5 3/4.11 RADICACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3:"ce-t at i :- . .... . 3/' 11-1

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-4 Lauid Reawitt: 're:tment 3y::::... 3/4 11 -

Liquid Holdup Tanks...................................... 3/4 11-9I

-Ghemic:1 'r::t :nt P nds. .'. . . .. .. ..... . 3/4'12 .

3/4.11.2 GASEQUS EFFLUENTS wwas .mww.. . . .. . , . ..... . . ........., ./ ' .. J

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- Mate rial # - ":rticul:t: ca r, . .. , 3/2 11 12

--G442 u: *2de::t 7 eatment 3yttom . 3 " 11-15 Explosive Gas Mixture..., ............,................ . 3/4 11-'; d' .

Gas Storage Tanks................. ........ ... ..... . . 3/4 11-tFE CATAWBA - UNITS 1 & 2 XI

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LIMITING COND TJ0NS FOR OPEPATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE-5 3/4.11.3 SOLID RADI0ACTI WASTES............-... .... ............

3/4: 11-1B. >

3/4.11.4 TOTAL 00SE........... ................... ............... 3/4 11-19.

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l 3/4.12 RA0!0 LOGICAL ENVIRONMENTAL MO TORIN N

3/4.12.1 MONITORING PROGRAM ........... .., ..............,....... 3/4-12-1 TABLE 3.12-1 RADIOLOGICAL ENVIRONMEN L MONIT NG PROGRAM........ 3/4 12-3 l TABLE 3.12-2 REPORTING LEVELS F0 ADI0 ACTIVITY C "ENTRATIONS

. IN ENVIRONMENTAL SAMP .......... ......... ........... 3/4 12-9 4

TABLE 4.12-1 DETECTION CAPA ITIES FOR ENVIRONMENTAL SA E l ANAL.YSIS........ ..... ............................ ..... 3/4 12-10 l 3/4.12.2 LAND USE CENS ......................................., . 3/4 12 3/4.12.3 INTERLABO ORY COMPARISON PROGRAM,... ,....... ..._... ,, 3/4 12-15 l

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BASES SECTION PAGE 3/4.0 APPLICABIL E ............................................... B 3/4 0-1 -

3/4.1 REACTIVITY CONTROL SYSTEMS l 3/4.1.1 80 RATION CONTR0L.......................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS..................... .................... B"3'/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.......... ..................... B 3/4 1-3 i

, 3/4.2 POWER DISTRIBUTION LIMITS (Unit 1).............., .. ....... B 3/4 2-1 2

3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 1).... ...................... B 3/4 2-1 i 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Unit 1)................. B 3/4 2-1

, 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 1)........................ B 3/4 2-3 3/4.2.5 DNB PARAMETERS (Unit 1)................................... B 3/4 2-3 3/4.2 POWER DISTRIBUTION LIMITS (UNIT 2)........................ B 3/4 2-5 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 2)............................ B 3/4 2-5 3/4.2.2 and 3/4.2.3 HEAT. FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NOCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Unit 2).......................... B 3/4 2-7

-3/4,2.4 QUADRANT POWER TILT RATIO (Unit 2)........................ B 3/4 2-9 3/4.2.5 DNB PARAMETERS (Unit 2)................................... B 3/4 2-10 3/4.3 INSTRUMENTATION

- 3/4.3,7. and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY-FEATURES ACTUATION SYSTEM INSTRUMENTATION............... - B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4-3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION.............................. B 3/4 3-7 Xil CATAWBA - UNITS 1 & 2 -XII!o Amendment No. -(Unit 1)

Amendment No. (Unit 2)

BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4,1 REACTOR CCOLMT LOOPS AND COOLANT CIRCULATION, . . . . . . . . . . . . B 3/4 4-1 3/4.4.2 SAFETY VALVES................ ............................ B 3/4 4-1 3/4.4.3 PRESSURIZER............................................... B"3'/4 4-2 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-2 3/4.4.5 STEAM GENERATORS.......................................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 3/4.4.7 CHEMISTRY................................................. B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY......................................... B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-7 i

CATAWBA - UNITS 1 & 2- XIII Amendment No. (Unit 1) l Amendment No. - (Unit 2)

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.. BASES ;

SECTION -PAGE i

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' 3/4.8 ELECTRICAL POWER SYSTEMS "

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! 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, i ONSITE POWER DISTRIBUTION ................................- B 3/4 8-1 l 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.............. 4 ... B 3/4 8-3 1

d l 3/4.9 REFUELING OPERATIONS .

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} 3/4.9.1 BORON CONCENTRATION....................................... B 3/4 9 ! 3/4.9.2 INSTRUMENTATION........................................... B 3/4 9-1

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l 3/4.9.3 IDECAY TIME..-.............................................. B 3/4 9-1 j 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................... B 3/4 9-1 3/4.9.5 -COMMUNICATIONS............................................ B 3/4 9-2

! 3/4.9.6 MAN I P U LATO R C RAN E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4-9 ! 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE: POOL _ BUILDING. . . . . . . . . . .

B 3/4 9-2

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s 3/4.9.8. RESIDUAL HEAT REMOVAL- AND COOLANT CIRCULATION. . . . . . . . . . . . . B 3/4.9-2 i 3/4.9.9 and 3/4.9.10 WATER LEVEL - . REACTOR VESSEL and . -

STO RAG E P 00 L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4'9 l- 3/4'.9.11 FUEL-HANC.ING VENTILATION EXPAUST SYSTEM..................- B'3/4 9-3

! 3/4.10. SPECIAL TEST EXCEPTIONS 4 . - -- .

i' 3/4.10.1-SHUTDOWN MARGIN........................................... B 3/4-10-1 l-j 3/4.10.2 GROUP: HEIGHT, INSERTION -AND POWER OISTRIBUTION LIMITS..... B 3/4~10-1 2 3/4.10.3 PHYSICS _ TESTS............................................. ' B : 3/4 1~

I 3/4.10. 4 REACIO R COO LANT: L00 P S. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 5

l 3/A.10.5 POSITION. INDICATION SYSTEM - SHUTD0WN..................... B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTSL I' . .

3/4.11.1~ LIQUID EFFLUENTS........................... ........... ..._ B'3/4111-1 .-

- 3/4.11.2 GASEOUS EFFLUENTS........................................ BJ3/411-+

3/4.11.3 SOLIC RA010 ACTIVE WASTES.......................... ...... 3 3,4 11 0

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J/ 9. a4. 9 4WIML UUGL.......-................................... .... J - Ji 7 +4 a b

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_ CATAWBA - UNITS 1 & 2 XV j-(.

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BASES 1 I SECTION PAGE 3/4.12 RADIOLOGICAL ENVIRO.4 ENTAL MONITORING 3/4.12.1 MONITORING PROGRAM. ...................... ............. B 3/4 12-1 3/4.12.2 LAND USE CENSUS..... ................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPA ISON PROGRAM..... ................ B 3/4 17.-2 CATAWBA UNITS 1 & 2 XVI

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OESIGN FEATURES SECTION PAGE 5.1 SITE -

5.1.1 EXCLUSION AREA.............................................. 5-1 5.1. 2 LOW POPULATION 20NE......................................... 5-1 5.1. 3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS.................... 5-1 FIGURE 5.1-1 EXCLUSION AREA....................................... 5-2 FIGURE 5.1-2 LOW POPULATION Z0NE.................................. 5-3 FIGURE 5.1-3 UNRESTRICTED-AREA AND SITE B0UNDARY FOR RADI0 ACTIVE LIQUID EFFLUENTS................................ 5-4 FIGURE 5.1-4 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIDACTIVE GASEOUS EFFLUENTS............................... 5-5 R CONTAINMENT ;

5.2.1 CONFIGURATION............................................... 5-1

5. 2. 2 DESIGN PRESSURE AND TEMPERATURE-............................ 5-6 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES............................................. 5-6 5.3.2 CONTROL R00 ASSEMBLIES......................................- 5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE............................. 5-6 5.4.2 V0LUME....................................................$. 5-6 5.S METEOROLOGICAL TOWER LOCATION................................. 5-6 5.6 FUEL STORAGE 5.6.1 CRITICALITY.................:............................... 5-7 5.6.2 DRAINAGE.................................................... 5-7 5.6.3 CAPACITY..................................................... 5-7

~.7 5 COMPONENT CYCLIC OR TRANSIENT LIMIT........................... 5-7 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. 5-8 4

CATAWBA - UNITS 1 & 2 XVI

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ADMINISTRATIVE CONTROLS i t

i SECTION- PAGE-i 6-1 l 6.1 RESPONSIBILITY..............................................

6. 2 ORGANIZATION................................................ 6-1 ;

. 6.2.1 0FFSITE and ONSITE ORGANIZATIONS.......................... 1 l

6.2.2 UNIT STAFF.....................'........................... 6-1 i FIGURE 6.2-1 0ELETED............................................ 6 i -

't FIGURE 6.2-2 0ELETED............................................ 6-4 l

i TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION......................- . .

6-5 ,

6.2.3 CATAWBA SAFETY REVIEW GR00P...............................- 6-6'.

I F unc ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 6-6L r

i Composition............................................... 6 !

i Responsibilities.......................................... 6

! Records................................................... -- 6-6:

I 6.2.4 SHIFT TECHNICAL ADVIS0R.................................... 6-6 6.3 UNIT STAFF QUALIFICATIONS................................... 6-6

! 6.4 TRAINING.................................................... 6-6 i

6.5 REVIEW AND AUDIT............................................ 6 o i

6. 5.1 TECHNICAL REVIEW AND CONTROL- ACTIVITIES. . . . . . . . . . . . . . . . . . .. 7

! 6.5.2' NUCLEAR SAFETY REVIEW BOARD-(NSR8)........................ 8 l Function................................................... ' 6-8' I Organization..............................................- 6 Review..................................................... 6-10 i Audits....................................................- 6-10 i- Records........................,...........,.............. 6-11--

b 6.6 REPORTABLE EVENT-ACTION............. .......................- . 12~. -

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[ 6.7 SAFETY LIMIT VIOLATION...................................... 6-12 6.8- PROCEDURES AND PR0 GRAMS..................................... .

6-13

, 6.9 REPORTING REQUIREMENTS......................................

6-15 6.9.1 ROUTINE REP 0RTS........................................... 15- __

Startup Report............................................ ,

6-15 1

i i i XVII . Amendment No.

CATAWBA -UNITS-1 & 2 - - -(Unit 1)

. Amendment No.- (Unit 2)L r y c- - - - ~ , , . + ,, - , . , , ,.-.,-.,w m,-

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} ADMINISTRATIVE-CONTROLS 4 :. ,

j SECTION PAGE r

Annual Reports...............................,............ 6-16.

j- Annual Radiological Environmental Operating. Report........ 6 ,

Semiannual Radioactive Effluent Release Report...... ..... 6-17 l Monthly Operating Reports................................. 6-19-II Core Operating Limits Report......................,....... _

6-19-IF l 6.9.2 SPECIAL REP 0RTS........................................... 6 l_ 6.10 RFCORD RETENTION....................................'.......-

6-201 i

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6.11 RADIATION PROTECTION PR0 GRAM............................... 6-21 6.12 HIGH RADIATION AREA...................................... . . 6-21

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6.13 PROCESS CONTROL PROGRAM (PCP)......................_......_... 6-22 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)..................... 6-23 i

l 6.15 MAJOR CHANGES TO LIQUID,-GASEOUS, AND SOLID RADWASTE TREATHENT SYSTEMS.......................................... 6-23

? 6.IL SMOO lh ll (/LADIOLMICAt EFFFwbWcoWTutsh j oF THg Pfort,,,,,,,,,,,_,,,,, ,,,,,,',,,, g, _ a tf,

! 7.0 SPECIAL TEST PR) GRAM........................................ 7-1 i

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M ill CATAWBA - UNITS 1 & 2 . X rn Amendment No. (Unit 1)

. Amendment No. (Unit 2).

l T he RnNocd$C' CHlacrd'Co&Ok astl f5('O'f60dl RacU&<d 4f YC indenwbbnEnvsronmchl -TkcYt ,th ov(k bMonduks m

Ntclvke infr (Ph/tbk/S'erIlon (+ . 8 '{ n nk pt A.muaj ac&iopenf 64ronwel citedk5 and Sede -anove I fdtuMc- EN(ve.&

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DEFINITIONS Chrff.viref e / (. c 4 b&SpecrfdcchhnJ N<d S</cb Arv 6. 't. l./Pe fyii.r 6 a/oc0 r-hL (f. f. 7 s MI .k ( *nMinel ) in ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time l interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance l Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be: l

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 opera-tion 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.

MASTER RELAY TEST 1.16 A MASTER RELAY TEST shall be the energization of each master relay and l verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER (S) 0F THE PUBLIC f 1.17 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa- { l tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded-from this category are persons who enter the site to service equipment or to make deliveries.

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

OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology l and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program, c --

CATAWBA - UNITS 1 & 2 1-3 Amendment No. (Unit 1)

Amendment No. (Unit 2) '

DEFINITIONS RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate to l the reactor coolant of 3411 MWt.

REACTOR BUILDING INTEGRITY 1.27 REACTOR BUILDING INTEGRITY shall exist when: I

a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed,

b. The Annulus Ventilation System is OPERABLE, and

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

REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from I when the monitored parameter exceeds-its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in l Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which l the reactor is suberitical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither l owned, nor leased, nor otherwise controlled by licensee.

SLAVE RELAV TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and' l verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

DElsT2?D SOLIDIPICATICN 1.33 SOLIDIFICf.T!0N shall be th ccaversica cf =t =stes inte a form that meetr- l

-shipping and burial ground requirements.

CATAWBA - UNITS 1 & 2 1-5 Amendment No. (Unit 1)

Amendment No. (Unit 2)

I INSTRUNENTATIO MI.0ACTIVELIQU EFFLUENT MONITORING INSTRUMENTATION LIMITINGCONDITION\0ROPERATION s ,

3.3.3.10 The radioact ve liquid effluent monitoring instrumenta ton channels shown in Table 3.3-12 s 11 be OPERABLE with their Alarm / Trip S tpoints set to ensure that the limits o Spectfication 3.11.1.1 are not exces ed. The Alarm /

Trip Setpoints of these c nnels shall be determined and adju ted in-accordance with the methodology and p ameters in the OFFSITE DOSE CALC LATION MANUAL (ODCH).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liqu effluent monitori g instrumentation channel Alarm / Trip setpoint less onservative thai required by the above specification, immediately suspend the-re ease of radioactive-liquid-effluents monitored by the ffected cha el,'or declare the channel inoperable. ,

b. With less than the minimum nu er of adioactive liquid affluent monitoring instrumentation cha els PERABLE, take the ACTION shown ,

in. Table 3.3-12. Restore the i p able instrumentation to OPERABLE status within the time specified the ACTION or explain in the next Semiannual Radioactive Effluent ease Report pursuant to L;ecifica-tion 6.9.1.7 why this inoperabi t was not corrected within the time specified,

c. The provisions of Specificat on 3.0.3 re not appl b ble.

SURVEILLANCE REQUIREMENTS ,

i 1 4.3.3.10 Each rad!sactive liqu effluent-monitoring strumentation channel shall be oemonstrated OPEP.ABLE y performance of the CH NEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, a ANALOG CHANNEL OPERATION TEST operations at the frequencies shown in Tab e 4.3 8.

RELOCATEP 70-r-tut cMtWR. IG

}

CATAWBA - UN S1&2 3/4 3-80 ' Amendment No. 48 (U it 1)

-Amendment No. 41-(Un t 2);

____ _ _ _ _ ._ _ _-_. .. . . _ . .. . . _ - ~ - _. . - ... -. _ _ . _ .. . _ _ _ .- - - -

TABLE 3.3-12 g

g RADI0 ACTIVE LIQUID EFFLUEN'T MDMITORING INSTRUMENTATION

. MINIMUM CHANNELS E OPERABL' ACiION INSTRtMENT

~

N

1. Ra ' clivity Monitors Providing Alarm and Aut ic Termination of Release

a. Waste Liqu ischarge Monitor (Low Range - EMF-49) 1 pe tation 40

b. Turbine Building S Monitor (Low Range - EMF-31) 1 42

c. Steam Generator Water Samp '

tor Gow Range - EMF-3 1 43 s

' d. Monitor Tank Building Liquisi Discha Monitor -57) I per station 40 Y

$ 2. Continuous Composite Samplers and Sampler F Mo ' or

a. -Conventional Waste Water Tre nt Line 1 per station 42

b. Turbine Building Sump 1 per station 42*

' 3. Flow Rate Measurement vices

.3 % a. Waste L# d Effluent Line 1 per ation 41 EE b.

g% h 22 nventional Waste Water Treatment Line > M 1 per station 41 55 .

? $

22 c. Low Pressure Service Water Minimus Flow Interlock I per station

?* .

41 O

em d.- Monitor Tank Building Waste Liquid Effluent-Line om 9 %4 1 per station 41 22 e.- Turbine Building Sump Demineralizer Skid Totalizer 1 per station 41* l

.hh h- h

_vv _

}

TABLE 3.3-12 (Continued)

TABLE NOTATIONS "During us of demineralizer (EMF 31 in off norma mode) ,

ACTION STATEMENTS ACTION 40 - With the num er of channels OPERABLE less tha required by the Minimum Chann 15 OPERABLE requirement, efflue t releases via this pathway may c itinue for up to 14 days provi ed that prior to initiating a rt ease:

a. At least tw independent samples are nalyzed in accordance with Specif ation 4.11.1.1.1, and

b. At least two echnically qualified aembers of tht facility staff indepen ntly verify:

gggp 7t 1. The dischar > line valving, nd

2. The manual po tion of the c mputer input for the release

%/)(1 ch(AfTFN. /b rate calculati ns performe on the computer, or the entire release rate ca culations if such calculations a -

performed manual y, Otherwise, suspen rele se of radioactive ef fit. 4 via this pathway.

ACTION 41 With the number of channels RABLE less than required by the Minimum Channels OPERABLE re frement, effluent releases via th u pathway may continue for up o 30 days provided the flow rate is estimated at least once per 4 h urs during actual releases. Pump performance curves generat d in lace may be used to estimate flow.

ACTION 42 - With the number of ch6nne s OPERA LE-less than required by the Minimum Channels OPERABL requirem nt, effluent releases via this pathway may contin' e for up to 30 days prodded grab samples are analyzed for radio tivity at a ower limit of detection of no more than 10 7 microC te/ml:

a. At least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the specific activity of the secondary coolan is greater than 0. 1 microcurie / gram DOSE EQUIVALENT I-13 , or

b. At least once er 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months wbtn the sp cific activity of the secondary coo ant is less than or equal to 0.01 microcurie / gram DOSE EQUIVAL 4T I-131.

ACTION 43 - With the numbe of channels OPERABLE less th required by the Minimum Chann s OPERABLE requirement, gaseou effluent releases via the atmo heric vent valves (off-normal mo e) may continue pro-vided grab amples of steam generator water are analyzed for radio-activity f up to 30 days at a lower limit of tection of rio more than 10 7 icrocurie/ml:

a. At le t once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whon the specific ac ivity of the seco ary coolant is greater than 0.01 microcuri / gram DOSE EQUI ALENT I-131, or

b. At east once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific at.tiv 'ty of the st ondary coolant is less than or equal to 0.01 mic oCurie/ gram 0 SE EQUIVALENT I-131, CATAWBA - UNI 1&2 3/4 3-E2 Amendment No.66 (Unit 1)

Amendment No.60 Unit 2)

TABLE 4.3-8 S-Y RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRtMENTATION SURVEILLANCE REQUIREMENTS IE

ANALOG CHANNEL E-CHANNEL SOURCE CHANNEL OPFRATIONAL INSTRLMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing are and Automatic Termination

"- of ease'

a. Waste Li *d Disc'narge Monitor (Low Range - 0 P R(2) 1)

EMF-49)

b. Turbine Building S nitor (Low Range - 0 M R7 Q(1)

EMF-31).

w c. . Steam Generator Water Sample Mo ~ or D M R(2', Q(1)

K '(Low Range . EMF-34)

Y d. Monito:- Tank Building Liquid Discharge D P R(2) Q(1)

$ Monitor (EMF-57)

2. Continuous Composite Samplers and Sampler Flow Monitor

a. Conventional Waste _ Water Trea ine D(3) N. . R N.A.

b.- Turbine Building Sump DC) N.A. R N.A.

p.

$@ 3. Flow 71te Measuremen vices 0

- @ E- . -

S

$$ a. Waste ~ uid Effluent Line D(3) O ' -i N.A. R .A.

.e e 22 b. nventional Waste Water Treatment _Line D(3) x%

.b Ch N.A. R N.A.

-~oo

c. -Low Pressure Service Water Minimum Flow D(3) g N.A. R Q SE Interlock d c2- d.' [MonitorTankBuildingWasteLiquidEffluent D(3) .

M.A. R Q

3. 3. Line- -

r ,+ D

.me e. Turbine Building Sump - D(3) N.A. R N.A.

'Demineralizer Skid Totalizer

l.

(-

4 l j TABLE 4.3 8 (Continued) l TABLE NOTATIONS 1

j (1) The ANALOG CHANN L OPERATIONAL TEST shall also demonstr te that automatic

isolation of this athway and control room alarm annun lation* occur if (

) any of the followi g conditions exist:

)

i i a. Instrument indi ates measured levels above the larm/ Trip Setpoint, i

{ or l l b. Circuit failure ( arm only), or

c. Instrument indicate a downscale failure ( arm only).

! l 1

(2) The initial CHANNNEL CALIB TION shall be perf rmed using one or more of '

l the reference standards cer ified by the Nati nal Bureau of Standards (NBS) i or using standards that have een obtained f om suppliers that participate '

1 in measurement assurance acti ities with NB . These standards shall permit calibrating the system ver its int ded range of energy and.

j measurement range. For subsequ nt CHANNE CALIBRATION, sources that have ,

j been related to the initial cali ration s all be used.

' (3) CHANNEL CHECK shall consist of ver fyin indication of flow during periods of release. CHANNEL CHECK shall be ma 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, batch releases are made, i

T i

l '

l i

I j -.

i /2nochTF9 79 l.

TTM ctWTOL IV -

I -

i f

i i

4 e

"For EMF-57, the a rm annunciation is in the Monitor Tank Building Control Room and on the HTB C trol Panel Remote Annunciator panel, i CATAWBA - UNITS &2 3/4.3-84

'. . Amendment No. 65. Unit 1)

Amendment No.'59.( nit 2)

(

p r, , ..-u.e- n 9 r -. + - = - y w yme- 1 '=r*"-"'*>'t**'*e * = - *

w '

-'e "-- * ' * * " * ' -

.- . - . - . - _ = - . . _ - - - . _ . - . . -

d

~

1 INSTRUMENTATION i

i Et.PLoS WG

ninenu v,ur GA!!^"! EF"'""?" MONITORING INSTRUMENTATION

, LIMITING CONDITION FOR OPERATION l

80 en ks'n 1 3.3. 3.H- The +444444444. gase+w-+"!uent- monitoring instrumentation channels j shown in Table 3.3-13;. phall be OPERABLE with their Alarm / Trip Setpoints set to i ensure that the limitTof Specificatior.: 3.11.2.1 :nd 3.11.2.5 are not exceeded.

The Ah-/T-!p hip: int: Of th::: :h:rn:1: ::: ting ;;;;ificati;n 3.11.08 en.1; .

{dggin;d;nd;dja;tedin;;;;rd:nt: uith-th; ;;th;d;i;;y :nd ;;r:::ter; in

- m a.

, la.

( APPLICABILITY: As shown in Table 3.3-tib-l ACTION:

an egloso .

i

a. With a redi;ective-gas:::: Of'luent monitoring instrumentation c'iannel Alarm / Trip Setpoint less conservativt than required by the above

specification, im: di;tely suspend-the reise:e of redi;;;tive

-g;;;;;; cffluent; a,enitered-by the effected channel, er-declare the .

channel inoperableenE % tb ActioV skwa ie- Tallc. 3.1 ~ /A l b. With less than the minimum number of rfc f; h; ga::::: :ff1;;nt i

~

monitoring instrumentation channels OPERABLE..take the ACTION shown in Table 3.3- M Restore the inoperable instrumentation to OPERABLE i status within the time specified In the ACTION, ;r :np hin in th:

n;xt hai:rnu;l ":d k;;tive Cffluent Releeee Reptrt oursuant to t

. Specification 6.9. . h this inoperability was not ?orrected l within the time spec ied. %ug a

The provisions of Specification 3.0.3 are not applicable.

c.

l e /it' vntvecuNv 4 a. fruki Rcret ,Prouc to ne Cmmd slen and IdEd SURVEILLANCE REQUIREMENTS Io c6dvu

4. 3. 3.41- Each rei,pethe gas:::: :"hent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK,-50"RCC=

-CllCCK,- CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequ'encies shown in Table 4.3-9.

8 i

s 4

50 CATAWBA - UNITS 1 & 2 3/4 3 Amendment No. (Unit 1)-

Amendment No. (Unit 2)

- - , = + , , . . . - - ~ - - , ,. - - ,

i P

11 .

TABLE 3.3 9 R Ptorive- ,

L 5 = 10ACT!VC-GASC005 [TTLUCf! MONITORING INSTRUMENTATION ,

E-2 ,

I MINIMUM CHANNELS .

E INSTRUMENT OPERABLE APPLICA8ILITY ACTION HOLDUP SYSTEM P a. Noble Gas Activi ' tor - I

" Providing Alars'and Automa -

Termination of Release (Low Range - EMF-50) per sta ~

45

b. Effluent ow Rate i ng Device 1 per station 46

}

w 2

' f -

. WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System fSQ :

w / W G -i !

. a. Hydrogen Monitors 1/ train per station *f I

-H .

+s~

gg

b. Oxygen Monitors ' 2/ train per station */ 49- !

3. ondenser Evacuation System Noble Gas 1 1,2,3,4 N Act ' Monitor (Low Range - EMF-33) --

r

4. Vent.5ystem

~

a. Noble Gas Activity Moni 1 47 N

(Low Range - EMF-36) .

b. Iodine Sampler (EMF-37) SC

c. Particulate Sampler-(E 1 50

. ' d .' Flow Rate or 1 46 L

e. ler Flow Rate Monitor- 1 i_ [

e ,

i I

.[

n TABLE 3.3-13 (Continued)

R_ADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

'.. MINIMUM CHANNELS

'E INSTRUMENT OPERA 8LE APPLICABILITY ACTION

5. Conta nt: Purge System

" Activity Monitor - Providing Noble G Alarm and tic Termination of Release 1 48 (Low Range - -39) ,

6. Containment Air Release a ition System Noble Gas Activity Monitor - viding 1 45 Alarm (Low Range - EMF-39) w

' 7. .. Monitor Tank Building HVAC N

$ a. Noble Gas Activity Monitor - Providing r station *** 47 Alarm (EMF-58) ,

b. Monitor Tank. Building Effluent F Rate 1 per stati 46 Measuring Device-

,, ~1 %I ee p

==

-- it e 00 L_L i@

.. ^^ .

N- .

. S0 E

L -. - - - - - - - _ - _ - - -

TABLE 3.3 13 (Continued)

TABLE NOTATIONS

At all times excs t when the isolation valve is closed and lock .

"* During WASTE GAS H LDUP SYSTEM operation.

- - At all times.

CTION STATEMENTS ACTION 45 - With the n ber of channels OPERABLE less th n required by the Minimum hannels OPERABLE requirement, e contents of the tank (s) m y be released to the environ ent for up to 14 days provi d that prior to initiating the release either:

a. Vent' system noble gas activity mo ator providing alarm and au omatic termination release (Low Range - EMF- ) has at least on channel OPERABLE, or

b. At least two i ependent samp es of the tank's contents are an lyzed, and a least two technically qualified member of the fa ility staff independently verify:

1. The discharge valve ineup, and

2. The manual port'o of the computer input for the release rate ca: lations performed on the computer, or th ntire release rate-calcula-tions if such I lations are performed manually.

Otherwise, suspend rel ase of adioactive effluents via this pathway.

ACTION 46 - With the number of hannels OPER BLE less than required by the Minimum Channe s OPERABLE req irement, effluent releases via this oathway ay continue for p to 30 days provided the flow rate i estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION.47 - With the numb of channels OPERABLE ess'than required by the Minimum annels OPERABLE require nt, effluent releases via this pa way may continue for up t 30 days provided grab sampi are taken at least once pe 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these sam es are analyzed for radioacti ity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 - With th number of channels OPERABLE less han required by the Mi imum Channels OPERABLE requirement, mmediately suspe d PURGING of radioactive effluents vi this pathway.

86Z-DN TD YTAR. ctWn% IL CATAWBA - UNITS &2 3/4 3-88

. . _ . - = - ~ . . ~__- -- . -.. . _ . _ . - - - -

j -

I

)

!e 19-l ,

TABLE 3.3 it (Continued)

! . TABLE NOTATIONS i k powy wd w Helut sing;ggy,, ,g

! ACTION 49 - With the numoer of channels OPERABLE one less than required i 1 tr by the Minimum Channels OPERABLE requirement, operation of i this system may continue provided grab samples are taken

, and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both

! channels inoperable, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months !

i during degassing operations and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4 during other operations, -

i 1 AC With the number of channels OPERABLE less t by j te hannels OPERABL,E Is4u4 , effluent releases e via the affec wte..h _, q continue for up to.30 days-

^

1 r C . 4 Tes are continuo eted with auxiliary I

moling equipment as required in Table .

1

! ACT10N +1-- With the number of channels OPERABLE one less than required j % by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

$GrLOCAw0 To

FEA( cawnnt /6 ;

i-i 4

s i

T d

a 8A

> CATAWBA - UNITS 1 & 2 3/4 3 _ . _ _ . . _ _ _

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

r T b F !

TABLE 4.3 '

9 EXPLostVE

.j . RAO:0AC' '."E GAS' mi', UTttEMI-MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

" ANALOG ;

CHANNEL MODES FOR E11CH i E CHANNEL E CHANNEL OPERATIONAL SURVEILLANCE =

U- INSTRUMENT CHECK C K CALIBRATION TEST 15 REQUIRED w j x

" i

. IE GAS HOLDUP SYSlEM i

" r-

a. Noble Gas Activi !

Provid nr. Alarm and Automa

Termis,at On of Release P R(3) Q(1)

(Low Range - EMF-50)- !

i j b. Effi .

em Flow Rate P N.A. R N.A.

4- asuring Device w- 9h 6

.1 f ~ WASTE GAS HOLDUP SYSTEM Explosive w

o Gas Monitoring System i y

[% ,

%n .-

a. ilydrogen Monitors D 4-A- Q(+) M */ O ,

7 *

b. Oxygen Monitors, D -90.*-- Q(fr) M

. Condenser Evacuat. ion System s

Noble Gas 'vity Monitor D h 'R(3)

N. 1, 2, 3, 4 F (Low Range - EMF- ,

4. -Vent System ,

a. Noble Gas Activity Monitor ,

M R(3) Q(2) l (Low Range - EMF-36) l b.'Iodi er (EMF-37) W N.A. M.A. N. .

i b

T

~

Di-d'W pr :Mel w T

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

4-

= 0 a

n- TABLE 4.3-9 (Continued) j' E y* RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

, ANALOG

c. CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED

'[ 4. Vent' System (Continued).

c. Pa "culate Sampler (EMF-35) W N.A. N.A. . N.A. *

. d. Flow Rate itor D N.A. R N. .

i- g i e. Sampler. Flow Rate itor D N.A. R N. A.-

7q i M p

5. Containment Purge' System f

y. Noble Gas Activity Monitor .- p w

. *4 Providing Alarm and Automatic Termination of Release (Low Range'- EMF-39)

D P R(3) Q(1) *** $g y

4

- 6.. Containment Air Release and p Addition. System e

y> Noble Gas Acti ' y Monitor- D P R(3) Q(1)

.g h Providing rm-i- g g' .(Low e. -EMF-39)

j. "" 7. ' itor Tank Building HVAC

. EN

a. Noble Gas, Activity Monitor - D M R(3) Q(2) **

l G; '. Providing' Alarm.(EMF-58)

b. Discharge Flow Instrumentation 0 N.A. R N.A. ***

c =

4

" - - - ~ ,- 5_. _ , . . . . , . . .r .,. ,iw-. * -ir--.

-.w - . , --em 4 -w.,, . . . . . . . - - - . - - - + - . . . _ - _ , . , . , - -,

3 .

TABLE 4.3-9-(Continued)

TABLE NOTATIONS At all the; except Ma th; b htkn nin b ci: :d :nd lochd.

, Duriy WAS E GAS HOLOUP SYSTEM operation.

m. . . . . . . ~ .

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

a. I rument indicates measured levels above the Alarm /Tr etpoint, or

b. Circuit fa re (Alarm only), or-

c. Instrument indic s a downscale failure arm only).

(2) The ANALOG CHANNEL OPERATIO TEST sha also demonstrate that control room alarm annuciation* occurs an f the following conditions exists: l

a. Instrument indicates meas- d le is above the Alarm Setpoint, or

b. Circuit failure, or

c. Instrument i cates a downscale failure. -

(3) The initial .NNEL CALIBRATION shall be performed usin ne or more of the refer ce standards certified by the National Bureau o tandards (NBS) or us standards that have been obtained from suppliers tha articipate in asurement assurance activities with NBS. Thesa standards.s 1 rmit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that h been related to the initial calibration shall be used.

(+) The CHANNEL CALIBRATION shall include the use of standard gas samples in

/ accordance with the manufacturer's recommendations. .In addition, a standard gas sample of nominal four volume percent hydrogen,' balance nitrogen, shall be used in the calibration to check linearity of the hydrogen analyzer.

(f-) The CFANNEL CALIBRATION shall include the use.of standard gas samples-in A accordance with the manufacturer's recommendations. In addition, a-standard gas sample of nominal four percent oxygen, balance nitrogen, shall be used in the calibration to check linearity of.the oxygen analyzer.

^

d&~LOCATff = Tt PrM ctwrev I6 ]

For EMF-b8, the alarm annunciaik: A in %

"e.. Lor tank Building Control Room and on the MTE Co.Livi ranel, Remote Annuncioiv. p al ty '

CATAWBA - UNITS 1 & 2 '3/4 3 Amendment-No. (Unit 1)

Amendment No. T(Unit 2)1

, INSTRUMENTATICJ BORON DILUTION MITIGATION SYSTEu l LIH!'ING CON 0! TION FOR ODERATION '

3.3.3.1. il As a min!mu*, two trains of the Boron Dilution Mitigation System shall be OPERABLE and operating ith Snutdown Margin Alarm ratios set at less than or equal to 4 times the steady state count rate.

ADD L

! AE!LI T MODES 3, 4, AND 5 ;_

ACT!CN:

(a) With one train of tne Boron Oilution Mitigation System inoperable or not operating, restore the inoperable train to OPERABLE s_ta_tus within_

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or (1) suspend all operations involving positive reactivity changes and verify that valve Nv 230 is closed and secured within:the next y hour, or (2) verify two Source Range heutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal'to one-half decade (square root of.10) above the steady state count rate and verify that the combined flowrate from both Reactor Makeup Water Pumps is less than or equal to 150 gpm (Mode-3.or 4) or 75 gpm (Mode-5) [

within the next hour.

(b) With both trains of the Boron Dilution Mitigation System inoperable or not cperating, restore the inoperable trains to OPERABLE status-within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or (1)' suspend all operations involving positive reactivity changes and verify that valve Nv-23011s closed and~ secured _within thei next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with-Alarm Setpoints less tnan or equal to one-half decade'(square-root of.10) above the. steady-state count rate and' verify that the-combined flow-rate from both Reactor Makeup Water Pumps is less than or equal to 150 gpm (Mode 3 or 4) or-75'gpm (Mode 5) l_

within the next hour.

SURVEILLANCE REQUIREMENTS _

4.3.3.h.1Eachtrain.oftheBoronDibtionMitigationSystemshall'be.: demon-strated OPERABLE by performance of:

(a) A CHANNEL CHECK at least on:e oer 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,- .

ET CATAWBA - UNITS 1 & 2 3/4 3-; L Amendment'No.- (Unit 1).

Amendeent No. (Unit 2)

INSTRUMENTATION SURVE!LLANCE REQUIDEMENTS (Centinuea)

(b) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and (c) At least once per 18 mortns the BOM5 shall be demonstrated OPERABLE l by:

(1) Verifying that each automatic valve actuated by the BDMS moves to its correct position upon receipt of a trip signal, and (2) Verifying each reactor makeup water pump stops, as designed, upon receipt of a trip signal.

Il 4.3.3 M .2 If using the Source Range Neutron Flux Monitors to meet the require-ments of Technical Specification 3.3.3.11, ll (a) The monthly surveillance requirements of Table 4.3 1 for the Source Range Neutron Flux Monitors shall include verification that the Alarm Setpoint is less than or equal to one-half decade (square root of-10) abose the steaoy-state count rate.

(b) ine combined flow rate frcm both Reactor Makeup Water Pumps shall be verified as less than or ecual to 150 gpm (Mode 3 or 4) or 75 gpm (Mode 5) at least once per 31 days. ,

l .

4 CATAWBA - UNITS 1 & 2 3/4 3 :-2; Amendment No. _(Unit .:

Amendment No. '(Unit C,

J l

INSTRUMENTATION 3/4.1.4 TURBINE OVERSPEED PROTECTION I

LIMITINGCON0!TIONf,0R, OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the ste&m supply.

U S_URVEILLANCE REQUIREMENTS i

4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a. At least once per 7 days while in MODE 1 and while in MODE 2 with the turbine operating, by cycling each of the following valves through at least one complete cycle from the running position:

1) Four high pressure turbine stop valves,

2) Six low pressure turbine intermediate stop valves, and

3) Six low pressure turbine intercept valves.

b. At least once per 31 days while in MODE 1 and while in H00E 2 with the turbine operating, by direct observation of the movement of each of the above valves and the four high pressure turbine control valves, through one complete cycle from the running position,

c. At least once per 18 months by performance of a CHANHEL CALIBRATION on the Turbine Overspeed Protection Systems,* and l

d. At least once per 40 months by disassembling at least one of each of the above valves (including the four high pressure turbine control valves) and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

"This surveillance need not be performed until prior to entering HOT STANDBY following the Unit 1 first refueling. (This applies to Unit 1 only.)

CATAWBA - UNITS 1 & 2 3/4 3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

4 I

i l

4 l I 3/4.11 RADIDACTIVE E LUENTS g

j 3/4.11.1 L10VID EFFLUE415 >

i

? CONCEN1 RAT 10N f!

f tlMITING CONDITION FOR OP ATION 1 1

l 1

I 1

3.11.1.1 The concentration f radioactive material relea d in liquid effluents ;

I to UNRESTRICTED AREAS (see F ure 5.1-3) shall be limite to the conce:

2 for radionuclides epecified in 10 CFR Part 20, ppendix B. Table II, Col For dis olved or entrained

{

) other than dissolved or entral ed noble gases. hall be limited to 2 x 10+4 microcurie /ml ;

i noble gases the concentration ;

j totalactivIty.

j t t APPLICABillTY: At all times. -

j '

i ACTION:

leased in liquid effluents to l~

}

With the concentration of radioactiv material limits, mmediately restore the concen--

UNRESTRICTED AREAS exceeding the abo i l r 1 tration to within the above timits. i 3

SURVEILLANCE REQUIREMENTS ' '

i _

l 1

4.11.1.1.1 Radioactive liquid wastes sh 1 be sampled.and analyzed according

! l to the sampling and analysis program of Ta e 4.11-1. .

l 4.11.1.1.2 The results of the radica tivity analyses shall be used in accordance- i with the methodology and parameters n the O M to assure that-the concentrations l at the point of release are maintai ed within he limits of.5pecification i '

j 3.11.1.1. '

l r . .

i l.

i. i RELDcA7iiD 7% I

?

i ;

L TfAR cH/tenrR. Ik i

j

[ t 3/4 11-1 i -- CATAWBA - UN 51&2 fhiwg4y n9r r- ---9 e-.=-9 g b--

+gf- y y yk -P g4-y-9 9 9 p.iny- ewy w-me.g-y Qe.,u9qy_ ...gmye.pmp,,.ar w--m.r-veyg-c'w---.e-ge- e+ 6,pg g - -- 9 -,==949 e

_ TABLE 4.11-1 ,.

RADI0ACI VE LIQUID WASTE SAMPLING AND ANALYSIS PROG AM l

\ /

LOWER LIMIT HINIMUM OF DETECTION LIQUID RELEASE SAMPLIN ANALYSIS TYPE OF CTIVITY (LLO)(1)

TYPE FREQUENC FREQUENCY ANA YSIS (pC1/ml)

1. Batch Weste P P !

Release Each Batch Each Batch P ncipal Gamma 5x10 7 l Tanks (2) mitters I3) p-131- lx10

l Any tank which /

discharges P M Dissolved and. lx10

liquid wastes One Batch /M -Entrained Gases by tither ifquid (Gamma Emitters) effluent moni- /

tor, EMF-49 or P 'H-3 lx10

I EMF- 57 Each Batch Composi e I) ;

Gross Alpha 1x10 7 -

/_ i P Sr-89, Sr-90 5x10.s i Each Batch Comp ite I4 l Fe-55 1x10 8 .

2. Continuous W (PrincipalGamma 5x10 7 ,

5 Releases (5) C ontinuous(6) omposite(6) VmittersI3)-

t h131 1x10 8

a. Conventional / \

l Waste Water M M Of olved and -lx10

l '

Treatment Grab Samp1 Ent ined Gases

}- Line (Ga Emitters) -

i \

i b. Turbine Building M- H-3 1:.10 5 i Sump Contin ous(0) Composite (6).

l h Gross.Alpka 1x10 7 0 Sr-89, Sr- 5x10 s Co tinuous(6) Composite (6)

Fe-55l 1x10 8 L *0uring use of demi eralizer ,ase of EMF _-31 in of f-normal- mode),

I

' 2 El ocA-TED TS ^

PskL cm iG

!- CATAWBA - UNIT 1&2 3/4 11-2 ?.mendment No. 66 (U it 1) ,

i Amendment 1o.- 60 (Un t.-2)

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

l l

l TABLE 4.11-1 (Continued) 1 TABLE NOTATIONS (1)The LLO is defined, for purposes of these specificati ns as the smallest concentration of ra oactivematerialinasampletbtwIllyieldanet count, above system ekgrouno, that will be det9ct d with 95% probability with only 5% p'robabil ty of falsely concluding tha a blank observation l renresents a real" si nal.

l For a particular measuremen system, which may inel de radiochemical j separation: ;

i 1

4.66 s L'.D =

E V 2.22 x 108 - exp (-Mt) l Where:

LLD the "a priori" lower lim t of d ection (microcurie per unit mass or volume),

s b = the standard deviativn of t ackground counting rate or of the counting rate of a blank sampi as appropriate (counts per minute),

l E = the counting efficiency (co ts er disintegration),

V = tne sample size (units of ass or olume),

l l

2.22 x 108 = the number if d sintegrati s per minute per microcurie, Y = the fractional radioch ical yield, w en applicable.

A = the radioacthe decay constant for the articular radionuclide (sec 1), and [

l At = the elapsed time etwesn the midpoint of ample collrction and i the time of counting sec). l t Typical values of E V, Y, and at shculd be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit repres nting the capability of a ueasurebent system and not as an a posterior (after the fact) limit for a part' ular measurement.

i

(2)A batch release i the discharge of liquid wastes of a iscrete volume.

! Prior to samplin for analyses, each batch shall be isol ted, and then thoroughly mixe to assure representative sampline.

Nl CCAT6T 71) \

Fw. cHarrst. (6 \

CATAWBA - UNITS 1 & 2 3/4 11-3 Amendment No. 37 ni\. 1)

Amendment No, 29 ( it 2)

l !

1 i

! TABLE 4.11 1 (Continued) 7-4 y

TABLE NOTATIONS (Continued) f (3)The principal gama mitters for which the LLO specif{ t; ion applies include the following radion lides: Mn 54, Fe-59 Co-58, Co 0, Zn*6% Ho-99, ,

Cs 134, Cs-137 -and Ce 141. The LLO for Ce 144 is 5 x 10 6 pCi/n.L 'This 4

j list does not mean the only these nuclides are to b considered. Other gama peaks that are id ntifiable, together with th se of the-above nuc-j 1 lides, shall also be ana yzed and reported in the afannual Radioactive i Effluent Release Report rsuant to Specification .9.1.7 in the format '

outlined in Reguintory Gu e 1.21, Appendix B, Re ision 1, June-1974.

l j (4)A composite sample is one i which the quantity of liquid sampled is proportional to the quantity of liquid waste d charged and in which the i method of sampling employed r sults in a spec en that is representative -

j of the liquids released.

i (5)A t.ontinuous release is the dis arge of li uid wastes of a nondiscrete 1

j volume, e.g., from a volume of a ystem th t has an input flow during the l continuout-release. .

l j (6)To be representative of the quantit es d concentrations of radioactive

]

materials in liquid effluents, sampi s hall be collected continuously in proportion to the rate of flow of th ffluent stream.- Prior to analyses',

all samples taken for the composite s 11 be thoroughly mixed in order - i for the composite sa'nple to be repre tative of the effluent-release.

1 .

( +

j i I i i b I i

t i-i 4

f_ b/DCA N %

YtM. cuerrex. Ic l I

i-

] CATAWBA'- UNITS &2 3/4 11-4

. . - - .a _

- , . - , , - . . - . - - . - . - - . _ : . - . . . + . - - . - , _ . . -

_ t i

RA010ACTIVF EFFLUE 5 DOSE LIMITING CONDITION FOR PERATION 3.11.1.2 Thedoseordos\commitmenttoaHEMBEROFTH PUBLIC from radioactive materials in liquid efflue ts released, from each unit to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calenda quarter to Uss than o equal to 1.5 mrons ta the whole body and less than or equal - 5 mrcats to eny organ, and

b. During any calendar ye r to less than o equal to 3 mrems to tho whole body and to less han or equal t 10 prems to any organ.

APPLICABILIT(: At all times.

ACTION:

(

a. With the calculated dose fro the elease of radioactive materials l in liquid effluents exceeding ny of the above limits, prepare and I submit to the Commission withi days, persuant to Specification '

6.9.2, a Special Report that id tifies the cause(s) for exceeding the limit (s) and defines the co ective actions that have been taken to reduce the releases and the pr posed corrective actions to be taken to assure that subseque re eases will be in complianco with the above limits. This Spec 1 Re rt shall also include: (1) the results of radiological anal ses of he drinking water source, and (2) the radiological impact on finis ed drinkia0 kRter supplies with regard to the requirements of 40 CFR art 141, Safe Drinking Water Act.*

b. The provisions of Spa.ci cation 3,0.3 ar not applicat,le.

SURVEILLANCE REQUIREMENTS I i 4.11.1.2 Cumulative dose cont ibutions from liquid ef luents for the current calendar quarter and the curr nt calendar year shall be determined in accordance with the methodology and par eters in the ODCM at least once per 31 days.

The requirements of ACT N a.(1) and (2) are applicable on1 if dri king n water supply is taken from th receiving water body within 3 miles downstream of the plant discharge.

AEl DC/TTEA TD u

W&ll CMkfT51L %

CATAWBA - UNITS 1 & 2 3/4 11-5 Amendment No. 48 (Unit 1)

Amendment No. 41 Unit 2)

- ~

RADIOACTIVE EFFLUEN $

LIQUID RA0 WASTE TREAT NT SYSTEM LIMITING CONDITION FOR ERATION 1 I 3.11.1.3. The Liquid Radwa te Treatrent System shall be OPERA LE and appropriate portions of the system shal be used to reduce releases of r dioactivity when the projected doses due to t e liquid effluent, from each u it, to UNRESTRICTED AREAS (see Figure 5.1-3) wou exceed 0.06 mrem to the who body or 0.2 mrem to any organ in a 31-day peri .

APPLICABILITY: At all times.

ACTION:

a. With radioactive ligt.ld ste being discha ged without treatment and in excess of the above li its and any por ion of the Liquid Radwaste Treatment System not in op ration, prepa and submit to the Commission within 40 days, ursuant to ' ecification 6.9.2, a Special Report that includes the foi owing inf ation:

1. Explanation of why liqui radwas c was being discharged without treatment, identification f an inoperable equipment or subsystems, and the reason or the inoperability, ,

2. Action (s) taken to restore t inoporable equipment to OPERABLE status, and

3. Summary descriotion of ?.c on(s taken to prevent a recurrence,

b. The provisions of Specificati n 3.0.3 re not applicable.

SURVEILLANCE REQUIfiirIENTS

/ \

4.11.1.3.1 Doses due to liquid rel ases from each u it to UNRESTRICTED AREAS shall be projected at least once p r 31 days in accor ance with the methodology and parameters in the ODCM when quid Radwaste Trea nt Systems are not being fully utilized.

4.11.1.3.2 The installed Liqu'd Radwaste Treatment Syst shall be considered OPERABLE oy meeting Specifica+ ons 3.11.1.1 and 3.11.1.2.

RELocmsg n VSAR. cH/+fTTYL iG CATAWBA - UNITS 1 & 2 3/4 11-6 Amendment No. 43 (Unit 1)

Amendment No. 41 Unit 2)

7/f.jlRADI0ACTIVEEFFLUENTS LIQUID HOLDUP TANKS ^ 3 bell I lJ Q W D E N # 1 LIMITING CONDITION FOR OPERATION 3.11.1.hThequantityofradioactivematerialcontainedineachtemporary unprotected outdoor tahk shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.

. APPLICABILITY: At all times. .

ACTION:

a. With the quantity of radioactive material in any of the above tanks 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 Semiannual Radioactive Effluent Release-Report, pursuant to Specification 6.9.1.7.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCERFEI,REMEN1s 4.11.1.dThequantityofradioactivematerial o ained in each of the a'aove tanks shall be determined to be within the above. limit by analyzing a representative sample of the tank's contents at:least once par 7 days wnen radioactive materials are being added to the tank.

(

4 l- .

', CATAWBA . UNITS 1 & 2 3/4 11-1 , Amendment No. (Unit 1).

Amendment No.. (Unit 2)

~

I .

/

RADI0 ACTIVE EFFLUENTS CHEMICAL TREATMENT PONDS LIMITING CONDITION FOR OPERA ION 1 <

3.11.1.5 The quantity of rad oactive material contained in each chemical treatment pond shall be limite by the following expressio :

A

f j h<1.0 J -

excluding tritium and dissolved or ntrained noble g es, Where:

A) = pond inventory limit for s gle radionue de "j", in Curies; C 10 CFR Part 20. Appendix B, able~ II, C lumn 2, concentration for 3 = single radionuclide "j", mic Curies /m ;

V = design volume of liquid and si try i the pond, in gallons; and -

264 = conversion unit, microcuries/Cu ie r milliliter / gallon.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactiv ma erial in any of the above listed ponds exceeding the above limi , i diately suspend all additions of radioactive material to th pond nd initiate corrective action to reduce the contents to Wi hin the imit,

b. The provisions of-Specific ion 3.0.3 re not applicable.

SURVEILLANCE REQUIREMENTS I \

4.11.1.5 The quantity of radion ive material cont ined in each batch of resin / water slurry to be transfe red to the chemical treatment ponds shall be determined to be within the abo e limit by analyzing representative sample -

of the batch to be transferred to the chemical trea t ponds and shall be limited by the expression:

I

< 0.006 jC 3

Where:

c) = radioactive r in/ water slurry concentration for adionucliue "j" entering the NRESTRICTED AREA chemical treatment onds, in x microcuries/ 111111ter; end C) = 10 CFR Par 20, Appendix B. Table II, Colurn 2, con ntration for single ra ionuclide "j", in microcuries/ milliliter.

R E~LOCATF9 7't F T M c t % ,P r n L I t CATAWBA - U TS 1 & 2 3/4 11-8 Amendment No. 48-(Unit 1)

Amendment No. 41 (Unit 2)

___m_m.___ m____ _ . _ _.__- . -

S .

l RADIDACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUEN 00$E RATE LIMITING CONDITION FOR OPERA ON ,

3.11.2.1 The dose rate due to a'dioactive materials relea ed in gaseous effluents from the site to areas at and beyoaJ the SITE B UNDARY (see Figure 5.1-4) shall be limited to the-f lowing:- ,

a. For noble gases: Less t n or equal to 500 ess/yr to the whole i body and less than or equ 1 to 3000 mrems/y to the skin, and

b. For lodine-131, for Iodine- 33, for triti , and for all radio-nuclides in particulate form with half-li es greater than 8 days:-

Less than or equal to 1500 m ms/yr to y-organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s), exceeding the above li its, immediately restore the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS

' 4.11.2.h 1 The dose rate due to nobl gases in ga eous effluents shall be determined to be within the above li ts in accorda ce with the methodology and parameters-in the 00CM.

4.11.2.1.2 The dose rate due to I dine-131 Iodine-1 , tritium, and al1~

radionuclides in particulate form with half-lives-grea r than 8 days in gaseous-ef fluents shall be determined to e within the above li its in accordance with the methodology and parameters n the 00CM by obtaining epresentative samples and performing analyses in acc rdance with the sampling a d analysis program

specified in Table 4.11-2.

b Rnocasy ro rm c# I' CATAWBA - UNI -1 & 2L 3/4 11-9J

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

_ _ . . __ . . . . . _ _ _ . _ _ . _ - . . _ . _ . . ._ _ . . _ _ . _ . . . _ _ _ _ _ . . _ = _ . . . _ _ . _ _ _ _ - . . . .

I

't I TABLE 4.11-2

_., RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Pf E' 1 MUM MI.1 LOWER LIMIT Of

. SAMPLING ANALYSIS TYPE OF DETECTION (LLD)(7) c- GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCl/ml)

L 1. Waste Gas Storage P P ;

Tank Each Tank Each Tank Principal Gamma Emitters (2) 1x10 4 -

Grab Sample /

g -Con et Purge

.2. P pg,g(3) Each PURGE I3) Principal Gamma Emitters (2)

Grab. Sample .-

5%

m M H-3 (oxide) , 1x10 8 d9 ;

)

WI Principal Gamma Em 1x10

O

3. Unit Vent

Grab Sample m 4 I3) H-3 (oxide} [ 1x10 8 p u 4. Containmer.t .tir D(3)(S)

^

Pripa'JammaEmitters(2) 1x10 4 h

) Release and lx10 s Addition System Grab Sample M xide)

)

S. All Release Types as listed in 3.

Continum.as(6) I-131 1x10 ** 3

/ Charcoal above.

/ Sample I-133 \ 1x10 e ,

Jefitinuous(6) t D I#3 Principal Gamma Emitters (2)' 1x10 28 Particulate !

Sample

- Continuous (6). M Gross Alpha IO} 1x10 83 h ,

Composite Par-ticulate Sample Continuous (6) Q Sr-89, Sr-90 1x10 82 Composite Par-ticulate Sample

Table 4.11-2 (Continued)

-h RADIOACTIVE CASEDUS WASTE SAMPLING AND ANALYSIS PROGRAM M,INIMUM LOWER LIMIT O

. SAMPLING ANALYSIS TYPE OF DETECTION (LLD){y)

ACTIVITY ANALYSIS (pCi/al) g GASEOUS RELEASE TYPE- FREQUENCY FREQUENCY d

g

6. - Waste Monitor

-Tank Building W

Grab Sample.

W Principal Gamma Emitters (2) 1 x 10 +

. e. Ventilation- H-3 (oxide) 1 x 10 ' #

/

Exhaust W I-131 1 x 10 31 Continuous (6) Charcoci Sample I-133 W /

Con ~ s(b) Parti : alate Principal Gamma Emitter I 1 x 10 18

- t:' Sample U "

Gros 1 x 10 18 A Continuous (6) Composite -

pha R- ticulate Sample Continuous I0I -

C si r- Sr-89, Sr-- 1 x 10 38 tic e Sample

.: m

'Ik aa > 0 f

gg nQ ~

~

$b M n

2;:

Oc +fa

~

d b

d

TABLE 4.11-2 (Continued)

TABLE NOTAT_ IONS _

! (1) The LLD is defined, for purposes of these specificati ns, as the smallest a concentration of rad active material in a sample th will yield a_ net

! count, abcVe system b ekground, that will be detect with 95% probability i robabili of falsely concluding tha a blank observation l l withonly5%p'real"sigal.

represents a l For a particular measur nt system,_which may 1 clude radiochemical l seoaration:

4.6 s b l LLD = ']

j E V 2.22 x 10s . Y . exp (- ) l 4

Where:

d LLD = the "a priori" lower 1 mit of etec+.fon (microcurie per unit i mass or volume), ,

i b = the standard deviation of h background counting _ rate or of s

, the counting rate of a blank sa le as appropriate. (counts per j minute),

1 i E = the counting efficiency ( unt perdisintegration), '

V = the sample size (units mass o volume),

i j 2.22 x 10s = the number of disintegrat ons per minute per microcurie, ,

I Y = the fractional radio emical yield, hen applicable, '

j A = the radioactive de y constant for th particular radionuclide j (sec 1), and !

! at = the elapsed ti between the midpoint-o sample collection and the time of countin (sec). l_

Typical _ values of , V, Y, and -at should be use _ in th'e. calculation.

1 It should be recogni d that the LLD is-defined as an priori (before i the fact) limit repr senting'.the capability of a measu ment system and: .

2 not as an a posteri ri (after the fact) limit for_a par icular measurement.

. RS % T@ n D A17 CK41'TCL Ib' r

CATAWBA - UNIT- 1_& 2 -3/4 11-11_ Amendment No.- 37 Unit 1)

L Amendment No. = 29 ( nit'-2),

TABLE 4.11-2(Continueg ,

TABLE NOTATIONS (Contigued) y (2) The principal gamma- itters-for-which the ALD specifica ion applies include the following adionuclides:- Kr-87, Kr-88, Xe- 33, Xe-133m, .

Xe-135, and Xe-138 in- ble gas releases and Mn-54, Fe 9 Cor58','Co-60, Zn-65, Mo-99, I-131, Cs 134 Cs-137,- and Ce-141-in lo ine and particulate .

releases. The LLD for Ce 144 is 5x10-9 pCi/ml.- This ist does not mean' that only these nuclides re to_be considered. Othe : gamma peaks;that;are identifiable, together wit those of the above nuc1 des,-shallnalso be anal--

yzed and reported in the-S iannual Radic> active Ef luent Release Report pursuant to Specification 6. 1.7 in the' format o tiined in Regulatory Guide 1.21, Appendix B, Revi ion 1. June.1974.-

~

> (3) Sampling and analysis shall al o be-performed o11owing shutdown, startup, or a THERMAL F0WER stabilizatio (powee level constant at-desired power .

~

level) after a-THERMAL POWER ch ge exceedin 15% of-RATED-THERMAL-POWER; within a 1-hour _ period, for- at.1 st rine of he three gaseous release types with this notation.

(4) Tritiumgrabsamplesshallbeteenkatlestonceper24hourswhenthe refueling canal is flooded.

(5)~ Required sampling and analysis frer,ue y during effluent release via"this pathway.

(6) The ratio of the sample flow volurae o t e-sampled stream flow volume-shall be known for the time period cover by e ch dose or dose rate calculation.

made in accordance with Specifica ons 3.1 .2.1, 3.11.2.2, and 3.11.2.3.-

.M

' (7) Samples shall be-changed at leas once per : hours and analyses shall' be --

completed within 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months after changing, or fter removal-from-sampler.

(8) The composite' filter (s) will e analyzed for'a he activi_ty-by analyzing one filter per week to ensur that at least fou filters are analyzed:- ,

i per collection period.

b

$ Et Q M T 5 0 'M>-

'i= ret 4HAfTtyt.@

1 CATAWBA - UNIT 1&2 <

3/4 11-12 i

\.

RADIOACTIVE EFFLUEMS DOSE - NOBLE GASES LIMITING CONDITION FOR PERATION 3.11.2.2 The air dose du to noble gases released in gaseous effluents from each unit, to areas at and beyond the SITE BOUNDARY (see figure 5.1-4) shall be limited to the following

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

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

APPLICABILITYi At all times.

ACTION

a. With the calculated air .e ' un radi ctive noble gases in gaseous effluents e. eecti g any , ui above mits, prepare and submit to the Commission w. thin 30 days, pursu t to Spacification 6.9.2, a Special Report that identifies he use(s) for exceeding the limit (s) and defines the corrective acti s hat have been taken to reduce the releases and the proposed co ct'<3 actions to be taken to assure that subsequent releases w 11 Le in compliance with the above limits.

b. The provisions of Specificatio 3.0. are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative-dose contribut i for the cu rent calendar quarter and current calenda.' year for noble gae s shall be dete ined in accordance with the methodology and parameters in he ODCM at least nce per 31 dsys.

Rao w 0 ro Ps/4R cHAfr6YL IG CATAWBA - UNITS &2 3/4 11-13 Amendment No. 4 (Unit 1)

Amendment Nd. 41 (Unit 2)

i l RADIOACTIVE EFFLUE S DOSE - 10 DINES 131, I INE-133, TRITIUM. AND RADIOACTIVE MATERI L IN PARTICULATE FORM LIMITING CONDITION FOR ERATION- ,,

3.11'.2.3 The dose to a M BER OF THE PUBLIC from Iodine- 31, Iodine-133, tritium, and all radionuel es in particulate form with alf-lives greater 4

than 8 days in gaseous effl nts released,- from each un t, to areas at and l

beyond the SITE BOUNDARY (se F gure 5.1-4) shall be 1 mited to the following:

a. During any calendar uarter: Less than or equal to 7.5 mress to any organ and, i

b. During any calendar yea : Less than or qual to 15 mrems to any organ.

APPLICABILITY: At all times. .

i

ACTION:

! a. With the calculated dose from the elease of. Iodine-131 Iodine-133, l tritium, and radionuclides in a iculate form with half-lives greater than 8 days, in gaseous efflue exceeding any of the above 11mitr, ion within 30 days, pursuant-to prepare and submit to the Commi i Specification 6.9.2, a Special R ort that identifies the cause(s) i for exceeding the limit and d fin the corrective actions that have been taken to reduce the rel ases nd the proposed corrective actions I to be taken to assure that ubseque t releases will be in compliance with the above limits.

i b. The provisions of Specif ation 3.0.3- re not applicable.

SURVEILLANCE REQUIREMENTS l ,

l -/

. 4.11.2.3 Cumulative dose cont ibutions for the cur nt calendar quarter and-4 current calendar year for Iod ne-131 Iodine-133,. tri ium and radionuclides

, in particulate form with hal -lives greater than 8 da -shall be determined.- '

in accordance with the meth ology and parameters'in t ODCM at least once per 31 days.

4

$5LDCATSlQ TD

- PrML cHRPT%R ((o .

4 3

i i !

-j CATAWBA - UNI S 1 & 2 3/4 11-14 Amendment No. 4 (Unit i)

Amendment No. 41 (Unit 2) j 1

RADI0 ACTIVE EFFLUE S GASEOUS RADWASTE TRE THENT SYSTEM LIMITING CONDITION FOR PERATION ,

3.11.2.4 The VENTILATIO EXHAUST TREATMENT SYSTEM and the ASTE GAS HOLDUP SYSTEM shall be OPERABLE a d appropriate portions of these systems shall be used to reduce releases of adioactivity when the project d doses in 31 days due to gaseous effluent rele ses, from each unit, to are at and beyond the SITE BOUNDARY (see Figure S. 4) would exceed either:

a. 0.2 mrad to air from amma radiation, or

b. 0.4 mrad to air from b ta radiation, or

c. 0.3 mrem to any organ o a HEMBER OF THE UBLIC.

APPLICABILITY: At all times.

ACTION:

4 a. With radioactive gaseous wast bein discharged without treatment and in excess of the above lim ts, repare and submit to the Commission within 30 days, purs a to Specification 6.9.2, a Special Report that includes the followl information:

1. Identification of any iner r le equipment or subsystems, and the reason for the inoper bil y,

2. Action (s) taken to rest re the operable equipment to OPERABLE status, and

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

b. The provisions of Specif cation 3,0.3 ar not applicable.

SURVEILLANCE REQUIREMENTS

/ \

4.11.2.4.1 Doses due to gase us releases from each uni to areas at and beyond the SITE BOUNDARY sha be projected at least onc per 31 days in accordance with the methodo gy and parameters in the OD when Gaseous Radwaste Treatment Systems re not being fully utilized.

4.11.2.4.2 The installe VENTILATION EXHAUST TREATMENT SYS M and WASTE GAS HOLDUP SYSTEM shall be e nsidered OPERABLE by meeting Specif ation 3.11.2.1 and 3.11.2.2 or 3.11.2. .

RELOCATST) TD PTAvt clWTot I6 CATAWBA - UNITS 1 & 2 3/4 11-15 Amendment No. 48 (Unit 1)

Amendment No. 41 Unit 2)

t a

T 4

RADI0 ACTIVE EFFLUENTS

=

v - 1/+.II.A GASEQUSdTFFLUEWYS-EXPLOSIVE GAS MIXTURE ,

i LIMITING CONDITION FOR'0PERATION l

i I .

3.11.2c6- The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 2% by volume whenever-the hydrogen concentration-l exceeds 4% by volume.

APPLICABILITY: At all times. .

I ACTION:

4 I a.- With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM 3

greater than 2% by volume but less than or equal to~4% 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. With the concentration of oxygen _in1the WASTE GAS-HOLDUP SYSTEM =

i greater than 4% by volume and the hydrogen concentration greater?

than 4% by volume, immediately suspend all additions' of waste gases i to the system _and reduce the' concentration of> oxygen to-less than or-

{ equal to 4% by volume; then take ACTION a. above.

i l c. The provisions of Specification ,3.0.3 are not applicable, i

i l SURVEILLANCE REQUIREMENTS-I I. .

4.11.2.0- The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP -

SYSTEM shall be determined to be within the above: limits by continuously

monitoring the waste gases-in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-tS of-Specification-3.3.3.tt.-

, l>~ lo i

4 p

i I

l l

),

CATAWBA -: UNITS 1 &-2; -3/4 11 : Amendment No. (Unit-1)

Amendment No. (Unit 2)-

f - am, - - s n , n

i J

L RADI0 ACTIVE EFFLUENTS i

e -GASEOV3 SFFLVEAfTS

GAS STORAGE TANKS i

LIMITING CONDITION FOR OPERATION 1

4 A .

! 3.11.2.6- The quantity of radioactivity contained in each gas storage tank ,

f shall be limited to less than or equal to 97,000 Curies of noble gases (con- ;

. sidered as Xe-133 equivalent).

APPLICABILITY: At all times.

(

ACTION:

a. With the quantity of radioactive material in any gas storage tank i exceeding the above limit, immediately suspend all additions of

! radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce.the tank contents to within the limit, and describe.the events-leading to this i condition in the next Semiannual Radioactive Effluent Release Report -

pursuant to Specification 6.9.1.7.

i b. The-provisions of Specification 3.0.3 are not applicable.-

i l SURVEILLANCE REQUIREMENTS ps .

! 4.11.2. The quantity of radioactive material contained in each gas storage.

' tank shall be determined to be withir, 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.

l' 4

4 i

1 i

e i

3 .

CATAWBA - UNITS 1 & 2 3/4 11-it- . Amendment No. (Unit 1).

Amendment No. (Unit' 2) --

t "t-pir-- g y-(*,

RADIOACTIVE EFFLU 'TS

$4OCATEY TD

\ FT/% CHA M lb 3/4.11.3 SOLID RADICACTIVE WASTES LIMITING CONDITION FO OPERATION

\ I 3.11.3 Radioactive was es shall be solidified or dewatered in ccordance with the PROCESS CONTRC PROG AM to meet shipping and transportatio requirements during transit, and dispo al site requirements when received t the disposal site.

APPLICABILITY: At all time .

ACTION:

~

a. With SOLIDIFICATION r dewatering not meeting disposal site and shipping and transpo ation requirements, su end shipment of the inadequately processe wastes and correct t PROCESS CONTROL PROGRAM, the. procedures and/or e Solid Radwaste S tem as necessary to pre-vent recurrence.

b. With SOLIDIFICATION or d atering not pe formed in accordance with the PROCESS CONTROL PROGR , test the i roperly processed waste in each container to ensure t at it meets urial ground and shipping requirements and take appro riate adm istrative action to prevent recurrence,

c. The provisions of Specificati n 3.0 are not applicable.

SURVEILLANCE REQUIREMENTS

\ I 4.11.3 SOLIDIFICATION of at least one rep esentative test specimen from at least every tenth batch of each type of w t radioactive wastes (e.g., filter sludges, spent resins, evaporator bottom , b ric acid solutions and sodium sulfate solutions) shall be verified in acco ance with the PROCESS CONTROL PROGRAM:

a. If any test specimen fails o verify OLIDIFICATION, the SOLIDIFICATION of the batch under test s 11 be susp ded until such time as additional test specimens can be ob ined, altern tive SOLIDIFICATION parameters can be determined in ac rdance with th PROCESS CONTROL PROGRAM, and a subsequent test v rifies SOLIDIFIC TION. SOLIDIFICATION of the batch may then be esumed using the a ternative SOLIDIFICATION parameters determined by the PROCESS CONT L PROGRAM;

b. If the initial test pecimen from a batch o waste fails to verify SOLIDIFICATION, th PROCESS CONTROL PROGRAM hall pro' tide for the collection and tes ing of representative test specimens from each consecutive bate of the same type of wet was until at least three consecutive ini al test specimens demonstrate OLIDIFICATION.

The PROCESS CON ROL PROGRAM shall be modified a required, as provided in Specificati n 6.13, to assure SOLIDIFICATION f subsequent batches of waste; and

c. With the in alled equipment incapable of meeting ecification 3.11.3 or clared inoperable, restore the equipmen to OPERABLE status or rovide for contract capability to process wastes as necessary to satisfy all applicable transportation a disposal require, nts. l l

CATAWBA - UNITS 1 & 2 3/4 11-18 Amendment No. 48 (Unit'1)

Amendment No. 1 (Unit 2)

m s RADIOACTIVE EFFLUENT J

3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR 0 ERATION s ,

3.11.4 The annual (calend year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases f radioactivity and to radiation from uranium fuel cycle sources shall be limit d to less than or equal to 25 rems to the whole body or any organ, except the thyroid, which shall be limi ed to less than or equal to 75 mrems. ,

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release f radioactive materials in liquid or gaseous effl ents exceeding t ice the limits of Specifi-cation 3.11.1.2a., 3.11.1. b., 3.11.2.2a. 3.11.2.?b., 3.11.2.3a.,

or 3.11.2.3b., calculations shall be mad including direct radiation contributions from the units and from o side storage tanks to determine whether the above imits of ecification 3.11.4 have been exceeded. If such is the cas prepar and submit to the Commission within 30 days, pursuant to Sp cific ion 6.9.2, a Special Report that defines the corrective act on be taken to reduce subsequent releases to prevent recurrence o e ceeding the above limits and includes the schedule for achievi conformance with the above limits. This 4ecial Report, as fined .in 10 CFR 20.405c, shall include an analysis that estimat s he radiation exposure (dose) to a MEMBER OF THE PUBLIC from ura um fuel cycle soun.es, including all effluent pathways and dire rad ation, for the calendar year that includes the release (s) vered this report. It shall also describe levels of radiation nd conce trations of radioactive material involved, and the cause of e exposure levels or concentrations. If the estimated dose (s) excee s the above imits, and if the release condition resulting in vio ation of 40 C . Part 190 has not already been corrected, the Speci Report shall - clude a request for a variance in.accordance v' h the provisions f 40 CFR Part 190.

Submittal of the report is considered a tim ly request, and a variance is granted until staff ction on the request is complete.

b. The provisions of Spe ification 3.0.3 are not pplicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose c tributions' from liquid and gas ous effluents shall be determir.ed in acc dance with Specifications 4.11.1 2, 4.11.2.2, and 4.11.2.3, and in accordanc with the methodology and paramet s in the ODCM.

4.11.4.2 Cumulative dos contributions from direct radiation rom the units and from radwaste stora tanks shall be determined in accordan e wi.th the methodology and parame rs in the ODCM. This requirement is ap icable only under conditions set f rth-in ACTION.a. of Specification 3.11.4.

RE~L0cATEy 71 VTAE cMFTsR. I6 CATAWBA - UNITS &2 3/4 11-i9 Amendment No. 48 Unit 1)

Amendment No. 41 ( nit 2)

4'

$ 3/4.12 RADIOLOGICAL VIRONMENTAL MONITORING 3/4.12.1 MONITORING PR RAM LIMITING CONDITION FOR OP ATION , .

s l 3.12.1 TheRadiologicalEn ronmental Monitoring Program- all?be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

t

!- ACTION:

1 i a. With tt.e Radiological E ironmental Monito ng Program not being

conducted-as specified _i Table 3.12-1, pr pare and submit to the l

Commission, in the Annual Radiological En ironmental Operating Report

required by Specification .9.1.6, a des ription of the rer.hons.for 7

not conducting the program- s required nd the plans for preventing a recurrence.

i b. With the level of radioactivi as t result of plant effluents in i an environmental sampling medi at specified location exceeding j the reporting levels of Table 3 12- when averaged over any calendar quarter, prepare and submit to t e Commission within'30 days, pursuant to Specification 6.9.2, a Specia eport that identifies the-cause(s) +

for exceeding the limit (s) and d nes.the corrective actions to be

taken to reduce radioactive-effl ts so that the potential annual 1

dose

to a MEMBER OF THE PUBLIC is ess than the calendar year: limits l

of Specification 3.11.1.2, 3.1 .2.2, or 3.11.2.3. When more.than one

~

of the radionuclides in Table .12-2. re detected in the sampling l, medium, this report shall be ubmitte if:

i concentration (1) concentration (2) + . . . > 1. 0 ji reportinglevel(1}*'reportinglev&l(2)-

When radionuclides other than those in Tab e 3.12-2 are det'ected and are the result of plant effluents, this rep rt shall be submitted'if the potential annual d e* to A MEMBER OF T -PUBLIC:from all radio-nuclides'is equal to . greater than the cal dar year limits of Specification 3.11.1. , 3.11.2.2, or 3.11.2.3. This report is not-

required if the meas red-level of radioactivit was<not the' result'of 4 plant effluents; ho4 ver, in such an event, the condition shall.be

reported and descr bed in the-Annual Radiologica Environmental

, Operating Report quired by Specification 6.9.1. . ,

The methodology and par ters used to estimate the potentia annual dose _to a MEMBER OF THE PUBLIC hall be indicated in this report.-

l-

R.FLOCATE0 70 i Ps& cHerat (6 I

. CATAWBA - UNITS &2 -3/4 12-1 e

) .

! RADIOLOGICAL ENVIRO ENTA'. MONITORING LIMITING CONDITION FO OPERATION ,

ACTION (Continued) f

c. With milk or fre h leafy vegetation samples unavail le from one or more of the sampi locations required by Table 3.1 1, identify specific location for obtaining replacement samp s and add them

' within 30 days to e Radiological Environmental nitoring Program i

given in the ODCM. The specific locations from hich samples were i unavailable may then e deleted from the monit ing program. Pursuant-

+ to Specification 6.14 submit in the next Semi nnual: Radioactive.

Effluent Release Repor documentation for a e ange in the 00CM including j a revised figure (s) and table for the ODCM r flecting the new loca-j tion (s) with supporting 'nformation identif ing the cause of the l

unavailability of samples and justifying _t e' selection of.the new' i

location (s) for obtaining amp ks.

d. The provisions of Specifica ion 3.0.3 a not applicable.

SURVEILLANCE REQUIREMENTS , ,

4.12.1 The radiological environmental moni ring samples-shall be collected i pursuant to Table 3.12-1 from the specific cations given in the table and figure (s) in the ODCM, and shall be analyz ursuant to the requirements of

- Table 3.12-1 and the detection capabiliti r uired by Table 4.12-1.

4 4

4 J

1 kE LOCATT9 70 TT&/L C4M/TGYL I6 l

4 CATAWBA - UNITS :&'2 3/4 12-2 Amendment Noe48 nit 1)-

' Amendment No.41 ( it 2)

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

d TABLE 3.12-1 *

.n. ,

T. RADIOLOGICAL' ENVIRONMENTAL MONITORING PROGRAM

g; .

NUMBER Of E' REPRESENTATIVE

'Z EXPOSURE PATHWAY- SAMPLES AND ' SAMPLING AND TYPE AND FREQUENCY III OF ANALYSIS

{ AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION FREQUENCY ,

Direct Radiation I2I : Forty routine monitoring stations Quarterly.

'.""'- Gamma dose quarterly.

either with two or more dosimeters-or with'one' instrument for measuring and recording dose -

rate continuously, placed as g 110ws:.

' oh

~

lAn inner ~of. stations, one.in w . Jeach meteoro I sector in the 7

g .y g general area of t

~

E BOUNDARY. <

T- An outer ring of stations, o _.* - i

" each meteorological sector.in-

--the.6- to 8-km range:from;the .

site; and~

~

' The balance of the statio l e

'N , -be placed'in special erest

" -areas such as ' ation centers, ,

nearby re nces, schools,'and

.in o r.'two areas ~to serv 6 as trol stations. .i

' {

I .. -

e t

-f

TABLE 3.12-1 (Continued) h -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E

2" NUMBEN OF REPRESENTATIVE SAMPLES AND SAMPLING AND TYPE AND FREQUENCY E EXPOSURE PAlllWAY I) OF ANALYSIS

~

AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION FREQUENCY m

~ ' Airborne adioiodine and Samples from five locations. Continuous sampler oper- Radioiodine Cannister:

e. 1-131 analysis w y.

m ticulates ation with sample collec-tion weekly, or more Three samples from close frequently if required by to the three SITE BOUNDARY dust loading. Par ate Sampler:

'ocations, in different ross beta radioactivity 7'D se rs, of the liighest analysis following calcu .d annual average filter change-(3) and h ground _ lev D/Q; camma isotopic analysis U) w 1

8 y of composite (by One sample from the location) quarterly.

g

'?

Ofn vicinity of a comununity

=having the highest calcu-g lated annual average gr -

o level D/Q; and One sampi rom a control 2 loca , as for example 15 to sa distant and in the least prevalent wind direction.

3. Waterb e ic analysis I4)

a. Surface Ib) One sample upstream. Composite sample over Gaassa is 1-month period.(6) y. o e One sample downstream. _ ,

Samples from one or two sources Quarterly. Gamma isotopicI4) and

b. Ground tritium analysis quarterly.

only if likely to be affected .

m

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

TABLE 3.12-1 (Continued)

$. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ai

- . NUMBER OF REPRESENTATIVE .

E EXPOSURE PATHWtY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE . SAMPLE LOCATIONS ( ) COLLECTION FREQUENCY OF ANALYSIS

]

. ~ 3. Waterborne.(Continued)

. e.

.m .c. rinking One sample of each of one to Composite sample over I-131 analysis on three of the nearest 2-wek priodIb) when C *PosRe Wn dose

.A water' supplies'that could be I-131 analysis:is per- calculate r th con-

-3 : affected by its discharge. formed; monthly com- "P 'I "* #

I ED posite otherwise. *l'" th*" 1 "#'"

g One s locad on.

e from a control per . year (8), Composite for gross beta and gamma

'-R: isotopic analyses I4)

- monthly. Composite for

-]

. C7- tritium analysir' quarterly.

C. ..

m .. . .

d. ' Sediment. One sample from downstream area Semiann 1. . Gamma isotopic analysis (4)-

. 'O ' f rom ' with existing or potential semiannually.

. Shoreline. recreatlonal'value.

'4. Ingestion ,

a. Milk Samp from milking animals . Semimonthly when Gamma 1 icI4)'and .

~

hree locations within'5 km animals are on pasture; I-131 analys emi-distance having the highest' monthly at.Other times. monti:1y d en anima dose potential.-- If there are .are on pasture; monthly.

none, then one sample'from at other times.

milking animals'in each of three areas between-5 to 8 km distant-where doses are calcu-latedt.obe.grgerthan 1 arem per yr One-sample from milking animals-at a

. control locat.$on'15 to 30 km distant and~in the least preva--

lent wind direction.

A w -

p f -

v .*v45' ,ra.,

I' TABLE 3.12-1 (Continued) 9 W RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM 6

2" NUMBER OF REPRESENTATIVE E EXPOSURE PA1HWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY SAMPLE LOCATIONS I) COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE _

]

4. Ingestion (Continued)

Fish and One sample each of a predatory Sample in season, or Gasvaa isotopic a ysis I4) nverte- species, a bottom feeder and a semiannually if they on edible po ons.

br forage species in vicinity of are not seasonal, plant discharge area.

e sample each of a predatory spe ' s,.a bottom feeder and a forage les in areas not t' influenced lant discharge.

c. Food One sample of each p ' ipal At tim harvest I9) . Gamma isotopic analyses I4)

A Products class of food products'fr on edible portion.

any area that is irrigated by water in which'11guld plant wastes have been b discharged.

k% Samples of t e different Monthly, when available.

Gamma isotopicI4) and I-131 analysis.

'4 kinds o oad leaf vegeta-tio rown nearest each of h o different offsite loca-tions of highest predicted annual average ground level s D/Q if milk sampling is not e performed.

One sample of each of the Monthly, when Gamma isotopicI4I'and I-131 similar broad leaf vegeta- available. analysis.

tion grown 15 to 30 km dis-tant in the least prevalent wind direction if milk sam-pling is not performed.

s

_ _ _ _ = - . - - _ . _ - _ _ _ - . - _ - _ . _

l l

4 J

TABLE 3.12-1 (Continued)

TABLE NOTATIONS

.(1) Specific parameters o ' distance and direction sector rom the centerline of the station, and ad itional description where per nent, shall be pro-vided for each and ever sample location in Table 3. 2-1 in a table and figure (s) in the 00CM. fer to NUREG-0133, " Prep ation of' Radiological Effluent Technical Specif cations for Nuclear Powe Plants," October 1978,

- and to Radiological Assess ent Branch Technical P sition, Revision 1, November 1979. Deviations re permitted from th required sampling schedule if specimens are un btainable due to c rcumstances such as hazardous conditions,.seasona unavailability, nd malfunction of auto-matic sampling equipment. If pecimens are_u. bt'ainable due to sampling equipment malfunction, effort s all be made complete corrective action

prior to the end of the next s ling-period All deviations from the-

sampling schedule shall be docum ted in th Annual Radiological Environ-mental Operating Report pursuant Specif cation-6.9 ' 6. It-is

recognized that, at times, it may t be' ssible or practicable-to con-

tinue to obtain samples of the medi of oice at the most desired location or time. In these instance s table alternative media and locations may be chosen for the parti u ar pathway in question and appro-priate substitutions made within 30 da s in the- Radiological- Environmental' l

- Monitoring Program. In lieu of any L'c nsee Event-Report required by-Specification 6.9.1 and pursuant to ec fication 6.9.1.7, identify the.

cause of the unavailability of samp s fo that pathway and identify. the -

j new location (s) for obtaining repl ement amples in the next Semiannual

Radioactive Effluent Release Repor and al -include in the report a-

revised figure (s) and table for t e ODCM:re ecting the new location (s).

(2) One or more instruments, such a a pressurize ion chamber, for measuring and recording dose rate contin usly may be us d in place of, or in addi-tion to, integrating dosimete . For_the purpo es of this table, a thermoluminascent dosimeter LD) is considered o be one phosphor; two 4

or more phosphors in a pack are considered as t o or more dosimeters.

Film badges shall not be us d as dosimeters-for me suring direct radiation.

(The 40 stations is not an absolute number. The n ber of direct radiation monitoring stations muy b reduced according to geo aphical. limitations;

, e.g., at an ocean site, me sectors will be over wa r so that the number of dosimeters may be re ced accordingly. The freque y of-analysis or i reacout for TLD system will depend upon the character tics of the speci-

,- fic system used and sh uld be selected to obtain optimu dose;.information

within minimal fading ).

(3) Airborne particulat sample filters shall be analyzed for ross beta radioactivity 24 h rs or more after sampling.to-allow for adon and thoron daughter d ey. If gross beta activity in-air-partic late samples is greater than -times the yearly mean of control samples,- amma isotopic analysi shall be performed'on the individual samples w ce raL a CATAWBA --UNIT 1&2 3/4 12-7 \

-TABLE-3.12-1 (Continued)- -

TABLE NOTATIONS-(Continued)-

(4) Gamma isotopic an lysis means the_ identification and uantification of gamma-emitting rad'onuclides that may_-be attributabl to the effluents from the' facility.-

(5) The " upstream sample" shall be-taken at a distanc beyond significant

influence of the disch rge. The " downstream" sa le shall be taken in an:

area beyond but near th mixing zone.1 " Upstream samples in an estuary must be taken far enough upstream to be beyond he plant influence.~ Salt __

water shall be sampled on when the-receising ater is utilized for-recreational activities.

(6) A composite sample is one in which the rate t which the liquid sampled is uniform and in which the- thod of sampi ng employed results inLa specimen that is representativ of the;ti averaged _ concentration at;the location being sampled. - In thi program aposite; sample _ aliquots shall_

be collected at time intervals t at are v ry short (e.g. , hourly) relative-to the compositing period (e.g. . . nthly lin_ order _to; assure obtaining a representative sample.

4 (7) Groundwater samples shall be taken this source is tappedL for crinking or irrigation purposes in areas wher the hydraulic gradient nr recharge properties are suitable for contami

- t on. R (8) The dose shall' be calculated for t e max num organ.and age group, using the methodology and parameterstin he-00 .

(9) If harvest occurs more than'one a year, sa ling:shall be performed-during each-discrete harvest.- f harvest oc urs continuouslyi--samplino-shall be monthly. Attention s all,be paid to including-samples of tuberous and root food produc s.

FeAWcw x ;g 4

CATAWBA---UNITS &2 3/4,12-8 ,

y if

TABLE 3.12-2 g

.y REPORTING LEVEL 5'FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES c5

" REPORilNG LEVELS WATER AIRBORNE PARTICULATE FI5il MILK FOOD PRODUCTS

~ iNALYSIS (pCi/2) OR GASES (pCi/m3 ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) e-li-3 20,000 fI)

Hn-54 1, 30,000 re-59 400 - 10,000 -,

dj b Co-58 1,000 30,000 9 b

w 1 Co-60 300- 10,000 w

b 300 20 A

'? Zn-65 -D w

Z r-Nb-95 400 1-131 2. 0.9 3 100.N Cs-134 30 10 .

1,000 .. \ 1,000 TP

'Cs-137 50 20 2,000- 70 2,'0,00

\ l Ba-La- 140 - 20 300 II)for drin ' g water samples. This is 40 CFR Part 141 value. If no drinking water pattway exists, a val'he

of 3 , 'O pCi/E may be used.

l

TABLE 4.12-1 II) I2}

DEiECTION CAPABILITIES FOR ENVIRONMENTAL SAMP:.E ANALYSIS LOWER LIMIT OF DEIECTION (LU )I )

~

FISH MILK FOOD PRODUCTS SEDILIENT M W/.IER AIRBORNE PARTICULATE

-OR GASES (pCi/m3 ) (pCl/kg, wet) (pfi/1) (pCl/kg, wet) (pCf /kg, dry)

ANALYSIS -(pCi/t)-

c.

-" Gro eta 4 0.01 g ,

?.

! 11- 3 00*

Hn-54 15 130 fe-59 30= 260 ~7 d 130 P

$ .Co-58,60 15

'Zn-65 30 .- 260 g Z -Nb-95 '15 1-131 - .1 I4)" 0.07 60

'15 0.05 1.30 15 60 150-Cs-134

0. 150- 18 180 Cs-137 . - 18 15 Ba-La-140 15~ ,

If no drinking water pat exists,.a value of 3000 pCi/t may be used.

4

' '~

'._.i..... . . _ _

C-

4 ;

[-

i i-l TABLE 4.12-1 (Continued) +

[ TABLE _KOTATIONS i (1) This list does no mean that only these nuclides a e-to be considered.

Other peaks that a identifiable, together with-- ose of-the above_ ,

nuclides, shall als be analyzed and reported in he Annual Radiological '

j Environmental Operat g Report pursuant _to Spec ication 6.9.1.6.-_ .

i (2) Required detection cap bilities for thermolumi escent dosimeters used i for environmental measu ements shall be in ac ordance with the recommenda-

] tions of Regulatory Gui 4.13.

! (3) The LLD is defined, for p ' poses of these ecifications, as the' smallest

, concentrations of radioact e material'in sample that will: yield a net

! count,'above system backgro d, that will be detected with 95% probability with only 5% probability of. 1sely conc uding .that a blank observation-represents a "real" signal. '

! For a particular measurement sy tem, ich may. include radiochemical ,

, separation:

4.66 s b '

l LLD =

E -

V -

2.22. - Y exp(- Aat) 4 Where:

i~

LLD = the "a priori" lower lim t of d tection (picoCuries per unit mass or volume),

s b

= the standard deviatic of the back round counting _ rate or-of the

counting rate of a bl nk sample.as ppropriate (counts.per minute), ,

l E = the counting effici ncy (counts per s_ integration),

V = the sample size ( nits of mass-or vol ),

2.22 = the number of d integrations per min ~ute er picocurie, 4; Y = the fractional radiochemical yield, when a licable, A = the radioact've decay constant for the parti ular radionuclide (sec.1),an !

At = the elaps time between environmental . collect n, or'end of the.sampi collection period, and time of count g (sec). l:

Typical values of_E, V, Y and at shculo be used in the c Icilation.-

M L OCJYl e D '7c i

WM CH/4MR / (,

CATAWBA - UN S1&2 3/4 12-11' Amendment No. 37 (Unit 1)-

\

[ Amendment No. 29 (Unit 2) a a -

-~ .- . - . .-- . .

i f

I TABLE 4.12-1 (Continued)

! TABLE NOTATIONS (Continued)

It should be recogn zed thatlthe LLO is defined as an a priori--(before the -

i fact) limit represen ing the capability of a m asurement system and not as-an a posteriori (afte the fact) limit for a rticular measurement.

AnaTyses shall be perf reed in such a manner hat the stated LLDs-will be achieved under routine onditions. 0ccasion ly background fluctuations, i

unavoidable small sample sizes, the presenc of interfering nuclides, or other uncontrollable circ mstances may rend r these LLDs unachievable.

i

In such cases, the contrib ting factors sh 11 be identified and described in the Annual Radiological nvironmental erating Report pursuant to j Specification 6.9.1.6.

(4) LLD for drinking water samples If no inking water-pathway exists, the 1

LLD of gamma isotopic analysi) ay be ed.

l 4

i l i

4 i

i a

WM CHAfu jg CATAWBA - UNITS' &2 3/4 12-12

4 f RADIOLOGICAL ENVIRO NTAL MONITORING ,

3 3/4.12.2 LAND USE CENS LIMITING CONDITION FOR OP ATION ,

!' 3.12.2 'A Land Use Census s 11 be conducted and shall-i ntify within a distance of 8 km (5 miles) the locati in each of the 16 meteoro ogical sectors of the nearest milk animal, the near st residence, and the nea est garden

of greater j than 50 m2 (500 fts) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION: ,

l a. With a Land Use Census i ntifying a lo tion (s) that yields a j calculated dose or dose c itment-gre er than the-valuts currently

! being calculated in Specif ation 4.11 2.3, identify the tcw loca-I tion (s) in the next Semiann 1 Radioa tive Effluent Release. Report j pursuant to Specification 6. 1.7.

b. .With a Land Use Census identi ing . location (s)'that yields a i calculated dose or dose commi n _via

( the same exposure pathway) 20% greater than at a location m which samples are currently.

being obtained in accordance wit Specification 3.12.1, add the new-

! location (s) within 30 days to t e adiological Environmental Monitoring i Program given in the 00CM. ~Th sa ling location (s),. excluding the-

control station location, hav g th . lowest calculated dose or dose j commitment (s), via the same- posure pathway, may be deleted from this monitoring program after Oc ber 31 o the year in which this Land Use i Census was conducted. Purs ant to Spe ification 6.14,_ submit in the L next Semiannual Radioactiv Effluent R ease. Report documentation for a change in the ODCM inci ding a revise figure (s) and table (s) for the ODCH reflecting the w location (s), ith information supporting the change 1n the se.np1 g locations.

l

!- c. The provisiens of Spec fication 3.0.3 are n t app 1_icable.

l

Broad leaf vegetation samp ing of at least three differe kin'dc of vegetation s may be performed.at the S E BOUNDARY in each of two diff ent direction sectors with the highest redicted D/Qs in-lieuLof the. gar n census. Speci-i fications for broad leaf vegetation sampling in Table'3.12 .4.c. shall be' followed, including ana ysis of control samples.

ORND 7"(>

Psd c H+f7s7C /6 .

4 CATAWBA - UNITS 1 & 2 3/4-12-13 Amendment-No. 48- Unit 1)

Amendment No. 41 ( nit 2)

~ . ,,

i I

l RADIOLOGICAL ENVIRONMEN L MONITORING SURVEILLANCEREQUIREMENTS\ ,

~

l' 4,12.I The Land Use Census ' hall be conducted during t growing-season at

least once per 12 months usi that information that wi i provide the be'st' results, such as by a door-to door survey, aerial surv y, or by consulting-i local agriculture authorities. -The results of the La d Use Census shall-be included in the Annual Radiolo ical-Environmental Op rcting Report pursuant to

~

Specification 6.9.1.6.

i l

l /

i l 3

.I 4

5

?

2 i

i 1

CATAWBA -- ITS 1 L 2 3/4 12-14

n i

RADIOLOGICAL ENVIRONMENT L MONITORING i

3/4.12.3 INTERLABORATORY MPARISON PROGRAM

! LIMITING CONDITION FOR OPERA ION- /

\

3.12.3 Analyses shall be perf med on all redioacti e materials, supplied as part of an Interlaboratory Comp rison Program that as been approved by the Commission, that correspond to s spies required by able 3.-12-1.-

1

APPLICABILITY: At all times.

ACTION:

a. With analyses not being pe ormed a required above, report the corrective actions taken to revent a recurrence to the Commission

in the Annual Radiological E viron ental Operating Report pursuant to Specification 6.9.1.6.

b. The provisions of Specificatio .0.3 are not applicable.

SURVEILLANCE REQUIREMENTS I \

4.12.3 The Interlaboratory Comparison Progr m'shall be described in the ODCM.

A summary of the results obtained as art of he above required Interlaboratory Comparison Program shall be included n the An ual Radiological Environmental Operating Report pursuant to Specifi ation 6.9. 6.

i -

i i

i 4

i t

MM N FcM cH+frst f(o 9

CATAWBA-- UN S1&2 3/4 12-15 Amendment No. 48 (Unit 1)

Amendment No. 41 Unit 2)

INSTRUMENTATf0N BASES 3/4.3.3.9 LOOSE-PART DETECTION SYSTEM

$L6CETY $

gg g4 [G The OPERABAILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

_10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioact . uid effluent instrumentation is prov o monitor and control, as applicab e, releases of radioact erials in liquid effluents during actual or potent leases quid effluents. The Alarm / Trip Setpoints for these instru -

I be calculated and adjusted in accordance with the methodolo parameters in DCM to ensure that the alarm / trip will occur to exceeding the limits of 1 art 20. The OPERABILITY an of this instrumentation is consistent with t frements

. of Gen esign Criteria 60, 63 and 6,4 of Appendix A to 10 CFR Part 5 .

/

40 cTPLoi I VG f

3/4.3.3.-It -RA&IGACHVE GASCOUS [ITLUENT MONITORING INSTRUMENTATION e q N Hve-The radicactive gasecu; cffhent-instrumentation is provided to monitor and cc..;-el, ;; sp;l b e h , th: rebate

. < edicecth _=terish " g::::::

efflecnts during actual or p;tential r:10:s:s of g:s :us effluents. Th;

- Aler-/ Trip Cetpcints for these instruments shall bc calculated and c.djusted in

- acce*dence "ith th: ::thedehgy :nd p;r: meter. in the OOC!i to en5wre that the

- ci;rm/ trip iil cccur prior to exceeding the limits of 10 CIR Part 20. This 4 trument:t hr :13 inc kdcs provisions-for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLOUP SYSTEM. wi. vf thi Insiiumentation i. wwn .icni -ith

~... .m...a..The-....m GPERASILIT'.l n..,m os. o,. onu n . . : - ., n.

.se,w . :, s a. -ww,

,o n vn ., , onu v,~s vi nyeuw x m n wu

- -10 CF9 Part 50. The sen:ithity of c.ny acbic gas activity monitcr us:d tc -

chou creplinne with the gaseem effkent ra kes: requirements of Specifica-tica 2.11.2.2 shall be such-that concentrations as le es 1 x 10-C mci /cc are---

mcasurable.

CATAWBA - UNITS 1 & 2 B 3/4 3-6 Amendment No. (Unit 1)

Amendment No./ (Unit 2) 1

)

.D

d INSTRUMENTATION BASES i Il 3/4.3.3.-te BORON DILUTION MITIGATION SYSTEM The operability of the Boron Dilution Mitigation System ensures that pro-tection against a loss of shutdown margin from a boron dilution event is pre-sent. This system uses two source range detectors to monitor the subcritical

multiplication of the reactor core. An alarm setpoint is continually calcu-lated as 4 times the lowest measured count rate, including compensation for background and the statistical variation in the count rate. Once the alarm setpoint is exceeded, each train of the Boron Oilution Mitigation System will automatically shut off both Reactor Makeup Water Pumps, isolate flow to the charging pumps from the Volume Control Tank, and align the suction of the charging pumps to highly borated wattr from the RWST. These actions automa-tically isolats the potential sources of diluted water and allow injection of highly borated water into the Reactor Coolant System.

4 In the event that the Boron Dilution Mitigation System is inoperable or not operating, the Source Range Neutron Flux Monitors may be used to provide protection against a loss of shutdown margin from a boron dilution event. If the Source Range Neutron Flux Monitors are used to monitor the subcritical multiplication of the reactor core, the alarm setpoint must be calibrated and periodically checked to ensure that it is less than or equal to one-half decade i above the steady-state count rate. In addition, the flow from the Reactor Make-up Water Pumps must be verified as below specified limits. These actions ensure that adequate time is available for the operator to recognize and terminate a dilution event prior to a loss of shutdown margin.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that-the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from . xcessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.

1 4

CATAWBA - UNITS 1 & 2 B 3/4 3-7 Amendment No. (Unit 1)

Amendment No. (Unit 2)

RELCC/YTS1 70 3/4.11 RADIOACTIVE FFLUENTS BASES \ \

I 3/4.11.1 LIQUID EFFLUEN . .

3/4.11.1.1 CONCENTR;TJN, This specification is p ovided to ensure that the oncentration of radio-active materials released in liquid waste effluents to NRESTRICTED AREAS will be less than the :.oncentratio levels specified in 10 FR Part 20, Appendix B.

Table II, Column 2. This limi ation provides additi al assurance that the levels of radioactive materials in bodies of water i UNRESTRICTED AREAS will

! result in exposures within: (1) the Section II.A sign objectives of

' Appendix I, 10 CFR Part 50, to a EMBER OF THE PUB IC, and (2) the limits of 10 CFR 20.106(e) to the popula ion. The conce tration limit for dissolved or entrained noble gases is based on the assum tion that Xe-135 is the controlling radioisotope and its MP in air (su mersion) was converted to an equivalent concentration in wa er using 1e methods described in Inter-national Commission on Radiological otectio (ICRP) Publication 2.

This specification applies to the rele e of radioactive materials in liquid effluents from all units at the it .

l l The required detection capabilities or radioactive materials in liquid

waste samples are tabulated in terms of lower limits of detection (LLDs).

Detailed discussion of the LLD, and oth r etection limits can be found in HASL Procedures Manual, HASL-300 (revised a nual ), Currie, L. A. , " Limits for Qualitative Detection ano Quant.itativ Date ination - Application to Radio-chemistry," Annal. Chem.' 40, 586-93 968), a d Hartwell, J. K., " Detection Limits for Racioanalytical Counting echnique " Atlantic Richfield Hanford Company Report ARH-SA-215 (June 19- ).

3/4.11.1.2 DOSE This specification is pro ded to implement e requirements of Sec-tions II.A, III.A and IV.A of ppendix I, 10 CFR P rt 50, The Limiting Condition for Operation implements the utdes set forth in Se tion II. A of Appendix I.

The ACTION statements provi the required operating flexibility and at the same time implement the gui es set forth in Section .A of Appendix I to assure that the releases of radio ctive material in liquid e luents to UNRESTRICTED AREAS will be kept "as lo as is reasonably achievable." Also, for fresh water sites with drinking wate supplies that can be potentia ly affected by plant operations, there is re sonable assurance that the opera ion of the facility-will not result in rad nuclide concentrations in the fi. shed drinking water that are in excess of he requirements of 40 CFR Part 141. The dose calcula-tion methodology and arameters in the ODCM implement the equirements in Sec-tion III.A of Appen x I that conformance with the guides o Appendix I be shown by calculati al procedures based on models and data, uch that the actual exposure of a MEMB R OF THE PUBLIC through appropriate pathw s is unlikely to

=

be substantially nderestimated. The equations specified in e ODCM for calculating the oses due to the actual release rates of radio ctive materials in liquid efflu nts are consistent with the methodology provide in Regulatory Guide 1.109, " alculation of Annual Doses to Man from Routine Re eases of CATAWBA - UN TS 1 & 2 83/411-1

bl-0GYTM TD RADIOACTIVE EFFLUENTS BASES I 1

DOSE (Continued)

Reactor Effluents for the P pose of Evaluating Complia e with 10 CFR Part 50, Appendix I," Revision 1, Oct er 1977 and Regulatory Gu de 1.113, " Estimating Aquatic Dispersion of Effluen s from Accidental ar. Ao tine Reactor Releases for the Purpose of Implementin Appendix I," April 19 .

This specification applies to the release of r ioactive materials in liquid effluents from each unit t the site. When hared Radwaste Treatment Systems are used by more than one unit on a site, he wastes from all units are mixed for shared treatment; b such mixing, t e effluent releases cannot accurately be ascribed to a specif unit. An e imate should be made of the contributions from each unit based n input con tions, e.g., flow rates and radioactivity concentrations, or, if not practi able, the treated effluent releases may be allocated equally to ach of t e radioactive waste producing units sharing the Radwaste Treatment stem. ror determining conformance to LCOs, these allocations from shared Radwa e Treatment Systems are to be added to the releases specifically atte but to each unit to obtain the total releases per unit.

3/4.11.1.I LIOUID RADWASTE TREATMENT SYS M TheOPERABILITYoftheLiquidRadw!teTreatmentSystemensuresthatthis system will be available for use whenev,r 11 uid effluents reg 're treatment prior to release to the environment. he re uirement that the approprihte pnrtions of this system be used when pecifie provides assurance that the releases of radioactive materials in iquid e luents will be kept "as low as is reasonably achievable". This sp .ification mplements the reauirements of 10 CFR Part 50.36a, General Design riterion 60 f Appendix A to 10 CFR Part 50 and the design objective given in ection II.0 o Appendix I to 10 CFR Part 50.

The specified limits governing th use of appropr' ate portions of the Liquid Radwaste Treatment System were s ecified as a sui ble fraction of the dose design objectives set forth in ection II. A of App dix I, 10 CFR Part 50, for liquid effluents.

This specification appli s to the release of ra 'oactive materials in

' liquid effluents from each u it at the site. When sh ed Radwaste Treatment Systems are used by more th n one unit on a site, the astes from all units are mixed for shared trea nt; by such mixing, the eft uent releases cannot accurately be ascribed to specific unit. An estimate hould be made of the t.ontributions from each u it based on input conditions, g,, flov ,ates and

.?dioactivity concentrat ons, or, if not practicable, the treated effluent releases may be allocat d equally to each of the radioacti e waste producing units sharing the Radw ste Treatment System. For determini g conformance to LCOs, these alloca ons from shared Radwaste Treatment S tems are to be added to the release specifically attributed to each unit t obtain the total releases per unit.

CATAWBA - UNITS 1 & 2 B 3/4 11-2 J A

3 k,O RADIOACTIVE EFFLUENTS BASES u qw u ef+LusNTS 37C.f+,il . I'p' 11.1. LIQUID 70T6IFP TANKS

. I The tanks included in this specification are til those outdoor radwaste tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of rrdioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix.B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.1.5 CHEMICAL TREATMENT PONDS The inventory limits of the chemical treatment ponds (CTP) are based on limit the consequences of an uncontrolled release of the plnd inventory The expre ion in Specification 3.11.1.5 assumes the pond inventory is formly mixed, that e pond is located in an uncontrolled area as defined i 0 CFR Part 20, and t the concentration limit in Note 1 to Appendix B 10 CFR Part 20 applies.

The batch limits o he resin / water slurry transferr to the CTP assure that radioactive material nsferred to the CTP are " low is reasonably.

acnievable" in accordance wit 0 CFR 50.36a. The ression in Specifica-tion 4.11.1.5 assures no batch w 1 be.transferr to the CTP unless the sum of the ratios of the-activity of the r ionuclide o their respective concentra-tion limitation is less than the ratio ft 10 CFR Part 50, Appendix I, Section II. A, total body dose level to t 10 CFR 20.105(a). whole body dose limitation, or that:

C i 3 mrem /vr 500 mrem /yr

.006 c)

Where:

oactive resin / water slurry concentration for ra 'onuclide c) = r j" entering the UNRESTRICTED AREA CTP, in microcuries '

milliliter; and-C3 = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", in microcuries/ milliliter.

Pet < ct+t/T5xt I4 I

CATAWBA - UNITS 1 & 2 8 3/4 li t

R6LtCATF0 Tt RADI0 ACTIVE EFFLUENT N Ib BASES ,

CHEMICAL TREATMENT PONDS Continued)

The filter /deminerali. rs using powdered resin and t blowdown d6 min-eralizer are backwashed or luiced to a holding tank. T tank will be agitated to obtain a representative s mple of the resin inventory in the tank. A known weight of the wet, drained re in (moisture content appr ximately 55 to 60%, bulk density of R out 58 p'ounds pe cubic foot) will then b counted. The concentra-tion of the resin slurry to be umped to the chemical treatment ponds will then be determined by the formula:

9 R C

J"J v T

Where; Q = concentration of radio tive m erials in wet, drained resin d for radionuclide "j", e. ludi tritium, dissolved or entrained noble gases, and radionu lid with less than an 8-day half-life.

The analysis shall includ least Ce-144, Cs-134, Cs-137 Co-58 and Co-60, in micro ies/ gram. Estimates of the Sr-89 and Sr-90 batch concentrat r ;nall be included based on the most recent monthly compe e analysis (within 3 months);

WR

total weight of resin i the torage tank in grams (determined from chemistry logs or cedures ; and VT = total volume of resi water mix re in stortge tank to be transferred to the amical trea nent ponds in milliliters. ,

The batch limits provide as rance that acti ity input to the CTP will be minimized, and a means of id tifying radioactf e material in the inventory limitation of Specification 3. .1. 5.

1/4.11.2 CASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification-i provided to ensure that the d se at any time at and beyond the SITE BOUNDARY from gaseous effluents from all nits on the site will be within the annu 1 dose limits of 10 CFR Part 20 t UNRESTR;r.TED AREAS.

The anr.ual dose limits are the doses associa'ed with the c centrations of 10 CFR Part 20, Appen ix 8, Table II, Column 1. These limi s prov Ne resenabla assurance that radio tive material discharged in gaseous ef luents will not result in the expos e of a MEMBER OF THE PUBLIC in an UNRES ICTED AREA, either within or o side the SITE BOUNDARY, to annual average oncentrations exceeding tne limi s specified in Appendix B, Table II of 10 C Part 20 (10 SFR 20.106(b) . For MEMBERS OF THE PUBLIC who may at times e within the SITE BOUNDAR , the occupancy of that MEMBER OF THE PUBLIC wi i usually be sufficiently lo to compensate for any increase in the at$ospheri diffusion CATAWBA - UN! S 1 & 2 B 3/4 11-4

\\

wxwev n RADI0 ACTIVE EFFLUENTS FrM cH& N &

l BASES DOSE RATE (Continued) \

factor above that for the SI BOUNDARY. Examples of c culations for such MEMBERS OF THE PUBLIC, with t appropriate occupancy f ctors, shall be given in the ODCM. The specified re ease rate limits restri t, at all times, the cc-responding gamma and beta do e rates above backgro nd to a MEMBER OF THE PUBLIC at or beyond the SITE B0 ARY to less than o equal to 500 mrems/ year to the whole body or to lest tha or equal to 3000 rems / year to the skin.

1:ase release rate limits also re trict, at all ti es, the corresponding thyroid dose rate above background to a child via he inhalation pathway to 1ess than or equal tv 1500 mrems/ye r.

J This specification applies to t release f radioactive materials in gaseous efflucnts from all units at t site. ,

The required detection capabilitie for radioactive material in gaseous

, waste samples are tabulated in terms of h lower limits of detection (LLDs).

I Detailed discussion of the LLD, and othe etection limits can be found in HASL Procedures Manual, HASL-300 (revise annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative D t rmination - Application to Radio-1 chemistry," Anal. Chem. 40, 586-93 (196 ), nd Hartwell, J.K., " Detection

< Limits for Radioanalytical Counting Te hniq s," Atlantic Richfield Hanford Company Report ARH-SA 215 (June 1975) 3/4.11.2.2 DOSE-NOBLEnNg This specification is provid d to implemen the requirements of Sections II.B. III.A and IV.A of Appendix I, 10 CFR Part O. The Limiting Condition for Operation implements the gu des set forth in ection II.B of Appendix 1.

The ACTION statements provide e required operati g flexibility and at the same time iiiiplement the guide set forth in Sectio IV-A of Apper4ix I to assure that the releases of adioactive material in aseous effluents to UNRESTRICTED AREAS will be ept "as low as is reason bly achievable." The Surveillan:e Requirements lemmt the requirements n Section III.A of-Appendix I that conforman a with the guides of Append I be shown by calcula-tional procedures based models and data such that ti actual exposure of a MEMBER OF THE PUBLIC th ugh appropriate pathways is un ikely to be substantially underestimated. The d e calculation methodology and pa ameters established in the 00CM for calcu ting the doses due to the actual ' lease rates of radioactive noole ga s in gaseous efflucnts are consiste with the methodology provided in Regulat Guide 1.109, " Calculation of Annual . oses to Man from Routine Releases o Reactor Effluents for the Purpose of Ev'luating Compliance with 10 CFR Part , Appendix I," Revision 1, October 1977 a d Regulatory Guide 1.111, " Met, ods for Estimating Atmospheric Transport a Dispersion of Gaseous Effluen in Routine Releases from Light-Water Cooled t eactors,"

Revision 1, Jul 1977. The ODCM equations provided for determ'.ning the air doses at and yond the SITE BOUNDARY are based upon the histor cal average atmospheric nditions. i

~

i CATAWBA UNITS 1 & 2 B 3/4 11-5

\

Rm 09mv m RADI0 ACTIVE EFFlVEN 9 Nd '

BASES ,_, ,

DOSE - NOBLE GASES (Cont ued)

This specification ap. lies to the release of radioac ve materials in j

gaseous effluents from each unit at the site. When shar Radwaste Treat-ment Systems are used by mor than one unit on a site, t e wastes from all units are mixed for shared tr atment; by such mixing; e effluent releases cannot accurately be ascribed o a specific unit. An stimate shoulc be made of the contributions from'each nit based on input c ditions, e.g., flow rates and rartioactivity concent tions, or, if not p acticable, the treated effluent releases may be allocat equally to each f the radioactives waste producing units sharing the Radwa te Treatment Sys em. For determining conformance to LCOs, these allocat ons from share Radwaste TrM tment Systems are to be added to the releases spe ifically at ibuted to er, unit to Mtain j

the total releases per unit.

3/4.11.2.3 OOSE - 100!NE-131, IODINE- J, T ITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM / !

l This specification is provided to i lement the requirements of Sections II.C. III.A, and IV.A of Appendix I, 10 Part 50. The Limiting Conditions for Operation are the guides set forth n etion II.C of Appendix I. The ACTION statements provide the required oper ing flexibility and at the samo a time implement the guides set forth i Secti IV.A of Appendix I to assure that the releases of radioactive mat rials in aseous effluents to UNRESTRICTED AREAS will be kept "as low as is re sonably ac ievable." The 00CM calculational methods specified in the Surveilla ce Requireme ts implement the* requirements in Section III, A of Appendix I th t conformance ith the guides of Appendix !

be shown by calculational proced res based on mo is and data, such that the actual exposure of a MEMBER OF E PUBLIC through ppropriate pathways is unlikely to be substantially u derestimated. The O M calculational methodology and parameters 6 r calculatin the doses due to the actual release rates of the subject materials are consis ent with the methodolog provided in Regulatory Guide 1.109, " Calculation o Annual Doses to Man from Routine Releases of Reactor Effluents for the urpose of Evaluating Comp 1 nce with 10 CFR Part 50, Appendix I," Revision 1, ctober 1977 and Regulatory G de 1.111, " Methods for Estimating Atmospheric T ansport and Dispersion of Gase s Effluents in Routine Releases from Light-kat r-Cooled Reactors," Revision 1, ly 1977. These equa-tions also provide for determining the actual doses based upon the historical average atmospheric c nditions. The release rate specific tions for Iodine-lil, Iodine-133, tritium, and radionuclides in particulate form ith half-lives greater than 8 days are dependent upon the existing radionuc ide pathways to man in the areas a and beyond the SITE BOUNDARY, The pathw s that were examined in the d velopment of the calculations were: (1) in ividual inhala-

' tion of airborne radionuclides, (2) deposition of radionuclide onto green leafy vegetatio with subsequent consurption by man, (3) deposi ion onto grassy-areas where af k animals and meat producing animals graze with c nsumption of the milk and eat by man, and (4) deposition on the ground with s bsequent '

exposure of an. ,

CATAWBA - NITS 1 & 2 B 3/4 11-6

J l

1 RADI0 ACTIVE EFFLUENTS

] BASES pnE 1001NL 131 IODINE 33. TRITIUM. AND RADI0 ACTIVE MAT!RI AL IN j E (Continueo) ,

l This sp eification 8ppi es to the release of radios ive materials in gaseous effinnu fri.T, dach u it at the site. When sha d Radwaste Treatment Systems are used by more than ne unit on a site, the stes from all units are mixed for shared treatment; by such mixing, the of luent releases cannot f

accurately be ascribed to a spe ific unit. An estima e should be made of the contributions from each unit bas d on input conditio s, e.g., flor *ates and radioactivity concentrations, or, if not practicabl , the treated effluent 4

releases may be allocated equally o each of the r ioactive waste producing units' sharing the Radwaste Treatme System. For etermining conformance to LCOs, these allocations from shared adwaste Tre ment Systems are to be added to the releases specifically attribu d to each nit to obtain the total releases per unit.

3/4.11.2.4 GASEOUS RADWASTE TREATMENT ~YSTEM The OPERADILITY of the WASTE GAS H0 - UP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEN ensures that the systems 11 be available for use whenever gaseous effluents require treatment prior o release to the environment. The requirement that the appropriate portions o these systems be used, when specified, provides reasonable assurance that the r le es of radioactive materials in gaseous effluents will be kept "as low s is reasonably achievable." This specification implements the requireme s of 0 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR rt 50, nd the design objectives given

. in Section 11.0 of Appendix I to 10 R Part 5 The specified limits governing the use of appropriate portions of e systems re specified as a suitable fractior of the dose design objecti es set forth in sections II.B and II.C of Appendix I, 10 CFR Part 50, for ga eous effluents This specification applies o the release of dioactive materials in gaseous eff'uents from each uni at the site. When hared Radwaste Treatmeit Systems are Jsed by more than e unit on a site, th wastes from all units are mixed for shared treatmen , by such mixing, the e fluent releases cannot accurately be ascribed to a s ecific unit. An estimat should be made of the contributions from each unit based on input ccnditions, e.g., flow rates and radioactivity concentration , or, if not practicable, t 5 treated effluent releases may be_ allocated qually to each of the radioac<ive waste producing J

units sharing the Radwast Treatment Syst&;r.. For determi ing conformance to LCOs, these allocations f om shared Radwaste Treatment Sys ems are to be added to the releases specifi lly attributed to each unit to obt in the total releases per unit.

SOLDC&T&T) n PtM cm*sx.IG,

.CATAW2A - UNIT 1 & ._ 2 8 3/4 11-7

RADI0 ACTIVE EFFLUENTS BASES U+,n.>.t. M oos alit-wcki%

f/4.11.2 + EXPLOSIVE GAS MIXTURE I

This . specification is provided to ensure that the concent'ation of poten-tially explosive gas mixtures contained in the WASTE GAS HOLDUF tYSTEM is main-tained below the flammability limits of hydrogen and oxygen. (A omatic control features are included in the system to prevent the hydrogen and o.1en concen-trations from reaching these flamability limits. These automatic introl feetures include isolation of the source of hydrogen and/or oxygen, stomatic diversion to recombiners, or injection of dilutants to reduce the coi $ntration below the flammability limits.) Maintaining the concentration of hydi 'en and oxygen below their flammability limits provides assurance that the reh es of-radioactive materials will be controlled in conformance with the requirs nts of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.h GAS STORAGE -TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification. Restricting the quantity of radioactivity contained -in each gas storage tank provides assurance that in the event of-an uncontrn11ed release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position.

ETSB 11-5, " Postulated Radioactive Releases Oue to a Waste Gas System Leak or Failure " in NUREG-0800, July 1981.

N /4.11.3 SOLIO RADI0 ACTIVE WASTES ecification implements the requirements of 10 CFR 50.36 General Desi riterion 60 of Appendix A to 10 CFR Part 50. rocess parameters inclu establishing the PROCESS CONTROL PP may include, but are not limited to te type,_ waste pH, waste /li ,/ SOLIDIFICATION agent / catalyst ratios, wast content, waste cipal chemical constituents, and mixing and curing times.

3/4.11.4 TOTAL DOSE This specification ' provided to meet the dose .. stions of 40 CFR ;

Part 190 that have n incorporated into 10 CFR Part 20 R 18525. The specification . uires the preparation and submittal of-a Spec port when-ever the culated doses due to releasch of radioactivity and to ra ~ ion-from nium fuel cycle source: 6xceed 25 mrems to the eole body or any o ,

ept the thyroid, which anall be limited to less than or equal to 75 mrems.

RELbCATGD TD Pred catnsYL (4 g a C/TAWBA - UNITS 1 & 2- B.3/4 11-e-

/

RADI0 ACTIVE EFFLU TS BASES ,

TOTAL DOSE (Continued) ,

For sites containing up t four reactors, it is. highly u likely that the resultant dose to a MEMBER OF THE PUBLIC will exceed th dose limits of 40 CFR Part 190 if the individual eactors remain within twic the dose design objectives of Appendix I, an if direct radiation dos from the units and from outside storage tanks are ke , small. The Special R ort,will describe a course of action that should result ' the limitation of t annual dose to a MEMBER OF THE PUBLIC to within the 40 CF Part 190 limits. F r the purposes of the Special Report, it may be assumed that e dose commitmen to the MEMBER OF THE PUBLIC from other uranium-fuel cycle so rces is negligib e with the exception that dose contributions from other nuclear uelcyclefaciitlesatthesamesiteorwithin a radius of 8 km must be considere . If the dos' to any MEMBER OF THE PUBLIC is estimated to exceed the requirsment of 40 CFR

art 190, the Special Report with a request for a variancs (provided t a releas conditions resulting in violation of 40 CFR Part 190 have not already en cor cted), in accordance with the provisions of 40 CFR 190.11 and 10 CF 20.4 c. is considered to be a timely request and fulfills the requirements 4 CFR Part 190 until NRC staff action is completed. The variance only relate the limits of 40 CFR Part 190, and does not apply in any way to the other r uirements for-dose limitation of 10 CFR Part 20, as addressed in Specifications .11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC d ri g any period in which he/she is engaged in carrying out any operation hat s part of the nuclear fuel cycle.

NOC&TW h cremt cewree a i

CATAWBA - U TS 1 & 2- 8 3/4 11 1 k B & Nr6f W Ps-M. a44f7TA (6 3/4.12 RADIOLOGICAL ENVI ONMENTAL HONITORING l

BASES \

3/4.12.1 MONITORING PROGRAM The Radfological Environm tal Monitoring Program re utred by this i specification provides represen ative measurements of ra f ation and of radio-active materials in those exoosu e pathways and for the e radionuclides that lead to the highest potential ra ation exposures of M BERS OF THE PUBLIC i resulting from the plant operatio This monitoring ogram implementsSection IV.B.2 of Appendix I to in CFR Part 50 and t reby supplements the ,

Radiological Effluent Monitoring ir gram by verifyi that the measurable j

concentrations of radioactive matari is and levels f radiation are not higher ;

il than expected on the basis of the of luent measure ents and the modeling of !

the environmental exposure pathways, utdance for this monitoring program is provided by the Radiological Assessmen Branch T hnical Position on Environ-mental Monitoring. The initially spect ied mon oring program will be effective for at least the first 3 years of comme ial o ration. Following this period, program changes may be initiated based o oper tional experience. !

- The required detection capabilities r environmental sample analyses are tabulated in terms of the lower limits of tection (LL0s). The LLDs required

by Table 4.12-1 are considered optimum for utine environmental measurements in industrial laboratories. It should be e ognized that the LLD is defined as an a priori (before the fact) limit r res nting the capability of a measure-ment system and not as an a posteriori fter he fact) limit for a particular measurement.

4 L.ttailed discussion of the LLD, nd other d tection limits, can be found in HASL Procedures Manual, HASL-300 revised ann 11y), Currie, L. A. , " Limits for Qualitative Detection and Quant ative Determ, ation - Application to

, Radiochemistry," Anal. Chem. 40, 5 -93 (1968), an Hartwell, J. K. , " Detection Limits for Radioanalytical Counti Techniques," At antic Richfield Hanford Company Report ARH-SA-215 (June 75).

. 3/4.12.2 LAND USE CENSUS This specification is pr vided to ensure that che es in the use of areas at and beyond the SITE BOUND Y are identified and that odifications to the Radiological Environmental nitoring Program given in t e 00CM are made if required by the results of his census. The best informa ion from the door-to-door survey, from aeri survey or from consulting wit local agricultural authorities shall be use This census satisfies the requ rements of Sec-tion IV.B.3 of Appendix to 10 CFR Part 50. Restrictino t e census to gardens of greater than 50 m2 p ovides assurance that significant ex osure pathways via leafy vegetables w 11 be identified and monitored since garden of this size is the minimum r quired to produce the quantity (26 kg/y ar) of leafy vegetables assumed i Regulatory Guide 1.109 for consumption b. a child. To determine this mini. m garden size, the following assumptions w re made:

(1) 20% of the gar n was used for growing broad leaf vegetatio (i.e, similar to lettuce and ca age), and (2) a vegetation yield of 2 kg/m2 ,

, CATAWBA - UNI 1&2 B 3/4 12-1

RADIOLOGICAL ENVIRONMDiTAL MONITORING BASES 3/4.12.3 INTERLACORATORY C MPARIS0N PROGRAM

\

l The requirement for part{cipation in an approved In riaboratory Comparison Program is provided to ensure \that independent checks o the precision and accuracy of the measurements o radioactive material iry environmental sample matrices are performed as part f the quality assurance program for environmental monitoring in order to demonstr that the results Afe valid for the purposes ofSectionIV.B.2ofAppendixItb10CFRPart50./

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i Pwt cwn y

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CATAWBA - NITS 1 & 2 8 3/4 12-2 -

a

ADMINISTRATIVE CONTROLS _

PROCEDURES AND PROGRAMS (Continued)

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

1) Training of personnel,

2) Procedures for sampling and analysis, and

3) Provisions for maintenance of sampling and analysis equipment. .

/MCfJ A +

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS l 1

6.9.1 In addition to the applicable reporting requirements of litle 10, Code of Federal Regulations, the following reports shall be submitted to NRC in accordance with 10 CFR 50.4.

STARTUP REPORT

6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of i fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

6. 9.1. 2 The Startup Report shall cddress each of the tests identified in the Final Safety / uiysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in.this report.

6. 9.1. 3 Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation,'or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

CATAWBA - UNITS 1 & 2 S-15 Amendment No. . (Unit 1)

Amendment No. 7 (Unit 2)

ADMINISTRATIVE CONTROLS ANNUAL REPORTS M i 6.9.1.4 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Annual Reports shall include the activities of the unit as described below;

a. Personnel Exposures Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including:contrac-tors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions 2/, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance.

(describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter. TLD, or film badge measurements. Small exposures totalling less than-20%_of the indi-3 vidual-total dose need not be accounted for. In the aggregate, at least 80% of j the total whole-body dose received from external sources should be assigned to

specific major work functions, i b. Primary Coolant Specific Activity

! Reports required on an annual basis shall include the re: Its of j specific activity analysis in which the primary coolant exceeded the

( limits of Specification 3.4.8. -The following information shall be-l included: 1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the i

first sample in which the limit was exceeded;-2) Results.of the last isotopic analysis for radiciodine performed prior to exceeding the e limit, results of analysis while limit was exceeded and results of

one analysis after the radioiodine activity was reduced to less than

limit. . Each result should include date and time of sampling and the

radioiodine concentrations;-3) Clean-up system flow history starting

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first' sample in which'the limit was exceeded;

! 4) Graph of the I-131 concentration and one other radioiodine, isotope

, concentration in microcuries per gram as a function of time for the i duration of the specific activity above the steady-state level;'and

5) The time duration when the specific activity of the primary coolant exceded the radioiodine limit.--

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ***

6.9.1.6 Routine Annual Radiological Environmental-Operating Reports covering-the operation of the unit during the previous calendar year shall be; submitted '

prior to May 1 of each year. The i ;!ti:1 r;;;rt :h:115: : t itt:d pri r t:

"ey i ef the y;;r felle.ia; initial criticelity. It#O(y 8, t{e, '

-1/ A single submittal.may be made-for e multiple unit station.- The submittal

~.

should combine those sections- that are common to-eM unit: t th; :t;ti n, 66 -

2/ This tabulation supplements the requirements of 6 20.407 of 10 CFR Part 20 3af 4-X**A single submittal,may be made for e multiple unit station.

Aef CATAWBA - UNITS 1 & 2 16 Amendment No. (Unit 1).

Amendment No. (Unit 2):

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1 I

4 ADMINISTRATIVE CONTROLS 4

N NNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) i e Annual Radiological Environmental Operating Reports shall include summari q interpretations, and an analysis of trends of the results of radiologict environmental surveillance activities for the report peri ,

including a e arison with preoperational studies, with operation controls as appropriate, M with previous environmental surveillance repp(ts, and an assessment of the observed impacts of the plant operation on tre environment.

The reports shall alsoh clude the results of the land use ensus required by Specification 3.12.2.

l The Annual Radiological En onmental Operat g Reports shall include the results of analysis of all radiolo al enviro ental samples and of all environmental radiation measurements en ing the period pursuant to the locations specified in the Table and Fig s in the ODCM, as well as summarized and tabulated results of these analys

~

and asurements in the format of the tableintheRadiologicalAssessmje ranch Tec ical Position, Revision 1, November 1979. In the event th t some individual ults are not available for inclusion with the repor the report shall be su itted noting and explaining the reasons for e missing results. The mis g data shall be j submitted as soon as p ble in a supplementary report.

I The reports all also include the following: a summary des ption of the Radiological E ronmental Monitoring Program; at least two legible s* cover- l ing all sampdng locations keyed to a table giving distances and direct s from the cent ine of one reactor; the results of licensee participation in t Inter oratory Comparison Program, required by Specification 3.12.3; discuss of 1 deviations from the sampling schedule of Table 3.12-1; and discussion of analyses in which the LLD required by Table 4.12-1 was not achievable.

, SEMIANNUALRADIOACTIVEEFFLUENTRELEASEREPORT*/

6.9.1.7hsoutine-Radioactive Semiaml Effluent Release Repor covering the operation of the unit during the previous 6 months of operation s all be submitted witnin 60 days af ter January 1 and July 1 of each year. The period of the first ce pcrt 0h:11 beg 4n with the det: cf initici criticolityr The Radioactive Efflu- l

! ent Release Repor shall include a summary of the quantities of radioactive liquid and gaseou effluents and folid waste released from the unit,0s outlin;d in ":guictorj Cuidc.1.21, "Meesttring, Evaluating, and hporting hdicactivity 1

-in Oclid Westes and-Re+eeses cf Redicecd ,e F.eterials ir U quid end Geseous

- Effivent; frem Light Weter Cecied Nucieer Power rients," "evision 1, June 1^Mr aith date svu,arized-en e quarterly basis felicwing-the formet cf Appendix 0 shareof. WTOLT' C N d CF@ffFil lb

0ne mep shall cever 5tetiene nee, the GITE 000NCARY, e 5ccvnd dali on.iude the more di5 tent 5tetivus. dc.

[A single submittal may be made for e vitiple unit station. The submittal should combine those sections that are common to-ell units et the stetien,6d unWT, hcwever, fcr units with :epcrate redwest; syste s, the submittei shell

-specify the releases cf radicective meteriel f a.1, eect sai;..

CATAWBA - UNITS 1 & 2 6-17 Amendment No. ' (Unit 1)

Amendment No. (Unit 2)

I-4 ADMINISTRATIVE C TROLS

I g

SEMIANNUAL RADI0ACT E EFFLUENT R_ELEASE REPORT (Continued)

The Radioactive fluent Release Report to be submitted wi in 60 days l after January 1 of eac year shall include an annual summary o hourly meteoro-logical data collected er the previous year. This annual s ary may be either in the form of an hour-b hour listing on magnetic tape of wi speed, wind direction, atmospheric st and precipitation (if mess ted), or in the form of joint frequency di ributility, ions of wind speed, wind di ection, and atmos-pheric stability." This s report shall includ6 an asses ment of the radia-tion doses due to the radica ive liquid and gaseous efflu nts released from the unit or station during the pr tous calendar year. This ame report shall also include an assessment of the r iation doses from radioa ive liquid and gaseous effluents to MEMBERS OF THE PUB 1C due to their activiti s inside the SITE

, BOUNDARY (Figures 5.1-3 and 5.1.d .during the report pe tod. All assumptions l used in making these assessments, .e., specific activ ty, exposure time and location, shall be included in the., reports. .The me orological conditions concurrent with the time of release f radioactive a erials in gaseous effluents, as determined by sampling frequency d measurement, shall be used for determin-ing the gaseous pathway doses. The a essment of r diation doses shall be per-formed in accordance with the methodo1 and para eters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Rep t to e submitted 60 days after l January 1 of each year shall also include as essment of radiation doses to

. the likely most exposed MEMBER OF THE PUBLI f om reactor releases and other -

nearby uranium fuel cycle sources, including ses from primary effluent path-ways and direct radiation, for the previous endar year to show conformance with 40 CFR Part 190, " Environmental Radiati n rotection Sthndards for Nuclear Power Operation." Acceptable methods for c Icu tting the dose contribution from l liquid and gaseous effluents are given in egula' ry Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Report shall inci e the following informa- l tion for each type of solid waste shipp d offsite du ing the report period:

a. Total Container volume, in ubic meters, 4

b. Total Curie quantity (dete mined by measuremen or estimate),

c. Principal radionuclides etermined by measurem t or estimate),

d. Type of waste (e.g., de tered spent resin, compa ted dry waste, evaporator bottoms),

e. Number of shipments, d

f. Solidification agent or absorbent (e.g., cement or et er approved agents (media)].

In lieu of submission with the first half year Radioactive Efflue Release l Report, the licensee has he option of retaining this summary of r uired meteorological data on s te in a file that shall be provided to the RC upon l request, g YWML CHf19']Tk I S' CATAWBA - UNITS 1 & 2 6 1B Amendment No.25 ( it 1) l Amendment No.15 ( it 2)

.\

R 6Z-0 CAT;=rD g ACHINISTRfTIVE CONTROLS g.

D4UL'LNUAL RADICACTIVE EFFLUENT RELEASE REPORT (Continued)

The MRa'e Effluent Release Reports shall include a . and descrip-tion of unplanned reTint rom the site to UNRESTRIC r x AS of radioactive materials in gaseous and liquw ' uents ma . ng the reporting period.

The Radioactive Effluent Re - epo 11 include any changes made during tne reporting per - , the PROCESS CONTROL . (PCP) and to the OFFSITE DOSE CA

4 N MANUAL (00CM), as well as a listing w locations for dos wu ations and/or environmental monitoring identified by ., d sensus pursuant to Specification 3.12.2. .

MONTHLY OPERATING REPORTS

6. 9.1. 8 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all cna11enges to the PORVs or safety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR So 4, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,

2. Shutdown Bank Insertion Limit for Specification 3/4.1.3.5,

3. Control Bank Insertion Limits for Specification 3/4.1.3.6,

4. Axial Flux Difference Limits, target band *, and APLND* for l Specification ' ? 1,

5. Heat Flux Hot Cnannel Factor, F K(Z),W(Z)"*,APLND" and {

W(t)BL forSpecification3/4.2.3,a,nd

6. Nuclear Enthalpy Rise Hot Channel Factor, FAHRL*** or, FRTP ,

- == AM 1 and Power Factor Multiplier, MFAH , limits for Specifica-tion 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:

1. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

July 1985 (W Proprietary).

(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial' Flux ND

Reference 5 is not applicable to target band and APL. ND

- References 5 and 6 are not applicable to W(Z), and APL ,andW(p.

- - Reference 1 is not applicable to FAHRl.

**** Reference 5 is not applicable to F RTP and MF g.

I?

CATAWBA - UNITS 1 & 2 6 Amendment No. (Unit 1) l Amendment No. (Unit 2)

ACHINISTRATIVE CONTROLS 1

CORE OPERATING LIMITS REPORT (Continued)

Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3

Nuclear Enthalpy Rise Hot Channel Factor.)

i 2. WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ j $URVEILLANCE TECHNICAL SPECIFICATION," June 1983 ('f Proprietary). ,

I (Metnocology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F gMethodology.)

3. WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION HODEL i USING BASH CODE," March 1987, ('d Proprietary).

j (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

4 BAW-10152 A, "N000LE - A Multi-Dimensional Two-Group Reactor Simulator," '

June 1985. !

(Methodology for Specification 3.1.1.3 - Moderator Temperature l Coefficient.) 1 5, BAW-10163P-A, " Core Operating Limit Methodology for Westinghouse-j Designed P%R's," June 1989.

(Methodology for Specifications 3.1.3.5 - Shutdown Rod Insertien

Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2,1 Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor.) ;

6. BAW-10168P, Rev. 1, "B&W Loss-of-Coolant Accident Evaluation Model for '

Recirculating Steam Generator Plants," September, 1989.

(Methocology for Specification 3.2.2 - Heat Flux Hot Ctrannel ,

factor.) i The core operating' limits shall be determined so that all applicable limits

, (e.g. , fuel themal-mechanical limits, core thermal-hydraulic limits, ECCS

, limits, nuclear limits such as shutdown margin, and. transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC in accordance with 10 CFR 50.4.

CATAWBA - UNITS 1 & 2 6-19/ Amendment No. - (Unit 1)

/ Amendment No. ' (Unit 2)

. n. Rearls of (cviewt j'ex{cemc$ 1%r c.hmt3ct rsalc 19 fee.tloe, 16, g g i (Rd'olopcal JWlvent ControlJ) 01C -f k e , P M R ,

j ADMINISTRATIVE CONTROLS I I l

REC 020 RETENTION (Continued) l

! h. Records of inservice inspections performed pursuari to these Technical :

Specifications; j t

i 1 Records of reviews performed for changes made to_ procedures or -

equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;

j. Records of meetings of the NSRB and reports required by Specification 6.5.1.-10; q

i k. Records of the service lives of all hydraulic and mechanical snubbers i required by Specification 3.7.8 including the date at which the service i life commences and associateo installation and maintenance records; i Records nf secondary water sampling and water quality; end -

1.

[ m. Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of i

4 the analysis at_a later dote. This should include procedures

! effective 'at specified tien d QA records showing-that these procedures were followe .an i 6,10.3 Records of auality' assurance activities required by the Operational 1- Quality Assurance Manual shall be retained for a period of time as recommended i by ANSI N.45.2.9-1974.

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

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device".or " alarm signal" required b paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area, yas defined in 10 CFR Part 20, in which the-intensity of_ radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates ~ shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation-protection-procedures (e.g., Radiation Protection Technician) or personnel continuously escorted by such individuals may ba exempt from the RWP issuance requirement during the performance of their assigned duties __in high radiation-areas with exposure rates equal to or less than >1000 mR/h, provided they are otherwise'following plant radiation protection procedures for' entry into such-high radiatian areas.= Any individual or group of individuals ~ permitted to enter such areas shall be provided with or accompanied by one or.more of the' '

following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area;'or ,

CATAWBA =- UNITS'l & 2 6 ' Amendment No. (Unit 1)'

Amendment No. -(Unit:2) 9

l ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO LIQUID, CASE 005, AND SOLIO RADWASTE TREATMENT SYSTEMS (continued)

2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; J

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously 4

predicted in the License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum

exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously

estimated in the License application and amendments thereto; I

6) A comparison of the predicted releases of radioactive materials,

in liquid and gasenus effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a j result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by tl.e Station Manager or the Chemistry Manager. '

l

b. Shall become effective upon review and acceptance by a qualified individual / organization.

INSERT D i

CATAWBA - UNITS 1 & 2 6-24 Amendment No. (Unit-1)

Amendment No. (Unit 2) i

INEAT A

.g Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in th: 000"(C W l4of (2) shall be implemented by operating procedures, and (3) shall in -tk, clude remedial actions to be taken whenever the program limits are PfA&j exceeded. The program shall include the following elements:

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

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

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix 1 to 10 CFR Part 50,

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

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce release 4 of radio-activity when the projected doses.in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,.

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

_ _ _ _ - - . _ _ . - - _ _ _ _ . 1

INWRT A (e sn+invel)

-0. 0. ' ;; Radioactive Effluent Controls Program (Cont.)

f*

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

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond tbe SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, n n 4.

_m ,2_2._.2______ ..__3 __; _.._a__ _,.<_u__i. ,, ___._2____.

"' _ld"'IT2 '!" 't . ll?. ' "" 7"M!'i'i"eC , I'.~ . ',~ '.L 1Ll:7"J.""""? ~

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-H-) Limitations on the annual dose or dose commitment to any MEMBER to 0F THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

+-- Radiological Environmental Monitoring Program 9

A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in=the 000",-C c< /6

2) conform to the guidance of Appendix I to 10 CFR Part 50, and h (3) include the following:

Frog

1) Monitoring, mmpling, analysis, and reporting of radiation and radionuclide, in the environment in accordance with the method-ology and parameters in the ODCM,

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

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

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1d INSEKT &

4 l The cetoct .sha(\ iad& svmmaeses, 'sn+trfreb$onJ, an9 ans(11i/

e of fresh of -ttc resvHr sf -tk RaAl algia ( e av ronmenini Msn decln7 ?repcam 40e k retorhhy ye-c,1L , 7ta ma4sek.l prov{Def i

shall Lc. conlisht aM vb djecfGe.r outlined ;n (s) cWhe /6 l

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q, , 5~k A f,e A n. nx4 anR re c scQ) & ce h c ferfor<ncS ' kil k rc%'eL <a cc p hrQ bi Qce c'i< Ao ~ (, . I o, L n , '711h Acumc4=%r r64 co 4 ~ : 193 c.tke M& f(3c

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{ ATTACllMENT 2

! CATAWBA SELECTED LICENSEC COMMITMENTS FOR i RADIOLOGICAL EFFLUENT CONTROLS 2 .

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J-L y;-- - ,s

16.3 DEFINITIONS The definitions in the Catawba Technical Specifications apply to defined terms used herein. The following additional defined terms appear in capitalized type and are appItcable throughout this Selected Licensee Commitment document:

16.3-1 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements, i

e 16.3-1

1 i

16,11 RA_010 LOG l.? ALLF F LU E N T S_C ON T RO.L S. .

j j RADI0 ACTIVE EFFLUENTS 16.11-1 LIQUID EFFLUENTS i

! CONCENT_ CE RATION I COMMITMENT l The concentration of radioactive material released in liquid effluents to -

! UNRESTRICTED AREAS (see Figure 16.11-1) shall be limited to the concentrations i specified in 10 CFR Part 20 -Appendix 0. Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained

] noble gases, the concentration shall be limited to 2 x 10 mferoCurie/mi

total activity.

APPLICABILIT1: At all times.

1 REMEDIAL ACTION:

! With the concentration of radioactive material released in liquid etfluents to-UNRESTRICTED AREAS exceeding the above limits, immediately restore the con-centration to within the above limits.

i TESTING REQUIREMEt!TS:

i Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 16.11-1, The results of the radioactivity analyses shall be used in accordance'with the methodology and parameters in the 00CM to assure that the concentrations at

! the point of release are maintained within the limits of SLC 16.11-1.

1

REFERENCES:

l 1. Catawba Offsite Oose Calculation Manual I

j 2. 10 CFR Part 20, Appendix B i BAS.ES:

4-This commitment is provided to ensure'that the concentration of radioactive--

materials released in liquid waste effluents to UNRESTRICTED AREAS will_be; ,

i' less than the concentration levels specified in 10 CFR Part 20. Appendix.B. ,

Table II, Column 2. This limitation provides_ additional _ assurance,that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will-

! result in exposures within: (1) the Section II.A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the i controlling radioisotope and its MPC in air (submersion) was_ converted to an-e

16.11-1 i

equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. ;

This commitment applies to the release of radioactive materials in liquid !

effluents from all units at the site. ;

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

Detailed discussion of the LLD, and other detection limits can be found in i .

HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to ,

Radiochemistry," Annal . Chem, 40, 986-93 (1968), and Hartwell, J. K.,

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield ;

Hanford Company Report ARH-SA-215 (June 1975).

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) -16.11-2

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.._.__._...._u _ . , _ _ __ _ . . .

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i TABLE 16.11-1 (Page 1 of 3) i RADIDACTIVE LIQUID _ WAST _E E MPLI_NG.AND ANALYSI_S._1R0 GRAM j .,

~

LO4C4 LIMIT i MINIMUM OFDETE0]gN >

i LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY _ (LLD) j TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml) i

1. Batch Waste P P J

Each Batch Each Batch Principal3 gamma 5x10

4 Release Tanks (2) Emitters .

j I-131 1x10 * ^

j Any tank which i discharges P - M Dissolved and 1x10"'

! liquid wastes One Batch /M Entrained Gases j by either liquid (Gammaemitters) i effluent moni- ,

tor, EMF-49 or EMF-57 P M -

H-3 1x10~'

I Each Batch Composite (4)

-Gross Alpha 1x W '

Sr-89, Sr-90

~

E O 5x10 '

Each Batch Composite (4)

Fe-55 1x10~'

s j 2.

Continuous W Principaf3 gamma 5x10' j Releases (5) continuous (6) Composite (6) Emitters i I-131 1x10"'

a. Conventional ~

Waste Water M M Dissolved and 1x10 '

Treatment Grab Sample Entrained Gases -

Line -(Gamma Emitiers).

b. Turbine Building Sump M H-3 1x10~'

Demineralizer Continuous (6) Composite (6)

Skid, EMF-31* Gross Alpha 1x10

~

Q~ St-89, Sr 5x10

Continuous (6)-- Composite (6).

~

Fe 1x10 '

. _u

0uring use of demineralizer (<j e of EMF-3] in off-normal mode);

16.11-3

, , r r - m-- w y ,-,.-

TABLE _16J1-1 (page 2 of 3)

LAB 1E NOTATIONS (1) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% prob-ability with only 54 probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 s b llO

E -

V 2.22 x 108 7 Y

exp (-kat)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume),

ss = the standard deviation of the background counting rate or of tMe counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

i i 2.22 x 10' = the number of disintegrations per minute per micro-j Curie, l Y = the fractional radiochemical yield, when applicable,

. X = the radioactive decay constant forithe particular radionuclide-l (sec~8),and l--

at = the elapsed time between midpoint of sample collection and time of counting (sec).

l-TypicalvaluesofE.V,YandAt'shalllbeusedin-the-calculation.

! It should be recognized that the LLD is' defined as an a Eriori (before the fact) limit repre-- 'ing the capability of a measurement system and-fter the fact)111mit for a particular' l - not as an a-posterior, i- measurement, (2) A batch release is the discharge of liquid wastes' of. a discrete l volume.

[ prior to sampling for analyses,-each batch shall be isolated,'and then j thoroughly mixed to assure representative sampling, f

, 16.11-4

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-.e, , , -.m,- r w['n - _,,w.'%.,w

. _ _ _ ~ . _ _ _ _ . _ - _ . _ . - - _ _ _ _ - - .__-._ .__ _ _ _ _ ___ _ _. _.

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TABLE 16,11-1 (Page 3 of 3) i

TABLE NOTATIONS I. Continued}

i :

4 3 l (3) The. principal gamma emitters for which the LLD specification applies l l include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65,

, Mo-99, Cs-134, Cs-137, and Ce-141. The LLD for Ce-144 is 5x10~' pCi/m1, j This list does not mean that only these nuclides are to be considered. r g' Other gamma peaks that are identifiable, together with those of the above ;

! nuclides, shall also be analyzed and reported in the Semiannual Radio- 6

! active Effluent Release Report in the format outlined in Regulatory Guide j 1.21, Appendix B, Revision 1, June 1974.

l (4) A composite. sample is-one in which the quantity of liquid sampled is- . ,

!. proportional to the quantity of_ liquid waste discharged and in which the: ;

I method of sampling employed results in a specimen that is. representative- ,

of the liquids released.

i ':

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

' continuous release, ,

I (6) To be representative of the quantities and concentrations of radioactive !

j materials in liquid effluents, samples shall. be collected continuously in i proportion to the rate of flow of the effluent stream. Prior to j analyses, all samples taken for the composite shall be thoroughly mixed i in order for the composite sample to be representative of the effluent

! release, 5

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16.11 RADIOLRGLCA LEFFLUENT CONTROLS i a i _I_NS_T RUM _EN_TA_T IO_N .l .

16.11-2 RADIDACTIVE l.1QVID EFFLUENT MONITORING INSTRUMENTATION !

! COMMITMENT i-

The radioactive liquid effluent monitoring instrumentation channels shown in i

! Table 16.11-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure -

L that the limits of SLC 16.11-1 are not exceeded. The Alarm / Trip.Setpoints of I these channels shall be determined and adjusted in accordance with the i methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM). ,

l APPLICABILITY: At all times.

REMEDIAL ACTION:

l a. With a radioactive liquid effluent monitoring instrumentation i channel Alarm / Trip Setpoint less conservative than required by the i above specification, immediately suspend the release of radioactive

, liquid ef fluents monitored by the affected channel, or declare the channel inoperable.

I b. With less than the minimum number of radioactive liquid effluent

] monitoring instrumentation channels OPERABLE, take the ACTION shown j in Table 16.11-2. Restore the inoperable instrumentation to OPER-4 ABLE status within the time specified in the ACTION. or explain in i tne next Semiannual Radioactive Effluent Release Report.why this inoperability was not corrected within'the time specified, j TESTING _ REQUIREMENTS:

Each radioactive liquid effluent n nitoring instrumentation channel shall be j demonstrated OPERABLE by performance of the CHANNEL CHECK,-SOURCE CHECK, i CHANNEL CAllBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the j frequencies shown in Table 16.11-3.

I

REFERENCES:

1. Catawba Offsite Oose Calculation Manual

2. 10 CFR Part 20 i

i 3. 10 CFR Part 50, Appendix A BASES:

The radioactive liquid effluent. instrumentation is provided to monitor.and

~

_ control, as applicable, the releases of radioactive materials in liquid ~

ef fluents during actual or~ potentia 1' releases of liquid ef fluents. _The j Alarm / Trip Setpoints for these struments shall be calculated and adjusted in

'16.11-6

P i

e BASES: (cont.)

4-accordance with the methodology and parameters in the ODCM to ensure that.the i

Alarm / Trip will occur prior to exceeding:the limits of 10 CFR Part 20. The-OPERABILITY and use of this instrumentation is consistent with the require-i ments of General Design Criteria 60, 63; and 64 of Appendix A to 10 CFR Part 50.

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TABLE 16.11-2 (Page 1 of 3)

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTP.UMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm And Automatic Termination of Release

a. Waste Liquid Discharge Monitor (Low Range - EMF-49) I per station 1

b. Turbine Building Sump Monitor (Low Range - EMF-31) 1 3

c. Steam Generator Water Sample Monitor (Low Range - EMF-34) 1 4

d. !ionitor. Tank Building Liquid Discharge Monitor (EMF-57) I per station 1

2. Continuous Composite Samplers And Sampler Flow Monitor

[

'a. Conventional Waste Water Treatment Line 1 per station 3 L - b. ~arbine Building' Sump 1 per station 3*

l 3. Flow Rate Neasurement Detices

a. Waste Liquid Effluent Line 1 per station 2

b. Conventional Waste Water Treatme a '.ine 1 per station 2

c. . Low Pressure Service Water Minimum Flow!

I nterlock 1 per station 2

d. :4cnitor Tank Building Waste. Liquid Effluent Line 1 per statfor- 2

e. Turbine Building Sump Deinineralizer Skid Totalizer.- 1 per station 2*

16.11-8

- 1

L 4

IABLE_16 J1__2 (Page 2 of 3) f TABLE NOTATIONS

During use of demineralizer (EMF-31 in off-normal modM ACTION STATEMENTS-ACTION 1 - With tt.a number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via

this pathway may continue for up to 14 days provided that prior to initiating a release; j a. At least two independent samples are analyze; in 4

accordance with SLC 16.11-1; and, I

b. At least tc.a technicallys 'lified members of the facility staf f indepardc."tly verify

1) The discharge line valving; 'and,

2) The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calculations if such'

~

calculations are performed manually.

Otherwise, suspend release of_ radioactive effluents via this pathway.

~

ACTION 2 - With the number of channels OPERABLE less than required by the-4 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue-.for up to 30 days'provided'the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual -

~

releases. Pump performance curves generated in place may be used to estimate flow.

i ACTION 3 - With the number of channels OPERAB'LE less than-required by the Minimum Channels-OPERABLE requirement,-. effluent releases via this-pathway may continue for up to_30 days provided grab l

. smples a.-e analyzed for radioactivity:at a lower limit of l 4

cetection of.no more th'n a 107 microcurie /ml:

a .- At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the s'pecific activity of

-the secondary coolant is greater than 0.01 microcurie / gram.

DOSE EQUIVALENT I-131, or-

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity (of' the secondary coolant is less.than or equal-to 0.01 -

microcurie / gram DOSE EQUIVALENT I-131.

16.11 1

4 9

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{ TABLE l6_1 h2 (Page 3 of 3)

L ACTION STATEMENTS 4

ACTION 4 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, gaseous effluent releases via the atmospheric vent valves (off-normal mode) may 4

continue provided grab samples of steam generator water are analyzed for radioactivity for up to 30 days at lower limit of detection of no more than 10~' microcurie /ml:

i

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram 4 DOSE EQUIVALENT I-131, or

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

4 i

4 16.11-10 a - w-

_ TABLE 16.11-3i 'Page 1 of 2) j RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL-INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Waste Liquid Discharge Monitor (Low Range - D P R(2) Q(1)

EMF-4T,

b. Turbine Building Sump Monitor (Low Range - D M R(2) Q(1)

EMF-31)

c. Steam Generator Water Sample Monitor D M R(2) Q(1)

(Low Range - EMF-34)

d. Monitor Tank Building Liquid Discharge D P R(2) Q(1)

Moni tor . (EMF-57) .

2. Continuous' Composite Samplers and Sampler Flow Monitor

a. Conventional Waste Water Treatment Line D(3) N.A. R N.A.

}'

l .

b. Turbine' Building Sutep D(3) N.A. R N.A.

3. Flow Rate Me&surement Devices

a. Waste Liquid Effluent Line D(3) N.A. R N.A.

b. Conventional Waste Water Treatment-Line~ D(3) N.A. R N.A.

c. Low Pressure Service Water Minimum Flow D(3)- N.A. R Q-Interlock

d. . Monitor Tank Building Waste Liquid Effluent D(3) N.A. R. Q Line 1

e. Turbine Building Sump D(3) H.A. R N.A.

Demineralizer Skid Totalizer 16.11-11

.- . .. .i

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. TABLE 16.11-3 (Page 2 of 2)

TABLE __ NOTATIONS a (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic-1 isolation of this pathway and contro11 room alarm annunciation

occur if-any of the following conditions exists:

! a. Instrument indicates measured levels- above- the Alarm / Trip Setpoint; i j or,

b. Circuit failure (alarm only); or, i c. Instrument indicates a downscale failure'(alarm only).

(2) The initial CHANNEL CALIBRATION shall'be performed using one'or-more:of 1

the reference standards certified by the-National Bureau _of Standards (NBS) or using standards-that have been obtained from suppliers'that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of

energy and measurement range. For subsequent CHANNEL CALIBRATION, _

sources that have been related to the initial calibration ~shall be used.

< (3) CHANNEL CHECK-shall consist of verifying indication of. flow during periods of release. CHANNEL CHECK shall be made at least once per a

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic,-or batch releases are made.

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For EMF-57, the alarm annunciation is in the Monitor. Tank Building Contro1I Room and on the MTB Control Panel Remote Annunciator _ panel.

16.11-12

16.11 RADIOLOGICAL _ EFFLUENT CONTR0_LS RADI0 ACTIVE EFFLUENTS 16.11-3 DOSE COMMITMENT The 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 16.11-1) shall be limited:

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

b. During any calendar year to less than or equal to 3-mrem to the whole body and to less than or equal to 10 mrem to any- organ.

APPLICABILITY: At all times.

i REMEDIAL ACTION:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit'to the -

Commission within 30 days, a Special Report that identifies the cause(s) for:

evading the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to-assure that subsequent releases will be in compliance with the above limits.

This Special Report shall also include: (1)-the results of radiological:

analyses of t<t drinking water source, and (2) the radiologicallimpact on-finished drinking water supplies with regard to the requirements of- 40 CFR Part 141, Safe Drinking Water Act.*

TESTING REQUIREMENTS:

Cumulative dose contributions from . liquid ef fluents for the current calendar quarter and the curren; calendar year shall be determined in accordance.with the methodology and parameters in the ODCM at least once per_31 days.

The requirements of REMEDIAL-ACTION-a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles _-

downstream of-the plant discharge.

16.11-13 $

= - - _ - _ _ - - _ _ _ _ _ _ a l

a

REFERENCES:

a

1. Catawba Offsite Dose Calculation Manual.

2. 40 CFR Part 141 ,

t

3. 10 CFR Part 50, Appendix I l BASES:

This commitment is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix-I to assure that the releases of radioactive material in lWid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonabij achievable" Also, for fresh water sites with drinking' water. supplies that can.be potentially.

affected by plant operations, there is reasonable assurance that the operation .

of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40LCFR Part 141. The dose calculation methodology and parameters in the ODCM implement the require-ments in Section III.A of Appendix I that conformance with the guides of-Appendix I be shown by calculational procedures based on models and data, such' that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. .The_ equations specified in the 00CM for calculating the doses due_to'the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation'of Annual Doses .;

to Man from Routine Releases of Reactor Effluents for the Purpose of-Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This commitment applies to the release of radioactive materials in liquid effluents from each_ unit at the site. When shared _Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be-made of the contribu-tions from each unit based on input conditions, e.g.,Jflow rates and-radio-activity concentrations, or, if not practicable,- the treated et fluent releases may be allocated equally to each of the radioactive' waste producing units- :l sharing the Radwaste Treatment System. For determining conformance to commit-ments, these allocations from shared Radwaste Treatment Systems are to be added to the roleases specifically attributed .to each unit: tu obtain the total:

releases per unit.

t 16.11-14

4 i-t 15.11 RADIOLOGICAL EFFLUENT CONTROLS-

RADIOACTIVE EFFLUENTS i '

16.11-4 LIQUID RADWASTE TREATMENT SYSTEM

$ COMMITMENT

} The liquid Radwaste Treatment System shall be OPERABLE and appropriate por-tions of the system shall be used to reduce releases of radioactivity when the j: projected doses due to the liquid effluent, from each unit, t'o UNRESTRICTED L AREAS (see Figure 16.11-1) would exceed 0.06 mrem to the whole body vr 0.2 l mrem to any organ in a 31-day period.

APPLICABILITY: At all timas.

REMEDIAL ACTION:

I With radioactive liquid' waste being discharged without treatment'and in excess of the above limits and any portion of the L1guid Radwaste Treatment-System not in operation, prepare and submit to_ the Commission within_30 days _.a-l Special Report that includes the following information:

T i 1. Explanation of why liquid-radwaste was being discharged without treatment, identification of any inoperable equipment or' subsystems,

and the reason for the inoperability, 1

! 2. Action (s) taken to restore the inoperable equipment to OPERABLE

status, and

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

TESTING REQUIREMENTS:

$ Doses due to liquid releases-from each unit toIUNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the: methodology'and

{ parameters in the 00CM when Liquid ~Radwaste Treatment Systems are not-being-

fully utilized.

The installed Liquid Radwaste Treatment System shall be' considered OPERABLE by meeting SLC 16.11-1 and 16.11-3.

REFERENCES:

1. Catawba Offsite Dose Calculation Manual,

2. -10 CFR'Part 50, Appendix A

3. 10 CFR ' art 50, Appendix I-t i:

4 16.11-15 I

i J

BASES:

The OPERABILITY of the Liquid Radwaste Treatment-System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate i portions of this system be-used when specified provides assurance that- the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This commitment implements the requirements of 10 CFR Part-50.36a, General Design Criterion 60 of Appendix A to 10-CFR Part 50 and the design objective given in Section II.D of-Appendix I to 10 CFR Part

50. The specifie6 limits governing the use of appropriate portions of the-

Liquid Radwaste ireatment System were specified as a suitable fraction of the

! dose design objectives set forth in_Section II.A of_ Appendix I, 10 CFR Part j 50, for liquid effluents.

This commitment applies to the release of radioactive materials in liquid '

effluents from each unit at the site. When-shared Radwaste Treatment Systems-l are used by hiore than one unit on a site, the wastes _from all units are mixed for shared treatment; by such mixing, the' effluent releases cannot: accurately

be ascribed to a specific unit. An estimate should be made of the contribu-tions from each unit based.on input conditions, e.g., flow rates and radio-8 activity concentrations, or, if not practicable,1the treated effluent releases may be allocated equally to each of the radioactive waste producing units

~

sharing the Radwaste Treatment System. For determining conformance to LCOs,

these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain1the total releases i per unit.

l d

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16.11-16

a i

16.11 RADIOLOGICAL-EFFLUENT CONTROLS 7

+

RADIOACTIVE EFFLUENE 16.11-5 CHEMICAL TREATMENT PONDS

, COMMITMENT 1

i The quantity of radioactive material contained in each chemical treatment pond

shall be limited by the following expression:

A 264 i.

V I _1 j C < 1*0 3

j excluding tritium and dissolved or entrained noble gases, Where:

A 3 = pond inventory limit for single radionuclide "j", in Curies; C. = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single J radionuclide "j", microCuries/ml; 4 V = design volume .of liquid and slurry in the pond, in. gallons; and i

i 264 =-conversion unit, microturies/ Curie per milliliter / gallon.

APPLICABILITY: At all times.

REMEDIAL ACTION:

With the quantity of radioactive material in any of the above listed ponds i

exceeding the above limit,-immediately. suspend all additions of radioactive material to the pond and initiate corrective action to reduce:the pond-contents to within the limit.

4 TESTING REQUIREMENTS:

The quantity nf radioactive material contained in each batch of resin / water.

slurry to be tran darrr.d to the chemical treatment ponds shall be, determined to be within the above limit by analyzing a representative sample.of'the batch 4

to be transferred to the chem cal' treatment ponds and shall be-limited'by the expression:

~

I

< 0.006 j C; d Where:

c3 = radioactive resin / water slurry concentration for radionuclide."j" i

16.11 . _ - .- .

a

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i 4

i entering the UNRESTRICTED AREA chemical treatment ponds, in

+

microCurt es/millili ter; and, 2

C 10 CFR 20, Appendix B, Table II, Column 2, concentration for single 4 3 = radionuclide "j", in microCurtes/ milliliter.

i

REFERENCES:

j. 1. Catawba Offsite Dose Calculation Manual.

! 2. 10 CFR Part 20, Appendix B

?-

', 3. 10 CFR Part 50, Appendix I BASES:

The inventory limits of the chemical treatment ponds (CTP)'are based on

! limiting the consequences of an uncontrolled release of the pond inventory, 4 The expression in this commitment assumes the pond inventory is' uniformly-t mixed, that the pond is located in an uncontrolled area as defined _in 10 CFR j Part 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR i

Part 20 applies.

i The batch limits of resin / water slurry transferred to the CTP assure that f radioactive material transferred to the CTP are "as low is reasonably 4

achievable" in accordance with 10 CFR 50.36a. The expression in-SLC 16.11-6

, assures-no batch will be transferred to the CTP~unless the sum of the ratios of the activity of the radionuclides to their-respective concentration limitation is less than the ratio of the 10 CFR Part 50, Appendix I, Section

. II.A, total body dose level to the 10 CFR Part 20.105(a), whole body dose

limitation,.or that

1 3 mremh r-y Cb < 500 mrem /yr = 0.006-y3 Where:

l-4 - ,

c radioactive resin / water slurry concentration for radionuclide "j" 3 = entering the_ UNRESTRICTED AREA CTP, in microCuries/ milliliter;. and, ;

C3 = 10 CFR Part 20, Appendix B,--Table II, Column 2, concentration:

for single radionuclide "j", in microcuries/ milliliter.

The filter /demineralizers using powdered resin and the blowdown demineralizer j are backwashed or sluiced to a holding tank. The-tank will be agitated to- !

i obtain a representative sample of the resin _ inventory in the tank. A'known weight of the wet, drained resin-(moisture content approximately 55 to G0%,

bulk density of about 58 pounds per cubic foot) will:then be counted. .The-1nneantration of the. resin-slurry to be~ pumped to the ch+mic:' he tment pnnds will'then be determined by th4 formula:

l 16.11-18

c) = bV NR T

Where:

Q) = concentration of radioactive materials in wet,' drained resin for radionuclide "j", excluding tritium, _ dissolved or entrained noi>1e gases, and radionuclides with less than an 8-day _ half-life.

The analysis shall include at least Ce-144, Cs-134,-Cs-137; Co-58 and Co-60, in microCuries/ gram._ Estimates of the Sr-89-and Sr-90 batch cor. centre. tion shall be_ included based a, the most recent monthly composite analysis (within 3_ months);

~

WR = total weight of resin in the storage tank-in grams;(determined '

from chemi try logs procedures); and,_

VT = t tal volume of resin water mixture in' storage _ tank to be transferred to the chemical treatment ponds in milliliters.

The batch limits provide _ assurance that activity input-to the CTP will_be minimized, anF . .aeans'of-Identifying radioactive material in the inventory limitation of this commitment. :

I a

16.11-19 J

5

1 3

16.11 RADIOLOGICAL EFFLUENT CONTROLS 1

RADIOACTIVE EFFLUENTS-1 i 16.11-6 GASEOUS EFFLUENTS-DOSE RATE COMMITMENT i

5

! The dose rate due to radioactive materials releaseed in gaseous effluents from 4 the site to areas at and beyond the SITE BOUNDARf (see Figure 16.11-1) shall I be limited to.the-following:

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

]

body and less than or equal to 3000 mren/yr to the skin; and,

! b. For Iodine-131,-for Iod:Je-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8

days: Less than or equal to 1500 mrem /yr to any organ, APPLICABILITY: At all times.

2 REMEDIAL ACTION:

i

{ With the dose rate (s) exceeding the above limits, immediately restore the a

release rate to within the above limit (s).

, TESTING REQUIREMENTS:

1 The dose rate due to noble gases in gassous effluents shall be_ determined to

{ be within the above limits in accordance with the methodology and parameters.

. in the ODCM, a'

The dose rate due to Iodine-131, Iodine-133,' tritium, and all radionuclides in particulate form with half-lives greater than_8 days in gaseous effluents i shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and '

l performing analyses in accordance with the sampling and analysis program'

. specified in Table 16.11-4.

REFERENCES:

1. Catawba Offsite-Dose Calculation' Manual, i

2. 10 CFR Part 20,_ Appendix B 3, 10 CFR Part 20 i

4 I

i 1-16.11-20

BASES:

This commitment is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units-on the site'will 60 within the annual dose limits of 10 CFR Part'20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II,-Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table _II of 10 CFR-Part 20 [10 CFR 20.106(b)]. For MEMBERS OF THE PUBLIC who may at times be within _the SITE BOUNDARY, the occupancy of that MEMBER OF-THE PUBLIC will usually' be suffi-ciently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for-such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall. be given :in the ODCM. The specified release rate limits restrict, at all times, the.

corresponding gamma and beta dose rates above background tota MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal' to 500 mrem / year to the whole body or to less than or equal to 3000 mrem / year to:the skin.

These release rate limits also restrict, at all times, the corresponding:

thyroid dose _ rate above background to a child via_ the inhalation pathway to less than or equal to 1500_ mrem / year.

This commitment applies to the release of radioactive materials in gaseous effluents from all units at the site. !

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

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

i

, 8 1

l 1

i i

16.11-21 l

n TABLE 16.11-4 (Page 1 of 4)

RADI0ACTIlfE GASEOUS t3ASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD)fI)

FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/ml)

GASEOUS RELEASE TYPE P P Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters (2) 1x10 '

1.

Tank- Grab Sample

~

Containment Purge Each PURGE (3) Each PURGE (3) Principal Gamma Emitters (2) 1x10 '

2.

Grab Sample M H-3 (oxide) 1x10 5

3. Unit Vent W(3) (4) g(3) Principal Gamma Emitters (2) 1x10~'

Grab-Sample H-3 (oxide) 1x10

D(3) (5) D(3)(5) Principal Gamma Emitters (2) 7xyg .

4. Containment Air Release and 1x10

Addition Sy= tem. Grab Sample M H-3-(oxide)

5. All Release' Types Cor.ti nuous( 6) ' D I7) I-131 1x10 22 as listed in 3 Charcoal above. Sample I-133 1x10 '

l 2'

Continuous (6) D(7) Principal Gamma Emitters (2) 1x10 Particulate Sample Continuous (6) M Gross Alpha f) 1x10 22 L

Composite L Particulate Sample Continuous (6) Q Sr-89, Sr-90 1x10 22 Composite-Particulate Sample 16.11-22

-o

^

~-

' TABLE 16.11-4 (Page 2 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING A;4D ANALYSIS PROGRAM MINIMUM LOWER. LIMIT OF i SAMPLING ANALYSIS TYPE OF DETECTION (LLD)(I)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/ml)

6. Waste Monitor _

W W Princip. Gamma Emitters (2) 1x10 '

Tank.Bui1 ding Grab Sampie-Ventilation H-3 (oxide) 1x10 '

Exhaust Continuous (6) W I-131 1x10 22 Charcoal Sample I-133 1x10 '

Continuous (6) W Principal Gamma Emitters (2) 1x10 2' Particulate Samp'e Continuous (6) g. Gross Alpha 1x10 22 Composi e Particulate Sample Continuous (6) Q Sr-F;, Sr-90 1x10 22 Composite Particulate Snmple 16.11-23

TABLE 16.11-4 (Page 3-of 4)

TABLE N0]ATION5; ll (1)' The LLD is defined, for purposes of these commitments, as the smallest I concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected _with-95% prob-~

ability with only 5% probability ~of falsely concluding that a blank -i observation represents a "real" signal.

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

4.66 s b l'O

E V 2.22 x 10' Y , exp (-lat)

Where:

LLD = the "a priori" lower limit of detec' tion (microcurie per unit l mass or volume);

s the standard deviation _of the background counting rate'or of-tNe=countingrateof.ablanksampleasappropriate(countsper minute);-

E = the counting efficiracy (counts per disintegration);

e V = the sample size (units of mass or volume);

2.22 x 10' = the number of disintegrations per minute per micro-Curie; Y = the fractional radiochemical yield, when applicable; i

A = the ..idioactive decay constant for the.particular radionuclide (sec 2); and, At = the elapsed time between midpoint of se.mple collection--and time-of counting (sec).

Typical-values of E, V, Y and-At shall be_used in the calculation.

3 It should be recognized-that the LLD-is defined as an a priori-_(before the fact) limit representing the capability of- a measurement system and not as an a posteriori'(after the fact)-limit for_a particular measurement.

16_.11-24:

l I

TABLE 16.11-4 (Page 4 of 4)

TABLE NOTATIONS (Continuedl- ;

(2) The principal gamma emitters for which the LLO specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, C0-58, Co-60,-

Zn-65, Mo-99, 1-131, Cs-134, Cs-137, and Ce-141 in Iodine and particulate releases. The LLD for Ce-144 is 5x10~' pCi/ml. This list does not mean that only these nuclides are to-be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual _ Radioactive Effluent Release Report, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER stabilization (power level constant at desired power level) after a: THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, for at least one of the- three gaseous _ release types with this notation.

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

(5) Required sampling and analysis frequency during effluent release via this pathway.

(6) The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate-calculation made in accordance with SLCs 16.11-6, 16.11-8,-and 16.11-9.

(7) Samples shall be changed at least once per 24' hours and analyses shall be completed within 48_ hours after changing, or after removal from sampler.

(8) The composite filter (s) will be analyzed for alpha' activity by analyzing one filter per week to ensure that at least four filters"are analyzed per collection period.

16.11-25 MM - m h -mmm-- - - - -__ *---_ __m___-m4-

P 16.11 M DI0 LOGICAL EFFLUENT CONTROLS INSTRUMENTATION 16.11-7 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION COMMI1 MENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 16.11-5 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of SLC 16.11-6 are not exceeded. The Alarm / Trip Setpoints of these channels meeting SLC 16.11-6 shall-be determined and_ adjusted.in'accora-ance with the methodology and parameters.in the ODCH.

APPLICABILITY: As shown in Table 16.11-5.

REMEDIAL ACTION: -

a. With a radioactive gaseous ef fluent monitoring: instrumentation ,

channel Alarm / Trip Setpoint less conservative than requitad by the above specification, immediately suspend the release of radioactive gaseous ef fluents monitored by the af fected channel, or declare the channel inoperable,

b. With less than the minimum number 'of radioactive gaseous ef fluent monitoring instrumentation channels OPERABLE, take the' ACTION shown in Table _16.11-5. _ Restore the inoperable instrumentation to OPERABLE status within.the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report why this-inoperability was not corrected within the time specified.

_TES P G REQUIREMENTS:

Each radioactive gaseous effluent monitoring instrumentation channel shall be

~

demonstrated OPERABLE by performance-of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL. TEST operations at the frequencies shown in Table 16.11-6.

REFERENCES:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 20 BASES:

.The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the-releases of radioactive materlah t yesecus effluents during actual or potential releases of 'gaseoi eifluents. The

- Alarm / Trip-Setpoints for.these-instruments shall 1,c't.alculated-and adjusted-in--

~

accordance with tne methodology and parameters in _the ODCM to ensure that the - ;

alarm / trip will occur prior to exceeding the limits of~10 CFR Part 20. The 16.11-26

t .

j OPERABILITY and'use of this-instrumentation--is consistent-with~the . .

. requirements of General Design Criteria 60,.63,.and 64 of Appendix A_to 10_CFR-L Part 50. The sensitivity of any noble gas activity monitor used to show--

compliance with the gaseous effluent release requirements of-SLC 16.11-8 shall

j be such that concentrations as low as.1 x 10-6 pCi/cc' are measurable.

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A TABLE 16.11-5 (Page 1 of 4)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. WASTE GAS' HOLDUP SYSTEM

a. : Noble-Gas Activity Monitor -

Providing Alarm end Automatic Termination of Release (Low

Range - EMF-50) I per station 1

, 'b. Effluent System F22w Rate

Measuring Davice 1 per station 2

2. CONDENSER EVACUATION SYSTEM NOBLE. GAS 1 1,2,3,4 3 ACTIVITY MONITOR (LOW RANGE - EMT-?3) l- 3. VENT SYSTEM-L a. Noble Gas Activity Nonitor' 1- 3 J(Low Range - EMF-36)

b. Iodine Sampler (EMF-37)- 1. 5

c. - Particulate ; Sampler (EMF-35) 1 5

d. Flow Rate Monitor. 11 2

2

e. SamplerLFlow. Rate Monitor 1

4. CONTAINMENT PURGE 1' SYSTEM

' NoblezGas. Activity 1 Monitor - Providing

- - 4-

' Alarm and Automatic Termination of 1 Release-(Low Range - EMF-39).

16.11-28

.. m

' I, TABLE 16.11-5 (Page 2 of 4)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

5. ~ CONTAINMENT ATR RELEASE AND ADDITION SYSTEM

1 Noble Gas Activity Monitor - 1 Providing- Alarm (Low Range - EMF-39)

6. MONITOR TANK BUILDING HVAC

- 3

a. Noble Gas Activity Monitor - 1 per station Providing Alarm (EMF-58) l b. Monitor Tank Building Effluent I per station 2 I EFlow Rate Measuring Device-L-

i 16.11-29

a. . ._-

. - = . .-

TABLE 16.11-5 (Page 3 of 4)

TABLE NOTATIONS i

I

At all times excent when the isolation valve is closed and locked.

- At all times. ,

ACTION STATEMENTS-j ACTION 1 - With the number of channels OPERABLE less than required the Minimum Channels OPERABLE requirement, the contents of i the tank (s) may be released to the environment for up to i 14 days provided that prior to initiating the release either:

a. Vent system noble gas activity monitor providing alarm and automatic termination of release (Low Range

- EMF-36) has at least_one channel OPERABLE; or, i

b. At least two independent samples of the tank's-contents are analyzed, and at least two' technically-qualified members of the facility staff independently verify:

i i- 1. The discharge valve lineup; and, i

l 2. The manual portion of the computer input for the release rate calculations performed on the i computer, or the entire release rate

. calculations if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 - With the number of channesOPERABLEIless-thanrequiredby the Minimum Channels OPERioLE requirement, effluent.

releases via this pathway may continue for up to 30 days

, provided the flow rate is estimated at.least once per i

! hours.

ACTION 3 - With the number of channels- OPERABLE-less than required by-the Minimum Channels OPERABLE. requirement, effluent 4

releases via this pathway _may continue _for up to 30 days 1 provided grab samples are 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 analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 4 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE: requirement, immediately suspend PURGING of radioactive effluents via-this pathway.

-16.11-30

~ . _

.I TABLE 16.11-5 (Page 4 of 4)-

TABLE NOTATIONS-I ACTION 5 - With the number of_ channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent' i releases via the affected pathway may continue for.up to i 30 days provided samples are continuously collected with-auxiliary' sampling equipment as required in Table 16.11-4.

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g TABLE- 16.11-6 (Page 1 of 3) '

'RADI0 ACTIVE GASEOUS EFFLUENT MONITGRING INSTRUMENTATION SURVEILLANCE RE00iREMENTS3 ANALOG

, CHANNEL LMODES FOR WHICH-

~

CHANNEL SOURCE CHANNEL OPERATIONAL ' SURVEILLANCEL INSTRUMENT CHECK CHECK- CALIBRATION TEST :IS-REQUIRED 1: 5 WASTE GAS HOLDUP SYSTEM.-

a. Noble GasiActivity Monitor :

Provf; m Alarm and Automatic -

--.Termit*i e of. Release' P P -R(3) Q(1)

-(Low Range : EMF-50) :;

ib: Effluent. System Flow Rate P N.A. 'R N.A. *

Measuring Device-

2. Condenser-Evacuation System

= Noble ~ Gas Activity Monitor- D M R(3)- N.A. 1, -2, .--3, 4 i

-(Low Range -; EMF-33)-.

~3; LVent'Systemf

a. Noble Gas Actisity Monitor.. D M R(3) Q(2).

'(Low Range. : EMF-36) ll .b. . Iodine Sampler .(EMF-37) W- N.A. N.A. N.A.

L 1

. 16.11-32

>= ,

TABLE 16.11-6 (Page 2 of 3)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL. S'JRVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED

3. Vent System (Continued)

c. Particulate Sampler (EMF-35) W N.A. N.A. N.A. =

d. Flow Rate Monitor' D N.A. R N.A. *

e. Sampler Flow Rate Menitor D N.A. R N.A *

4. Containment Purge System Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release D P R(3) Q(1) **

(Low Range - EMF-39)

5. Containment Air Release and Addition System Noble Gas Activity Monitor - O P R(3) Q(1)

Providing Alarm (Low Range - EMF-39)

6. Monitor Tank Building HVAC

a. Noble Gas Activity Monitor - D M R(3) Q(2) **

Providing Alarm (EMF-58)

b. Discharge Flow Instrumentat an D N.A. R N.A. **

16.11-33

..- J

l TABLE 16.11-6'(Page 3 of 3)

TABLE NOTATIONS

At all times except when the isolation valve is closed and locked.

- As, all times, u

1. The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint; or,

b. Circuit failure (Alarm only); or,

c. Instrument indicates a downscale failure (Alarm only).

2. The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation # occurs if any of the following conditions-exists:

a. Instrument indicates measured levels above the Alarm Setpoint; or,

b. Circuit failure; or,

c. Instrument indicates a downscale failure.

3. The initial CHANNEL CALIBRATION shall be performed using one or more of-the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from- suppliers i. hat participate in measurement assurance activities with NBS, These standards shall permit calibrating the-system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. J]

For EMF-58, the alarm annunciation is in the Monitor -Tank-Building Control Room'and on the MTB Control Panel Remote Annunciator Panel. i 16.11-34 I

- =. .

16.11 RADIOLOGICAL EFFLUENT CONTROLS RADICAClIXE_EFFLUEN_LS 16.11-8 DOSE - NOBLE-GASES COMMITMENT The air dose due to noble gases released in gaseous effluents, from each unit,-- '

to areas at and beyond the SITE BOUNDARY (see_ Figure 16.11-1) shall be limited' to the following:

a. During any calendar quarter: Less than or equal to_5 mrads for gamma radiation and less than or equal to 10 mrsd for beta radiation; and, 3 e- i

b. During any _ calendar year: Less than or equal to-10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

REMEDIAL ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and_ submit to the Commission within

-30 days, a Special Repor_t that-identifies'the cause(s)_for. exceeding _the.-

limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to-be taken to-assure thatu subsequent releases will be in compliance with the-above limits. ;

)

TESTING REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in-accordance-with the methodology and parameters in the 00CM at least once per 31 days.

REFERENCES:

1.. Catawba Of fsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix I BASES:

This' commitment is provided to implement the, requirements of Sections II.8, III. A-'and IV. A of Appendix 1,10 CFR Part 50. The-Limiting Condition for-1 Operation-implements-the guides set-forth in Section II,B of_ Appendix I. The-REMEDIAL ACTION statement provides the' required operating ~ flexibility and at the same time implement the guides set forth--in Section IV.A of Appendix I to-assure that the releases of radioactive _ material in gaseous ef fluents_ to

-UNRESTRICTED' AREAS will be kept "as_ low as is reasonably achievable". The Testing Requirements implement the requirements in Section.III.A of Appendix I 16.11-35 1

BASES: (cont'd) that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to.be substantially-underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent-with the method-ology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the' Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric-Transport and Dispersion of Gaseous Ef fluents in Routine Releases from Light-Water Cooled -

Reactors," Revision- 1, July 1977. The ODCM equations provided- for determining the air doses at and beyond the SITE B0UNDARY are based upon the historical average atmospheric conditions.

This commitment applies to the release of radioactive materials-in gasecut effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent-releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contribu-tions from aech unit based on input conditions, e.g., flow rates and radio-activity concentrations, lor,-if not practicable, the treated effluent releases may be allocated equally to each of the. radioactives waste producing units--

sharing the Radwaste Treatment System. For determining conformance to commit-ments, these allocations from shared Radwaste Treatment Systems-are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

I 16.11-36

16.11 A R_ADI_0LOGI_ CAL EFFLUENT CONTROLS RADI_0 ACTIVE EFFLUENTS.

16.11-9 DOSE -- 10 DINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM COMMITMENT The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous efiluents released, from each unit,- to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to.any organ; - and, "

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

APPLICABILITY: At all times.

REMEDIAL ACTION:

With the calculated dose from the release of_ Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of_the above limits, prepare and submit-to the-Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be-taken to assure that subsequent releases will be in compliance with the above limits.

TESTING REQUIREliENTS:

Cumulative dose contributions for the current calendar _ quarter and current calendar year for Iodine-131, Iodine-133, tritium and radionuclides in-particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

REFERENCES:

1. Catawba Offsite Dose Calculation-Manual.

2. 10 CFR Part 50, Appendix I

, BASES:

This commitment is provided to implement -the requf rements-of Sections II.C, i III.A,.'and IV.A of Appendix I,:10 CFR Part 50, and are the guides set forth-in Section II.C of Appendix I. The REMEDIAL ACTION statements provide the-required operating flexibility and at the same time implement the. guides set 16.11-37 1

l

f A

BASsS: (cont'd) forth in Section IV.A of Appendix I to assure that the releases of radioactive-materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The ODCM calculational _ methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The 00CM calculational methodology and' parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents'for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases.from Light-Water-Cooled Reactors," Revision 1, July 197'/.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate -mmitments for Iodine-131 Iodine-133, tritium, and radionuclides in partichea^.e form with half-livas yreater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) depositio; d radio-nuclides onto green leafy vegetation with subsequent consumptiv man,(3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contribu-tions from each unit based on input conditions, e.g. , flow rates and radio-at tivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to commit-ments, these allocations from shared Radwaste Treatment Systems are to be-added to the releases specifically attributed to each unit to obtain the totsi releases per unit.

16.11-38

[. _.

^ .

16.11 RADIOLOGICAL EFFLUENT CONTROLS RADIDACTIVE EFFLUENTS 16,11-10 GASEOUS RADWASTE TREATMENT SYSTEM COMMITMENT-The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 16.11-1) would exceed either:

a. 0.2 mrad to air from gamma radiation; or,

b. 0 4 mrad to air from beta radiation; or,

c. 0.3 mrem to any organ of a MEMBER OF_THE PUBLIC.

APPLICABILITY: At all times.

REMEDIAL ACll_0N:

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report that includes the following information:

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

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

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

TESTING REQUIREMENTS:

Doses due to gasenus releases from each unit to areas at and beyond the SITE-BOUNDARY p e be pro.iected at least once per 31 days in accordance wit'.. the-methodology-and parameters in the ODCM when Gaseous Radwaste Treatment Systems-are not being fully utilized.

The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by'meett.g SLCs 16.11-6,-16.11-8, or 16.11-9.

REFERENCES.:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix I-16.11 <

a in in s s i -.. ... . . -i- - ' -a1m-iiw i-~---~i-u -- --

. __ _ _ _ EE~ E~

l-BASES:

The OPERABILITY of _ the WASTE GAS HOLDUP' SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the-systems will be available for use whenever gaseous effluents require! treatment prior:to release to the environment - The-requirement that the appropriate portions of these systems _Le used, when specified, provides reasonable assurance that the releases of radioactive-materials in-gaseous effluents-will-be kept "as low i is reescribly- '

achievable". -This commitment implements the require, nts of-10 C7R 50.36a,_

General Design Criterion 60 of Appendix-A to 10 CFR F-rt 50, and the design objectives'given in Section II.D of Appendix.l.to-10_CFR Part_50. -_The specified limits governing the use of appropriate portions of the systems were-specified as a suitable fraction of the-dose-design objectives set-forth in ,

Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site..;When shared Radsaste Treatment Systems are used by more than one unit on a site, the wastes from all units-Are mixed for shared treatment; by such mixing, the effluent releases cannot accurately.

be ascribed to a specific unit. An estimate should be made of the contribu-tions from each unit based on input conditions, e.g., flow rates and radio-activity concentrations, or,-if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste _ producing units-sharing the Radwaste Treatment System.- For determining _conformance to commit-ments, these allocations from shared Radwaste Treatment Systems are-to be added to the releases specifically attributed to each unit to obtain the total-releases per unit.

3 16.11-40 4

i j 16,11 MD,[0L_0.GlCA_L_, EFFLUENT CONT ROLS - ,

i a

!- RADICACTIVE EFFLUENTS

j. 16.11-11 SOLIO RADI0 ACTIVE WASTES i -COMMITMENT ?

1 _

Radioactive wastes shall be solidified or dewatered in accordance with the

! PROCESS CONTROL PROGRAM to meet shipping and transportation requirements

during transit, and disposal site requiremer.ts when received at the disposal j site.

APPLICABILITY: At all times.

i j REMEDIAL ACTION:

l a. With SOLIDIFICATION or dewatering not meeting disposal site and -

shipping and transportation requirements, suspend shipmen'c, of the

! inadequately processed wastes and correct the PROCESS CONTROL-

! PROGRAM, the procedures and/rr the Solid Radwaste Systen as necessary to prevent recurrence, e j b. With SOLIDIFICATION or dewatering r.ot perforud in accordance with

the PROCESS CONTROL PROGRAM, test the improperly processed waste in j each container-to ensure that it' meets burial ground and-shipping requirements and take appropriate' administrative action.to prevent

{ recurrence. '

SURVEILLANCE REQUIREMENTS:

' SOLIDIFICATION of at least one representative test specimen from at least

every tenth batch of each type of wet radioactive wastes (e.g., filter l sludges, spent resins, evaporator bottoms, boric acid solutions and sodium j

sulfate solutions) shall be verified 'in accordance with the PROCESS CONTROL PROGRAM:

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

SOLIDIFICATION of the batch may'then be resumed using the' alterna-

tive SOLIDIFICATION parameters-determined by the PROCESS CONTROL PROGRAM;

b. If the initial test specimen from a batch of waste-fails to-verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative' test specimens from each consecutive batch of'the same type-of wet waste until~at least-three-consecutive initial test specimens demonstrate' SOLIDIFICATION. The.

16.11-41 i-

--~. - _

~ .~ _ _ . . , _

' PROCESS CONTROL PROGRAM shall-be modified'as_ required, to assure SOLIDIFICATION of subsequent batches of-waste; and,

c. With_the installed equipment incapable of meeting SLC 16.11-11 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to 'processLwastes as necessary t'o satisfy all applicable transportation and disposal _ requirements.

REFERENCE 1:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appandix A ,

3. 10 CFR Part 50 PASES:

This commitment implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include,-but are not.

limited to waste type, waste pH, waste / liquid /SQLIDIFICATION agent / catalyst ratios, waste oil content, waste principal chemical constituents, and mixing-and curing times.

l 1

l i

1 3

i 16.11-42:

4 i

i 4 i i

j 16.11 A RA0[010GICAL EFELULNT CONT _ROLS RADI0 ACTIVE EFFLUENTS

16.11-12 TOTAL DOSE COMMITMENT f

i i The annual (calendar year) dose or dose commitment to any MEMBER OF-THE PUBLIC-j due to releases of radioactivity and to radiation from uranium fuel cycle j sources shall be limited to less than or equal to 25 mrem to the whole body or j any organ, except the thyroid, which shall be limited to less than or equal to

. 75 mrem.

APPLICABILITY: At all times.

i i REMEDIAL ACTION:

With the calculated doses from the release of radioactive materials in liquid

or gaseous ef fluents exceeding twice the limits of SLCs 16.11-3a,16.11-3b, 16.11-8a, 16.11-8b, 16.11-9a, or 16.11-9b, calculations shall be made

including direct radiation contributions from the units and from outside i storage tanks to determine whether the above limits of this commitment have

{ been exceeded. If such is the case, prepare and submit to the Commission

! within 30 days, a Special Report that defines the corrective action to be

< taken to reduce subsequent releases to prevent recurrence of exceeding the

above limits and includes the schedule for achieving conformance with the

above limits. This Special Report, as defined in 10 CFR 20.405c, shall

. include an analysis that estimates the radiation exposure (dose) to a MEMBER F

0F THE PUBLIC from uranium fuel cycle sources, including all ef fluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and-the cause of the exposure i

levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the releas, condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a l variance in accordance with the' provisions of 40 CFR Part 190. Submittal of

! the report is considered a timely request, and a variance is granted until i staff action on the request is complete.

i TESTING REQUIR_EgNTS:

! Cumulative dose contributions from liquid-and gaseous. effluents shall be determined in accordance with SLCs 16.11-3, 16.11-8 and 16,11-9, and in

accordance with the. methodology and parameters in the ODCM.

Cumulative dose contributions from direct radiation from the units.and from radwaste storage tanks shall be determined:in accordance with the methodology and parameters-in the ODCM. This requirement is applicable.only under

-conditions set forth in the REMEDIAL ACTION of this commitment, 1

I . 16.11-43

-- m. e .c -

, y- ,----,

t 4

i

REFERENCES:

]_ _

1. Catawba Offsite Dose Calculation Manual.

2, 10 CFR Part 20 t

i 3. 40 CFR Part 190-

_ BASES:

This commitment is provided to meet the dose limitations of 40 CFR Part 100 1 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The commitment requires the preparation and submittal of a Special. Report whenever the calculated doses due to releases of radioactivity and to radiation from l uranium fuel cycle sources exceed 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

S For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose Ifmits of 40 CFR Part 190 if the individual reactors remain within twice_the dose design objectives of Appendix I, and if direct radiation doses from the units and i from outside storage tanks'are kept small. The Special Report'will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits, 'For the-purposes of the Specia' Report, it may be assumed that the dose commitment to the-4 MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40_CFR Part 190, the Special Report with a request for _a variance (provided the release conditions resulting in violation of;40 CFR Part 190 have not already-been corrected), in accordance with the provisions of 40 CFR_190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only .

relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in SLC 16.11-1 and 16.11 An individual is not considered'a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying-out any operation that is part of the nuclear fuel cycle.

16.11-44

16.11 RADIOLOGICAL EFFlVENT CONTROLS-RADI.0L_0GICAL ENVIRONMENTAL MONITORING 16.11-13 MONITORING PROGRAM COMMITMENT The Radiological Environmental Monitoring Program shall be conducted as specified in Table 16.11-7.

APPLICABILITY: At all times.

R_EMEDIAL ACTION:

a. With the Radiological Environmental Monitoring Program not being-conducted as specified in Table 16.11-7, pre' pare and submit to the Commission, in the Annual Radiological Environmental Operating.

Report, a description of the reasons for not conducting the program as required and the plans for preventir.g a. recurrence,

b. With the level of radioactivity as the result of. plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of_ Table 16.11-7 when averaged over any calendar quarter, prepare and submit to the Commission within 30-days, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive ef.fluents so that..the potential-annual dose

tc a MEMBER OF THE PUBLIC is'less than the calendar year limits of SLC-16.11-3, 16.11-8, and 16.11-9. When more than one of the radionuclides in Table 16.11-7 are detected in the sampling medium, this report shall be submitted if:

concentration (1)_ concentration (2)-

reporting level (1) . reporting level -(2) + > 1*0 When radionuclides other than those in Table 16.11-7-are: detected and are the result of plant effluents, this-report-shall be

submitted if -the potential annual dose

to A MEMBER OF THE PUBLIC -

from all radionuclides is equal to or-greater than the-calendar year-limits of SLC 16.-11_-3, 16.11-8 and 16.11-9. This-report is~not required if the measured level of radioactivity was not the result of plant effluents; however, in such.an event, the condition shall c be _ reported and described in- the Annual Radiological Environmental Operati_ng Report.

The methodology and parameters used to estimate the potential annual dose to s

a _ MEMBER _OF THE PUBLIC shall be indicated -in this repo~rt.

i e

-16.11-45 >

L . .

. .- - - - . .- . - . - - - - = - - -. . . - -.

i

]

_REMEDML_AC110N: (cont'd)

! c. With milk or fresh leafy vegetation samples unavailable from one or

more of the sample locations recoired by Table _16.11-7, identify

specific locations for obtaining replacement _ samples and add them within 30 days to the Radiological Environmental Monitoring Program 1; . given in the ODCM, The specific locations from which samples were

unavailable may then be deleted from the monitoring program,' Submit i in the next Semiannual Radioactive Effluent Release Report j -- documentation for a change in the 0DCM including a revised figure (s) and table for the'00CM reflecting the new location (s) with supporting information identifying the _cause of the unavailability i of samples and justifying the selection of the net location (s) for obtaining samples, TESTING REQUIREMENTS:

i l The radiological environmental monitoring samples shall be collected pursuant I J to Tabie 16.11-7 from the specific locations given in the table and: figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 16.11-7 and the detection capabilities required by Table 16.11-8. ,

REFERENCES:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50 Appendix I !

_ BASES:

The Radiological Environmental Monitoring Program required by this commitment provides represenative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that' lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation, This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements-the Radiological Effluent-Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided-by'the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The initially specified monitor _ing program will be effective for at least the first 3 years of commercial operation. Following this period, program change's-may be initiated based on-operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of_ the lower limits of detection (LLDs). The LL0s_ required' by. Table 16.11-8 are considered optimum.for-routine environmental: measurements in industrial laboratories. It should be recognized that the LLD is defined-as an a priori (before the fact)-limit representing'the capability of a measurement' system:and not as an a posteriori (after the_ fact) limit _for a particular measurement.

.)

16.11 i

I

~!

T BASES: (cont'd)

Detailed discussion of the LLD, and other detection-limits, can be'found in HASL-Procedures Manual, HASL-300 (revised annual.ly), Currie, L.A.,:" Limits for Qualitative Detection and Quantitative Determination - Application to i Radiochemistry," Anal. Chem, 40, 586-93 (1968), and-Hartwell, J,-K,,

" Detection Limits for Radioanalytical Counting Techniques, Atisatic Richfield Hanford Company Report ARH-S_A-215 '(June 1975).

i l

16.11-47:

i TABLE 16.11-7 (Page 1 of 7)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONSb11 COLLECTION FREQUENCY ___OF ANALYSIS I

1. Direct Radiation ( ) Forty routine monitoring stations Quarterly. Gamma dose quarterly.

either with two or more dosimeters or with one instrument for

' measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteerclogical sector in the j general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site; and, The balance of the stations to i be placed in special interest i

areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

16.11-48 I

p. ' , , .. - -

TABLE 16.11-7 (Page 2 of 7) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND AND/OR SAMPLE SAMPLING AND SAMPLE LOCATIONSO TYPE AND FREQUENCY

2. COLLECTION FREQUENCY OF ANALYSIS Airbarne ._

Radiciodiae and Samples from five locations.

Particulates Continuous sampler operation with sample _Radiciodine Cannister:

collection weekly, I-131 analysis weekly.

Three samples from close cr more frequently if required by dust to the three SITE BOUNDARY loading.

locations, in different Particulate Sampier:

sectors, of the highest Gross beta radioactivity calculated annual average analysis follcwing ground-level D/Q; filter change;I ) and One sample from the gamma isotopic analysis (4) l vicinity of a community of composite (by location) having the highest calcu- quarterly.

lated annual average ground-level D/Q: and i One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

3. Waterborne

a. Surface (5) One sample upstream. Composite samp "

1-month period. 6 Gamma is topic analysisN One sample downstream. monthly. Composite for

b. Ground b**EI*' I" * #"* "* 5 ""C* tritium analysis quarterly.

only if likely to be affected'h Quarterly. Gamma isotopic (#) and tritium analysis quarterly.

16.11-49

TABLE 16.11-7 (Page 3 of 7)

RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATINAY ' SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS I) COLLECTION FREQUENCY OF ANALYSIS ,

3. Waterborne (Continued)

Composite sa over I-131 analysis on each

c. Drinking One sample of each of one to three of the nearest 2-week period composite when the dose water supplies that could be when I-131 analysis calculated for the con-affected by its discharge. is performed; monthly sumption of the water ccmposite otherwise. isgreatg)thanImrem.

.. Composite One sample from a control per year location. for gross beta ay43ama isotopic analyses monthly. Composite for tritium analysis' quarterly.

d. Sediment One sample from downstream area Semiannually. Gamma isotopic: analysis N

'from with extsting or potential semiannually.

l

! Shoreline- recreational value.

'4. Ingestion

' a. Milk Samples from milking-animals Semimonthly when Gamma isotopic (#) and-in three locations within.5 km animals are on I-131 analysis semi-distance having the highest. pasture; monthly . monthly when animals dose potential. If.there are at.other times. are on' pasture; monthly:

none, then one sample from at other times.

- milking animals In each of three areas'between 5 to 8 km distant where doses are'ca':u-latedtpgge_greatert_han1 mrem One sample from

_ per yr. '

milking animals at a control. __

location 15 to 30 km distant and '

in..the least prevalent wind direction.

16.11-50

~'

y - -j

a : n .

TABLE 16.11-7 (Page 4 of 7)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE "

SAMPLES AND SAMPLING AND TiPE AND FREQUENCY EXPOSURE PATHWAY AND/0R 1 AMPLE SAMPLE LOCATIONS b COLLECTION FREQUENCY OF ANALYSIS 4 .. Ingestion (Continued)

Gamma isotopic analysis )

b. Fish'and :One sample each of a predatory Sample in season, or species, a bottom feeder and a semiannually if they on edible portions.

Inverte-bratas forage species in vicinity of are not seasonal.

plant discharje area.

=0ne sample each of a predatory d species, a bottom feeder and a forage species in areas not

. influenced by plant discharge.

One sample of each principal At time of harvest (9). Gamma isotopic analyses N :I

c. Food on edible portion.

' Products . class of food. products from any area that is irrigated by water in which . liquid plant wastes'have been discharged.

Samples of three cifferent Monthly, when Gamma isotopic and I-131 kindsLof broad leaf vegeta- ' available. analysis.

tion ~ grown nearest each of.

'two different offsite loca-

'tions of highest predicted' annual. average ground level D/0 ift milk. sampling is not perforiaed.

One sample of each of the ' Monthly, when Gamma isotopicb) and similar broad leaf vegeta- available. I-131 analysis.

tion grown'15 to 30'km dis-tant in the least prevaient wind direction .if milk. sm-pling-is not performed.

16.11-51 i

\

4 TABLE-16.11-7 (Page 5 of 7)-

l TABLEl0TATI_0M f - 1. Specific parameters of distance and direction sector from the centerline of the station, and additional description _where pertinent, shall.be provided for each and every sample location in Table 16.11-7 in a table j

< and figure (s) in the ODCH. Refer to NUREG-0133, " Preparation of Radiciogical Ef fluent Technical Specifications for Nucelar- Power Plants,"

.i October 1978, and to Radiological Assessment Branch Technical Position, 4 Revision 1, November 1979. Deviations are permitted from.the required i sampling schedule if specimens are unobtainable due to circumstances such j as hatardous conditions, seasonal unavai_1 ability, and malfunction of i automatic sampling equipment. If specimens are unobtainable due to

! sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. . All deviations from the sampling schedule shall be documented in the Annual

. Radiological Environmental Operating Report. It is recognized that, at i times, it may not be possible or practicable to continue _to obtain i samples of the media of choice-at the most desired location or time. In

the e instances suitable alternative media and locations may be chosen

for the particular pathway.in question and appropriate substitutions made l within 30 days in the- Radiological Environmental- Monitoring' Program.

! Identify the cause of the unavailability of samples for that-' pathway-and-l identify the new location (s) for obtaining replacement samples in the

!- next Semiannual Radioactive Effluent Release Report and also include in

{ the report a revised figure (s) and table for the DDCM reflecting-the new j location (s).

4

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

. Film badges shall not be used as dosimeters for measurir direct ,

radiation. (The 40 stations is not an absolute n' umber. The number of. '

j direct radiation monitoring stations may be reduced according to

geographical limitations; . e.g. ,- at an ocean site, some sectors will. be-over water so_that the number of dosimeters may be reduced accordingly.

The frequency of analysis or readout for TLD systems will.~ depend upon the

[ -characteristics of the specific system:used.and should be selected to l .obtain optimum dose information within minimal fading.-)-

3. Airborne particulate sample filters shall be analyzed for gross beta-

. radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more af ter sampling to-allow for radon and thoron daughter decay. If gross beta . activity in air particulate samples is greater than 10 times the yearly-mean_of control samples,. gamma

. isotopic analysis shall be performed ~on the individual samples.

4

.16.11-52 1

IABLE_16 s 1[17 (Page 6 of. 7) ,

TABLE NOTATIONS _(_ Continued).

4. Gamma isotopic analysis means the ~ identification and qu6ntification of gamma-emitting radionuclides that may be' attributable to the effluents from the facility.

5. The " upstream. sample" shall be taken at-a distance beyond significant ;

influence of the discharge. The " downstream" sample.shall be.taken~in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to be-beyond thel plant influence. : Salt water shall be sampled only when the receiving water is utilized for recreational activities.

6. A composite sample is one in which the rate at which the' liquid. sampled-is uniform and in which the method of sampling employed.results in a specimen that is representative of the time averaged concentration at the location being sampled. ..In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly);in order to assure obtaining a representative sample.

7. Groundwater samples shall be taken when this-source is tapped for-drinking or irrigation purposes in areas where the hydraulic gradient-or:

recharge properties are suitable for contamination.

8. The dose shall be calculated for the maximum organ and agcLgroup, using l the methodology and parameters in the ODCM.

[ 9. If harvest occurs more than once a year, sampling shall be performed

during each discrete harvest. If harvest occurs continuously, sampling I l shall be_ monthly. . Attention shall be paid to including samples of l l tuberous and root food products. ,

q i I s

l 1

< l\

I 16.11 ,

, + - - -n U ,

TABLE 16.11-7-(Page 7 of 7)

. REPORTING LEVELS FOR RADIDAC1.VITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

-REDORTING LEVELS l

WATER. AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pC1/2) OR GASES (pCi/m2 ) (pCi/kg, wet) (pC1/t) (pCi/kg, wet) -

H-3' 20,000(I)-

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 .300 10,000 Zn-65 300 20,000 l

Zr-Nb-95 400-I-131 .2 0.9 3 .100 Cs-134- '30 10 1,000 60 -1,000 Cs-137 50 20 2,000 70 2,000

.Ba-La-140 200 300 i

(1)For-drinking -water samples. ' This -is '40 CFR Part 141 value. If.no drinking water pathway exists, a value of 30,000 pCi/t'may be used.

p 16.11-54

TABLE 16.11-8 (Page 1 of 3)

I ) (2)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS l

LOWER LIMIT OF DETECTION (LLD)(3)

! MILK FOOD PRODUCTS SEDIMENT FISH WATER AIRBORNE PARTICULATE (pCi/kg, wet) (pCi/t) (pCi/kg, wet) (pCi/kg, dry) .)

, ANALYSIS (pCi/t) OR GASES ipti/m')

I Gross Beta 4 0.01 H-3 2000*

f 130 Mn-54 15 260 Fe-59 30 330 Co-58, 60 15 30 260 Zn-65 Zr-Nb-95 15 1 60 I-131 1(4) 0.07 60 150 0.05 130 15 Cs-134 15 18 80 180 18 0.06 150 Cs-137 15

. 15 Ba-La-140 "If no drinking water pathway exists, a value of 3000 pCi/t may be used.

l 16.11-55 u_.________ __

TABLE 116.11_-8-(Page2of3)

IABLE NOTAT10JiS_

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

~

1.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analy.ed and; reported in the Annua 1 Radiological Environmental Operating Report.

2. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommenda-tions of Regulatory Guide 4.13.

3. The LLD is defined, for purposes of these commitments, as the smallest cencontrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% pro-bability.with only 5% probability of falsely concluding that.a blank-observation represents a "real" signal,

~

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

) 4.66 s b j LLO = E V 2.22 Y exp (-Aat) t i

! Where:

LLD = the "a priori" lower limit of detection (picoCuries per unit-l mass or volume);

s b

= the ' standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts j: per minute);

i E = the counting efficiency (counts-per disintegratibn);

i j -V = the sample size (units of mass or volume);

2.22 = the number of disintegrations per minute per' picocurie; d

j ;Y = the' fractional radiochemical yield,' when applicable; U

1 = the radioactive decay constant for the particular ,

l radionuclide (sec'); _ and,- i At = the elapsed time between environmental collection, or end of the~ sample collection period, and time of counting.(sec).

Typical values of E, V,-Y and At-should be used..in the calculation.

L k

u

-16.11 ;

l 2

l

JA_BLE_1L.ll-8 (Page 3 of 3)

TABLE NOTATIONS _(Continue d i-

) It should be recognized that the LLD is_ defined as an a priori-(before.

~

the fact) limit representing the capability of a measurement system and not as an a p_osteriori (af ter the f act) limit for a particular

-measurement. Analyses shall be performed in such a manner that-the-i stated LLDs will be achieved under routine conditions,.' Occasionally _-

background fluctuations,' unavoidable smalll sample sizes, the' presence of:

1 interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the= contributing factors shall be identified and described in the Annual Radiological Environmental-

Operating Report.

1.- LLO .for drinking water samples. If no drinking water pathway exists, the l LLD of gamma isotopic analysis may be used.

l t

i 1

j '..

1 I-b l

L j'- i h

i.

4 4 _

16.11-57: .

.b

16.11 RADIO 10_Gl_ CAL _EfF_L1 VENT C0_NTR0l,S

$ RADIOLOGICAL ENVIRONMENTAL MONITORING j' 16.11-14 LAND USE CENSUS COMMITMENT l A Land Use Census shall be conducted and shali . identify within a distance of 8 i km (5 miles) the location in each of the 16 meteorological sectors of the

} nearest milk animal, the nearest residence, and the nearest garden

of greater than 50 m2 (500 ft 2) producting broad leaf vegetation.

i 4

APPLICABILITY: At all times.

REMEDIAL ACTION:

i j a. With a Land Use Census identifying a locationts) that yields a j calculated dose or dose commitment greater than the values currently

, being calculated in SLC 16.11-9, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, i

. b. With a Land Use Census identifying a location (s) that yields a i calculated dose or dose commitment (via the same exposure pathway)

, 20% greater than at a location from which samples are currently

being obtained in accordance with SLC 16.11-13, add the new 1' location (s) within 30 days to the Radiological Environmental Monitoring Program given in the 00CM. The sampling location (s),

excluding the control station location,- having the. lowest calculated

dose or dose commitment (s), via the same exposure pathway, may be

, deleted from this monitoring program after October 31 of the year in i which this Land Use Census was conducted, Submit in the next i Semiannual Radioactive Effluent Release Report documentation for a-

! change in the ODCM including a rev_1 sed figure (s)-and-table (s) for the ODCM reflecting the new location (s), with information'suppor_ ting j the change in the. sampling locations, i

TESTING RE(LULREMENTS:

The Land Use Census shall be conducted during the. growing season'at least once i

per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture-authorities. The results of the Land Use Census-shall be included in the Annual Radiological Environmental Operating Report.

Broad leaf vegetation s:mpling of at least three different kinds of j vegetation may be performed at the SITE BOUNDARY in each of two different- i

, direction sectors with the highest predicted D/Qs in_ lieu of the garden ;

census. Commitments for broad leaf vegetation sampling in Table

, 16.11-7.4.c shall be followed, including analysis of control samples, i

4 16.11-58 II

>s- ,.-

--+%-~.m =+ws - . -yo-4...+- --gp #wN 1r+-4m

REFEMNCES:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix I BASES:

This commitment is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to_the Radiological Environmental-Monitoring Program given in the ODCM are made if required by the results of this census. The best information from the door-to-door survey, f rom aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Apper; dix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m provides assurance that 8

significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.v., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m'.

f i

16.11-59

16.11 _RADIOLOGICALEFFLUENLC.0NTROLS L

RAQlQL0filCALENVIRONMENTALMON[TQRING 16.11-15 INTERLABORATORY COMPARISDN PROGRAM ,

l

[0MM IMENT _

Analyses shall be parformed on all radioactive materials, supplied as part of an Interlaboratory Come .rison Program that has been approved by the Commissi ., that correspond to samples required by Table 16.11-7. !

ADPLICABiLITY: At all times.

REMEDIAL _6$11QN:

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

TESTING REQUIREMENTS:

The Interlaboratory Comparison Program shall be described in the ODCH. A ;

summary of the results obtained as part of the above required Interlaboratory

~

Comparison Program shall be included in the Annual Radiological :nvironmental Operating Report. 1 REfERENRE$:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix I BASES: ,

J The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and ;

accuracy of the measuraments of radioactive material in environmental sample ;

matrices are performed as part of the quality assurance program for '

environmentti monitoring in order to demonstrate that tht 'esults are valid -

for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.

s 4

L L

i 16.11-60 l i b l

16.11 RADIOLOGICAL EFFL @ (T CONTROLS REf0RTS 16.11-16 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT AND SEMIANNUAL EFFLUENT RELEASE REPORT COMMITMENT 16.11-16.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL O MRATING REPOR1*

Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the preetous calendar year shall be submitted prior to May 1 of each year.

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

! The reports shall also include the results of the land use census..

The Annual Radiological Environmental Operating Reports shall include the--

results of analysis 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

! format of the table in the itadiological Assessment Branch Technical Position, i Revision 1, November 1979. In the event that some individual results are not i available for inclusion with the report, the report shall be submitted noting i and explaining the reasons for the missing results. -The missing data shall be i submitted as soon as possible in a supplementary report.

! The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps **

, covering all sampling locations keyed to a table giving distances and dir-i ections from the centerline of one reactor; the results of licensee participa-i tion in the Interlaboratory Comparison Program, required by-SLC 16.11-15; l discussion of all deviations from the sampliag schedule of Table 16.11"7; and i- discussion of all analyses in which the LLD required by Table 16.11-8 was not achievable.

A single submittal' may be made for the station. l

. ** One map shall cover stations near the SITE BOUNDRY, and a second map shall include the more distant stations.

I i

16.11-61'

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

16.11-16.2 SCHIANNUALRAD10 ACTIVE EFFLUENT RELEASE _ rep 0RT (see Note)

The Semiannual Radioactive Effluent Release Report covering the operation of s the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The kadioactive Effluent Release Reports shall include a summary of the quantitles of radinactive liquid and gaseous effluents and solid waste released from the unit.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stablitty, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. [In lieu of submission witn the first half year Radio-active Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.) This same report shall include an assess-ment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include ,an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBER OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and-location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. Tl.e assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed HEMBER OF THE VUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation". Acceptable methods for calculating-the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period:

a. Total Container volume, in cubic meters,

b. Total Curle quantity (determined by measurement or estimate),

16.11-62

- ~

t

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

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

t

e. Number of shipments, and ;

f. Solidification agent or absorbent (e.g., cement or other approved I agents (media)). !

The Radioactive Effluent Release Reports shall include a list and description ;

of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Oedioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose i calculations and/or environmental monitoring identified by the land use census pursuant to SLC 16.11-14. .

Note:

A single submittal may be made for the station. .The submittal should combine i those sections that are common to both units.

s

)

i s

16.11-63 ;

W 7 *"

"*TT*F y Fw w *3' P' by*N$ d-.3af'N'-et'e"' -P'.w -"

Tin * #ffW *

% 9 * "'y~' '

SITE BOUNDARY PERIMETER FENCE , y" %

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/,W g NSW y~

g DAM t~

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f NUCLEAR SERVICE f

WL1 4 WATER POND - 'l ~

2500 FT. R. ,- ,

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!' EXCLUSION / '

BOUNDARY ,.

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,/ n INTAKE STRUCTURE

/ j I MONITOR TANK SUILDING b( (GASEQUS RELEASE POINT)

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i . . .ME m ........n:::n::n ::n n

>: nn v 2

1

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TUR8INE DGS p

REACTOR 8LDGS.

STATION VENTS (GASEOUS RELEASE POINTS EL 718,75)

/

i SWITCH -'

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/

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I \ a YARD '/ COOLING l l TOWER

' AUX, ARD 2

, w

1 ; ; ; j ACCESS ROAD _ BLDG, I .

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i TOWER TRAINING CENTER

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I DISCHARGE '

N STRUCTURE (LIQUID RELEAS h' [ '

POINT) CHEMICAL '

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f TREATMEN /

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h, CO RD 1' 132 .

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FIGURE 16.11-1

~ CATAWBA - UNITS 1 AND 2 *

, , _ . ~ , _ .

. _ . . -

ML20097G155

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