ML20082G578
| ML20082G578 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 06/10/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20082G498 | List: |
| References | |
| NUDOCS 9108190230 | |
| Download: ML20082G578 (168) | |
Text
_ _ _ _ _ _ - _ _
AUACHMENLD PROPOSED._CHAMESJO AEPENDIX A IICHNICALSELCIE1 CATIONS 0LFACIL11Y OELRAUMJ.1CENSESRf.-31dEE-66._MPI ILANDJtPE:71 IL 'ptdAt10D BnidWOLSlatica i
Ety_Litthati: II RtylitL Rigu : !I VI VI VII A/11 XIII 'XI!! -
XIV- 11V XV 4V XVIII 1VI!!
XXI 4XI 1-4 4 '
1-6 A-6 3/4 3-57 through 73 3/4 3-59 through 75 3/4 11-1 through 19 3/4 11-1 through 19 3/4 12-1 through 14 3/4 12-1 through 14 B3/4 3-6 B3/4 3-6 B3/4 11-1 through 7 B3/4 11-1 through 7 B3/4 12-1 B3/4 12-1 B3/4 12-2 B3/4 12-2 6-17 6-17 6-19 6-19 6-20 6-20 6-21 6-21 6-23 6-23 6-25 6-25 6-26 6-26 ZNLD/651:22 .
o10919o230 910610 DR ADOCK0500y:4
_ _ __ __ _ _ _ _ . _ .-__ _ . - ~ _ _ _ _ .. - _ _ _ ._ -__ _ _ - - - _ - _ _ _ . - ~
INDE_X DEFINITIONS SECTION
, _f' T7, r;i g l PAGE 1.32 50 L-I DI F I C AT 10N. ;v. s. r. . . . . . . . . . . . . n . . . . . . . . . . . . . . . . . 4 , . . .
1-6 1.33 SOURCE CHECK............................................... . 1-6 1.34 STAGGERED TEST BASIS........................................, 16 1.35 THERMAL P0WER................................................ 1-6 1.36 TRIP ACTUATING' DEVICE OPERATIONAL TEST....................... 16 1.37 UN I D E N T I F I E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ., . . . . . . . . 16 1.38 UNRESTRICTED AREA............................................ 1-6 1.39 VENTI LATION EXHAUST TREATHENT SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.40 VENTING...................................................... 1-7 1.41 WASTE GAS HO LDUP SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 TABLE 1.1 FREQUENCY N0TATION...................................... 18 TABLE 1.2 O P E RAT I O N A L H0 D E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .19 1
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l BYRON - UNITS 1 & 2 Il
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
SECTION ';
PAGE l 3/4.3.3 MONITORING INSTRUMENTATION i
Radiation Monitoring for Plant Operations................ 3/4 3 39 ;
TABLE 3.3 6 fiADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS................................ 3/4 3 40 i TABLE 4.333 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE f.
t REQUIREMENTS........................................ 3/4 3-42 i Movable Incore Detectors................................. 3/4 3-43 ~ i Seismic Instrumentation.................................. 3/4 3-44 TABLE 3.3 7 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3 45 Meteorological Instrumentation........................... 3/4 3 47 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION. 3/4 3. 48 ...........
TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION !
L SURVEILLANCE REQUIREMENTS........................... 3/4 3-49 !
Remote Shutdown Instrumentation.......................... 3/4 3-50 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION............ 3/4 3-51 l
TABLE 4.3 6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................... 3/4 3 52 ;
Accident Monitoring Instrumentation...................... 3/4 3 53 ,
TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION ................. 3/4 3-54 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION j
SURVEILLANCE REQUIREMENTS........................... 3/4 3-55 ;
Loose-Part Detection System.............................. 3/4 3-56 $ !
-Radioactive-Liquitiffbnt "wnitoringimt -nt tien m -3/4 317- U
-TAB LE S r3 RA010 ACTIVE-LIQUI D - E F F LUENT-MONITOR ING #
--IHsieuMENTAT40N 4/' 343 e%%wa . ]
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LIMITlHG CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS SECTION .P A..G_E.
4ABLE 4.>O, RADIOAC44VE-ti4010-EfftVENHONHORING
, 4ETEMENTATiON-GURVE4RANCE-REQUIREMENM. . . . . . . . . . 9/4M
- k Monitorin*g Instrumentation.
. Rad 44acti n Cassous 4 m u nt 3/4 3-l @
TA i r 4.'3-13,ftA010AGT14E-GASE005-EfftCENT HONITORING f
Y%'D INSTRUMENTATION.................................... 3/43M%
TAfit E 4. 31* RAD 10ACTW4-GASEOE-E4tVEM, HON!TORING b"* INSTRUMENTATION SURVEILLANCE REQUIREMENTS........... 3/4 3 D'A,[@
TABLE 3.3-14 HIGH ENERGY LINE BREAK INSTRUMENTATION................ 3/43-72,Q 3/4.3.4 TURBINE OVERSPEED PROTECT 10N............................. 3/43-73$
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.............................. 3/4 4-1 Hot Standby.............................................. 3/4 4-2 Hot Shutdown............................................. 3/4 4-3 Cold Shutdown - Loops Fi11ed............................. 3/4 4-5 Cold Shutdown - Loops Not Fi11ed......................... 3/4 4-6 Loop Isolation Valves-Operation.......................... 3/4 4-7 Loop Isolation Valves-Shutdown........................... 3/4 4-8 3/4.4.2 SAFETY VALVES Shutdcyn............................................... 3/4 4-9 0perating.............................................. 3/4 4-10 3/4.4.3 PRESSURIZER..........................................'.... 3/4 4-11 3/4.4.4 RELIEF VALVES............................................ 3/4 4-12 3/4.4.5 STEAM GENERATORS......................................... 3/4 4-13 TABLE 4.4-1 MINIMUM HUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION......................... 3/4 4-18 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION....................... 3/4 4-19 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems................................ 3/4 4-20 Operational Leakage...................................... 3/4 4-21 '
m%an. m mgM
L,JMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS i l
SECTION g i 3/4.10 _ SPEC!AL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN 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 TE5TS............................................
3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS....................................
3/4 10 4
- 3/4.10.5 POSITION IN0! CATION SYSTEM - SHUT 00WN.................... 3/4 10 5 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS c..._............................................. 3/4-11 -TABL E-4 r11-1-RADI OACTI VE-t-!QU10 +AS TE-S AMPi i NG-AMD-
""iV615440CaJ"..................:............... 3/4 -11 4
-0eee........................r m .... rn r..... n......... .W -li-fr-- '
-44wi44*dwest+ T r::t :n t-4y*4eerre. . . . . . . . . . . . . . . . .'. . . . . 4/4-14=N t Liquid Holdup Tanks................................'......
3/41141 3/4.11.2 GASEOUS EFFLUENTS 0 ;; "
t:................................................ 4/4-1F9--
-TABLE 4.11-2 RA010 ACTIVE-GAHOE - W'.STE .'.""LI"O 'S ANAL %I S ^ R00 RW. . . . . . . . . . . . . . . . .w. r. . . . . . . . . . . . . 3/4-11-10 00 : ": t h 0 : : : ; . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . r. . . . . . . . 0/4 19- i Oc;e - Iedine-iSI-end-13h-Tritivm; and-Redirectiw
-Mater 4eb4w9et4ala te -Fem. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/' 14-0 :::= "edwa:t: T ::' :nt 5,y:4ee........................ 3/4-11-1 F Explosive Gas Mixture....................................
3/411-M 2 Gat Decay Tanks.......................................... 3/411-N 3 l
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BYRON - UNITS 1 & 2 . XIII i
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-. - - _ = - . . _ -- . - - --- _- _.. - -
LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE REOUIREMENTS SECTION 3/4.1 . SOLID RADI0 ACTIVE WASTES................................ 3/4 11-18 3/4.11.4 10u q 0SE.......................................... .... 3/4 11-19 3/4.12 RADIOLOGICAL ENVI ONMENTAL HONITORING V
3/4.12.1 MONITORING. PROGRAM......... ..
........................ 3/4 12-1 TABLE 3.12-1 RADIOLOGICAL ENVIRONM TL ITORING PROGRAM........ 3/4 12-3 TADLE 3.12 2 REPORTING LEVE R RADI0ACTIVIfY40NCENTRATIONS IN ENV ENTAL SAMPLES.,............. .......... 3/4 12-9 TABLE 4.12-1 DE ION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS.................................... 3/4 12-10 3/4.13 . LAND USE
/ CENSUS.......................................... 3 2-13 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM....................... 3/4 12 4 O
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BYRON - UNITS 1 &'2 XIV
BASES SECTION PAGE 3/4.0 APPLICABILITY............................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION 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 3/4.2__ POWER OISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX 0!FFERENCE..................................... B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....... B 3/4 2-2 FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX O!FFERENCE VERSUS THERMAL P0WER.................................. B 3/4 2-3 3/ 4.2. 4 QUADRANT POWER TILT RATI0................................. B 3/4 2-5 3/4.2.5 DNB PARAMETERS............................................ B 3/4 2-6
,3/4.S_ INSTRUMENTATION 3/4.3.1 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 YURBINE OVERSPEED PROTECTION.............................. B3/43@
u t.,
3/4.4 REACTOR COOLANT SYSTEM C'p.a " " ] m" ".' "
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............. B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................. B 3/4 4-2 l 3/4.4.3 PRESSURIZER............................................... B 3/4 4-2 l
l 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-2 l
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3/4.9.6 REFUELING 3/4.9.7 NACHINE......................................... t 3/4 P 2 CRANI TRAVEL - $ PENT FUEL $TORAGE FACILITY................ t 3/4 6-2 3/4.9.8 RE5! DUAL NEAT REMOVAL AND COOLANT CIRCULATION. t 3/4 Pt . . . . . . .
3/4.9.9 CCNTAINMENT PURGE !$0LAT!0N
$YSTEM........................ t 3/4 P3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR YE$$EL and
$TORAGE P00L............................................ 8 3/4 P3 3/4.9.12 FUEL HANDLING BUILDING EXNAU$T FILTER IPLENUM 3/4 P 3 SYSTEM 3/4 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 $HUTDOWN MAR 0!N.............. ............................
8 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DI57R13UT!0N 8LIMITS.... 3/4 10 1 3/4.10.3 PHYSICS TE5TS..............-.............................. 8 3/4 10-1 3/4.10. 4 R EACTOR C0OLANT L00PS. . . . . . . . . . . . . . .I .3/4 . . 10-1 3/4.10. $ POSITION INDICATION SYirEM - $NUTD0WN.8. 3/4 . . .10-1 3/4. n RADI0 ACTIVE EFFLUEQ1 3/4. n.1 L IQUID FF'lcNT+ .f.Y.3. 7.# D. . . . . . . . . . . . . . . . . . . . . . . . . . L 3/4.n.2 "'^"!
' SWIGE3 o.#.'.I'.'! 7.'. 6,y, ,y,mTs3
. ,,, f,6,p, ,0,o,A y m $f , ,
,,, , 7, gf4 n.sg g 1/471173--$0L!D-RA010ACT!Yt-WASTE $. . . . . . . . . . . . . .94 . . ./4-H4 1/471174 - 70TAL-00SE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,
3/442 RADIOLOGICAL ENVIRONMENTAL MONITORING '
3/4.12.1 MONITORING PROGRAN..........
....................... 8 3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4.12.3
........................... ... 8 3/4 12-1 INTJRLA80 N Y COMPARISON PR0 GRAM....................... /4-124 i
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8YRON - UNITS 1 & 2 XVI!! I AMEN 0MENTNo.h
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ADMINISTRATIVE CONTROLS SECTION PAGE i 6, 7 SAFETY LIMIT V10LAT!0N........................................ 6-15
\
- 6. 8 PROCEDURES AND PR0 GRAMS....................... ............... 6-15 6.9 REPORTING REQUIREMENTS........................................ 6-18 6.9.1 ROUTINE REP 0RTS............................................. 6-18 Startup Report......................................'........ 6-18 Annual Reports.............................................. 6-18 Annual Radiological Environmental Operating Report.......... 6-19 Semiannual Radioactive Effluent Release Report.............. 6-20 Honthly Operating Report....................................
6-21 Radial Peaking Factor Limit Report..........................
6-21 6.9.2 SPECIAL REP 0RTS............................................. 6-22 6.20 RECORD RETENTION............................................. 6-22 6.11 RADIATION PROTECTION PR0 GRAM,................................ 6-23 6.12 HIGH RADIATION AREA.......................................... 6-23 6.13 PROCESS CONTROL PROGRAM (PCP)................................- 6-25 6.14 0FFSITE DOSE CALCULATION MANUAL (0)CM)....................... 6-25 v
--0.10 MAJOR-C4+ANGE+-TO-t-!Otfie-6ASECUS. - AND SOLIO RA0 WASTE
-TAEATHENT SYSTDiO %
- F26-ft&ktr Qts Or ,t word ruusJ BYRON - UNITS 1 & 2 XXI
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DEFINITIONS OFFSITE DOSE CALCULATION MANUAL WSERr i y -
1.18f 4-.0FJSHE-00SE1AtttfLATIO ~MANUAt-t SCM)contain sna i ltqe methoso ogy mrTit meters used in thq calcula on of of ite coses Jabous d li id effluent , in the etoraKoactive efflugnt rgnitor og Alarm /T(rgSetpoinalculatiog of gaseou and in the-conduct f.theand liqu(d Environ-pte T' Scie ++g4ee44eMteH ng r, up om. -
OPERABLE - OPERABillTY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capaole of performing its specified function (s),
and when all rtcessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are requie<d for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATING LIMITS REPORT 1.19a The OPERATING LIMITS REPORT is the unit-specific document that provides-operating limits for the current operating reload cycle. These cycle spccific operating limits shall be determined for each relomi cycle in accordance with Specification 6.9.1.9. Plant operation within these operating limits is adcressed in individual specifications, OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specif1ed in Table 1.2.
DHVSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam jenerator tube leakage) through a nonisolable fault in a Reactor Coolant System component -
body, pipe wall, or vessel wall.
PROCESS CONfROL PROGRAM _ p u as i) u 1.23 samo ing,\ fixuttn C0ttfR0rPROGRAi'i analyses,7ests, and (r'te) snali contain the-current i viinu?ss) sure that prohqssing and packaging of solid dioactiveN astes based o erminations processing,01 actual or simulated we solid waslas will,be accom'p shed to be made to %n trated in
$m such a yay as to assure gefnpliance wi 0 CFR Pat W 20, 61. 71 an {ederal and St11te. regulations r -tfuriakgroun equirements, and othar requirements f loverning the disliosal of radioactive wastes. )
BYRON - UNITS 1 & 2 14 Amendment No. % -
DEFIN!TIONS SOLIDIFICATION j DD 1.32 b "IfICAilCs moi; L. se conve,.;m, of -d auts shicMn; .d MHa! gr;.:nd requhements. ...ie. ;m fa- Wt SOURCE CHECK 1.33 A SOURCE CHECK shall be the qu.11tative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of: * !
a.
A test schedule for systems, subsystems, trains, or other designated components equal subintervals, obtained andby dividing the specified test interval into n b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
THERMAL POWER 1.35 coolant. THERMAL POWER shall be the total core heat transfer rate to the re TRIP ACTUATING DEVICE OPERATIONAL TEST 1.36 Trip trip functions. Actuating Device and verifying OPERABILITY of alarm, The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.37 UNIDENTIF'IED LEAKAGE shall be all leakage which is not IDENTIFIED L or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
BYRON - UNITS 1 & 2 1-6
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INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMll!NG CONDITION FOR OPERATION i
3.3.3.9
'N !
Theradioactiveliquideffluentmonitoringinstrumentatiopdhannels !
shown in Table 3.3 12 shall be OPERABLE with their Alarm / Trip Setnsints set to i ensure that the limits of s Specification 3.11.1.1 are not exceedeyl The Alarm / i Trip Setpoints of these'thannels shall be determined and adjustard in accordance ;
with the, methodology and parameters in the OFFSITE DOSE CALCU T10N MANUAL (00CM).
APPLICABILITY: At all times. N ACTION: -
- a. With a radioactive liquid effluent monitoring instrumentation channel I Alarm / Trip Setpoint less conservative Ahan required by the above !
specification, immediately suspend the release of radioactive liquid effluents monitored by-the effected channel, or declare the l channel inoperable. i
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/ .
i
- b. Witn less than the minimum numb'r e of radioactive liquid effluent monitoring instrumentation channels OPERABLE take the ACTION shown !
in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within the time spicified in the ACTION, or explain in the next l Semiannual Radioactive Effluent Release Report pursuant to Specifica- L tion 6.9.1.7 why thisA noperability was not corrected within the time specified. ;
,/ '
- c. F The provisions of' Specifications 3.0.3 and 3.0.4 are not ' applicable.
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-SURVEILLANCE RE0V! REPENTS j
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\ f 4.3.3.9- Eaqti radioactive liquid effluent monitoring instrumentation channel ;
shall be demonstrated OPERABLE by performance-of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at l the freytluencies shown in Table 4.3 8.
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{' 8YRON - UNITS 1 & 2 3/4 3-57 Amendment No. K l ;
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IABLE 3.3-12 RADICACTIVE L IQUID ErittJLNT MONITORitG INSTRUMENTATION /
, N,,
_ N fliNIMUM
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\s INSTRUMENT C:iANNELS OlFRABLE
/
ACTION Radioactiv'ity Monitors Providing Alarm and Automatic Termination of Release 4
a.
I
- b. Liquid Radwiste Ef fluent Line (ORE-PR001)
- c. Fire and Oil Su=p Discharge (ORE-PR0'15) 1 31 1
Condensate Polisher Sump Discharpe (ORE-PR041) 34
- 2. s 1 34 Radioactivity Monitors PrcWiding f.lara But Not Providing Automatic Termination of Release '
s i
- a. Essential Service Water '
C"7 I rn 1
- 1) L' nit 1 e F
\ u 's 31 j h ni j a) RCFC 1A and IC Outlet (IRE-PR002) ' s .
1 '
o x 32 -
b) RCFC IB and ID Outlet (IRE-PR003) s, 1
32
- 2) Unit 2 ,
a)
RCFC 2A and 2C Outlet (2RE-PR002) -
/ '
1 32 b) RCFC/2B and 2D Outlet (2RE-PR003) 1N s
- b. Stati 32 owdown Line (ORE-PRO 10) fk 3. Flow R 1 'N I x !MeasurementDevices 32 -
/$ a.
Liquid Radwaste Effluent Line (toop-WX001)
- f '
1
[ ]x I <>
- b. Liquid Radwaste Effluent Low Flow Line (Loop-WX630) 33 l i'
' 1 I c. 33 i
y Station Blowdown Line (Loop-CWO32) 1 33 -
I e.
)
- ~ W_ ,
TABLE 3.3-12 (Continued)
AC110N STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the
\n V Minimum Channels OPERACLE requirement, effluent releases via this pathway may continae for up to 14 days provided that prior i i
to initiating a relwase: :
- a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and /
- b. At least two technically qualified members of the facility staff ihdependently verify the release rate calculations and {
i discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway. l ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels Of(RABLE requirement, effluent releases via this ,
pathway may continue for up to 30 days provided that, at least !
once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for I radioactivity at a lower limit of detection of no more than 10 7 1 microcurie /m). I ACTION 33
- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is i estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. '
performance curves generated in place may be used to estimatePum flow, i
i ACTION 34 - With the number of channels OPERABLE less than required by the ,
Minimura Channels ODERABLE requirement, effluent releases via this ! .
pathway may continue for up to 30 days provided grab samples are l analyzed for radioactivity at a lowet limit of detection as i specified in Table 4.11-1:
- a. At deast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specifje activity of the secondary coolant is greater than 0.01 micraCurie/ gram DOSE
, EQUIVALENT l-131, or
, bl At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific act ity of the
/ secondary coolant is less than or equ11 to 0.01 microcurie /gran e
/
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MRON - UN145 1 1 J 3/4-3 $ A AMENO"[Ni M 6
k TABLE 4.3-8 3 ~
RADICACTIVE LIQUID EFFLUENT MONITCR;NG INSIRUMENTATION SURVEILLAKE REQUIR s ,/
h j5 N DIGITAL ~ , ANALOG M INSTRUMENT N CHANNEL SOURCE CI:ANNEL CHANNEL / CHMc4EL CHECK OPERATIONAL OPERATIONAL J. 1. N CHECX CALTBRATION TEST TEST y
Radioactivity Monitors Providing .
Alarm and Automatic Termination of Release a.
'\
l-
- b. Liquid Radwaste Ef fluent Line (ORE-PR001) D P Fire and Oil Sump Discharge (ORE-PR005) R(3)# Q(1) N.A.
- c. D M R(3)
Condensate Polisher Sump Discharge D M Q(1) N.A (0.iE-PR041) '
R(3) Q(I) N.A 2.
Radioactivity *1onitors Providing Alarm But Not Providing Automatic Termination ,
of Release --
a.
Essential Service Water p
~
, 1) 0,it 1 '
a) RCFC 1A and IC Out1[t (IRE-PR002) D M R(3) b) RCFC IB and/ID 09tlet (IRE-PR003) D Q(2)
M R(3)f Q(2)
N.A.
N.A.
- 2) Unit 2 / '
a) RC b) RCFC A and 2C Cutlet (2RE-PR002)D M R(3),
28 and ZD Outlet (2RE-PR003) D M R(3), N Q(2) N.A.
b.
/ '-
Q(2) N.A. l Station Blowdown Line (ORE-PR0101 3.
/ D M R(3)s Q(2) N.A.
Flow p date Measurement Devices s f E /
A Liquid Radwaste Effluent Line N
N
- 5 (Loop-WX001) ' j D(4) N. A. R, I
- b. N. A.
s Liquid Radwaste Effluent Low Flaw Line Q f (Loop WX630) I '
- c. D(4) N.A. R ;
Station Bicwdown Line (Loop-CWO32) N.A. Q I D(4) N.A. R N.A. Q l
- ~
~
/p_ TABLE 4.3 6 (Continued) N TABLE _ NOTATIONS ) ;
i
- Th'd pecified 18 month interval may be extended to 32 months for Cy le 1 only.
l (1) The O!GITAL CHANNEL OPERATIONAL TEST shall also demonstrate ist automatic f isolation of this pathway and control room alarm annunciat n occur if any of the following conditions exists: f a.
Instrument indicates measured invels above the Al rs/ Trip Setpoint, or I
- b. Circuit failure (monitor loss of communicati s - alarm only, detector loss of counts, or monitor loss of power), r ;
- c. Detector check source test failure, or
/ i
- d. Detector channel out-of-service, or I
f
- e. Monitor loss of sample flow. l .
(2) The DIGITAL CHANNEL OPERATIONAL TES Vshall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
a.
Instrument indicatesd measure Itvels above the / Alarm Setpoint, or
- b. Circuit failure (monitoy loss of communications - alarm only, detector loss of counts, or monitor loss of power), or ;
- c. Detector check sou test failure, or f
s
- d. Detector channe ' t of-service, or f
- e. Monitorlossffsampleflow. \
l /
(3) \
one or more of j The initial CHANNEL CALIBRATION shall be performed thereference/tandardscertifiedbytheNationalBureau usin'g'of Stan 3 (NBS) or usi 1 participate.pgstandardsthathavebeenobtainedfromsupphersthat in measurement assurance activities with N8S. These standards,
{ shall pereft calibrating the system over its intended range o(senergy and
} measurement range. For subsequent CHANNEL CALIBRATION, sources 5at have been Tated to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during p riods
- of- elease. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on j d s on which continuous, periodic, or batch releases are made.
\
l b,
\ \
l \ bEJT" DY40N "u171 1 &2 AMENOMw un_12
- 3. - .
__ ~ <L,.J/At41 ____
INSTRUMfNTATION /3,g[
4AMt4044 vf4A S 40uS- UMEH7 MON I TO R I NG I N S T R UMI NT AT I O N
[]MIT]NG CONDst!0N FOR OPERATION
[bbd_
A 3.3.3.10 The nd(eact4*e-$eteevn-ef fluent monitoring instrumerntation channels shown in Table 3.3 13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification (4r11.2.1 ud 3.11.2.5 are not exceeded.
=4h+ Atter4H; Ect;ciet: ;f the;e chraeli-seet4eg4 pee 4fiativn-371 Men-stratP
= h G+termine51mt attjttsted-ir, ecceedenc+-*4tA4he-methodelegy-andterameters%
t h ODCH-~
APPLICA0!LITY: As shown in Table 3.3 13
^ "'
g h,j/,,uet .p
- a. With 6/ pedioact4ve-geeeev+-ef44*entemonitoring instrumentation channel Alarm / Trip 5etpoint less conservative than required by the above specification, .4mmedlete4y-+wspeed-the-eeleete-of-redioact4ve-
.gaseew-stf.luents channelinoperable,7p.dref,i u- W[ittki_;he 7GL. stfe,gygLghtcath
< /cA shom #^ W mdetg It.l ate 13 the_., ' /- -
b.
With less than the minimum number of cedfeective-geseews-efWeeChin, fpp monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3.3 13. Restvre ttie-4noperable-instrumentatise 10 ONRAMi-etettre-within-the-44eenpecified-ir, the - AC440N, cr-ev444*-(*-the-asxt Semiennuel-Rediesetive-Effitrent-Reient-Report pur;eenW fpecificatien-8 1 1.7 wny this invp r eM444y w:: r.;t ;crrecid withir, the t4ee-specified,
- c. The provisions of Specifications 3.0.3, and 3.0.4 are not appilcable.
SURVEILLANCE REQUIREMENTS
/ m Qesjum Ps) fn?
4.3.3.10 Each4ed4+eetive-teeeette-eff4 vent-monitoring instrumentat on channel
-shall be demonstrated OPERABLE by performance of the CHANNEL CHECKg $00 Ret-C+tftth CHANNEL Call 6 RATION and OlGITAL CHANNEL OPERATIONAL TEST at the f re-quencies shown in Table 4.3-9.
67 BYRON - UNITS 1 & 2 3/4 3-ha, Amendment No. g f
TABLE 3.3-13
- g RALIG4ii. : ""5"~'" EFFLtIENT MDEITORING INSTRtMENTATION#
O MM Z
MINIMUM C11AMELS hy
- c. INSTRtMENT OPERABIE APPLICABILIM ACTICM
- =
><3 y 1. p W .1 7:- - i t u . :, ,:,:' = "-it :--
w p a Noble G x Activity u;-;* -
% Ti viidi. 3 "
larm
- pi u : , s- c---- -- ,
r1nr-ppn?pni 1 k sy im nano m or-ennsany $ 3 M din h t.r rior-enn?nr1 4 n _,r_
-- m .)
- u. _- - .-.m -.--,.a sm . . . - 0 1
g d. E iii ga. 6 f3 sii II L k
+ g L _ l r-; h . 9- (tm" "*" }
Y )
y c. {q n i{Iuw nate ave 43uriee9 Cr v i ts- M
[ r s r ru v rr tid Osed)
J d 2. A Pi--+ "e-' h i S- ' n; Sp ' - - a i ' ?
& rivult beh eb b $ w $ 1y NGild
, Provioim; hiwa i} tilgh Range (2Mt rnuicu) d-. bh3 OG A 5~[ ( 6. U b 3 7- . -E wi'eJ /
- t. E^d i im 3ewier ( ArtL-inC26C) 4
, ,a
,E .
I 15Caleic :uwlU (NE """2 *)
4 m
- u. [## 1^TI Syairm i A w " I' "_
g m>.. ;, oe. .m a=r ==
b J,
K e. .wier i.
wm.ms#
nate m m...; ~+- _A ,
M
, -v-m- .--y _-,r.,e---- . , - - --,--.-.,,u
,, ,,,n-v-- ---,n---, - , , , _ , , - - - , . . , . .
y-e,y ,,--y- ,% 3 - ,,- - .-,r. - - . - . -. y _.m. r.-
(
l
=
r i ;
i
- of
! E tXfL Givt (in3 TABLE 3.3-13 (Continued) .I i * ^JZ'^^!?"'
- M'2 9 P'"O! MONITORING INSTRUMENTATIO/
c
! z MINIMUM CHANNELS INSTRUE NT 3 -. OPERABLE w APPt ICA8ILITY ACTIOeg 3 y 3. Gaseous Waste Man'+ges $1 Systen !
y a. Hydrogen Anaiy.-r if1A'-GW8000)
- 1 ** l 3a I
- b. e,vgen Analyzer (0AT-GW8003) ,
I t **
3a
! c 4 ,te Gas Compressor Discharge ]
{ aygen Analyzer (042DGWOO4) /
t i b 1 *** , ,
! .-_. 38
- 4. Gas Decay Tank Syst== -~
f l
-- i w _
g a.
le Gas Activity Monitor - Providing I
- , Ala Automatic Termination of i * ;
Release -PR002A ar.d 28) i [ 2
- i % 5. Containment Purge Syst i
I i 8 !
! a. Noble Gas Activity Monitor
, reviding 1
1 Alarm (RE-PR0018) 1
- 37 i b. Iodine Sampler a (RE-PR0010)
- 40 I c. Particulate Sampier g (RE-PR001A) 1 * ,[
4 a
3 40 6 Radioactivit itors Providing Alare and i
l Aut
~
losure of Surge Tank Vent-Component g ing water Line (ORE-PR009 and RE-PR009) 2 *
{ _ _. - _ ._ _,...____._ _ 41
_ _ _ _ _ , _ (
r 1
f i
I t
t
..,...,..,_....-.._..~_m . . ~ ,.. -,,._-...__,. .._ ,~,o..... _ __~. . . - _ . _ , _ - . _ . . , . , _ . . _ . _ _ _ _ _ _ . , . . , ~ - . , . . _ . - . . _ . _ . _ _ . - ._.,,,__...._..._..L
YABLE 3.3 13 (Continued)
TABLE NOTATIONS
- % uM
'"During
- Waste Gas Compressor Operation."During W A1) instruments required for Unit 1 or Onit 2 operation .
p ,
ACTION STATEMENTS T10N 35
{
Vith the number of channels OPERABLE required by the less
~ than Minimum Channels OPERABLE requirement. the / conte mayto be prior released initiating to the environment for up the release: at -
to 1
( a.
a 4least red, and two independent samples of the tank's co wnt
- b. At less staff indep technically qualified membe of the facility oischarge vaKnti,y lve 1 neup.verify the releasi rate calculations and }
{
Otherwise
' pathway. , suspend release 4 s radioactive effluents via this ACTION 36 - With the number of channels Minimum Chahnels OPERABLE requirement, an required byOPERABLE the efhvent relea pathway via this the flo es)) mated at4ay least continue for up to 30 days provid46 once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. s ACTION / 37 [ With the number an ofrequired channels the OPER of radioactive effluents via this pathway. Mini RGING ACTION 38 J With the number of chan'.wis OPiRABLE an required by less the th Minimus Channels OPEhBLE requirement, operation ystem may of 3 th per1 haurs @.: ring degassing operations 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations, &
ACTIO!L1 With inimum-chann the number i of channels OPEPABLE an required by less the th
'h pathwaymaycbsOPERABLErequirement hoe-for-un M 30 if4 uent grab releases via this
" rovided MMaud%@iC!A 2'"'N' samples'""# are-
)
BYRON - UNITS 1 & 2 -
i 3/43.g, 53 AmendmentNo.%
_--r:'- ~ ' ,._.._g.~---- #
i l
I I
TABLE 3.3-13 (Continued) e N ACTION STATEMENTS (Continued) x {
i ACTION 40
\ of channels OPERABLE less than required i I-he With the Minimum numbs Channe (ls UM AA Q requirement, effluent s via relthe affected pathway may contT or up to 30 day. ovided samples are continuously collected with ( ia pling equipment as required in Table 4.11 2, ACTION 41 - With the number of ch n OPERABLE less than requ by the t
. Minimum Channels E requirement, effluent releases 4 this [
pathway may co t ue for up to 30 days provided that.-at lea [
once per 1 .ours, grab samples are collected and analyzed for ;
radio 6c vity at a lower limit of detection of no more than 10 7 t misf6 Curie /ml. i 0-- I
( 7 !
l t
r l
l l ;
l i i
f I
i I
j' &
f 4
1 11A 3=66 fie - Pf TS 1
- 7 'r 7.-vii. M. K r
{
, __. _ _ , _ _ _ _ _ _ _ _ _ . . , _ _ _ . _ _ . _ . _ _ _ , . _ . . , - . . _ _ _ _ . . _ . _ _ _ _ . . _ _ . _ . . .._____J
EXPLotvC GAS TA8LE 4.3-9 s
p
-^ :S"U!"" Z'l""Z [TTL*C"! MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS I
DIGITAi CHANNEL MDDES FOR WHICH
! C3%NNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE g
FUNCTIONAL UNIT 1NOT tJ M I)) CHECK CALIBRATION TEST
' _ CHECK IS REQUIRED w f
_, 1. p M _..t Y:rt "c ti..:,y 'y;^ = Ux't I u
s .i . a ii . . ;., L.. ; ;# - .
F.o,ia;. , ,,;es
- 2) "'? *- ;- (1 5- *
- J D K )
- 2) iow aange ( m raui -) 0 3)## Q )
- 2. hei x T- ;?r- (Inr-pan w ) 3)## )
]
il - m, ,i,-oi .e.
c - ?: r yne-pansn') 3)## g(2)
- 4. TI #
i Eff _.. Sy>i " ":- 2 A.
N . .. inn uevice G O 't^^ M)
- c. ? ; M r h *ete 5 ;..-' g p' A. Q 3--f:: (1 9 "*'S5)
Wr up
- 2. . . .m ;. . ..;. L..ii .;, , ',, 6 L. ;. T.o y, --i-- *-+ Gity m .itor_
r . . o ms ,s . . . _-
k o e - .. _ < , r- ==)
- m... w =m) i
+ );' .
)
)
y s x w - 3_,.:.. au ==) na)09 e &-
- c. Fariicui 6e ~~ ;e. (2"' - ?*a ?** ) h 4 )
4 1 -
f I i :=
g, g TABLE 4.3-9 (Continued) g .
0.0;;^C"M *.5E^J^ ', Iira: "2 MONi10 RING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
' c 5 DIGITAL g CHANNEL SOURCE CHAMMEL MODES FOR WHICH FUNCTIONAL UNIT CHANNEL OPERATIONAL y
CPECK SURVEItLANCE
_ CHECK CAllBRATION TEST
- e. 15 REQUIRED
, . Z. Ti m .a.i 1 ito. my system uni t iwo-t 4
(c a.t;.. J )
- n. 2 ::; w ,; W i = E? = w =
" n .c' ; S:cir: ('?^7 'ZZ .,)
~ '
I'df)
"~
~~ E
- 3. Gaseous Waste Management System y a. Hydrogen Analyzer (OAT-GW8000) D 4.A. Q(4) M **
$ b. Oxygen Analyzer (OAT-GW8003) D N.A. Q(5) M **
[>
h c. Waste Gas Cogressor Discharge 0xygen Analyzer (OAIT-GWOO4) D M.A.
7
- M) M ***
7
- 4. Gas Decay Tank System
- a. w Noble Gas ' 't Monitor - o Providing Alars a omatic P
R(3)" Q(1)
- 2 Termination of Release (ORE-PR002A and 28) g s 5. Containment Purge System 'e j
f a. Noble Gas Activity Monitor -
l 5 Providing Alars (RE-P D P
- R Q(2)
I E b. Iodine 5 P 1
P R(3)#f N.A. *
(RE-P )
h c. articulate Sampler P P
- R(3)09 N.A.
(RE-PR001A) i ~
~
j.. TABLE 4.3-9 (Contino-d) e j.*
3 a N i
h RADI0 ACTIVE GASEOUS EFFLUENT MONITORING In3IRUNENTATION SURVEILLANCE REQUIREMENTS g ;
j 2
g DIGITAL \ \
l.
CHANNEL SOURCE CHANNEL CHANNEI.
OPERATT J L PSOES FOR WHICH g FUNCTIONAL UNIT CHECK CHECK' Cf.liBRATION TEST SURVElitANCE .
) 4 15 REQUIRED !
l 4 6. Radioactivity Monitors Providing
" Alarm and Automatic Closure of ,/ :
r Surge Tank Vent Component Cooling /
,/
Water Line (ORE-PR009 and RE-PR009) D M R(3),, Q(1) / * '
/ i j .'N. ,.-
/ l
. m , 7
, s a 1
e
~ x' ,
>b } \
)'
l \
/ !
! i i !
f b C( [
1
,l '
i , .
\ l [
- x
, , N. l I N
'k
,/ '
\
\ .
l
/ 'N,
,. f x
. ,l 4 ~ ~ - -
_ _ , . . ~ , _
~%
i t
.I l
. . }
TABLE 4.3-9 (Continued) t
_ TABLE NOTATIONS i m o i u- c
- During WASTE GAS H0 LOUP SYSTEK operation .
'"During Weste Gas Compressor Operation, bilinstrumentsrequiredforUnit1orUnit2 operation.
imine m iii v R ,mhL^;;.;l n,,,,vu1-u Wer 05tt) su ei -...u. ivi 0, $ ' ^^ % .
}
(1) 4 hv4941AL inef iny of of this CHANNEL pathway and OPERATIONAL control room alars annunciation TEST oc shall ur if also {
t
. 11owing conditions exists: !
I !
a.
Instrument in cates measured levels above or larm/ Trip $etpoint, f
- b. Circuit failure (monitor 1gs - k loss of counts, or monit6'r loss communications alam only, detector ower), or !
- c. Detecto {
i source test failure, or i-
- d. p {
Det ctor channel out of-service, or 1 ";Jdtodett-of-saan).t flow.
m MrD) ',
(2)uA M:C17Au o cn==6 vrtRAllunn Tiii snaii aino m.vumn, son wm vi ' :
alarm annunciation occurs if any of the following co 4tions exists: i i
- i. Instru !
indicates measured levels above Alarm Setpoint, or !
a.
Circuit failure (mo loss of unications alarm only, detector t
loss of counts, or monito of power), or
- . Detector check r#festfa !
1.
Detec ptannel out of service, or !
L Monitor 193Lof smale flow.
( M d u s) _
i (3)n the Win;i;.I Z'?%i. CAUnkai4vn siiill W yvnormec usin more or l
e standards certified by the Nati T l
N85) or u w q that have . u of Standards 1 participate in measu ^_r-r ned from suppliers that i
ihall pe ing the system nce activities with N85. These standards
- u *** r w.
- masur t range. For subsequent CHANNEL CALIBRA ed range of energy and !
M pa.Ja h iva su U,.
',M'4~**14heutia" e.11 W v vu. , ._r:" tg havey -
j (4) !
The CHANNEL CALIBRATION shall include the use of standard gas samp containing hydrogen and nitrogen.
(5)
The CHANNEL CALIBRATION shall include the use of standard gas sample containing oxygen and nitrogen.
j I
t BYRON - UNITS 1 & 2 3/43-% AmendmentNo.)(
- , - - . -. . A'-o m._ - - - - __ ..,__,..--m.,._ - _ - - - - . _ _ . - . - - . - - - - - , ,
~~
INSTRUMENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS LIM 111NG CONDITION FOR OPERATION 3.3.3.11 The high energy line break instrumentation shown in Table 3.3-14 shall be OPERABLE.
l APPLICABILITY: As shown in Table 3.3-14. >
ACTION:
- a. With the number of OPERABl.E auxiliary steam isolation instruments less than the Minimus Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or suspend '
the supply of auxiliary steam to the Auxiliary Building, or establish a +
continuous watch in the affected area (s) until the inoperable sensors are !
restored to OPERABLE status.
b.- With the number of OPERABLE steam generator blowdown line isolation instru- '
ments less than the Minimum Channels OPERABLE as requirsd by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or .
limit the total steam generator blowdown flow rate to less than or equal to 60 gpm or establish a continuous watch in the affacted area (s) until the inoperable sensors are restored to OPERABLE status,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.-
SURVEILLANCE REQUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST AND CHANNEL CALIBRATION at least once per 18 months.
I r I
L 9
BYRON - UNITS 1 & 2 3/4 3- W h AEWENT NO. [ ;
. . . - - _ - . . . - . - . - ~ . _ . - . - - . . - - - . . . ~ . . - - - ~ . - . . - - . . .
4
-1.-
Table 3.3-14 HIGH ENERGY LINE BREAK INSTRUMENTATION Isolation Instrument Function Minimum Channels Applicable Channel OPERABLE MODES
- 1. Auxiliary Steam OTS-AS031A 1
- Isolation OTS-A5032A OTS A5031B 1
- OTS-AS0328 OTDA5031C 1
- OTS-AS032C STS-A5031D 1
- CTS-AS032D OTS-AS031E 1
- OTS-AS032E ,
OTS-A5031F 1
- OTS-AS032F
- 2. Steam Gene m .r TS-SD04SA Blowdowel L1 -
1 1,2,3,4 TS-50045B
- Isolation-TS-SD046A 1 1,2,3,4 TS-50046B TS-SD04SC 1 1,2,3,4 T5-S00450 TS-SD04GC- 1 1,2,3,4 TS-500460 e
i i-
[
- Required when auxiliary steam is being supplied, from any source, to the Auxiliary Building.
BYRON - UNITS 1 & 2 - MEIElfENT ND.
3/4 3- K h {
w ~ - . , , , q - ,e
- ~ . - - -- . - . . . - . - . - - . _ _ -
k 1
i i
INSTRUMENTATCON '
3/4.3.4 TURBINE-OVERSPEED PROTECTION 1
LlHITING CONDITION FOR OPERATION l
3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPLICABILITY:- MODES 1, 2, and 3. I 3
ACTION:
- n.
- With one throttle valve or one governor valve per high pressure turbine f steam line inoperable and/or with one reheat stop valve or one j reheat intercept valve per low pressure turbine steam line inoperable, j restore the Inoperable. valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, t 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1
- b. With the above required Turbine Overspeed Protection System otherwise f
inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolatt the turbine from the steam supply, i t
I SURVEILLANCE REQUIREMENTS
~
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: .
I
- a. During turbine operation at least once per 31 days by direct obser- !
vation of the movement of the valves below through one complete cycle )
f rom the running position: i i
- 1) Four high pressure turbine throttle valves, '
- 2) Four high pressure turbine governor valves, t
- 3) Six turbine reheat stop valves, and
- 4) Six turbine reheat intercept valves. i
- b. Within 7 days prior to entering MODE 3 from MODE 4, by cycling each !
of the 12 extraction steam.nonreturn check valves from the closed position, ;
i
- c. During turbine operation at least once per 31 disys by direct observa- I tion, of freedom of movement of each of the 12 extraction steam non-return check valve weight arms, -i
- d. At least once per 18-months by performance of-CHANNEL CALIBRATION. ,
on the Turbine Overspeed Protection Systems, and ;
- e. At least once per 40 months by disassembling at least one of each of the valves given in Specifications 4.3.4.2a. and b above, and per- :
forming a visual'and surface inspection of valve seats, disks and i stems and verifying no unacceptable flaws or corrosion. t BYRON - UNITS 1 & 2 3/4 3-heendment No. K T 9
-tr,.. ,. _ - -
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS l; r
CONCENTRAh0N f
\
LIMITING CONDITION FOR OPERATION !
?
3.11.1.1 The concentra' tion of radioactive material eleased in liquid effluents :
to UNRESTRICTED AREAS (see Figure 5.1-1) shall b v11mited to the concentrations specified in 10 CFR Part 20, Appendix B, Table . Column 2, for radionuclides other than dissolved or entrained noble gase i For dissolved or entrained ,
noble gases, the concentration \shall be lip ted to 2 x 10 4 microcurie /ml total activity. '
\x / -
/ !
APPLICABILITY: At all times. [ [
ACTION: /
/ \
- a. With the concentration ofjtadioactive, material released in liquid effluents !
j to UNRESTRICTED AREAS exceeding the ab'ove limits, immediately restore the concentration to within'the above limits'.. ,
b.
/. l I
l The provisions of 5 cifications 3.0.3 and 3.0.4 are not appitcable. I -
t
\ !
SURVEILLANCE REQUIREMENTS
. i 4.11.1,1,1 Rad etiveliquidwastesshallbesampledandanalyzedaccordingl to the sampling and analysis program of Table 4.11-1.
4.11.1.1.2 /The results of the radioactivity analysis shall be used in accord # !
ance withjthe methodology and parameters in the ODCM to assure that.the con-centrations at the point of release are maintained within the limits of $
Specifi 'ation 3.11.1.1. ;
/
/ >
-%. /
/ i t
I JUL i i
t t
BY9C" U"ITS P& 2. 3/4 1 R .
i h
i
~ _ _ . _ . . -
--._m
-TABLE 4.11-1 RADI0 ACTIVE L10VIO WASTE SAMPLING AND ANALYSIS PROGRAM ;
LQW(RLIMIT f MINIMUM A$ DETECTION j i
' LIQ JD RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)(I)
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml) ;
- 1. Batch \ ' P P 7
Releash Each Batch Each Batch Princip Gamma 5x10 l Tanks I2 Emitt s I3)
-6 y J1 1x10
-5
'\ P M Dissolved and 1x10 j One Batch /M Entrained Gases
\ (Gamma Emitters)
\ !
-5 )
P M H-3 1x10 EachBakch Comp ite( ) ,7 ;
y Gross Alpha 1x10 ;
P \ !Q
' Composite (4)
Sr-89, Sr-90 . 5x10
-8 f
v EachBatch/ -6
/ \ Fe-55 1x10
- 7
- 2. Continuous / Principal Gamma 5x10 Releases (5) Contirtuous(6) Compol(te(6) bitters (3) b a.-Cir.cuiating I-131 10
[
] Water ~
Blowdown M M Dissolved and 1x10
-5 i i !
I Grab Sample Entrained Gases "
l (Gamma Emitters) l
- b. Waste Watar I' Treatment -5
{ System M Hg- 1x10 Disch ge Continuous (6) Composite (6) )
to F Gross ha 1x10-7 [
\ 8
- c. Condensate Continuous (6) Composite (6) 9 3 " 09' I " 90 N 5x10 ;
olisher _
Sump Fe-55 1x10 Discharge BYRON - UNITS 1 & 2 3/4 11-2 AMENDMENT NO, 15
TABLE 4.11-1 (Continued) x RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT I MINIMUM 0F DETECTION
/
LIQ Q RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY / (LLD)(1)
TYP( FREQUENCY FREQUENCY ANALYSIS (pCi/ml) 3.Continkus W I) W I) Principal codIna 5x10 7
, Release O Grab Sample Emitters (N Essential Service Watez Reactor N Coolant Fan
'\
i Cooler (RCFC)
, Outlet Line s I,
'N /
\ j I-131 1x10.s i
f Dissolved ana i' s ,
Entrained Gases (Gamma Emitters) 1x10 5
, H-3 1x10 5 1
s
/ \
t
/ 's
/ N N
/'
! /
4.NI1,1m 2,4 11->
TABLE 4.11-1 (Continued)
. TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, 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% robability th-only 5% probability of falsely concluding that a blank servation re esents s'"rea.1" signal.
For a particular measurement system, which may include radiochemical separat on: .
- 'h LLD = , /
f.V 2.22 x los . y . exp ( u g)- ,
Where:
i- -
N
-l LLD = the loh r limit of detection (microcuries per unit mass or l volume), \
s y*thestandardijeviationofthebackgroundcountingrateorof i
the counting rate of a blank sample as approptiate (counts per
-minute),_ \
E = the counting efficiency (counts per disintegration).
N Y = the sample size (units'of mass or volume),
2.22'x 108 = the number of. disintegrations per minute per microcurie,,
-l.
Y = the fractional radiochemical yield, when applicable,
- A =-the radioactive decay constant for the particular radionuclide
-l (sec 1), and .
5 At 2 the elapsed time between the midpoint of sample collection.and.-
the-tine of counting (sec).
Typical values of E V, .Y, and at should be u' sed in the calculation.
It should be recognized that the LLD is defined as a'before the . fact limit representing the capability _ of a measurement system and not.as an after the fact, limit for a particular measurement, c -(2) A batch release is the discharge of liquid wastes of a discrete _ volume.
Prior to sampling- for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure
/ representative sampling. \
O
-BYRON - UNITS 1 & 2 3/4 11-4
L TABLE-4.11-1 (Contincea) I TABLE NOTATIONS (Continued) j (3) 1he principal gamma emitters for which the LLD specification applies f i
tnclude the following radionuclides: Mn-54 Fe-59, Co-58, Co-60, 2n-65,- -
ho-99, Cs-134 Cs-137, Ce-141, and Ce-144 This list does not mean that ;
ohly 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 i ;
pursuant to Specification 6.9.1.7 in the format outlined in egulatory '
Guide 1 21, Appendix B Revision 1, June 1974. l
' v i
' (4) A composite sample is one in which the quantity of li id sampled is i proportional to the quantity of liquid waste discharfed and in which the ;
method of sampling employed results in a specimen,that is representative i' i of the liquids released.
/ f
/ t (5) A continuous release is the discharge of liquid wastes of a nondiscrete ,
volume, e.g., from a volume of a system that bas an input flow during the ;
continuous release. ,/ '
t' >
(6) To be representative of the quantities _ahd concentrations of radioactive i materials in liquid effluents, samples'shall be collected continuously in ;
proportion to the rate of flow of the' effluent stream. Prior to analyses, e all samples taken for the compositeEshall be thoroughly mixed in order !
for the composite sample to be representative of the effluent release, !
(7) Not required unless the Essential Service Water RCFC Outlet Radiation
~
Monitors l.RE-PR002 and}RE-PR003' indicates measured levels greater than -
1 x 10 8 pCi/ml above background at any time during the week. I
~
9 3 .
I 5
fg b i
f i L
/ l \
/ / :
/ !
! /
/ !'
/
! / / ;
.{ / /
\
4
/
/
/ !
\
/ :
BYRON - UNITS 1 & 2 3/4 11-5 / [
i
__._ .. _ . _ . - - _ . _. . . . _ . = _ . _ _ _ _ _ . . . - . _ . _ _
~
RADICACTIVE EFFLUENTS ^s x .
DOSE
\ .
)
1 LIM 1 TING CONDITION FOR OPERATION
/
N-
/[
3.11.1.N'\ The dose-or dose commitment to a MEMBER OF THE PUBL'IC from radioactiv materialsin liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure'.5.1-1) shall be limited: '
\
- a. Dur'ing any calendar quarter to less than or equal to 1.5 mrems to '
the whole body and to less than or equal,to 5 mrems to any organ, and , .
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all' times.
ACTION- ,
- a. With the calculathd dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commis~sion within 30 days pursuant to Specifica-tion 6.9,2, a Special' Report that identifies the cause(s) for '
exceeding the limit (s) and defines the corrective actions 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 l with the above limits,
- b. The provisions of Specificat ons 3.0.3 and 3.0.4 are not applicable.
\
SURVEILLANCE REQUIREMENT 5 \
l- .
'.; 4.11.1.2 Cumulative dose contributions from liq id effluents for the current
- calendar quarter and the current calendar. year sha'1,1 be determined in accordance i with the methodology and parameters in the ODCM at least once-per 31 days.
4 i
\&
\
B.YRON - UNITS 1 & 2 ~
-3/4 11-6 l -
l
.= . - - . - - _ _ - . ..-- . - __ - -- - -- . - . - . - - - . - - .
10 ACTIVE EFFLV$RT5 ;
~
LIQUID RADWASTE TREATMENT SYSTEM \v i
LIMITING CONDITION FOR OPERATION
~
\
3.11.1.3 The, Liquid Radwaste Treaunent System shall pe OPERABLE and appropriate i portions of the system shall be used to reduce releases of radioactivity when the projected doses due.to the liquid effluent, from each unit, to UNRESTRICTED :
AREAS (see Figure 5.1-1) would exceed 0.06 mrem t/ the whole body or 0.2 mrem )
to any organ in a 31-day period. /
APPLICABILITY: At all times.
/ :
/ . t
/
(
ACTION: /
i i a. With radioactive liquid waste'being discharged without treatment and :
)
in excess of the above limits and any portion of the Liquid Radw6ste .
Treatment System not in operation, prepare and submit to the !
Commission within 30 days, pursuant to Specification 6.9.2, a Special ,
Report that includes the following information: '.
- 1. Explanation-ofwhsliquidradwastewasbeingdischargedwithout !
treatment, identification of any inoperable equipment or !
, subsystems, and the reason for the inoperability, .
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and ;
- 3. Summary description of action (s) taken to prevent a recurrence, f j b. The provisions of Specifications 3.0.3 and 3.0.4 are not' applicable. '
i t
t SURVEILLANCE ~ REQUIREMENTS i
\ $
4.11.1.3.1 Doses due to liquid releases from eachx nit to u UNRESTRICTED AREAS shall be projected at least once per 31 days in e:cordance with the methodology ;
and parameters in the ODCM When'the Liquid Radwaste Treatment System isl ot ,
i
,being fullyuses>Hemt '
t 4.11.1.3.2 -The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.y\
/ \ l h} OL I
f ;
I \ ;
i BYRON - UNITS 1 & 2 3/4 11-7 f
L ,
J
,__ .~ --_
4.1} RADI0 ACTIVE EFFLUENTS A
LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any outside tanks shall be Ilmited to the-following: l
- a. Primary Water Storage Tank 5 2000 Curies, and
- b. Outside Temporary Tank 5 10 Curies.
APPLICABILITY: At all times.
ACT13N:
- a. With the quantity of radioactive. material in any of the above Ifsted tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILL.ANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above
-tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
BYRON - UNITS 1 & 2 3/4 11-[ AmendmentNo.{
(RADJ0ACTIVEEFFLUENTS ~
3/4.11.2 GASEOUS EFFLUENTS
-)
DOSE RATE LIMITING CONDITION FOR OPERATION
/
3.11.2.1 The dose rate due to radioactive materials released in gaseous-effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shal,1 be limited to the following:
- a. For noble' gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and
- b. For Iodine-131 and 133, for tritium, and for all ra/dionuclidas in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. /
APPLICABILITY: At all times.
ACTION: !
- a. With the dose rate (s) exceeding the abo 0e limits, immediately restore the release rate to within the aboveflimit(s).
/
- b. The provisions of Specifications 3I0.3 and 3.0.4 are not applicable.
s
/
\/
SURVEILLANCE PE0VIREMEN15 A 4.11.2.1.1 The dose rate due to/ noble asys ing\gaseous effluents shall be ;
determined to be within the abo've limits in\accordance with the methodology and parameters in the ODCM. ,/
4.11.2.1.2 The dose rat vdue to lodine-131 andN133, tritium, and all radio-nuclides in particulate' form with half-lives grea'ter than 8 days in gaseous effluents shall be det' ermined to be within the above limits in accordance with the methodology and 4arameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
N
/
l ,
l ,
D BYRON - UNITS 1 & 2 3/4 11-9 1
.l
_.,.___,._,..= - ~
~
TABLE 4.11 y. ,x Y RADI0 ACTIVE GASEOUS' WASTE SAMPLING AND ANALYSIS PROGRAM -
e
,/
/ i c MINIMUM LOWER LIMIT OF i 5 . SAMPLING ANALYSIS TYPE OF , ' DETECTION (LLD)( ) !4 d GASE M RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS / (pCi/ml)
,. 1. Waste'Ga ecay Each Tank' Each Tank Principal Gamma Emitters (2) 1x10
-4 1
% Tank Grab Sample e' '/
- 2. Containment Purge h PURGE (3)'Each PURGE I) Principal _G&simaEmitters(2) 1x10
-4 ample
!!-3 1x10'I
- 3. Auxiliary B1dg M(4)(5) Principal Gasuna Emitters (2) ~4 1x10 Vent Stack Grab Sample
_7 w (Units 1 and 2) '
H-3 1x10 Continuous (6) ,
g7) \ 1-131 1x10 I
4 - Charcoal Sample k133 1x10 f Continuous (6) y(7) Pri h al Ganuma Emitters (2) 1x10
~II f
' 'Q
Particulate Sample
\ N Continuous (6) ~II '
, j
' M Gross Alpha 1x10 ;
'-- Composite ;,
- ,/ Particulate Sample i.
,- Continuous (6) Q, Sr-89, Sr-90
- 1x10'II Composite Particulate Sample
},,
Continuous -6 Noble Gas Monitor ^
Noble Cases Gross Beta or 1x10 {_
Gamma
/~J
._.m - -
- _ - - _ ~ . . . - ~ . - = _ - - - - - - _ - - .
_p.i i+wvhM#--
TABLE 4.11-2 (Continued)
TABLE NOTATIONS (1) The D.is ' defined,- for purposes of these specifications, as the smallest concentration-of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% p bability with only'i% probability of falsely concluding that a blank ob rvation represents i real" signal.
-foraparticulabaeasurementsystem,whichmayincluderad chemical separation: '\-
\
'N 4.66 s b
! LLD =
l E V 2.22 x q06 Y exp (-Aat) y where: '
LLD = the lower limit of 'etection d (micrqCuries per unit 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 per minute),
E = the counting efficiency (counts per disintegration), . -
V = the sample size (units of mass or volume),
2.22 x 105 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A =.the radioactive decay constant for the particular r&dionuclide (sec 1), and s l At-= the elapsed time between the midpoint of sample collection and the time of coanting (sec). '
i
\
l Typical values of E V, Y, and at sh'ould be- used in\the calculation.
\
Itshouldberecog'[112edthatthe-LLDisdefinedasabeforethefactlimit
-representing the: capability of a measurement system and not as an after the fact-limit'for a particular measurement. \
/ \
l' !' -[ ,
,/ L C.
4 !
l l l /
g-. /
]
BYRON - UNITS 1 & 2 3/4 11-11 _
ts
= . .. - -. - - - ~ . _- -_
~
TABLE 4.11-2 (Continued) f- ..
(
TABLE NOTATIONS (Continued)
(2) e principal gamma emitters for which the t.LD specification applies lude the following radionuclides: Kr-87, Kr-88, Xe-133, Xe Co-5(533m, Co-60,Xe-135, In-65, and Xe-138 Mo-99, in Cs-134, I-131, noble gas releases Cs-137, ar.d Mn-54, Ce-141 Fe-59 in and Ce-144 iodin nd particulate releases. This list does not mean that ly these nuclid are to be considered. Other gamma peaks that are ide ifiable, togetherhiththoseoftheabovenuclides,shallalsobeana zed and reported fg the Semiannual Radioactive Effluent Release Re rt pursuant to Specific tion 6.9.1.7, in the format outlined in Regul ory Guide 1.21, Appendix B, evision 1, June 1974.
(3) Sampling and a lysis shall also be performed followt g shutdtwn, startup, or a THERMAL PO R change exceeding 15% of RATED THpftMAL POWER within a . --
1-hour period. / ) N
/
(4) Tritium grab sample \s-shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. /
\ /
(5) Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, w never spent fu ds in the spent fuel pool. -
(6)Theratioofthesamplef}owratetothesampledstreamflowrateshall be known for the time period covered by each dose or dose rate calculation made in accordance with Spec fications 3.11.2.1, 3.11.2.2, and.3.11.2.3,
/
(7) Samples shall be changed at le t'once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after,Mhanging, or after removal from sampler, Sampling shall also be performedat least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER,Within a\1-hour period and analyses shall be completed within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />sjef changing. When-samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.
This requirement does not apply if: (1) analysis shows that the DOSE
~ ~
EQUIVALENT I-131 cone.entration in the reactor coolant has not increased morethanafactorof3,and(2)thenoblkgasmonitorshowsthateffluent activity has not increased more than a fact r of 3.
/
NR BYRON - UNITS 1 & 2 3/4 11-12 ,
tr
.i RADI0 ACTIVE EFFLUENTS
]-
HSE-NOBLEGASES i
LIMI NG CONDITION FOR OPERATION I 1 i i
3.11.2.2 he air dose due to noble gases released in gas us effluents, from !
-each unit, areas at ana beyond the SITF BOUNDARY (see Figure 5.1-1) shall !
be limited t the following: j i
- a. Durin any' calendar quarter: Less than or qual to 5 mrads for gamma diation and less than or equal to O mrads for beta radiation.
j-and -
j
- b. During any alendar year: Less than o equal to-10 mrads for_ gamma- i radiation an'd . less than or equal to 2 mrads for beta radiation. i
\ !
APPLICABILITY: At all tiines.' I t
ACTION':
~ I a.
.Withthecalculatedairdosef%abom effluents exceeding any\of the radioactive ve nobleand limits, prepare gases in gaseous submit to
- the Commission within 30 Nayjs pursuant to Specification 6.9.2, a i Special Report that-identifjes the cause(s) for exceeding'the. limit (s) !
anddefinesthecorrective/aqtionsthat.havebeentakentoreduce '
the releases and the proposed' corrective actions to be-taken to assure that subsequent r leasesswill be in compliance with the above .
limits.
\x i f
- b. The-provisions of Specifications 3.V.3 and 3.0.4 are not appl % ble.~
t
/ \ !
/ l
/ '
' SURVEILLANCE REQUIREMENTS f
.t~
/
4.11.2.'2 CumulativeMosecontributionsforthecurrentcalendar'quarterand ?
current calendar yeaf for noble gases shall be determine in s accordance with !
the methodology in,d parameters _in the ODCM at least once r 31 days.
l i
-j
/
ttb +
/ i I,
BYRON - UNITS 1 & 2 3/4 11-13 J f
1
RAD 10ACT NT5 _ -
\ DOSE - I0 DINE-131. AND 133, TRITIUM, AND RADIOACTIVE MATERI AL IN PARTICULATE FORM LIM ING CONDITION _FOR OPERATION
'N N /
3.11.2.3 itie dose to a MEMBER OF THE PUBLIC from Iodine-131 arid 133, tritium, and all rad 6nuclides in particulate form with half-lives gre'ater than 8 days in gaseous effluents released, from each unit, to areas,at,and beyond the SITE r
BOUNDARY (see Figure 5.1-1) shall be limited to the foifewing:
\
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and s Less than or equal to 15 mrems to any
~
- b. During any c lendar year: l organ, s 8
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of Iodine-131 and 133, ,
tritium, and radionuclides in particulate form with half-lives l greater than 8 days, in gaseous effluents exceeding any of the above
> limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) '
for exceeding the limits and defines the corrective actions that have been taken to reduce the releases &nd the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, q
- b. The provisions of Specifications 3',0.3 and 3.0.4 are not applicable. 3
\ !
\ l I
SURVEILLANCE REQUIREMENTS N l l
I l , /
\
4.11.2.3 Cumulative dose contributions for the curren\ calendar quarter and f current calendar year for Iodine-131 and 133, tritium, hnd radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with.the methodology and parameters in the ODCHNat least once per 31 days. /
\A i
l l
/
/
BYR N - UNITS 1 & 2 3/4 11-14 -- i s_.
~ ~ ~ ~
RADIOACTIVE EFFLUENTS
- GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2. The VENTILATION EXHAUST TREATMENT SYSTEM and the WAS GAS HOLDUP SYSTEM s ,all be OPERABLE and appropriate portions of these systems shall be
-used to reduce releases of radioactivity when the projected doses j in 31 days ,
due to gaseous effluent releases, from_each unit, to areas /at and beyond the ,
SITE BOUNDARY (see Figure 5.1-1) would exceed: /
\ /
- a. 0.2 mrad to air from gamma radiation, or / -
N
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3mrehtoanyorganofaMEMBEROFTHEPUBLIC.
APPLICABILITY: At all times.
' ACTION:-
- a. With radioa:tive, gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the i Commission within 30 days,-pursuant to Specification 6.9.2, a Special Report that tincludes the following information:
- 1. Identification ch any inoperable equipment or subsystems, and the reason for the'inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to orevent a recurrence. !
s ,
- b. The provisions of Specification's 3.0.3 and 3.0.4 are not applicable. I
\ !
\ I SURVEILLANCE REQUIREMENTS \ _ f
/ \ l 4.11.2.4.1 Doses due to gaseous releases from each' unit to areas at and beyond the SITE BOUNDARY shall be projected at lea's,t once per 31 days in
-accordance with the methodology and parameters in the ODCM when Gaseous Radwaste-Treatment Systems are not being fully utilized.
N 4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT' SYSTEM and WASTE GAS HOLDUP ,5YSTEM shell-be considered OPERABLE by meeting Specification 3.11.2.1 and 3,11.2.2 or 3.11.2.3.
BYRON - UNITS 1 & 2 3/4,11-15 -
N '
......-,.,_,__..__....._..m.,
l t
i RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE l
LIMITING CONDITION FOR-OPERATION i
t 3.11.2.5 The concentration of oxygen in the WASTE GAS. HOLDUP SYSTEM shall be f limited to less than or equal to 2% by volume whenever the hydrogen concentration i exceeds 4% by volume.
APPLICABILITY: At all times. !
t ACTION:
- l
- a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume but less than or equal to 4% by volume, e reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. !
t
- b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEh !
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 i equal to 4% by volume, then take ACTION a abo'e. v ;
9 The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i l- SURVEILLANCE REQUIREMENTS [
4.11.2.5 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.3.3-13 of Specification 3.3.3.10. ,
i l
e l
l BYRON - UNITS 1 & 2 j 3/4 11- Ks @ ,
RADIDACT3VE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x10* Curies of noble gases (considered as Xe-133 equivalent).
APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
I BYRON - UNITS 1 & 2- 3/411-}R()h
r ~-
RADIOACTIVE,, EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTES t LIMIT CONDITION FOR OPERATION 3.11.3 R pactive wastes shall be solidified or dewatered in acc ' dance with the PROCESS DQNTROL PROGRAM to meet shipping and transportation quirements during transit \ and disposal site requirements when received a the disposal site.
APPLICABILITY: A all times.
ACTION:
- a. With SOLIDI { CATION or dewatering not meeti g disposal site and shipping and transportation requirements, uspend shipment of the inadequately phecessed wastes and corte the PROCESS CONTROL PROGRAM, the pro:edures a d/or the solid waste y stem as necessary to prevent recurrence,
- b. With SOLIDIFICATIONN r dewatering r.pt performed in accordance with the PROCESS CONTROL PROGRAM, test Ahe improperly processed waste in each container to ensure that it/neets burial ground and shipping requirements and take approprials administrative action to prevent recurrence,
- c. TheprovisionsofSpecifica3,fons3.0.3and3.0.4arenotapplicable.
SURVEI'LLANCE REQUIREMENTS \
\
4.11.3 SOLIDIFICATION of at least one representative test specimen from at least ever tenth batch of each, type of wet radioactive wastes (e.g. , filter sludges, spent resins, evaporat'or bottoms. botic acid solutions and sodium sulfate solutions) shall be verified in accord ce with the PROCESS CONTROL PROGRAM: ,
- a. If any test soecimen fails to verify 5 .IDIFICATION, the SOLIDIFICATION of the batch under test shall be suspendgd until such time as additional test specimens.can be obtained, alternatiye SOLIDIFICATION parameters can be determined in accordance with the PqoCESS CONTROL PROGRAM, and i subsequent test verifies SOLIDIFICATION. SQLIDIFICATION of the batch may then be' resumed using the alternative 50 IDIFICATION parameters determined by the PROCESS CONTROL PROGRAM;
- b. If the initial test specimen from a batch of,walte f ails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shat 1 provide for the collection and testing of representative test spe'cimens from each consecutive batch of the same type of wet waste u ' il at least 3 consecutive initial test specimens demonstrate SOL IFICATION. The PROCESS CONTROL PROGRAM shall be modified as require , as provided in Specification 6.13, to assure SOLIDIFICATION of sL sequent batches of waste; and l .c . With the installed equipment incapable of meeting Speci ication 3.11.3
/ or declared out-of-service, restore the equipment to ope able status or provide for contract capability to process wastes as n gessary to
/ satisfy all applicable transportation and disposal require nts.
YRON - UNITS I & 2 3/4 11-18 j
a RAD 10ACTMFT[UDIT5 -
h 4.11.4 TOTAL DOSE 4k C
-LIMITh G CONDITION FOR OPERATION i
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3.11.4 The. annual-(calendar year) dose or dose commitment to any ME ER OF THE PUBLIC due to releases of radioactivity and to radiation from ur nium fuel i cycle sourcess shall be limited to les: than or-equal to 25 areas to the whole i body or any organ, except the thyroid, which shall be limited to 1 ss than or !
equal to 75 mrems. !
APPLICABILITY: At a'll times. f ACTION: \ .
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- a. With the calculated doses from the release of radi active materials i in liquid 0 6 gaseous effluents exceeding twice th limits of j Speci fication\3.11.1. 2a. , 3.11.1. 2b. , 3.11. 2. 2a. 3.11.2.2b., '
3.11.2.3a.,or\3.11.2.3b.,calculationsshouldpemadeincluding direct radiatio'n contributions from the units jtnd from outside storage '
tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, p pare and submit to the ;
Commission within 30 days, pursuant to Spe, fication 6.9.2, a Special i Report that defines the corrective action /to be taken to reduce sub- l sequent releases to prevent recurrence of exceeding the above limits !
and includes.the schedule for achieving'conformance with the above limits. This Special Report, as defiped in 10 CFR 20.405c, shall j include an analysis that estimates the radiation exposure (dose) to a '
MEMBER OF THE PUBLIC from' uranium fdel cycle sources, including-all ;
effluent pathways and direct radipfion, for the calendar year that ;
includes the release (s) covered Fy this report. It shall also describe levels of radiation and concentrations of radioactive l material involved, and the cause of the exposure levels or concen- i trations. If the estimated Jose (s) exceeds- the above limits, and l if the release condition rekulting in violation of 40 CFR Part 190 t has not already been corpfcted, thexSpecial Report shall include a j request for a variance n accordance'with the provisions of i 40 CFR Part 190. Suby ttal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. !
- b. The provisions Specifications 3.0.3 and .0.4 are not applicable.
SURVEILLANCE REQUIREMENTS !
4.11.4.1 Cumulati e dose contributions from liquid and g\ a ous effluents !
shall be determi d in accordance with Specifications 4.11. 2, 4.11.2.2, and '
4.11.2.3, and accordance with the methodology and paramete s in the ODCM.
4.11.4.2 ulative dose contributions from direct radiation fr m the units and from dwaste storage tanks shall be determined in accordance ith the .
methodolj[gy and parameters in the 00CM. This requirement is applic le only 'l under nditions set forth in ACTION a of Specification 3.11.4.
f BY N - UNITS 1 & 2 3/4 11-19 u -
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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM Libi! TING CONDITION FOR OPERATION
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3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.
APPLICABILI At all times.
ACTION: ,
I
- a. With the diological Environmental Monitoring Pr ram not being i conducted a specified in Table 3.12-1, prepare d submit to the Conui s sion, the Annual Radiological Environ ntal Operating Report require by Specification 6.9.1.6, a d, cription of the j reasonsfornothonductingtheprogramasrquiredandtheplansfor {
preventing a recu ence. I 4
i
- b. WiM the level of ra ioactivity as the sult of plant effluents in an environmental sampt g medium at a /pecified location exceeding the reporting levels of able 3.12-2 4 hen f averaged over any calendar quarter, prepare and sub to the pursuant to Specification 9.2,.a,fommission Special Report within that30 days, identifies the cause(s) for exceeding (mit(s) and defines the corrective l actions to be.taken to reduc dioactive effluents so that the ;
}
potential annual dose
- to a ME ER OF THE PUBLIC is less than the
! calendar year limits of Spepific tions 3.11.1.2, 3.11.2.2, or j 3.11.2.3. When more than one of e radionuclides in Table 3.12-2 I are detected in the samp)(ng mediu this report shall be submitted I if: /
concentration )
- concen ation (2) +
reporting level (1) reporting evel (2) .41.0 f
When radionuclides other than those in Tabi 3.12-2 are detected'and i are the result /of plant effluents, this repo shall be submitted if the potentic / annual dose
- to-A MEMBER OF THE 'UBLIC from all radio-nuclides is equal to or greater than the calen r year limits of Specifica ons 3.11.1.2, 3.11.2.2, or 3.11.2.3.- This report-is not
- requiredj df the measured level of radioactivity w not the result of plant effluents; however, in such an event, 'the con ition shall be -
reporte'd and described !n the Annual Radiological En ironmental-Operating Report required by Specification 6.9.1.6.
- The methodology and parameters used to estimate the potential annual ose to i
a MEM 1R OF THE PUBLIC shall be indicated in this report.
B RON - UNITS 1 & 2 3/4 12-1 -
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-1 RADIOLOGICAL ENVfRONMENTAL MONITORING
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LIMh1NGCONDITIONFOROPERATION- -)
ACTION ( tinued)
- c. Wit milk-or fresh leafy vegetable samples unavailaMe from one or more the sample locations required by Table 3.12'-1, identify specif locations for obtaining replacement sangiles and add them within 3 days to.the Radiological Environments 1 Monitoring Program f
- given in t ODCM. The specific locations from which samples were 4
-unavailable y then be deleted from the monitoring program. Submit controlled version of the ODCM within 180 days including a revised figure (s) and tb le reflecting the new location (s) with supporting i information ident fying the cause of-the unavailability of samples I, and justifying the election of the new location (s) for obtaining samples, l d. The provisions of Spechfications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmenta onitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s)intheODCM,andshallbeanalyzedpursuantto-therequirementsof ,
Table 3.-12-1 and the detection capabilities required by Table 4.12-1, i
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BYRON - UNITS 1 & 2 3/4 12-2 1 7 ~
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) - TABLE 3.12-1' 3
- g RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM NUMBER OF' E -REPRESENTATIVE
- Z EXPOSUR THWAY . SAMPLES AND. SAMPLING AND TYPE AND FREQUENCY
'* AND/OR S LE ' SAMPLE-LOCATIONS (3) COLLECTION FREQUE Y OF ANALYSIS
'1. Direct Radi (2) Forty routine monitoring stations - Quarterly. Gamma dose quarterly.
N either with' two or. more dosimeters ith one. instrument for measur-ing .d: recording dose' rate contintlessly, placed as follows:
N An inner ring h stations, one in l each meteorologicaV sector in the general area of the SITEsBOUNDARY; R An outer ring of stations, one p
- each meteorological sector in p M the 6- to 8-km range from the J, site; and
< The balance of'the stations
/ to be placed in special
/ interest areas such as popu-
/ -
1ation centers, nearby residences, schools, and in .
/ one or two areas to serve as control stations. '
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. ~
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_ TABLE 3.12-1 (Continued)
- o RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
@ NUMBER OF '
, REPRESENTATIVE e E SURE PATifWAY SAMPLES AND SAMPLING AND TYPE AND EQUENCY
$ AN R SAMPLE SAMPLE LOCATIONS (y) COLLECTION FREQUENCY OF LYSIS w
- 2. Airbor s
,. Radiciodine Samples from five locations: Continuous sampler adioiodine Cannister:
1 y Particulates operation with sampi 1-131 analysis weekly.
Three samples fra close to collection weekly r-the three SITE BOUNDARY loca- more frequently -.
t s, in different sectors, required by st Particulate Sampler:
of highest. calculated loading. Gross beta radioactivity annual erage ground level D/Q: analysisfollogg fiIter change; and g i
One sample the vicinity of gamma isotopic analysis a community hav the highest of composite (by location:
K calculated annual erage und- - quarterly.
- 1evel D/Q; and @
IJ One sample from a ntro
'{ location, as- example 1 o 30 km dis and in the leas preval wind direction.
- 3. Waterborne -
- a. Surface (5) One sample upstream. Compo te sample over Gasuna isotopic analysis I4)
One sasple downstream. 1-month riod by monthly. Composite for weekly gra amples. tritium analysis quarterly.-
- b. Gr d Samples from one or two sourc Quarterly. Gamma isotopicI4} and triti tu only if likely.to be affected analysis quarterly.
- c. Drinking One sample of each community Composite sample I-131 *"*I Y SIS " **Ch drinking water supply over 2-week period (6) g; composite when the dose
/ downstream of the plant when I-131 analysis iculated for the consump-within 10 kilometers. is performed, monthly Li of the water is greater comp 3 site otherwise. than area per year. (8) Co n-One sample from a control posite orgrossbetaag locatia= gamma is opic analyses e monthly. Composite for
% tritium analysis quarterly.
_ . . . _ . - _ _ , _ _ . . . - , . _ _ . ~ _ _ , . . _ . ~ . _ . - _ . _ _ _ _ _ , . . _ . , _ . _ . . _ . . . , _ . . . . _ _ _ . _ . _ _ _ _ _ _ _ . . _ . _ ,
r TABLE 3.12-1 (C6iitiiiiied) -
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
\E HUMBER OF .
[' . REPRESENTATIVE g EXPOS HWAY SAMPLES AND SAMPLE LOCATIONS (y)
SAMPLING AND TYPE AND FREQtIENCY q AND/0R . PLE COLLECTION FREQUENCY OF ANALYSTS
- 3. Waterborne (Continued)
- d. Sediment One sample from downstream area Semiannually.
f P l N from with existing or potential [ Gamma isotopic analysis semiannually. l shoreline recreational value.
- 4. Ingestion ,
- a. Milk Samples rom milking animals Semimontbi when Gamma isotopicO) and I-13'1 in three lohtions within animals are on analysis semimonthly when' 5 km distance has i:eg the highest ' pasture, monthly at animals are on pasture; I dose potential. K there are other times. monthly at other times. l none, then, one sample from milking j q animals in each of thres sareas a
between5to8kmdistant\
g wheredosesarecalculatedgbe 4 greater than I mrem per yr
.\ p i One sample from milking animals f at. a' control location,15 to 30 km t
/ distant and in the least prevalent }
j ' wind direction. l
- b. Fisitaind' ' Representative samples of Three time er year Gamma isctopic analysis )
f inverte- commercially and recreationally (spring, summ and on edible portions. i brates important species in vicinity fall). -
of plant discharge area.
Representative samples of commercially and recreationally ,
important species in areas not i influenced by plant discharge. l
- c. Food Representative samples of the At time of harvest.(9) Gamma isotopic analyses Products principal classes of food products on edible portion.
l from acy area within 10 miles of the plant that is irrigated by /
water _in.which liquid plant. -
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___ wastes have been discharged. _f
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F TABLE'3.12-1 (Continued) q.
g RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM r
-z
, NUMBER OF-c- REPRESENTATIVE
'$ EXPOSU PATHWAY SAMPLES AND- SAMPLING AND -
g , g) - TYPE AND FREQUENCY.
AND/OR SAMPLE SAMPLE LOCATIONS COLLECTION FREQUENCY,, OF ANALYSIS w '
,. 4. Ingestion (Continued) x
- c. Food- SamplesofthNe:differentkinds . Gamma isotopic (*} and'I- l'
- Products of broad leaf vegetation. grown.. ',, Monthly when available. analysis.
1 (continued) nearest each of two different; offsite locations of highest . N '
r I
predicted annual avefage ground- '~
level D/Q if milk sampling is not l performed. -' . t
, OneMNpleofeachofthesimilar Monthly when Gamma isotopicI4) and I-E 1 l } trroad leaf vegetation grown available. alysis.
y 15 to 30 km distant in the least
'N '/;/ prevalent wind direction if milk m sampling is not performed.
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TABLE 3.12-1 (Continued) t TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one unit, and additional description where pertinent, shall be provided fo each and every sample location in Table 3.12-1 in a table and figure (s) in e ODCM, Refer to NUREG-0133, " Preparation of Radiological Effluent ;
Techn cal Specifications for Nuclear Power Plants," October 1978, and to i Radio) ical Assessment Branch Technical Position, Revision 1, Novembey /
1979. eviations are permitted from the required sampling schedule f I specimens \are unobtainable due to hazardous conditions, seasonal f unavailability, malfunction of automatic sampling equipment and her legitimate reasons. If specimens are unobtainable due to samp ng equip-j ment malfunction, every effort shall be made to complete corr ctive action prior touthe end of the next s nmpling period. All d 41ations from the sampling schedule shall be docuneited in the Annual Ra iological Environmental Operating Report pursuait to Specification .9.1.6. It is recognized that, at' times, it may not be possible or practicable to !
continue to obtain samples of the med'a of choice at tfie most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions \ nade within 30 days in the Radiological 4
Environmental Monitoring Program given in the ODCM. Submit controlled !
revisions of the ODCM withinN180 days including a revised figure (s) and table reflecting the new location (s) with' supporting information identifying the cause of the unavailability jf samples fr that pathway and justifying the selection of the new location (s) for obtaining samples,
/
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously reay 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. !
Filmbadgesshallnotbeusedas' dosimeters.formeasuringdirectradiation.l The 40 stations is not an absolute number. The number of direct radiation i monitoring stations may be reduced according to geographical limitations; I 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 l readout for TLD systems will depend upon the characteristier of the specific system used and should_be selected to obtain optimum dose vmormation wi%
- minimal fading. / \
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(3) Airborne particulate sampic filters shall be analyzed 'for gross beta radio-l activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay./ If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, ' amma isotopic analysis sha)1 be performed on the individual samples.
/
(4)Gammaisotopicanalysismeanstheidentificationandquantifihationof gamma-emii. ting radionuclides that may be attributable to the et luents from the facility.
N BYRON - UNITS 1 & 2 3/4 12-7 k'
MT TABLE 3.12 1 (Continued) j 4
I TABLE NOTATIONS (Continued) ,
(S) The " upstream sample" shalt be taken at a distance beyond s dificant influence of the discharge. The " downstream" sample shal e taken in an l area beyond but near the mixing tone.
(6) A composite sample is one in which the quantity (ali ot) of liquid sampled !
is proportional to the quantity of flowing liquid a in which the method !
of sampling employed results in a specimen that W representative of the l liquid flow. In this program composite sample altquots shall be collected !
at time intervals that are ver short (e.g. , hMirly) relative to the com- l 1
positing period (e.g. monthly in order to assure obtaining a representa- i I
tive' sample., / j
%- / ,
(7)Groundwatersablesshallbetakenwhenthissourceistappedfordrinking l or irrigation p0rposes in areas where the hydraulic gradient or recharge !
properties are su ble for contamination.
(8) The dose shall be cahulated for the maximum organ and age group, using the l methodology and parame s in the 00CM. !
(9) If harvest occurs more than once a year, sampling shall be performed during i each discrete harvest. If'%arvest occurs continuously, sampling shall be !_ l' monthly. Attention shall be aid to including samples of tuberous and root food products. '
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l / TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS [ (}
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LOVER LIMIT OF DECTECTION (LLD)(2)(3)
E FISH MILK TOOD PRODUCTS SEDIMENT U WATER AIRBORNE PARTICULATE OR GAS (pCi/m3 ) (pCi/kg, wet) (pCi/f) (pCi/kg, wet) (pCi/kg, dry)
ANALYSIS (pCi/t)
[
e m Gross Beta 4 0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 g m
130 Co-58,60 15 E
- 260
'A*
(
Zn-65 30 4 '
Zr-Nb-95 15 N
, x o
I-131 I#) 0.07 1 60\
I 15 0.05 130 15 60 xN 150 1
Cs-134 0.06 150 18 80 180 Cs-137 18 15 15
- \
Ba-La-140 -
- If no drinking water p thway exists, a value of 3000 pCi/t may be used.
/
/ - . - -
---JAB W 4.18 3 (Continued)
TABLE NOTATIONS This list does not mean that only these nuclides are to be cons ered. I (1) D(her peaks that are identifiable, together with those of theove l nut ides, shall also be analyzed and reported in the Annual diological Env tonmental Operating Report pursuant to Specification 6. 1.6, (2) Requi ed detection capabilities for thermoluminescent do imeters used for !
environmental measurements shall be in accordance with he recommendations '
of Regulatory Guide 4.13. !
'\
(3) The LLO is defined, for purposes of these specific tons, as the smallest i concentrations of radioactive material in a samp that will yield a net ;
count, above system background, that will be d eted with 95% probability l
with only 5% prhbability of falsely concludin hat a blank observation I l represents a "rehl ' signal. '
- 4 i, Foraparticularmeasurementsystem,whic)mayincluderadiochemical separations !
/ :
4.66 s b /
LLD =
E V
- 2.22 Y
- epp, j (-Mt)
Where: /
LLD = the "a priori" loytIr limit of detection (picoCuries per' unit mass or volume), j i s b = the standard-deviation of the background counting rate or of the counting rate,6f a blank sample as appropriate (counts per minute),
E = the count,ing efficiency (counts per disintegration),
V = the sample size (units of mass or volume), ;
/
j 2.22 = 'e number cf disintegrations per minute per picocurie. 4 Yat fractional radiochemical yield, when applicable, A =/the radioactive decay constant for the articular-radionuclide, l (sec 1), and
/ -s At = the elapsed time between sample collectiont or end of the ; .
sample collection period, and time of counting (sec). !
l x , <
Typical values of E, V, Y, and at should be used in the calculation. ;
s i i
s i v BYRON - UNI
_TS 1 & 2 -
3/4 12-11 .
c
---A m. i ..#-...._ - ...._. ,. .. +.._-.__ .-.-,- - ,. . _, -,,. ..,m -....._.......,-,_,.,.r. .~....~.m,,, . - . . , , - - , . , - - . ,
[ '
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_ TABLE 4.12 1 (Continued)
L Nh TABLE NOTATIONS (Continued)
It should be recognized that the LLD is defined as/a before the fact Nmit representing the capability of a measuremerd system and not as an f after the fact limit for a'particular measuremept. Analyses shall be i performed in such a manner that the stated LLDs will be achieved under 1 routine conditions. Occasionally background Aluctuations, unavoidable smallsamplesizes,thepresenceofinterfefingnuclides,orotheruncon- '
trollable'scircumstances may render these LLus unachievable. In such cases, the'tontributing factors shall be Jdentified and describcd in the Annual Radio') gical Environmental Operating Fer.9rt pursuant to Specifica-tion 6.9.1.6. / ;
(4) LLD for drinking sater samples. ]f no drinking wattr pathway exists, the /
LLD of gamma isotopic analysis mey be used.
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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS
%L(C %
L1HITING CONDITION FOR OPERATION 3.1h2 A Land Use Centus shall be conducted and shall identify mi in a j distance of 8 km (6 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, and the nearest residence.' for dose calculation, a garden will bt assumed at the nearest residence.
APPLICABILITY: At all times.
ACTION:
- a. With a Land Ute Q nsus identifying a location (s) that yields a !
calculated dose or dose commitment greater than the values currently ?
being calculated in Specification 4.11.2.3, identify the new f location (s) in the next Annual Radiological Environmental Operating -
- Report, pursuant to Specification 6.9.1.6. l
- b. With a Land Use Census identifying a location (s) that yields a calculated!
doseordosecommitment(viathesameexposurepathway)20%greaterthan/
at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to .
the Radiological Environmental Monitoring Program given in the ODCM. l The sampling location (s), excluding the control station location, i 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 which this Land Use Census was conducted, l
Pursuant to Specification 6.14, submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCH reflecting the new location (s) with information supporting the change in sampling ;
! locations, j i
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. '
l
! SURVEILLANCE REQUIREMENTS
! l 4.12.2 The Land Use Census shall be conducted during the growing season at l least once per 12 months using that information that will provide the best jl l 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 l
included in the Annual Radiological Environmental Operating Report pursuant to i Specification 6.9.1.6.
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BYRON - UNITS 1 & 2 3/4 12-13 i
l
. . - , . . ~ . . - . - . - . - . . - , . - . - - . . . . - . . . - . - . - . - . . . . . - - - .- -.. __-N
RADIOLOGICAL ENV!RONMTNTAL MON!?0 RING 3/4.32.3 INTERLABORATORY COMPARISON PROGRAM
, llMITINGCONDITIONFOROPERATION l
3.12.3 Analyses shall be performed on radioactive mater) 15 supplied as part of an Interlaboratory Comparison Program that has been Approved by the Commission, that correspond to samples required by Ta 1e 3.12-1.
APPLICABILITY: At all times.
ACTION: /
i
- a. With analyses not being petformed as' required ab6ve, report the
! corrective actions takin to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to $pecification 6.9.1.6.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, i
i SURVEILLANCE REQUIREMENTS N i
N 4.12.3 The Interlaboratory Comparison Pro' gram 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 Environmental Operating Report pursuant to Specification 6.9.1.6.
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/ 1 BYRON - UNITS 1 & 2 3/4 12 14
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b
s INSTRUMENTATION BASES 3/4.3.3.8 LOOSE PART DETECTION SYSTEM 1
The OPERABillTY of the loose-part detection system ensures that sufficient l capability is available to detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant 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.
M wtrb 3/4. 3. 3. 9 A RABMACYivf-titefD-EFFtttfwT-teNIMMNG-MIRuutuip4og r ing. racinctive-tiriutu en1uent-instrumentat1Un TrpruV15erto7eniter-'
a nd contrT T-as, applicable, the releases of radioactive materials in li3uid a f fluents during actual-or potential releases of liquid etf.luents.Mhe AEr~m/
Trip Setpoints for these instruments shall be calculated and adjusted in i ccordance with the methodology and p8 Tasters in the ODCM to ensure that the
~
plarm/ trip will occur prior'to exceeding the Timits_of 10 CFR Part 20. The
~
OPERABILIlY and'Ose of this instrumentation is consistent-with the requirement {
gfSenen1DesignCriteria60,63,and64ofAppendixAto10CFR-Part_50.
l 3/4.3.3.10 RA&MAC 1 LWM- MONITORING INSTRUMENTATION
.The-radioactive 1steous eff4ttent-ittstrumentation-is provided to monitor
.and-controt nis applicable; the Teteases vf i adioact4*e-wateriTh in vowvus anJuants-duringTetcaT~bryotential releases-of-gaseous-ef fluents. The-61 ara /Teip-Setpotrit's~foTuese instF0mehts~shalTheTaTdniiTeratu adiost+d Ja-accordanee+4 th-the-methodology-4nd-paramatere 4 n the ODCM-to-ensure that the-44+rm/te49-w(44-ocete-peter te sceeding the-timits or 10 CFR Port-20.
The instrumentation ah o includes provisions for monitoring 'and centivil kg.)
the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERAILMTV andste-of-this-bsteementetien-45 conc h bnt with the-requ4cementsaf-Geeeral-Des 94 &Cr4 tar 44 60, 63and-44-of apponMr A to-40-OfR-tart $0rthe sensitivity vi aiu noble-gae-activity monitor-.usad-to show-comp 14ence-with-ttre giseous err 1UeTirrelease requirements of 5,pecM4 cation-3711K5h811 be ruttrthat concentrations-es-4cw as lx10 8 uCi/cc v+-measuratic ,
3/4.3.3.11 HIGH ENERGY LINE BREAK ISOLATION SENSORS The OPERABILITY of the high energy line break isolation sensors ensures that the capability is available to promptly cetect and initiate protective action in the event of a line break. This capability is required to prevent the potential for damage to safety-related systems and structures in the auxiliary building, h
BYRON - t1 NIT-1 B 3/4 3-6 AMENDMENT NO. K
N11'RIDT0ACT!vEEFFLUENTS
]
BASES ,
3/4.11.1 L10010 EFFLUENTS -
3/4.11.1.1 CONCENTRATION N / f This specification is provided to ensure that the conces/ tration of radio- f active materials released in liquid waste effluents to UNR$TRICTED AREAS will belessthantheconcentrationlevelsspecifiedin10CFfart20,AppendixB, Table !!, Column 2.
This limitation provides additiona} assurance that the result in exposures within: in bodies of water in pHRESTRICTED AREAS will levels of radioactive materials (1) the Sectbn II. A des'ign objectives of A)pendix 1, 10 CFR Part 50, to a HEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. l The conce6tration limit for dissolved <
or entrained noble gases is based upon the assumption that Xe-135 is the f controlling radioisotope and its HPC in air (submersion) was converted to an t equivalent concentration in water usin f, Commission on Radiological Protection (g the methods ICRP) described Publication 2. in International j
4 This specification applies to the release of radioactive materials in liquid effluents from all units at the site.
' The required detection 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 HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits i for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.
l 40, 586-93 (1966), and Hartwell, J. K. , " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford
}
t Company Report ARH-SA-215 (June 1975).
3/4.11.1.2 D0SE _
This specification is provided to implement'the requirements of Sec-I
' tions II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The limiting Condi-tion I.for Operation implements the guides set forth'in Section II. A of Appen-dix The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in'31 quid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably-achievable." 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
,N f
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BYRON - UNITS 1 & 2 B 3/4 11-1 I
1 e rL M f '~~ ~ ~
BAS I
.DO.S__ (Continued) of Ap ndix ! be shown by calculational procedures based on models,and data, !
such th9t the actual exposure of a HEMBER OF THE PUBLIC through appropriate l pathways is unlikely to be substantially underestimated. The equations specified '
intheObHiorcalculatingthedosesduetotheactualreleaseratesof radioacti(vtmaterialsinliquideffluentsareconsistentwiththemethodology provided irt sRegulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releinses of Reactor Effluents for the Purpose of Evaluating Compliance '
with 10 CFR Pgrt 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 specification applies to the release of radioactive materials in liquid effluents from each reactor 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 contributions from each ' Unit based on input conditions, e.g. , flow rates and radioactivity 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 LCOs, these allocations from sbared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. /
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to,the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releuses of radioactive materials in liquid effluents will be kept "as low as ;
is reasonably achievable". This specificationsimplements the requirements of 10 CFR 50.36a, tieneral Design Criterion 60 of Appendix A to 10 CFR Part 50 e and the design objective given in Section II.D of -Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the Liquid Radwaste Tr/atment System were specified as a suitable fraction of the dose !
design objdctives set forth in Section II.A of AppendikxI, 10 CFR Part 50, for l liquid effluents. N !
/ \
This specification applies to the release of radioactive, materials in l
liquip effluents from each unit at the site. When shared Raddaste Treatment !
Systems are used by more than one unit on a site, the wastes frbe all units are i mixe'd for shared treatment; by such mixing, the effluent releasehcannot accurately be ascribed to a specific unit. An estimate should be 'mede of the
- contributions from each unit based on input conditions, e.g. , flow rates and radioattivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing BYRON - UNITS 1 & 2 B 3/4 11-2
b c l t. k J ,l
$/[,11.l.I 3%,g RADIOACTIVE EFFLUENTS 1/4 l 1. I 2 ht ICb 5/q ll .I .3 btlelcd BASES l
l LhWIDRADWAS7{TREATMdTSYST{M(Co inued) units ating the waste Treata t Syst g. F det rmi ing opfo e to LCOs, th e alloca (ons from sh e Radweste atment stems te t e added to e tel ses s ec\fically at ribu d to unittoogaint t 'al r eases per nit.
-3/4.11.1.4 LIQUID HOLOUP TANKS The tanks listed in this specification include all 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 hurrounding area
, drains connected to the Liquid Radwaste Treatment System.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B Table II, Column 2, at the nearest potable water supply and the nearest surface water, supply in an UNRESTRICTED AREA.
~ ~
k3/C11~.2~GASE0VS EFFLUENTS N~
- x. s 3/4'n.2.3 DOSE RATE p h N
This' specification is provided to ensure that the dose at any time t and }
beyond the SITE. BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.
The annual dose limits are the doses associated with the concentrations-of 10 CFR Part 20, Appendix B. Table II, Column 2. 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 sufficiently low to compensate for any' increase in the atmospheric diffusion factor above tha*. for the SITE BOUNDARY. . Examples of calculations for such ancy factors, shall be given MEMBERS in the 00CM. OF TheTHE PUBLIC, specified withrate felease the limits appropriate r occup'estrict, at all times, the corresponding gamma and, beta dose rates above background to-a MEMBER OF THE PUBLIC at or-beyond ,the' SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole bodyfer to less than or equal to 3000 mrems/ year to the skin.
!Thesereleaseratelimitsalsorestrict,atalltimesthecorrespondingthyroid dose rate abefe background to a child via the inhalation pathway to') ss than L or equal,t61500 mrems/ year.
This specification applies to the release of radioactive materials in us effluents from all units at the site.- ;
BYRON - UNITS 1 & 2 B3/411%h 1
'~ i
._- _ - _. -~
RA0X0 ACTIVE EFFLUENTS BASES DOSE RATE (Continued) f The required detection capabilities for radioactive erfals in liquid !
wastesamblesaretabulatedintermsofthelowerlimits4fdetection(LLDs).
Detailed discussion of the LLD, and other detection limits can be found in i HASL Procedures Manual HASL-300 (revised annually), Jurrie, L. A. , " Limits for Qualitative Detection and Quantitative Determination - Application to ;
Radiochemistry," linal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection !
Limits for Rad 1oanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). l 3/4.11.2.2 DOSE - NOBLE GASES '
This specification is provided to implement the requirements of Sec-tions II.B. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condi-tion for Operation implements the guides set forth in Section II.B of Appen-dix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to "
UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appen-dix ! that conformance with the guides of Appendix I be shown by calculational 4 procedures based on models and data such that the actual exposure of a MEMBER i 0F 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 radio- '
active materials in liquid effluents are consistent with the methodology pro-vided 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. "Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous t Effluents 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 BOUNDARY are based upon the historh;al average atmospheric !
conditions.
- This specification applies to the release of radioactive materials in ;
gaseous effluents from each unit at the site. When shar'ed Radwaste Treatment Systems are used by more than one unit on a site, the wastys 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' contributions from each unit based on input conditions, e.g. ,\(low rates and '
radioactivity cnneentrations, or, if not practicable, the treat d effluent ; ,
releases may be allocated equally to each of the radioactive was producing units sharing the Radwaste Treatment System. For determining con rmance to ;
LCOs, these allocations from shared Radwaste Treataent Systems are be added tothereleasesspecificallyattributedtoeachunittoobtainthet(al releases per unit. \
/ BYRON - UNITS 1 & 2 L/ lL3/4 11 L 'd
f- - . _ _ _ _ ,
I RADIDACTIVE EFFLUENTS BASES 3/4.1'1.2.3 OOSE - 10 DINE 131 AND 133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTIC01. ATE FORM i
This\
Sections II.C, III.A and IV.A of Appendix I, 10 CFR The LiPart 50.' specific Conditions f6r Operation are the guides set forth in Section I VC of Appendix 1.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of assurethatthereleasesofradioactivematerialsingaseou/ppendixIto s effluents to j UNRESTRICTEDAREA$yillbekept"aslowasisreasonablyJchievable." The ODCM calculational methods specified in the Surveillance Regdirements implement the requirements in Section III. A of Appendix I that conformance with the guides i of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate j pathways is unlikely to be substantially underestimated. The ODCM calculational !
niethodology 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 1977.
i These. equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionucliae pathways to man, in the areas at and beyond the SITE 80VHDARY. The pathways that were examined in the development.of these calculations were: (1) indi-vidual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and sneat producing animals graze with '
consumption of the milk and meat by man, and (4) deposition on the ground with l subsequent exposure to man.
\, l 6
This specification applies to the release l' gaseous effluents from each unit at the site. \ofhen radioactive shared Radwaste materials in Treatment Systems are used by more than one unit on a site) the wastes from all units are l mixedforsharedtreatment;bysuchmixing,theeN1uentreleasescannot l accurately be ascribed to a specific unit. An est 4 ate should be made of the ;
contributions from each unit flow rates and radioactivity concentrations, or,based if not practicable on input conditio\,s, he treatede.g., effluent '
releases may be allocated equally to each of the radio ive waste producing l units sharing the Radwaste Treatment System. For detera ng conformance to I LCOs, these allocations from shared Radwaste Treatment Sy ems are to be added l to the releases specifically attributed to each unit to obt n the total releases per unit.
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SyRON - UNITS 1 & 2 8 3/4 11-5
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RADIDACTIVE ErrLUENTS BASES l f3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM ^
The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST i TREATMENT SYSTEM ensures that the systems will be avai V 1e for use whenever gaseous elf kents require treatment prior to release f- e environment. The requirement tha( the appropriate portions of this syste.a ,J used when specified provides reasonable. assurance that the releases of radioactive materials in gas-eous effluents will't>e kept "as low as is reasonably achievable". This specifi-cation implements the requirements of 10 CFR 50.36c, General Design Criterio -
of Appendix A to 10 CFR Part 50 and the design objectives given in Secti 1. 0 of Appendix I to 10 CFR Part 50. The specified limits governing th. e of appropriate portions of the Gaseous Radwaste Treattnent System were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
This specification 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.releales cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g. bflow rates and radioactivity concentrations, or, if not practicable, the treat'ed ef fluent
}releasesmaybeallocatedequallytoeachoftheradioactivewastsproducing /
units' sharing the Radwaste Treatment System. For determining conforeance to l LCOs, these allocations from shared Radwaste Treatment Systems are to be added i to 'th~e' releases specifically attributed to each unit to obtain the total /
(rfleases per_AnD __. -
/
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of ntially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is itained below the flammability limits of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
I 3/4.11.2.6 GAS DECAY 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 Specifica_ tion.
3 / 4 . ) \ . 7. . \ DekW
\ 1 MW 3/7. n . I 3/4 . fl .1 3
btM BYRON Nfif B3/411-k
RADIDACTIVE EFFLUENTS BASES GAS DECAY TANKS (Continued)
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC l at the nearest 51TE BOUNDARY will not exceed 0.5 rem. This is consistent '
with Standard Review Plan 11.3, Branch Technical Position ETSB 115, I
Postulated Radioactive Releases Due to a Waste Gas System Leak or f ailure,"
in NUREG-0B00, July 1981.
374.11.3 SOLID RADIDACTIVE WASTES ,
This specification implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters ,
inhyded in establishing the PROCESS CONTROL PROGRAM may include, but are not i limited to, waste type, waste pH, waste / liquid /SQLIDIFICATION agent / catalyst ratios bwaste oil-content, waste principal chemical constituents, and m ting i and curing times. ;
3/4.11,4 TOTAL DOSE
/
This specification is provided to meet the dose limitatimis of 40 CFR j Part 190 that have been incorporated into 10 CFR Part 20 byA 6 FR 18525. The i
! specification requires the preparation and submittal of a Special Report i whenever the calculated doses due to releases of radioac(ivity and to radiation
< from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, i except the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites containing up to four reactors, it is _ highly unlikely that the l resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of I 40 CFR Part 190 if the individual reactors redain within twice the dose design f objectives of Appendix 1, and if direct radiation doses from the r,. actor units f and outside storage tanks are kept smal) The Special Report will describe a I course of action that should result in'the limitation of the annual dose to a
!MEMBEROFTHEPUBLICtowithinthe40CFRPart190 limits. For the purposes of
, the-Special Report, it may be assumed that the dose commitment to the' i
' 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 withi d radius of 8 km mQst be considered, If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR
, Part 190, the Special Aeport with a request for a variance (provided the 1 release conditions re,sulting in violation of 40 CFR Part 190 have not already
~
4 (been ccrrected),,$h accordance with the provisions of 40%FR 190.11 and 10CFR20.405c,AsconsideredtobeatimelyrequestandfQfillsthe l requirements Af 40 CFR Part 190 until NRC staff action is co gleted. The
{ variance onfy relates to the limits of 40 CFR Part 190, and doh not apply in
'any way to'the other requirements for dose limitation of 10 CFR ) rt 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1. An individual not consj(ered a MEMBER OF THE PUBLIC during any period in which he/she engaged
.l in carrying out any operation that is part of the nuclear fuel cycle, i / --
V BYRON - UNITS J & 2 B3/4lik
N 3/4.12 RADIOLOGICALENVIRONMENTALMONITORQG ,
BA5ES 3/4.12,1 MONITORING PROGRAM i
The Radiological Environmental Monitoring Program required by this !
specification provides representative measurements of radiation and of i radioactive materials in those exposure pathways and for those radionuc1) es ki that lead to the highest potential radiation exposures of MEMBERS OF TWC PUBLIC resulting from the station operation. This monitoring prograrp' implementsSection IV.B.2 of' Appendix ! to 10 CFR Part 50 and thereby supplements the .
radiological effluent monitoring program by verifying that the measurable l concentrations of radioactive materials and levels of radiation are not higher i than expected on the basis of the effluent measurements and the modeling of !
the environmental exposure pathways. Guidance for this-monitoring program is t provided by the Radiological Assessment Branch Technical Position on :
Environmental Monitoring - The initially specified monitoring program will be '
effective for at least the first 3 years of commercial operation. Following j this period, program changes may be initiated based on operational experience. ,
r The required detection c'pabilities a for environmental sample analyses are i tabulated in terms of the lower limits _of detection (LLDs). The LLDs required ,
by Table 4.12-1 are considered optimum for routine environmental measurements i in industrial laboratories. It should be recognized that the LLD is defined ;
as a before the fact limit representing the capability of a measurement system l and not as an after the fact limit for a particular measurement. j r
Detailed discussion of the LLO, and other detection limits, can be found l in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , "Liniits ;
for Qualitative Detection and Quantitative Determination - Application to ;
Radiochemistry," Anal. Chem, 40, 586-93 (1968), and Hartwell, J. K., " Detection l Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA 215 (June 1975). -
3/4.12.2 LAND USE CENSUS /
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This specification 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 Environmenta14tonitoring Program given in _the ODCH are made if required by the results of this census. The best Iqformation from the door to door survey, fr.om aerial survey, or from consulting with local agricul-tural authorities sha)1 be used. This census satisfin) the requirements of l Section-IV.B.3 of Appendix I to 10 CFR Part 50.- An annual garden census will not be required since the licensee will-assume that thert is a garden at the nearest residence /in each sector for dose calculations. :
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BYR0( - UNITS 1 & 2 B 3/4 12-1 i
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RA930 LOGICAL ENVIRONMENTAL MONITORING ~%_
N N
BASES ' _ /
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory ;
Comparison Program is provided to ensure that independent checks on the precision '
and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for i
environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.
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BYRON - UNITS 1 & 2 B 3/4 12-2
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l ADMINISTRATIVE CONTROLS t PROCEDURES AND PROGRAMS (Continued)
- b. In-Plant Radiation Monitoring *I A program which will ensure the capability to accurately determine i the airborne iodine concentration in-vital areas under accident l conditions. This program shall include the following:
i
- 1) Training of 9ersonnel, I i
- 2) Procedures for monitoring, and l
- 3) Provisions for maintenance of sampling and analysis equipment.
- c. ,5,econdary Water Chemistry l
A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
- 1) Identification of a sampling schedule for the critical variables and control points for these variables, ;
- 2) Identification of the procedures used to measure the values of i the critical variables, ;
. 3) Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage, .
- 4) Procedures for the recording and management of data, ;
- 5) Procedures defining corrective action for all off-control point !
chemistry conditions, and i
- 6) A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action. ,
- d. Pust-accident Samplina
- 1 A program which will ensure the capability to obtain and analyze .
reactor coolant, radioactive iodines and particulates in plant ,
gaseous effluents, and containment atmosphere samples under accident !
conditions. The program shall include the following: ,
- 1) Training of personnel, !
- 2) Procedures for sampling and analysis, and
- 3) Provisions for maintenance of sampling and analysis equipment. i e, -
a I
[. FINM w kT 3.1 r
BYRON - UNITS 1 & 2 6-17 .
i
ADH]NISTRATIVE CONTROLS __
REPORTING REQUIREMENT $ (Continued)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- pus" I Jo u t i n e AMUIT Ra~di o l o g i c 4TTnvironUTiTT F 0p e r a t i n g wptrrtTT5 v e r i n g3 KTiMpiration of the Unit during the previous calendar year shall be submitted t' prior to May 1 of each year. The initial report shall be submitted prior to May the year following initial criticality.
/
The' Annual Radiological Environmental Operating Reports shall incivde summaries, interpretations, and an analysis of trends of the resultsAf the radiological environmental surveillance activites for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also= include the results of the Land Use Census required by Specification 3.12.2.
TheAnnualRadio1cgicalNnvironmentalOperating/samplesandofall R orts shall include the t
results of analysis of all rad logicalenvironmenta) environmental radiation tneasurem ts taken during pie p od oursuant to the locations specified in the tables syf figures in ,'1e OL , as well as summarized and tabulated results of these analyst ( and meattremet i the format of the table in the Radiological Assessment Braoch TethnicD Posi x , Revision 1 November 1979. In the event that some ', 'y(,aal*,< ) Ore not available for inclusion with the report, the reportjifh explaining the reasons for the missing perw th Thetiimissing se SL. data 1ttedshall noting t,e and submittedassoonaspossibleinasu; amer tryreport.
The reports shall also include' we following: summary description of the Radiological Environmental Mpfiitoring Program; at east two legible maps" covering all sampling locations / keyed to a table giving istances and directions from the centerline of one re,a6 tor; the results of licens participation in the Interlaboratory Compari 6n Program and the corrective tions being taken if the specified program is t being perfortned as required by pecification 3.12,3; reasons for not conductj g the Radiological Environmental Honn.pring Program as required by Specifica pon 3.12.1, and discussion of all deviatid s from the sampling schedule of/ Table 3.12-1; discussion of environmental sa ole measure-
. ments that exceed)fie reporting levels of Table 3.12-2 but are not he result of pit.nt effluenji, pursuant to Specification 3.12.1; and discussion of all analyses in wh <h the LLO required by Table 4.12-1 was not achievable.
\
"A s hgle submittal may be made for a multiple unit station.
8),Dne map shall cover stations near the SITE BOUNDARY; a second shall include
< more distant stations. \
BYRON - UNITS 1 & 2 6-19
ADMINISTRATIVE CONTROLS trPORTING RE0VIREHENT5~Tt6ntinued) __ __
The Annual Radiological Environmental Operating Report shall also inci e an anhual summary of hourly meteorological data collected over the prevpw 1 year. This annual summary may be eit* in the form of an hour-by-htwf 111 sting on magnetic tape of wind m : e ,d direction, atmospher W stability, tand precipitation (if measured), @ h N k em of joint frequency distribu-
~
tions of wind speed,-wind direct % v's eta pheric stability." This same report shall include an assessmeri V e tr M tion doses due to the radioactive liquid and gaseous e' d+ .-Swad from the Unit or Station during the previous calendar year. ' d 644. report shall also include an assessment of the radiation doses frorn noioactiSr liquid and gaseous effluents to HEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure $.1-1) during the report period. All assumptions ysed in making these i assessments, i.e., specific activity, exposure time and location, shall be f
included in these reports, The meteorological conditions concurrent with the j time of release of radioactive materials in gaseous effluents, as determined J by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCH. t The Annual Radiolog'ieal Environmental Operating Report to be submitted prior to May I of each year shall also include an assessment of radiation doses to.the most likely exposed HEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary ef fluent pathways and direct radiation, for the previous calendar year to show con-formance w nh 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuc shr Power Operation." Acceptable methods for calculating the dose contrjb}utionfromliquidandgaseouseffluentsaregiveninRegulatoryGuide s JMD9, Rev.1, 0ctober 1977
]
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT **
~
- 6.9.1.U htGe Semiannual RaTioactive Ef fluent Release Reports covering the bpefiTToi5 of the unit during the previous 6 months of operation shall be Lubmitted within,60 days af ter January 1 and July 1 of each year. 3eperiod of the first report shall begin with the date of initial criticapty.
The Semiannual Radi'cac4ive Ef fluent Release Reports,.shall include a i bummary of the quantities of N dioactive liquid andJassous effluents and {
tolid waste released from the uni as outlined ,irTegulatory Guide 1.21, 1 i
- In lieu of submission with the Annual Radio %gical Environmental Operating Report, the licensee ha,s th'e option of retaini?Ipsthis summary of required meteorological data pn' site in a file that shall b N rovided to the NRC upon request.
'A single subm ttal may be made for a multiple unit station N he submittal should.gombine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal hall specify the releases of radioactive material from each unit, N l L -
BYRON - UNITS 1 & 2 6-20 l
l u..__
l ADNINISTRATIVE CONTROLS j pREPORTING REQUIREMENT 57C5nUnved) 3
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized !
- on a quarterly 4 asis following the format of Appendix B thereof. For solid
> wastes, the formR for Table 3 in Appendix B shall be supplemented with three
! additional cattgorien! class of solid wastes (as defined by 10 CFR Part 61)< --
type of container (e.g A LSA, Type A. Type B, Large Quantity), and 50LIDif!CA-
! TION agent or absorbent (t.g., cement, ures formaldehyde). /
! TheSemiannualRadioactiveEffluentReleaseReportssha11'includealist
'and description of unplanned releases from the site to ENRESTRICTED AREAS of radioactive materials in gaseous and ligeid effluents made during the reporting priod. ,
The Semiannual Radioactive Effluent Re'1 ease Reports shall include any thanges made during the reporting period to the-PCP, pursuant to Specifications
.S.13, as well as any major changes to Liquid, Gaseous or Solid Radwaste Treat-lmentSystems,pursuanttoSpecification6.15.
The Semiannual Radioactive Effluent Release Reports shall also include
,the following: an explanation as to why the inoperability of liquid or gaseous
- effluent monitoring instrumentation was not corrected within the time specified iin Specifications 3.3.3.9 or 3.3.3.10, respectively; and description of the-events leading to liquid holdup tanks or gas storage tanks exceeding the limits f Specification 3.11.1.4 or 3.11.2.6, respectively.
MONTHLY OPERATING REPORT
- 6. 9.1. 8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety valves, i
shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
OPERATING LIMITS REPORT l
6.9.1.9 Operating limits shall be established and documented in the OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle, i The analytical methods used to determine the operating limits shall be those previously reviewed and approved by the NRC in Topical Reports: 1) WCAP 9272-P- A " Westinghouse Reload Safety Evaluations Methodology" dated July 1985,
- 2) WCAP 8385 " Power Distribution Control and Load Following Procedures" dated September 1974, 3) NFSR-0016 " Benchmark of PWR Nuclear Design Methods" dated
! July 1983, and/or 4) NFSR-0081 " Benchmark of PWR Nuclear Design Methods Using the Phoenix-P and ANC Computer Codes" dated July 1990. The operating limits shall be determined so that all applicable limits (e.g., fuel thermal-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 OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional l Administrator and Resident Inspector.
BYRON - UNITS 1 & 2 6-21 AMENDMENT NO. %
1
ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)
- c. Records of radiation exposure for all individuals entering radiation control areas;
- d. Records of gaseous and liquid radioactive material released to the environs;
- e. Records of transient or operational cycles for those unit components identified in Table 5.7 1;
- f. Records of, reactor tests and experimerfts; g.- Records of training and qualification for current members of the unit staff;
- h. Records of in-service inspections performed pursuant to these Technical Specifications;
- i. Records of Quality Assurance activities required by the QA Program;
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;
- k. Records of meetings and results of reviews and medits peeformed by
. the Offsite Review and Investigative Func'. ion and tne Onsite Review and Investigative function;
- 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records;-
- m. Records of secondary water sampling and water quality;jnf
- n. Records of analysis required by the. Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures
-effective-at specified times anc' QA records showing that these
-procedures were followedy 3 un
- o. Emu sJ 1 6.11- RADIATION PROTECTION PROGRAM ,
l Procedures for personnel radiation protection shall be prepared consistent L 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 Pursuant to Paragraph 23.203(c)(5) of 10 CFR Part 20, in lieu of the
" control device" or_" alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/hr at 45 cm (18 in.) from the radiation BYRON - UNITS 1 & 2 6-23
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) h3. ThePCPshallbeapprovedbybeCommissionpriortoimplemen tion.
)
6.13.2 L t.nsee-initiated changes to the PCP:
a.
/y Sha11QesubmittedtotheCommissionintheSemiannualdadioactive Effluent sRelease Report for the period in which the, change (s) was made.
Thi(submittalshallcontain:
' /
- 1) Suf ficiehQy detailed information to tota'kly support the rationale for the change without benefit of additional or l supplemental 1(ormation;
- 2) A determination thatxthe ch'ange did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes;N qd
- 3) Documentationofthefactthathchangehasbeenreviewedand found acceptable by the Onsite Review Investigative Function.
- b. Shall become effective upon review and acceptance b 'the Onsite 4
Review and Investigative Function in accordance with Specification
'_E; -
6.14 JFFSITE DOSE CALCULATION MANUAL (ODCM) 7'&.44f.1~TheODCMshallbeaMrovedbytheCommissionpriortoimplementation. \
MI 6.14.2 " Licensee initiated changes to the ODCM:
- a. Shall'be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.9.1.8 within 90 dar of !
the date the change (s) was made offactive. This submittal shall contain: s '
y '
- 1) Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,s Information submitted should consist of a package of those pages qf the 00CM to be changed with each I page numbered, dated and contain(ng the revision number, together with appropriate analyses'or evaluations justifying >
the change (s);
\ N '
- 2) A determination that the change will not reduce the accuracy or reliability of dose calculations or Setpoint determinations; and
- 3) N Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigativ'equnction,
- b. Shall become effective upon review and acceptance by the Onsite' Review b and._lnytitig411ve Function in accordance with Specification 6.5.2 BYRON - UNITS 1 & 2 6-25 AMEN 0 MENT NO. 2{
I I
f~~ ~ ~ ~ ~ ~ ~ ~ ~~
^
/ ADMINISTRATIVE CONTROLS
/
6.15 MAJOR CHANGES TO LIQUID, GASE0US, AND SOLIO RADWASTE TREATMENT SYSTEMS
- l6.15.1 Licensee initiated major changes to the Radwaste Treatment Systems
. (liquid, gaseous, and solid): .
[
i-
- a. Sh 11 be reported to the Commission in the Semiannual Radioactive i Eff ent Release Report for the period in which the evaluation was revie d by the Onsite Review and Investigative function. The dis- '
cursion f each change shall contain e ,'
1)- A sum $ary of the evaluation that led to the determination that ,
the chahge could be made in accordance with 10 CFR 50.59;
- 2) Sufficien detailed information totally support the reason for the change without benefit.o additional and supplemental information; \ /
- 3) A detailed descr tionoft$ equipment, components,andprocesses ,
involved and the terf aceii with other plant systems.
,e I 4) An evaluation of the chpnge which shows the predicted releases of radioactive materi s in liquid and gaseous effluents and/or
' quantity of solid waste that differ from those previously predicted in the Lice'nse application and amendments thereto;
- 5) which shows'the expected maximum AnevaluationofthechangkPUBLICintheUNRESTRICTEDAREA exposures to a MEMBER OF TH and to the general populatioristhat dif fer from those previously estimated in the License app 1f atior, and amendments thereto;
- 6) A comparison of the predicted r leases of radioactive materials, in liquid and gaseous effluents nd in solid waste, to the actual releases for-the period pr or to when the changes are to be made; 7)- An estimate of the exposure to plant operating personnel as a result of the change; and 1 1
- 8) D6cumentation of the fact that the cha ewastsviewedandj
' /Tound acceptable by the Onsite Review a d Investigative Fuqction,
/ .
- b. Shd11 become effective upon review and accepta ce by the Onsite Review 6d Investigative Function in accordance with ecification 6.5.2.
l i
\ .
" L i c'/ensees may choose to submit the information called for in this specifi?ation as part of the annual FSAR update. ,
6
\/>
j.
,; BYRON - UNITS 1 & 2 6-26 -
INSERT 1 f The OrrSITE DOSE CALCULATION MANUAL (ODCH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive 4
gaseous and 11guld effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Efiluent Controls and Radiological Environmental l Monitoring Programs required by Sections 6.8.4e and 6.8.4f and (2) !
descriptions of the information that should be included in the Annual -
Radlological Environmental Operating and Semi-annual Radioactive Ef.tluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.
INSERT 2 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulaa, 1 sampling, analyses, test, and determinations to be made to ensure that pro essing and packaging of solid radioactive wastes based on demonstrated j pr.eessing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CPR Parts 20, 61, and 71, State ;
regulations, burlal ground requirements, and other requirements governing the ;
disposal of solid radioactive waste. !
l O
(2699H/0272H/11) ,
s- _. ,y . , . , . ..,.m,.___.g.m.
i INSERT 3 i
- e. Radisa cths_E LLlutaL_ Con Ltal1J rsg ram ;
i
- A program shall be provided conforming with 10 CTR 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 the ODCM, (2) shall be implemented by ,
Station procedures, and (3) shall include remedial actions to be taken l whenever the program limits are escoeded, The program shall include the :
following elements j
. 1) Limitations on the operability of radioactive 11guld and gaseous ;
munitoring instrumentation including surveillance tests and setpoint j determination in accordance with the methodology in the ODCM, !
- 2) Limitations on.the concentrations of radioactive material released in l 11guld effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendia B, Table II, Column 2,
- 3) Monitoring, iampling, and analysis of radioactive liquid and gaseous >
effluents in accordance with 10 CTR 20.106 and with the methodology I and parameters in the ODCM,
]
- 4) Limitations on the annual and quartwrly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS cor. forming to Appendis 1 to 10 CTR Part 50, ,
- 5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current 6 calendar-year in accordance with the methodology and parameters in ;
the ODCM at least every 31 days, [
t
- 6) Limitations on the operability and use of the liquid and gaseous !
effluent treatment systems to ensure that the appropriate portions of j
~
these systems are used to reduce releases of radioactivity when the ;
projected doses in a 31-day period would escoed 2 percent of the i guidelines for the annual dose or dose conenitment conforming to i Appendla I to 10 CTR Part 50, l t
- 7) Limitations on the dose rate resulting from radioactive material !
released in gaseous effluents to areas beyond the SITE BOUNDARY f conforming to the doses associated with 10 CFR Part 10, Appendia B, ;
Table 11, Column 1, !
i l- 8) Limitations on the annual and quarterly air doses resulting from I noble gases released in gaseous effluents from each unit to areas ,
! beyond the SITE BOUNDARY conforming to Appendia 1 to 10 CFR Part 50, j
- 9) Limitations on-the annual and quarterly doses to a MEMBER Of THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate. form with half-lives = greater than 8 days in gaseous [
effluents released from each unit to areas beyond the SITE BOUNDARY j conforming to Appendis I to 10 CTR Part 50, and ;
I
~
f (2699M/0272M/12) , !
I
!t l
-. - . - . - _ - . - . . .._.__.-.a- - - . - - . _ _ _ _ . _ _ . _ _ _ _ . . _ . - - . . - - . , ..
.x ,-
- 10) Limitations on th$ cnzuel dos? or do30 commitm3nt to cny HEMBER Or THE PUBLIC du3 to ro10ctos ( $ Tcdh hetivity cod to radiation f rom uranium fuel cycle sources conforming to 40 CTR Part ?.90,
- f. Radis1Dgic al t ntitsme AL11.,}ignLLoting ..P r ogIm A program shall be provided to monitor the radiation and radionuelldes in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential esposure pathways, and (2) verification of the accuracy of the ef fluent monitoring program and modeling of environmental esposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendla 1 to 10 CTR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identifled and that modifications to the monitoring p'rogram are made if required by the results of this census, and
- 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precisicn and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality atsuranc,e program for , environmental monitoting.
9 M
(2699H/0272H/13) ,
4
+ - . v- -- , x, ,,, ,,en - ,
INSERT 4 6.9.1.6 Tha Annuca Rcolologicc1 Environm3ntc1 Op3rcting R3 port covoring tho operation of the unit during the previous calendar year shall be submitted 4 before Hay 1 of each year. The report shall include summerles, interpretations, and analysis of trends of the results of the Radiological Environmental Honitoring Program for the reporting period. The anterial provided shall be consistent with the objectives outlined in (1) the ODCH end (2) Sections IV.B.2, IV.B.3, and IV.C of Appendis I to 10 CFR Part $0.
- A single submittal may be made for a multi-unit station.
INSERT $
6.9.1.7 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shat,( Includ. a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) couslatent witM the objectives outlined in the ODCH and PCP and (2) in conformance with 10 CI'R 50.36a and Section IV.B.1 of Appendix ! to 10 CTR part 54.
- A single submittal may be made for a multiestit station. The submittal should combine those sections that are common to a*1 units at the stations however. for units with separate radweste systems. the submittal shall specify the releases of radioactive material from each unit.
(2699H/0272H/14) ,
INSERT 0 6.13.1 Changes to the PCPt
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2o. This documersot< n shall contain
- 1) Suf ficient information to support the change together with the appropriate analyses or evaluations justifying the chtage(s) ano,
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to esisting requirements of rederal, State, or other applicable regulations.
- b. Shall become ef fective af ter review and acceptance by the Onsite Review and Investigative function (Onsite Review).
INSERT 7 6.14.1 Changes to the ODCMt
- a. Shall be documented and records of reviews performed shall be retained by Specification 6.10.20. This documentation shall contain:
- 1) Sufficient informatio'n to s',pyort the change together with tne appropriate analyses or evaluations justifying the changots) and,
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CTR 20.106, 40 CTR Part 190, 10 CTR 50.36a, and Appendix I to 10 CTL Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculatioas,
- b. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Managst on the date specified by the Onsite Review and Investigative Function.
- c. Shall be submitted to the Commission in the it v. of a complete, legible copy of the entire ODCH as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made ef fective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
(3423M/0329M/2)
- INSERT 8 Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
i I
9 8
9 m
(2699M/0272M/16) ,
\
l DEFINITIONS SECTION PAGE f.bstzTrb 1,32 50L:0:T!CATIO" .............................................. Ab4h 1.33 SOURCE CHECK................................................. 1-6 1.34 STAGGERED TEST BA515......................................... 1-6 1.35 THERMAL P0WER..............................................., 1-6 1.36 TRIP ACTUATING DEVICE OPERATIONAL TE5T....................... 1-6 1.37 UNIDENTIFIED LEAKAGE......................................... 1-6 1.38 UNRESTRICTED AREA............................................ 1-6 1.39 VENTI LATION EXHAUST TREATMENT 5YSTEM. . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.40 VENTING...................................................... 1-7 1,41 WASTE GA5 HOLOUP 5YSTEM...................................... 1-7 TABLE 1.1 FREQUENCY NOTAT!0N...................................... 1-8 TABLE 1.2 OPERATIONAL M00ES..................................... 19 BRAIDWOOD - UNITS 1 & 2 II
r f
t LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS l r l
\ f i
SECTION PAGE j 3/4.3.3 MONITORING INSTRUMENTATION j Radiation Monitoring for Plant Operations................ 3/4 3-39 !
TABLE =3.3-6 RADIATION MONITORING INSTRUMENTATION I.
FOR PLANT 0PERATIONS................................ 3/4 3 40 7 TABLE 4.3-3_ RADIATION MONITORING INSTRUMENTATION l FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS........................................ 3/4 3-42 Movable Incore Detectors................................. 3/4 3-43 )
Seismic-Instrumentation.................................. 3/4 3-44 [
TABLE 3.3 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3-45 ]^
Meteorological Instrumentation...................... .... 3/4 3-47 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............. 3'4 3-48 l TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................... 3/4 3-49. l t
Remote Shutdown Instrumentation.. ....................... 3/4 3-50 :
3/4 3-51 TABLE 3.3-9 REMOTE SHUT 00WN' MONITORING INS 1RUMENTATION............ l
~ TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION [
SURVEILLANCE REQUIREMENTS..................... ...,. 3/4.3-52 i Accide'nt Monitoring Instrumentation.,,.............,..... 3/4 3-53 r 1 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION....... ...... ... 3/4 3-54 [
TABLE 4.3-7 ACCIDENT. MONITORING INSTRUMENTATION r SURVEILLANCE' REQUIREMENTS........................... 3/4 3-55. !
TABLE 3.3-11--(This table number is not used.)..................... -3/4-3-57 ;
Loose-Part Detection System.............................. 3/4 3-58 ]
om diescthe Liquid Ef f bent "critering4ngreent: tier 3/d 2-5? {
"B L E --3. 3- 12 oA0!OACTIVE LIQUID EFFLUENT "0FITOR!9C t
-lWrTRUMENTATION. .. . .. .... ... . . .. .. 3/' 3-50 MBLE d.3-8 DA0!0 ACTIVE-.44 QUID EFrtygyt unp!79p;yg ,
INSTDUMENTAT40N SUDVEJtLANCE DEQUIDEMENTS. 3/^ :-52 j Radioec-tive Cascous Ef f h:nt "Oniudeg-lwA+ mentation 3/1 3-5; i' Eg loswe_ Co.s Men. b- Tr.Shm eAken~ . . . . . . . .
3/4 3-Sc) i.
+
BRAIDWOOD - UNITS 1 & 2 VI t
. - .. .-~ - . . . - - - - . - - - . . - - - - . . - - -
t, i !
t LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
-l 3'
SECTION PAGE i EgPLo5tVE 6 AS 7 (
-TABLE 3.3-13 "'0IO^CTIVE 0^0E000 EffLUC T MONITORING !
INSTRUMENTATION.................................... 3/43-h TABLE 4.3-9 ^ ^ 0:0.7 sN5mGo3
.CTIVE 0^0:000 L iLU:NT-MONITORING l
INSTRUMENTATION SURVEILLANCE REQUIREMENTS........... 3/43-N I
- High Energy Line Break Isolation Sensors. . . . . . . . . . . . . . . . . - 3/43-N h TABLE 3.3-14 HIGH ENERGY LINE BREAK INSTRUMENTATION............... 3/43-k l 3/4.3.4 _ TURBINE _OVERSPEED PROTECTION............................. 3/43-N 1
3 /4.- 4 REACTOR COOLANT SYSTEM !
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION l Startup and Power Operation.............................. 3/4 4-1 i Hot Standby.............................................. 3/4 4-2 i t
Hot Shutdown................................. ........... 3/4 4-3 i Col d Shutdown - Loops F111 ert. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-5 Cold Shutdown - Loops Not Fi11ed......................... 3/4 4-6 Loop Isolation Valves-Operation.......................... 3/4 4-7 f loop Isolation Valves-Shutdown........................... 3/4 4-8 ,
3/4.4.2 SAFETY VALVES :
Shutdown.........................,,.................... 3/4 4-9 i
-0perating.............................................. 3/4 4-10 3/4.4.3 PRESSURIZER.............................................. 3/4 4-11 r 3/4.4.4 RELIEF VALVES............................................ 3/4 4-12 f 3/4.-4.5 STEAM GENERATORS........................................._ 3/4 4-13
-i s
TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED l
DURING INSERVICE ~ INSPECTION......................... 3/4 4-1B [
TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION....................... 3/4 4-19 !
3/4.4.6 . REACTOR COOLANT SYSTEM LEAKAGE !
i Leakage Detection Systems................................ 3/4 4-20 l Op e rati o nal Le a ka ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4-4-21 l TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...... 3/4 4-23 :
3/4.4.7 CHEMISTRY................................................ 3/4 4-24 i
i BRAIDWOOD - UNITS 1 & 2 VII AMENDMENTN0.k r
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, LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER 015TRIBUTION LIMITS... 3/4 10-2 3/4.10.3 PHYSICS TESTS............................................ 3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS.................................... 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................... 3/4 10-5 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS r.oncentrauca .
m 11-1 JASLE 4,414-. RA040ACT!VE L! QUID-WAGTE - EA""LINC fMO.
-ANALM IS-P"OCRAM,............................... . 'M1 ,
-Cose.. .................,,.................... m ....... 3/4144--
~
liquid Aadwaste. Trea tmont-Sy6tearrrvn . . . . . . . . . . . . . . . . . . 3/4414 --
Liquid Holdup Tanks......................'............. . 3/411-gl.
3/4.11.2 GASEOUS EFFLUENTS
--De s e-R a te . . . . . . . rr . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ..... 3/4-44 4 --
-TAB LE-4 r114-R AD ICAC-T I VE-GA SE005 -WA STE-SAMPt-}NG-AN&-
-ANAL-Y S I S-PROGRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 3/4 1440-Cose = Noble-Cases.,,,,,, . . . . . . . . . .. ... 3/' 1144--
.-Cose a-Jodine=131-and-133rT-r4ttua r an4Jadioac4two-
-Matsrtal inJarticulate-Som. . , ....., ............ 3/441 -04 seou s 44dwa s te- Trea tme nt 4ys tem . . ............ ... 3/44145--
Explosive Gas Mixture. .......................... ...... 3/4 11-g2.
Gas Decay Tanks..........................................
3/4 11-F3 BRAIDWOOD - UNITS 1 & 2 XIII
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3/4.11.3 S 0 AA010 ACTIVE WASTES............................. .. 3/4 11-18 .
3/4.11.4 TOTAL 5E....................................... ....... 3/4 11-19 ;
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' ' ' i J DIOLOGICAL EN @NMENTAL MONITORING ',
u.1 o rT0u m ,,0GR ..... ......... ....................... 3/4 u-1 ;
t TA8LE 3.12 RADIOLOGICAL ENVIRONM MONITORING PROGRAM........ 3/4 12-3 .
TABLE 3.12-2 -REPORTING LEVELS F0 I TIVITY CONCENTRATIONS j IN ENVIRONMEN SAMPLES..... ..................... 3/4 12-9 s
.TA8LE 4.12 1 DETECTION 8!LITIES FOR ENVIRO NTAL ;
SAMP ANALYS!5...................... ............ 3/4 12-10 '
3/4.12.2 LAND U CENSUS................................ ........ 3/4 12-13 !
3/4.12.3 I RLA80RATORY' COM8 ARi%ON- PRMRAM "
- * +- b*.1 12-16 j-i.
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BRAIDWOOD - UNITS 1 & 2 XIV 1
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BASES SECTION PAGE 3/4.0 APPLICABILITY............................................... 3 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION 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 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................... B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....... B 3/4 2-2 FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX OIFFERENCE VERSUS THERMAL P0WER.................................. B 3/4 2-3
..' 3/4.2.4 QUADRANT POWER TILT RATI0................................. B 3/4 2-5 3/4.2.5 DNB PARAMETERS............................................ B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINE'ERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............... B 3/4 3-1 3/4.3.3 HONITORING INSTRUMENTATION................................ B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION.............................. B 3/4 3 )
3/4.4 REACTOR COOLANT SYSTEM
'Th.smay0lu14 g 4 gg a M ,ha 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............. B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................. B 3/4 4-2 3/4.4.3 PRESSURIZER............................................... B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-2 tim'I f LXd de vy my
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p tf BRAIDWOOD - UNITS 1 & 2 XV J ghF
- .. . ~ . -- - .- . - . - _ - . _ . --. . - . . .
BASES I
SECTION PAGE 3/4.9.6 REFUELING MACHINE......................................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY................ B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............. B 3/4 9-2 3/4.9.9 CONTAINMENT DGE ISOLATION SYSTEM........................ B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L........ . ................................... B 3/4 9-3 3/4.9.12 FUEL HANDLING BUILDING EXHAUST FILTER PLENUM SYSTEM....... B 3/4 9-3 3/4.10 SPECIAL TEST-EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................- B 3/4 10-1 3/4.10.2 GROUP HEIGHT INSERTION, AND POWER DISTRIBUTION LIMITS.... B 3/4 10-1 3/4.10.3 PHYSICS TESTS............................................. B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN..................... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS pt.SgP TAuKb g 3 **11' B 34 11-1 Yxb4NbM."25MWAF ********** .
3/4. n. 2 aS:0uS crr=e . . . . . ....................
./ NG*iiidifisdu*1. . . . . . . . . '. B. 3/4 u-u .
3/^.11.3 00 LIfHtA&f 0Aen vE WAS T E 3. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . a-3/441-y-
-3/4.11.4 TOTAL 00SE............................................... B 3/4-11 TM -1E JtADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROG ..... ........................... -1 3/4.12.2 LAND USE CENSUS................. . .............. B 3/4 12-1 3/4.12.3 INTERLABORAIDAV-COMPAR SON PR0 GRAM..................... B 3/4 12-2 rw BEY /
BRAIDWOOD - UNITS 1 & 2 XVIII AMENDMENT NO. 25
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ADMINISTRATIVE CONTROLS SECTION .
PAGE 6.7 S A F ETY L I M I T V ! 0 LAT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-15 6.8 PROCEDURES AND PROGRAM 5....................................... 6-15 6.9 REPORTING REQUIREMENTS........................................ "6-18 6.9.1 ROUTINE REP 0RTS......... ................................... 6-18 Startup Report.............................................. 6-18 Annual Reports.............................................. 6-18 Annual Radiological Environmental Operating Report....... .. 6-19 Semiannual Radioactive Effluent Release Report....... ...... 6 20 Monthly Operating Report................................ ... 6-21 Radial Peakina F4ftor Iimit Renart '-11 6.9.2 SPECIAL REP 0RTS............................................. 6-22 6.10 RECORO RETENTION........................................ ... 6-22 6.11 RADIATION PROTECTION PR0 GRAM,............................ ... 6-23 6.12 HIGH RADIATION AREA........................................ 6-23 6.13 PROCESS CONTROL PROJRAM (PCP)............................... 6 25 6.14 0FFSITE 005E CALCULATION MANUAL (00CM). . . . . . . . . . . . . . . . . . . . . . . 6-25 4
4rl5-MAJOR-CHANGES--TO-L4QMO-GASECUS , AND 00L40 " AO'.!ASTE
-TR E AT ME N T- SY S TE M S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 as '
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I 8RAIDWOOD - UNITS 1 & 2 XXI
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DEFINITIONS OFFSITE DOSE CALCULATICN MANUAL Refb d'b h*d A 1.18 :The OriSITC 005: CALCULATION P"!UAL (00GM) chal' cent:4n the -ethodology
- and parameters. asad-in + he calculatina of offsite desas due +n rad 4cactive
-gaseous-+nd liquid cfhentir-4e-the-ealedetien of-j;;;cca; :nd 'iquid
+4heet-monitteing-Alarm %ip-6etpoints-end-fe-the conduct-of the Erv rcr-- i menta! Radielegica! Monitering % gr:-
OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), a and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATING LIMITS REPORT 1.19a The OPERATING LIMITS REPORT is the unit-specific document that provides operating limits for the current operating reload cycle. These cycle-specific operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.9. Plant Operation within these operating limits is addressed in individual specifications.
OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
PROCESS CONTROL PROGRAM (jgf4.Ac4 W kS N 1.23 The PROGESS CONTROL PROGRAM 4GCP) chal' contair the current fermu'es.,
- s enpling, analyses , t esti, 2Dd dStgrminadnne tn he mario tn ancore that
-PPOGess-ing-and-packagleg-of-sO44-PadiGaGt4Ve-wastes- Dased-on-demonstr4ted.
-process 4eg-of-aGtual-or-+4mulated-wete-soMd-wastet wi be acccmp'i ched 4-sue a-way-as-to-assurewompMance-with 10 CFR Paet 20, 61, 71 and Fedcr:1 mnd Stata-regulations, burial ground requirements r -and4ther requireme-t Onuarning the riisnasal nf ear 44^ective 'estos BRAIDWOOD UNITS 1 & 2 1-4 Amendment No. 15 I
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DEFINITIONS
(
SOLIDIFICATION gg {
1.32 FMATMM-sM ? ' b th: :;r.versi:r,of wet w ee: 'e: : fw-u.atr
. mosts-shipping eM ber441_greue requiments, SOURCE CHECK .
1.33 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:
- a. A test schedule for systems, subsystems, trains, or other designated ccaponents obtained by dividing the specified test interval into n equal subintervals, and
- b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
inE N . eG Es 1.35 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. -
UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
BRAIDWOOO UNITS 1 & 2 1-6 l
INSTRUM TATION RADIDACTI LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CON TION FOR OPERATION /
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3.3.3.9 The radio ctive liquid effluent monitoring instrumentatio channels shcwn in Table 3.3-1 shall be OPERABLE with their Alarm / Trip Set ints set to ensure that the limits of Specification 3.11.1.1 are not exceede . The Alarm /
Trip 5etpoints of these hannels shall be determined and adjus d in accordance with the methodology and -arameters in the OFFSITE DOSE CALC ATION MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
- a. With a radioactive liquid effluent moni oring instrumentation channel Alarm / Trip Setpoint less c servative han required by the above specification, immediately s spend e release of radioactive liquid effluents monitored by the ffected channel, or declare the channel inoperable.
- b. With less than the minimum num er f radioactive liquid effluent monitoring instrumentation pfiannels OPERABLE, take the ACTION shown in Table 3.3-12. Restore rhe inoper le instru.nentation to OPERABLE status within the time sp,ecified in th ACTION, or explain in the next ffluent Release eport pursuant to Specifica-SemiannualRadioactive/noperabilitywasntcorrectedwithinthetime tion 6.9.1.7 why thi 4 i specified.
- c. The provisions Specifications 3.0.3 and 3. 4 are not applicable.
SURVEllLANCE REQUIRJ ENTS s 4.3.3.9 Ea radioactive liquid effluent monitoring instrumentati n channel shall be d onstrated OPERABLE by performance of the CHANNEL CHECK, URCE CHECK, C NEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL EST at the fre uencies shown in Table 4.3-8.
BRAIDWOOD - UNITS 1 & 2 3/4 3-59 I I
TABLE 3.3-12 x
h RADIDAC'.IVE LIQUID EFFLUENT MONITORING INSTRUMENTATION [
6 g h MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION c
z U 1. Radioactivity Mon' tors Providing Alarm and
[ Automatic Terminatio of Release Liquid Radwaste Ef f ' bent Line (ORE-PR001) 1 31
[ a.
Fire and Oil Sump (0RE PR005) 1 1 34 b.
Condensate Polisher Sump Discharge (ORE-PR041) 1 34 <
c.
- 2. Radioactivity Monitors Providing \
Alare But Not Providing Automatic Terminatiolix of Release 4 \
2 .
Essential Service Water
- a. N l h 1) Unit 1 \ N e
1 32 a) RCFC 1A and IC Outlet (IRE-PR002) \
r N 1 32 b) RCFC IB and ID Outlet (IRE-PR003) \
%% 2) Unit 2
/
,/
1 32 a) RCFC 2A and 2C Outlet (2RE-PR002)'
1 32 b) RCFC 28 and 2D Outlet (2RE-PR003) 1 32
% b. Station Blowdown Line (ORE-PR01
- 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Eff1 t Line (Loop-WX001) 1 8 33
- b. Liquid Radwaste ffluent Low Flow Line (Loop-WX630) 1 Station Blowdown Line (Loop-CWO32) 1 33 c.
i
t TABLE 3.3 12 (Continued)
ACTION STATEMENTS
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ACTION 31 ith the number of channels OPERABLE less than required y the nimum Channels OPERABLE requirement, effluent releas s via t s pathway may continue for up to 14 days provided hat prior to 'nitiating a release:
- a. A least two independent samples are analyZ in accordance wit Specification 4.11.1.1.1, and
- b. At leait two technically qualified memb 5 of the facility staff i'hdependently verify the relean rate calculations and discharge ine valving.
Otherwise, suspend release of radioac ive effluents via this pathway. s ACTICh32-WiththenumberofAtannelsOPER LE less than required by the Minimum Channels OPERABLE requi ement, effluent releases via this pathway may continue for ep t 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samp es are collected and analyzed for radioactivity at a lower l'init of detection of no more than 10 7 microcurie /ml. ',
ACTION 33 - With the number of ch nels PERABLE less than required by the Minimum Channels OP ABLE requirement, effluent releases via this pathway may contin for up to 30 days provided the flow rata is estimated at leap once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance cur es generated in place may be used to estimate flow. 'N ACTION 34 - With the n ber of channels OPERABLE IN'ss than required by the Minimue C annels OPERABLE requirement, effluent releases via this pa way may continue for up to 30 days provided grab samples are a lyzed for radioactivity at a lower limit of detection as spec ied in Table 4.11-1: 'y a At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific \ activity of the secondary coolant is greater than 0.01 mib oCurie/ gram DOSE EQUIVALENT l-131, or
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> wher. the specific acti (ty of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.
I 3/4 3-61 Amendment No. 6 BRAIDWOOD - UNITS 1 & 2
TABLE 4.3-8 RADIDACTIVE LIQUID EFFLUENT MONITORING INSIRUMENTATION SURVEILLANCE REQUIREMENTS h
- ANALOG DIGITAL E
c CHANNEL CHANNEL o CHANNEL OPERATIONAL OPERAT10t" CHANNEL SOURCE CHECK CHECK CAllBRATION TEST TEST /
INSTRUMENT
[
z O 1. Radioactivity Monitors Providing Alarm and Automa
- Termination of Release
[ P R(3)# Q(1) N.A.
~ a. Liquid Radwaste Ef Iqent Line (GRE-PR001) D N.A.
rge (ORE-PR005) D M R(3) Q
- b. (1) N.A.
- c. FireandOilSumpDis%umpRischarge Condensate Polisher S D M R(3)
- 2. Radioactivity Monitors Providing Albra But Not Providing Automatic Termination \
g of Release
{
- a. Essential Service Water
- 1) Unit 1 R(3)# Q(2) N.A.
a) RCFC 1A and 1C Outlet (1RE-PR002)
D 4 M R(3)# Q(2) N.A.
D b) RCFC IB and 10 Outlet (IRE-PR003)
$, 2) Unit 2 h
a) RCFC 2A and 2C Outlet (2RE-PR002 0 M -\(J R Q(2) H. A.
N.A.
P M R(3)* Q(2) b) RCFC 28 and 20 Outlet (2RE-PRO )
M R(3)# Q(2) N.A.
D
- b. Station Blowdown Line (ORE-PRO l y 3. Flow Rate Measurement Devices 1
z a. Liquid Radwaste Eff1 nt Line N.A. R# N.A. Q
" (Loop-WX001) D(4)
$ b. Liquid Radwaste ffluent low Flow N.A. R N.A.
Line (Loop WV 0) O(4)
N.A. R N A. Q
- c. Station Bir down Line (Leep-CWO32) D(4) t r
i TABLE 4.3-8 (Continued) t TABLE NOTATIONS
- The spec fied 18 month interval may be extended to 32 months for cycle 1 oni , l (1) The O1GITAL CHANNEL OPERATIONAL TEST shall also demonstrate that auto atic isolatioh of this pathway and control room alarm annunciation occur f any of the following conditions exists:
- a. Instrume t indicates measured levels above the Alarm / Trip etpoint, or
- b. Circuit fail re (monitor loss of communications - al Ym only, detector lossofcounti or monitor loss of power), or
- c. Detector check rce test failure, or
- d. Detector channel o t-of-service, or
- e. Monitor loss of samp \ flow.
(2) The DIGITAL CHANNEL OPERAT101 t. TEST shall also demonstrate that control rocm alarm annunciation occurs any of/the following conditions exists:
- a. Instrument indicates measurec}xig/els above the Alarm Setpoint, or
- b. Circuit failure (monitor los, xcommunications - alarm only, detector loss of counts, or monito oss of power), or
- c. Detector check source test failure, or
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- d. Detector channel ou /
of-service, or
- e. Monitor loss of mple flow.
(3) The initial CHANNEL CAllBRATION shall be performe susing one or more of the reference st 6dards certified by the National Bttreau of Standards (HBS) or using tandards that have been obtained fronhsuppliers that participate i measurement assurance activities with NBS. These standards shall permi) calibrating the system over its intended rhqge of energy and measuremept range. For subsequent CHANNEL CALIBRATION, sources that have been rel ted to the initial calibration shall be used.
(4) CHAN .L CHECK shall consist of verifying indication of flow d ing periods of elease. CHANNEL CHECK shall be made at least once per 24 urs on ys on which continuous, periodic, or batch releases are made, a
G
'pe&g BRAIDWOOD - UNITS 1 & 2 3/4 3-63 AMENDMENT NO. 2
' INSTRUMENTATION _ gkpt,3wg Q45 RA0!OACT!VE~CASCOUS EFFLUENT-MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION upleuve p 3.3.3.10 The r:dic :tiv: ;;;;;.-- file;nt* monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip 5etpoints set to ensure that the limits of Specification \ 3.-11.2.1 :nd 3.11.2.5 are not exceeded.
Jh: ^!ar-!'-fp S tp: int ef there chana=1e - : tin; f p::ifiestien 3.11.2.1,;..ii p: d3tgrrin:d :nd ;dju;t;d * ::: erd:n;i ith th: :thedeiepy i~d p=e et:r;-in
~
u ,. vuon.
APPLICABILITY: As shown in Table 3.3-13 ACTION:
.ugle we ps WithmAr radi ::tiv: ; ':;u_ effluent monitoring instrumentation y
a.
channel Alarm / Trip 5etpoint less conservative than required by the above specification, ' ::dietely ;;; pend th: rei ::: ef .adieective ge;;;u, ciilucni. ;;riter:1 by th: offected channel, er declare the channel inoperableg ud 6.h. h AcxtoM d.wn b 'T3.A 3.%- t%
e leswo g+4
- b. With_less than the minimum number of r:di;;;ti._ .....sp;
. efflumns )
monitoring instrumentation channels OPERABLE take the ACT!0N shown in Table 3.3-13. Restere-u,e inepsieble in>L umentetier :: OPERACtt-statu; within the tim :pect' icd in the ^.CTION, er explain in th: :
.aext Se-!annueL S44to::tive E "!uent Rele::: Report pur;;:nt 1:
Spec!'icatica 6.9.1.7 uhy this inoperab!14ty 'as act creeec+=d
~!thi- the ti e spec!'ied.
1 t c .- The provisions of Specifications 3.0.3,.ard 3.0.4 are not applicable.
l l
l SURVEILLANCE REQUIREMENTS 4.y y 6 n v 4.
4.3.3.10 Each radioactive ,g.sg 2 ::;.; Of'luent monitoring instrumentation channel-
- shall be demonstrated OPERABLE by performance of-the CHANNEL CHECK,400RCE-
-Cli:CY., CHANNEL CALIERATION and DIGITAL CHANNEL OPERATIONAL TEST at the f re-quencies shown in Table 4.3-9.
1 BRAIDWOOD - UNITS 1 & 2 3/4 3-
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[ L1 35 P J CE C ee-CJ e*%#
- y. I,)
+l %s e= e e=4 e+ 5J +> %# CJ C ('L es h C"1 ... %s %s CL u. C7 *J 17) *e- .
%,e (/
r U
E!U 43 ,a lE t> Ei C;
.e-D lE
.e- 1
(>
C?) de 1.
fi r3 C/ =ct C3; l',
- l- C71 ID 1. r) di.
ce - -
C3:
Ci "1" +1 ':1 C On t> v) es p C: t}'1 U) +#
- 1. +>f3
)tp #%
ll$ e C) t,)e- r3 C e- O di ( .) t>r= r) C e- O CJ y +> c;<: 0; c) CL C7 :5Cl *J < 4 C'. 10 t'L CJ :%C)
+> vi e LJi "" Ck:: di +e vi e - 6t>
D- >== .. Q: EE 9 Z C: O (31 J' C fp tn U.Y) 1: O 17) G #3 ft) Ch u.W M) ll: CD ) e* ; **
- u.J CD e 4: CD) l W e== +3 C; ett 4) 01 +ea 3 E 3 C + 4].-)C) :p f: u-- 1- Ci: 2: C =
'j QJ :) $ .C le. Q:
=> l+t m c, o us v C1. ) "t ... v w es. o C6 CC +' C;++ C; *e* :) :. I e- I *a q:
<>'8= L: ** $:7 et 64 e+
Ci 41 Q
=
>v'>
C:
cr c--
gi o yg e.>
4 ef
+ W
("J. p=
16u
-} o c--
.C) o 4* **-
V f.ft)w *. r) 0 Z D' C) 1,. p%r= f4l te4. I3e .4 # ? > C) l r%#"% () QCs r3
==. ;:;C. eiel =e n, uJ 44we 2: C ,,. es N e-4 C4 L44 E ui -
e\ Dee
i C' g&
q r3 v1I co' . , , s ,
Q 0-- - . . . .
F I
- k l
i w BRAIDW000 - UNITS 1 & 2 3/4 3-
TABLE 3.3-13 (Continued)
% EWih CS
- VL %S #
3 RAGIGACTIVE G'5EOUS EfftVENT MONITORING INSTRUMENTATION E
8 MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION INSTRUMENT E 3. Gaseous Waste Management Sys' s u ** 38 Hydrogen Analyzer (OAT-GW8000) 1 a.
[
- b. Oxygen Analyzer (OAT-GW8003) 1
- 38 (
[ (
- c. Waste Gas Compressor Discharge ***
1 38 [3 Oxyg?n Arialyzer (OAIT-GW004)
Gas Decay Tank System t' a. le Gas Activity Monitor - Providing i AlarrNd Automatic Termimtion of
- 35 2
Y Release (CRE'-fR002A x and 28) o 5. Containment Purge System N
- a. Hoble Gas Activity Monitor - Providing
- 37 Alarm (RE-PR001B) N 1
- b. Iodine Sampler (RE-PR0010) b
- 40
- c. Particulate Sa 1
\
- 40
[ (RE-PR001A) o ko 6. Radioac ' ty Monitors Providing Alarm and Aut ic Closure of Surge Tank Vent-Component
- oling Water Line (ORE-PR009 and RE-PR009) 2 N 6
X .
I
l TABLE 3.3-13 (Continued)
TABLE NOTATIONS i
"At-eli t' e .
- During WASTE GAS HOLDUP SYSTEM operation.
- During Waste Gas Compressor Operation, All instruments required for Unit 1 or Unit 2 operation.
f ACTION STATEMENTS 10N 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the t 5) may be released to the environment for up to 14 days prov that rior to initiating the release:
- a. A east two independent samples of the ta k s contents are analy d
- b. At least two chnically qualifi 4 members of the facility staff independe verify th elease rate calculations and discharge valve lin .
Otherwise, suspend rel a e of a ioactive effluents via this pathway. i ACTION 36 - With the numbe of channels OPERABLE les han required by the Minimum Jbefinels OPERABLE requirement, efflu nt releases via this pathwpy'may continue for up to 30 days provided44e flow rate is es)itnated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ACTION)?<WiththenumberofchannelsOPERABLElessthanrequiredb e Minimum Channels OPERABLE requirement, immediately suspend P NG of radioactive effluents via this pathway.
ACTION 38 - With the number of channels OPERABLE less than required by the T Minimum Channels OPERABLE requirement, operation of this system may continue provided grab samples are taken and analyzed at least once q per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
++
ACUQM 39 =-With-the-number h is OPERABLE requireme of-charnels OPEAAStE-Tw then-requir-d. M '"via thiL pathway may cont da s provided grab samples are ken-st 1 C once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an s mep n are analyzed 1 i
foe-eadioactiv&ty within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A BRAIDWOOD - UNITS 1 & 2 3/43-6f1 AmendmentNo.i.
/
TABLE 3.3-13 (Continued) ,/
ACTION STATEMENTS (Continued) f'
,/
ACTION 40 - With numberofchannelsOPERABLEless-t(anrequiredbythe Minimum annels OPERABLE requirement,-effluent releases via the affected thway may continue for.up'to 30 days provided samples are continu sly collected witt) auxiliary sampling equipment as required in T le 4.11-2. /
,/
ACTION 41 - With the number o chantiels OPERABLE less than required by the Minimum Channels 0P ABLE requirement, effluent releases via this pathway may co3tinue r up to 30 days provided that, at least once per 12, hours, grab mples are collected and analyzed for radioact ' it of detection of no more than 10 7 microcur,1vity ie/mi. at a lower
/
b y
BRAIDWOOD - UNITS 1 & 2 3/4 3-68
TABLE 4.3-9
, EGudos/s. GAS y DAg{ga{y{ {A.5FOUS EFELUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS { O - DIGITAL
$ CHANNEL MODES FOR M11CH 8 CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE CHECK CHECK CALIBRATION TEST 15 REQUIRED c- FUNCTIONAL UNIT 5 no4- asei.
d 1. alant '/cnt "critaring Syste: " nit I w o- 2_ u egje c. ac t ytty g-ity. - m Praviding ^!ar? (
- 1) High Raage'(IDE-PD0?nn) p-37py q{;y-9 Le" R2 ;^ (IRE DRO?99) R(3) ( (
-)
t, . Iedinc Sa p?ce (IRE-PRO??C) M )1F#j QJ2) ( ( f (3)## cQ( , Pcrticelat Srpier (IRE PRC20A)
-c. D w N 'A. R##
D d. Eff]uent System T;cw ";te w "cc;uring Ocvicc (La^P "*"1") g' (
- e. s - !er riy o3te g 35yr t a; 4.A. Rf# $ 7 i
F Device (IF1 "R255) ( ] C / 4.t tisM
- 2. Mant "cnt " nitcr i ~; Syst- - Uni + 'e
. u.mu.~
c.,
--- i, + c. o t. e.,., u.m. o.s ,. ,., -
1 3T m Z
- 1) N!gh D3ng. (pp{ Dpg?gg} gy g k t) tou " cage (2er aee2ee) bg g)## qd )
9
- j (y Iodin- Sa-!er (?RE oRo?eC) g(3)## Q )
,5 5
(
* -c . u niceiete s ie- (2DE o=02e-)
7 g'n, Qg
i l TABLE 4.3-9 (Continued) g EK ftof, glL G45 # E RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E DIGITAL 8 CHANNEL MODES FOR WHICH SOURCE CHANNEL OPERATIONAL SURVEILLANCE
' CHANNEL CHECK CHECK CALIBRATION TEST 15 REQUIRED E FUNCTIONAL UNIT l 0
- 2. Plant Vent "sniter'ng Sysic - Uni t !=
-(emt4need) o. " Effluent Systt: Flow " ate- -tF A* R#
d. Fe: sering Ocvice-(100P-V'020) O rp?cr T?cw "etc "casuring U K. R# c. n evice (2FT-PA1f,5)
- 3. Gaseous Waste Management System M D N.A. Q(4) M
{ a. b. Hydrogen Analyzer (OAT-GW8000) Oxygen Analyzer (0AT-GW8003) D N.A. Q(5) M
** l g
- c. Waste Gas Compressor Discharge *** 1 e D N.A. Q(5) M N 0xygen Analyzer (OAIT-GWOO4)
Gas Decay Iank System s Activity Monitor - P P R(3)## Q
) a. No e I /J Provid(ing Afara and Automatic Termination of RDe ca n s (0RE-PR002A and 28) p 5. Containment Purge System x N
3o. a. Noble Gas Activity Monitor y
- P ## Q(2) l Providing Alarm (RE-PR0018)'
Iodine Sampler / D P P R(3)## N.A. b. [ o (RE- IC)
- P R(3)## N.A.
A Particulate Sampler P (RE-PR001A)
-TABLE 4.3-9 (Continued)-
RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION' SURVEILLANCE REQUIREMENTS a DIGITAL: 6 OR WHICH 8 SOURCE CHANNEL CHANNEL: OPERATIONAL MOD-VEILLANCE.
-. CHANNEL e FUNCTIONAL IT _ ' CHECK- CHECK CALIBRATION TEST '15 REQUIRED 3
d 6. Radioactivi nitors Providing g Alarm and Autom Closure.of
- e. Surge Tank Vent.C nt Cooling
- m Water Line (ORE-PR009 RE-PR009) D. M R. )## Q(1) 3
' x
=
SiE E 5
i TABLE 4.3 9 (Continued) TABLE NOTATIONS 4 t eli time 5<
**During WASTE GAS HOLDUP SYSTEM operation. ***During Waste Gas Compressor Operation. l All instruments requi+ed for Unit 1 or Unit 2 operation. #The --5prcif4ed 10 month-4fttervel msj bc Wed-t+4Feenth; f or cycle 1 cr!y, rJ,4 U S . d (1)(he ITAL CHANNEL OPERATIONAL TEST shall also demonstrate that autom isola o y f this pathway and control room alarm annunciation occur any of the ToQowing conditions exists;
- a. Instrumentindicits measured levels above the m/ Trip 5etpoint, or
- b. Circuit failure (monitor loss o unications - alarm only, detector loss of counts, or monitor s of power or
- c. Detector check ce test failure, or
- d. Detet,to channel out-of-service, or \
A totl055_OLiample_ flow, m get Us-A (2)d Q. UITAt CHANNEL OPRATIDNAL IL51 shall also demonstrate that control f room aTar annunciation occurs if any of the following conditions ejitt's:
- a. Instrument iridiu es measured levels above the Al re , or
- b. Circuit failure (monitor M of comniunit alarm only, detector loss of counts, or monitor los. ower),or
- c. Detector check source lure, or
- d. Detec out-of-service, or r Monitor l01SJf_illn.ple flow.
(3) pTheM A. as.2 _ Q CHANNEL CALIBRATION shall be performed using one or mor V rds certified by the National Burea' naards the (NBS) referencG7t4(dardNha or using stan ve been obt nad m suppliers that participate in measurement assur - ties with NB5. These standards shall permit calibratJng-the-Tjsi.em over its range of energy and measurement r4 C or subsequent CHANNEL CALIBRATION, s have
.heem-reTited to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen. (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen. W8 BRAIDWOOD - UNITS 1 & 2 3/4 3-Jf (;3 Amendment No. $'
I'NSTRUMENTATION HIGH' ENERGY LINE BREAK ISOLATION SENSORS '. l.
= LIMITING CONDITION FOR OPERATION .
3.3.3.11' The'high energy line break instrumentation shown in Table 3.3-14
=shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3 ACTION: a.. With the number of OPERABLE auxiliary steam isolation instruments less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or suspend
-the supply _of: auxiliary steam to the Auxiliary Building, or establish a continuous watch in the affected area (s)-until the inoperable sensors are restored to OPERABLE status.
- b. With the number of OPERABLE steam generator blowdown _line isolation instru-ments.less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the-inoperable instrument (s)'to OPERABLE status within 7 days, or limit the total' steam generator blowdown flow rate to less than or equal to 60_gpm or establish a continuous watch in-the affect.ed area (s) until the inoperable sensors are restored to OPERABLE status.
.. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVE!L!ANCE AEOUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be--demonstrated OPERABLE by the performance of_an ANALOG CHANNEL OPERATIONAL
-TEST and CHANNEL-CALIBRATION at least once:per 18 months.
BRAIDWOOD - UNITS 1 & 2 3/4 3- hi
TABLE 3.3-14 HIGH ENERGY LINE BREAK INSTRUMENTATION ISOLATION INSTRUMENT MINIMUM CHANNELS APPLICABLE FUNCTION CHANNEL OPERABLE H0 DES
- 1. Auxiliary Steam OTS-A5031A 1
- Isolation OTS-A5032A OTS-AS031B 1
- OTS-A5032B OTS-A5031C 1 OTS-A5032C OTS-AS031D 1 OTS-A5032D OTS-A5031E 1 OTS-AS032E OTS-AS031F 1 OTS-AS032F
- 2. Steam Generator TS-SD045A 1 1, 2, 3, 4 Blowdown Line TS-SD045B Isolation TS-SD046A 1 1,2,3,4 TS-SD046B TS-SD045C 1 1,2,3,4 TS-SD0450 TS-50046C 1 1,2,3,4 TS-SD046D
- Required when auxiliary steam is being supplied, from any source, to the ;
Auxiliary Building. BRAIDWOOD - UNITS 1 & 2 3/4 3- bI t
I i i INSTRUMENTATION I I 3/4.3.4 TURBINE OVERSPEED PROTECTION L f LIMITING CONDITION FOR OPERATION
- i, 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE. }
APPLICABillTY: MODES 1, 2, and 3. 1 1 ACTION:
- a. With'one throttle valve or one governor valve per high pressure turbine ,
steam line inoperable and/or with one reheat stop valve or one i reheat intercept valve per low pressure turbine steam line inoperable, j rest >re the inoperable valve (s) to OPERABLE status within 72 hours, ! or close at least one valve in the af fected steam line(s) or isolate ! the turbine from the steam supply within the next 6 hours.
- b. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours isolate the turbine from the steam supply, j i
SURVEILLANCE REQUIREMENTS l 4.3,4.1 The provisions of Specification 4.0.4 are not applicable. 4.1.4.2 The above required Turbine Overspeed Protection System shall be ! demonstrated OPERABLE: l
- a. During turbine operation at least once per 31 days by direct obser- !
vation of the movement of the valves below through one complete cycle ; i from the running position:
- 1) Four hi p pressure turbine throttle valves, !
Fcur high pressure turbine govcrnor valves, j
-2)
- 3) =Six turbine reheat , top valves, and
- 4) Six turbine rcheat intercept valves. ,
- b. Within 7 days prior to entering MODE 3 from MODE 4, by cycling each !
of the 12 extraction tteam nonreturn check Valves from-the closed ! position, j
- c. During turbine operation at least once per 31 days by direct observa- l tion, of freedom of movement of.each of the 12 extraction steam non- !
return check valve. weight arms, l
- d. At least once per 18 months by performance of CHANNEL CAllBRATION !
l L on the Turbine Overspeed Protection Systems, and j
- e. At-least once per 40 months.by disassembling at least one of each'of (
the valves given in Specifications 4.3.4.2a. and b. above, and per- > forming a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion. BRAIDWOOD.- UNITS 1 & 2 3/4 3- (d [--.- ..m,y..-,,mmm_,,, n,... . . . , , , . . . _ . . .,y-., .y m ,w,. s. , w ..,-.y,.v---..-,,,, ,mw.,
s , t 4 i 3/4.11 RADICACTIVE EFFLUENTS
# l 3/4.11.1 L10V!D [FFLUENTS !
NC(NTRATION
\ :
LIMITING CON 0! TION FOR OPERATION / k 3.11.1.1 h concentration of radioactive material releas in liquid effluents toUNAESTRICT50 AREA $(seeFigure5.1-1)shallbelimiteddotheconcentrations specified in 10sCFR Part 20, Appendix 8, Table !!, Co1M 2 for radionuclides ! otherthandissolgdorentrainednoblegases. For di(solved j or entrained ; noble gases the cdecentration shall be Ilmited to I x 10
- microcurie /m1 totalactivIty. N e I
APPLICA8!LITY: At al fees. 6 ACTION: .
- a. With the concentration ofsradioac ive matarial released tr. liquid ef fluents i to UNRESTRICTED AREAS exceeding'the above .1mits. im== M ataly e*9 Met tr4 ;
concentration to within the' Wove limits. .
- b. The provisions of Specif ca/ tions\ 3.0.3 and 3.0.4 are not applicable. ?
50RVf!LLANCE REQU!REMENTS r
/ \ :
4.11.1.1.1 Radienctive liquid wastes shall be sampled and analyzed according to the sampling'and analysis program of Table 4.14-1. l 4.11.1.1.2 ,'T e results of the radioactivity onely shalt be used in accord-ancewitMbemethodologyandparametersinthe00CMtoassurethatthecon- ! centrations at the point of release are maintained with n the limits of Specification 3.11'.1.1. i l [ I I y
'9 ,
i t
,BRAIDWOOD - UNITS 1 & 2 3/4 11-1 ;
F
..;. ...,,.3, * , . . . . . . . .. . , . . . !
i TABl[ 4.11 1 RA010ACTIVt LIQUID WA51t SAMPLING AND ANALY515 PROGRAM [0WERLIMli Of DillC110N MINIMUM LIQUID RELCA5{ SAMPLING ANALY515 1YPE Of AC11VITY (LLD)II) 1YPE 'N FRl0VENCY FREQUENCY ANALYS15 (pti/ml)
- 1. Batch Release
\PEach Batch P
[ach Batch
/
4amma 5 10
~7 I2) Principal,3) 1an6S \ [ mitier,[
N\ l1) 1:30
.e P
\
One Batch /M N M D(asolvedan.1
'!ntrained Gases 1 x 10'
N / (Gamn.J [mitters) P / H3 1m10 ' Compos)4v I4)
~
[ach Batch ,7 A Gross Alpha 1s10 P , Sr 89, Sr 90 5:10'8 Each Batch Composite ( \
/ -6 Fe-55 1x10
~2
- 2. Continuous V M incipal Gamma 5:10
- 6) Composite (6) p,),,,,,(5) Continuo ( ,,,(3) 1x10
- a. Cireviating 1-131 \
Water 3 Blowdown M M Dissolve and 1x10 r Entrained ases
- b. Was ' Water
[ ab Sample ( amma M ns) Treatn.ent -5 Discharge o M g) H-3 1:10 Circula g Continuous (6) Composite Watn scharge Gross Alpha 1:10-7 C. Con sate s Po her Sump 3 0' chargt 0 Sr-89, Sr ~40 5 0 Continuous (6) Composite (6) Fe 55 ini l BRAIDWOOD - UHlT51 & 2
,Ad 3/4 11-2 Amendment No. 6
\
l
i
\
l TA8LE 4.11 1 (Continued) RADICACTIVE LIQUID WASTE SAMPLING AND ANALYS!$ PROGRAM'
/
LIQUID LEASE SAMPL!NG MINIMUM ANALYS:$
/
TYM 0F ACTIVITY LOWER LIMIT 0F DETECTION (LLD)(1) TYPE FREQUENCY FREQUENCY , ANALYSIS (pC1/al)
- 3. Continuous Wil) WC7) Principal Gamma 5:10 7 Release (5) Grab Sample faitters(3)
Essential Service Water Reactor / Containment Fan ' Cooler (RCFC) outlet Line
Sx/ ,
j N
/' \ 1 131 1x10 8
/
\N Olssolved and
/ .. .
. \ .. Entrained (Camma. Emitters)Gases- 1x10 *
/ kJ 1x10 6 4
6 4
#kt' BRAIDWOOD - UNITS 1 & 2 3/4 11-3
- -.m - . .._.- _
-.. , ._-.,,,,.s . _ , . , . , _
-.c ,m.
\
( TABLE 4.11 1 (Continued) TABLE NOTAT!0NS (1) e LLO is defined, for purposes of these specifications as t smallest consentrationofradicactivematerialinasamplethatwIllyieldanet courn above system background, that will be detected with $s% probability with ly 5% probability of falsely concluding that a blan4' observation represe : a "real" signal. For a parti lar measurement system, which may include adfochemical separation: LLD = 4.66 :b E*V*2)2xlos,y,,,,(.x3g) Where: LLO = the lower limit f detection (microcuries per unit mass or volume), sb = the standard deviatio of the, background counting rate or of the counting rate of a blanb ampke as appropriate (counts per minute), , E = the counting efficiency (cou ts per disintegration), , V = the sample size (units of mass r volume), 2.22 x 108 = the nuseer of disintegr ions per minute per microcurie, Y a the fractional radiochemical yield, when applicable. A a the radioactive decay constant for th particular radionuclide (sec 8), and /
. At a the elapsed / time between the midpoint o sample collection and the time of counting (sec).
Typical lues of E. V, Y, and at should be use in the calculation. It should recognized that the LLO is defined as a b fore the fact limit represent /ngthecapabilityofameasurementsystemand,otasanafterthe fact li it for a particular measurement. (2) A baJth release is the discharge of Ilquid wastes of a dis ete volume. Prj4rtosampilngforanalyses,eachbatchshallbeisolate and t en thoroughly mixed by a method described in the 00CM to a ure epresentative sampling.
+ ,
BRAIDWOOD - UNITS 1 & 2 3/4 11-4 t *
. _ _ . _ _ _ -.___~--___.._.._.___________m._..__._
s t i TApl[ 4,}}.} (Continued) 7A8tf NOTA 710Ns (Continued) (3) Th principal gamma eettters for which the RD specificati applies inct e the following radionuclides: Mn 54, Fe-59, Co*)M Co 60, 2n 65 Mo 99, s 134. Cs 137, Ce 141, and Ce 144 only the nuclides are to be considered. Other Thislistfoesnotmeanthat gasma peaks that are-identifiab , together with those of the above nue11 des shall also be analyzed and eportedintheSeelannualRadioactiveEffiventReleaseReport Pursuant to 50 ification 6.9.1.7 in the foros't outlined in Regulatory , Guide 1.21, Appe in S. Revision 1, June 1,974. '
/ '
(4) A composite sample i one in which tha 4uantity of liquid sampled is proportional to the qu tity of liquid waste discharged and in which the method of sampling emplo d results in a specimen that is representative of the liquids released. j i (5) A continuous release is the dis rge of liquid wastes of a nondiscrete volume, e.g. from a volume of a stes that has an input flow during the continuous re, lease. / (6) To be representativt of the quantities a concentrations of radioactive satorialsinlipideffluents,st.:pleaat.4%t,4c4.1heteccot.tinec,usly in proportion,to,the rate of flow of the offluen\ stream, Prior-to' analyses, all samples ,taken for the composite shall be th oughly mixed in order for the composite sample to be representative of effluent release. (7) Not re ed unless the Essential Service Water RCFC' let Radiation Monittsrs Rf PR002 and RE PR003 indicates measured levels rester than 1
/p'10*pCi/n1abovebackgroundatanytimeduringtheweK BRAIDWOOD - UNITS 1 & 2 3/4 11 5 l
l
I
- t. o 4
l RA010 ACTIVE EFFLUENTS t I
$E 11MI 4NG CONOTTION FOR OPERATION l 3.11.1.2 1 materials in ;
dose or dose commitment to a MEM8ER OF THE PUBLIC from radioactive quid effluents released, from each unit, to U #ESTRICTED AREAS
/
(see Figure 5.2 ) shall be Ilmited:
- a. During a calendar quarter to less than or ual to 1.5 arems to the whole dy and to less than or equal t - arems to any organ, and
- b. During any cale ar year to less than Ar equal to 3 arems to the whole body and to ess than or equal o 10 arems to any organ.
APPLICA8!!,fiY: At all tjoes, ACTION:
- a. With the calculated done the release of redies';tive materials
- in liquid effluents ex n any of the above ilmits, prepare and '
submit to the Commiss withi tion 6.9.2,aSpec14I)Reportthe30 days, pursuant to Specifica-identifies the cause(s) for exceeding the limit (s)*and defines he corrective actions that have
, been taken to re ce the releases an' the proposed corrective actions to be taken to ssure that subsequent eleases will be in compliance with the abo limits.
- b. The provi ions of Specifications 3.0.3 and 0.4 are not applicable.
$U,RVr!LLANCE/ EQUIREMENTS <
4.11. Cumulative dose contributions from liquid effluents for he current cale r quarter and the current calendar year shall be determined accordance wi the methodology and parameters in the 00CM at least once per 31 s.
/
BRAIDWOOD.- UNITS 1 & 2 3/4 11-6 l
- l. . . _ _ _ - . _ _ , . = - - - - - - . - - , - - . ~ - - - - - - - - - - - - - -' -- ~' '- ' ' ~ ~ ' - ~ ~
. =
RADI0 ACTIVE EFFLUENTS L_ U!D RADWA$7E TREATNENT $YSTEM LIM xCOND1710N FOR OPERAff0N 3.11.1.3 The L uid Radweste Treatment System shall be OPERA 8 4 and appropriate portions of the
/
the projected dos tem due shall be used to reduce releases of radioactivity when to the liquid effluent, from each unft, to UNRESTRICTED AREAS (see Figure 5. 1) would exceed 0.06 ores to the whole body or 0.2 ares to any organ In a 31- period.
/
APPLICA81LITY: At all t s. /
/
ACTION: .
- a. With radioactive 114 dwastebeingd)schargedwithouttreatmentand in excess of the above limits and aqf portion of the Liquid Radwaste Treatment System not in eration.,$repare and submit to the Commission within 30 days pursuant to Specification 6.9.2, a Special Report that ir.cludes the f lusifeg iniut e lun; f......
- 1. Explanation of why liqui redwaste was being discharged without treatment, identifica_ tion f any inoperable equipment or subsystems, and the /eason or the inoperability,
- 2. Action (s) taken
- restore th inoperable equipment to OPERABLE status, and
- 3. Summary desc/iption of action (s) aken to prevent a recurrence,
- b. The provision f Specifications 3.0.3 a 3.0.4 are not applicable.
SURVE!LLANCE RE001 EMENTS 4.11.1.3.1 ,Soses due to liquid releases from each unit to NRESTRICTED AREAS Shall be pr'ojected at least once per 31 days in accordance w th the mechodology and parapeters in the 00CM when the Liquid Radwaste Treatment ystem is not being 11y utilized. 4.M.1.3.2 The installed Liquid Radwaste Treatment System shall considered pRABLEbymeetingspecifications3.11.1.1and3.11.1.2. J 8RAIDWOOD - UNITS 1 & 2 3/4 11-7
.h g 0
.' I '
g ( i k r
, o
\ i I
3 /4.11 RADICACTIVE EFFLUENTS 1 4, l LIQUID HOLDOP TANKS ' 4 LIMITING CONDITION FOR OPERATION i 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved ! er entrained noble gases, contained in any outside tanks shall be limited to the following: .
- a. Primary Water Storage tank i 2000 Curies, and
- b. Outs'de Temporary Tank i 10 Curies.
APPLICA$fLITY: At all times. ACY10N:
- a. With the quantity of radioactive saterial in any of the above. listed :
tanks exceeding the above limit immediately suspend all additions-of radioactive material to the tank, eithin 44 howe's , educe tiew Look contents to-within the+11mit, and describe the events-leading to - this condition in the next sentapoual Radioactiv Q ffluent Release Report, pursuant to Specification 6.9.1.7.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
1 i _SURVE!LLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive saterial contained in each of the above ' tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. 0 l. BRA 10wo00 - UNITS 1 & 2 3/411-[I e.* 4 4 e se s 8 8 *
- e
.._-..r . _ _ . . . . ...,m_.. ,,_r,,,. ,_ ,,. ,,,._,.g-..... . . - _ . - . . . _ , , _ , , _ _ . , - ~ . -
o +
\
i
. l I
RADI0 ACTIVE EFFLUENTS I 1 3/4.11.2 CASE 005 EFFLUENTS 005E RATE j f i L TING CONDIT!0N FOR OPERATION l I 3.11.2.1 Th dose rate due to radioactive materials released i. gaseous effluents-fr e-site to areas at and beyond the $1TE SOUN RY (see ! Figure 5.1 1) : be limited to the following:
- a. For noble ses: Less than or equal to 500 sp es/yr to the whole ;
body and I than or equal to 3000 arems/ 'to the skin, and l
- b. For !odine 131 d 133, for tritium, and or a11 radionuclides in !
particulate form th half lives greatep than 8 days: Less than ! or equal to 1600 nr s/yr to any orgon. ! APPLICABILITf; f.t all times. ACTION e
~~
- a. With the dose rate (s) exceedihq the above limits, immediately restort ,
the release rate to with in the bove limit (s). l
- b. The provisions of Spec fications 0.3 and 3.0.4 are not applicable.
/ i SURVE!LLANCE REQUIREMENT _$
4.11.2.1.1 The do ate due to noble gases in gaseo ffluents shall be ; determined to be ithin the above limits in accordance wi the methodology i andparameters/ the 00CM. 4.11.2.1.2ffhedoserateduetolodine-131and133, tritium, d all radio- I , nuclides A particulate form with half-lives greater than 8 days in gaseous ; i ef fluen shall be determined to be within the above linits in ac rdance with r l the me,t odology and parameters in the 00CM by obtaining representat e samples l and p6rforming analyses in accordance with the sampling and analysis ogram , sp ified in Table 4.11-2. i 36 BRAIDWOOD - UNITS 1 & 2 3/4 11-9 ! l
., a s.,,,, .; .,,+....e- ,s. * '
, * =* *
.. . ?>
b
. 2
= TAttE 4.11-2 b
!\
RACIDACTIVE GASEl*JS WASTE SAMPLIN3 AND ANALYSIS PROGRAM MINIMUM : OWER LIMIT OF SAMPLING ANALYSIS TYPE OF E GASE0US REL ASE TYPE FREQUENCY DETECTION (LLD)III FREQUENCY ACTIVITY ANALYSIS (pCl/el) '
- 1. Vaste Gas Dec Each Tank Each Tank FrIncipal Gamma E 3,3g -4 I *'
Tank s(2) Grab Sample -
- 2. Containment Purge PURGE I3) I3) ~
Each PURGE al Gahna Eeltters(2) Ix10 " Grab Sample Frtncip /
\ d-/ 1x10'#
l 3. Auxillary Bldg M(4)(5) rincipal Gamma EulttersIII 1x10'" l
,' Vent Stack Crab Sampie M t* (Units 1 and 2) _ H-3 1x10
-2 Continuous (6) g(7 ' I-131 1x10 -12 i h; ' Charcoal Sample 51131 -10 1x10 l .
M Continuous (6 V y(7) PrincipalGammaEmitters(2) 1x10'II l
~ 1 'tinuous(6) l*M"'
M
. Gross Alpha
\ 1x10'II j , Cosposite i
Particulate Sample' N
~
Continuous (6) Q Sr-89, Sr-90 1x10"II Composite Particulate Sample Continuous Noble Gas Monitor -6 I Noble Cases Gross Beta or 1x10 Gamma l
s JABLE4.11-2(Continued) TABLE NOTATIONS p/ The LLD is defined, for purposes of these specifications, as the smallest oncentration of radioactive material in a sample that wil ield a net c wit nt,only above5%system background, probability of falselythat will be detected concluding that a blanwit)k observation 5% probability repre nts a "real" signal, For a par cular measurement system, which may include radiochemical separation: 4.66 : D LLD = Ea V- 22 x 108
- Y exp (-AAf)
Where: LLD = the Icwer limit f detectiph (microcuries per unit mass or volume), sb = the standard deviation the background counting rate or of the counting rate of a bisok s pie as appropriate (counts per
~
minute), - E = the counting effic ency (counts er disintegration), V = the sample size /(units of mass orlume), 2.22 x 10' = the/ number of disintegration per minute per microcurie, Y = the fr:ctfonal radiochemical yield, when plicable, A a the ra oactive decay constant for the part ular radionuclide (sec 1) /and atadheelapsedtimebetweenthemidpointofsample ollection and the/ time of counting (sec). ypical values of E, V, Y, and at should be used in the 1culation. It/should be recognized that the LLD is defined as a before the et limit f 4presenting the capability of a measurement system and not as an fter the fact limit for a particular measurement.
/
/
T # . BRAIDWOOD - UNITS 1 & 2. 3/4 11-11 1
. ,g. ...,.. .. . *. * = * *.
3- ,
\
TA8LE 4.11 2 (Continued) . TABLE NOTATIONS (Continued) ; 4 (2)T rincipal gamma esitters for which the LLO specification ap i es 1 inc1 the following radionuclides: Kr-87 Kr-88 Xe-133, 1 Xe133e,Xe135,andXeIS8innoblegasreleasesa,ndMn54 .e-59, Co 58, Co , Ze65 Mo-99, !*131, Cs 134. Cs 137, Ce 141, nd Ce 144 in iodine and ticulate releases. This list does not se that only these 1 nuclides are t be considered. Other gamma peaks that e identifiable, together with t e of the above nuclides, shall als9 e analyzed and reported in the $ annual Radioactive Effluent Release Report pursuant to Specification 6.9. 7, in the format outlined fi Regulatory Guide 1.21, Appendix 8. Revision 1, June 1974 (3) Sampling and analysis shal also be performed following shutdown, startup, or a THERMAL POWER change en eding 15% of TED THERMAL POWER within a 1 hour perled. (4) Tritive grab samples shall be take 4t least once por 24 hours when the refueling canal is flooded. (5) Tritium grab samples shall be t en at ast once per 7 days from the spent fn*1 paal area, wheeeve spent fuu. h in th sp:nt fuel p::1. , (6) The' ratio of the sample f)4w rate to the s led stream flow rate sh'all
- be'*1 mown for the~ time se or dose rate calculation made in accordance 5pecifications wl)#pov'iod covered by each and 3.11.2.3.
3.11.2.1, 3.11.2.2, (7) Samples-shall be cManged at 1,ast once per 7 days d analyses shall be completed withi/48 hours af ter changing, or af ter r oval from sampler. Sampling shal'/also be performed at least once per 24 urs for at least 7 days followi ng each shutdown, startup or THERMAL POWE change exceeding 15% of RATIO THERMAL POWER within a 1 hour period and ana ses shall be complete #'within 48 hours of changing. When samples collec ed for 24 hrurs are an fyzed, the corresponding-LLDs may be increased by a.f tor of 10. This cuirement does not apply if: (1) analysis shows that t DOSE EQU2 ALENT I 131 concentration in the reactor coolant has not i reased mefe than a factor of 3, and (2) the noble gas monitor shows that ffluent etivity has not increased more than a factor of 3.
.A I
8RAIDWOOD - UNITS 1 & 2 3/4 11 12
,g . e ee * * * '
, . .. . . . . \. . .........4 . . . . . . . . . , , .-
4 i l _., RA010ACTTVE EFFLUENT $
$f a N08tf GA$ES l N
LIMIT!E CON 0! TION FOR OPERATION 3.11.2.2 T air dose due to noble gases released in gas us effluents, from each unit, to 4reas at and beyond the $1TE BOUNDARY (se figure $.1 1) shall be limited to the following:
- a. During a calendar quarter: Less than equal to $ erads for gamma rad etion and less than or equal 10 mrads for beta radiation, and
- b. During any calen,dar year: Less th or equal to 10 mrads for gamma radiation and less than or equal o 20 mrads for beta radiation.
APPLICA8ILITY: At all times. ACTION:
- a. With the calculated air ese from radioactive noble gases in gaseous effluents exceeding an of'the above limits, prepare and submit to pursuant to Specification 6.9.2. a the Consission
$pecial Report that withi 30 days,'Nthe cause(s) for exceeding the dentifies and defines the c rective actibqs that have been taken to reduce the releases and he proposed corPactive actions to be taken to assure that su equent releases will be in compliance with the above limits. \
- b. The provis ons of Specifications3 and 3.0.\3.0.4 are not applicable.
$URVE!LLANCE/ EQUIREMENTS
/-
4.11.2.2 Cumulative dose contributions for the current calend quarter and current' calendar year for noble gases shall be determined in ac rdance with the 'thodology and parameters in the 00CM at least once per 31 d s. I BRAIDWOOD + UNITS 1 & 2 3/4 11 13
-r , , , ., , ~ ve v e- , w ,.. -- . - -
1 t t
.g ,
I RA010ACT!vt EFFLUENTS
=
00$E !
!00!NE-131 AND 133. TRIT!UM AND RA0!0ACT!vE MATERIAL !N PARTICULATE, FORM i
LIM NG CON 0! TION FOR OPERATION / ,
-[
3.11.2.3 1 dose to a MEMBER OF THE PUBLIC free lodine 131 and 33, tritium, I i and all redien Ildes in particulate form with half lives great 4r than 8 days in gaseous eff1 [ ts released, from each unit, to areas at and'beyond the SITE a 800M0ARY (see Figu l.1 1) shall be limited to the followi,mg:
/ l a.- During any c endar quarter: Less than or equa'l to 7.5 arems to any t
ergan, and [
- b. During any calen at years Less than or equal to 15 areas to any organ. N -t
}
t APPLICA8!LITY: At all times.
}
ACTION:
- a. - With the calculated dose f Ahe release of lodine 131 and 133 !
tritium,'anJr*dionuclidesJ. articulate form with half-lives greater than 8 days,ain paseou effluents exceeding any of the above ! limits, prepare and suba' t to t Commission within 30 days. pursuant toSpecification6.9.2/aSpecial eport that identifies the.cause(s) i for exceeding the liaits and defin - the corrective actions that have ' l been taken to reduct ,the releases an the proposed corrective actions ! to be taken to assu're that subsequent eleaser will be in compliance : with the-above its.
- b. The provisions of Specifications 3.0.3 an 3.0.4 are not applicable. f u
/- i SURVEILLANCE REQUIREMENTS
/ j 4.11.2.3 umulative d'ose contributions for the current calenda quarter and current alendar year for Iodine 131 and 133, tritium and radion lides in [
parti late form with half-lives greater than 8 days shall be dote ned in i acc dance with the methodology and parameters-in the 00CM at least o e per l 3 days, i t h anAltM000 - UNITS 1 & 2 e 3/4 11 14 ! i f
, . . . . , _ . . - . . . _ . , . - . , , . . , . . . . . - . _ . _ . . _ _ - . _ _ . _ . _ -.-..,._..____-._..,__..__.._______.____a--_.+.
_ . - - - . - - - - - - _ _ _ . ~ . - - . - - . -
. +
s s i RADICACTIVE EFFLUENTS SE005 RA0 WASTE TREATMENT SYSTEM L CON 0!T10N FOR OPERATION 3.11.2.4
$YSTEM Theb sha11 VENTILATION EXHAUST TREATMENT SYSTEM and the WAS
/
PERA8LE and appropriate portions of these sysths shall be used to reduce due to gaseous of eases of radioactivity when the projected dpfes in 31 days uent releases, from each unit, to arens 41 and beyond the
$1TE SOUNDARY (see igure 5.1 1) would exceed:
- a. 0.2 arad to ir from gamma radiation, or
/
- b. 0.4 erad to al from beta radiation, or
- c. 0.3 orem to any o an of a MEMBER OF TH PUBLIC.
APPLICABILITY: At all times. ACTION. a.' With radioactive gaseous aste/ eing discharged without treatment andinexcessoftheaboveIJ4its,prepareandsubmittothe Commission within 30 days, ursuant to Specification 6.2.2, a
$pecial Report that inci s he following information:
- 1. Identification of ny inop rable equipment or subsystems, and the reason for t 'e inoperabl ity,
- 2. Action (s) tak to restore ths inoperable equipment to OPERABLE status, and
- 3. Summary scription of action (s) ken to prevent a recurrence,
- p. The provisi ns of Specifications 3.0.3 ano 3.0.4 are not applicable.
~
SURVEILLANCE RE tREMENTS s 4.11.2.4.1 Doses due to gaseous releases from each unit to a as at and beyond th $1TE SOUNDARY shall be projected at least once per days in accorda e with the methodology and parameters in the 00CM when eous Radwas Treatment Systems are not being fully utilized. } 4.1}[2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GAS WAS l HOLUUP SYSTEM shall be considered OPERABLE by meeting Specification 3.11. 1 l d 3.11.2.2 or 3.11.2.3.
/
BRAIDWOOD - UNITS 1 & 2 3/4 11 15
- - , . . ~ , . . . - , ~.-. ,,, - , ,,,n. , - . , . . .,.~.,.n.. ,. , . ~ . - - - . . . . . , , - . . . , . - .
\
\
t AA0!0 ACTIVE EFFLUENTS i EXPL0$!VE CAS MIXTURE LIMITING CONDITION FOR OPERATION l i 3.11.2.5 The concentration of oxygen in the WASTE CAS HOLDUP SYSTEM shall be , lietted to less than or equal to 21 by volume whenever the hydrogen concentration ; exceeds 4% by volume. i APPLICA8!LITY: At all times. ACTION:
- a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume but less than or equal to 4% by volume, }
reduce the oxygen concentration to the above limits within 48 hours. !
- b. With the concentration of oxygen in the WA$7E GAS HOLDUP $YSTEM greater than 4% by volume and the hydrogen concentration greater i than 4% by volume, im414tely suspend all additions of waste cases :
to the system and reduce the concentration of oxygen to less than or ; equal to.4% by~volumei then take ACT!0N a. above, r
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not app 1tcable. I t
$URVE!LLANCE REQUIREMENTS i
4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP b SYSTEM shall be determined to be within the above limits by continuously sonitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen { and oxygen monitors required OPERABLE by Table 3.3 13 of Specification 3.3.3.10. : l L i 8RAIDWOOD UNITS 1 & 2 3/411-)I S. f _ --- _ , _ . - . , , . , _ _ . ~ ~ . . _ . _ _ _ . _ , . _ . _ , - . __ _ . _ , _ - . , _ . _ - . . _ - - . . . _ _ _ _ _ ,
, A l l l RADIDACTIVE EFFLUENTS i GAS DECAY TANK $ LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x10* Curies of noble gases (considered as Xe 133 equivalent). ' APPLICABILITY: At all times, ACTION:
- a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours, reduce the tank contents to within the limit, and describe.the events leading to this condition in the r.ert Semiannusi Radioactive Effluent Avlvene Evpurt, purs.uen( Ls.5peqili4stion 6.i.l.7.
- b. The provisions of $pecifications 3.0,3 and 3.0.4 are not applicable.
$URVE!LLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank.
O BRAIDWOOD - UNITS 1 & 2 3/4ll-17h,
+
\
RADICACTIVE EFFLUENTS r i . 3/4.11.3 SOLIO RA0!0 ACTIVE WASTES . L IT!W1 CON 0!T!0N FOR OPERATION _ 3.11.3 adioactive wastes shall be solidified or dewatered in Accordpice with the PROC )tements during tra CONTROLit, and disposal PROGMM to meetwhen site requirements shippingreceived andattransportation th reau: tite. l APPLICA8!LITY: At all times. ACTION:
- a. CATION or dewatering not meeting disposal site and WithSOLIDI{hansportationrequirements,suspendshipmentofthe shipping and ;
inadequately processed wastes and correct th,' PROCESS CONTROL PROGRAM,
- the procedures ah/or the solid waste system' as necessary to prevent i recurrence.
b.
\
WithSOLIO!FICATIONhrdewateringnotpe/ rformed in accordance with ; the PROCESS CONTROL PRQGRAM, test the, improperly processed waste in i each container to ensurg that it meets burial ground and shipping '; requirements and ::ke :;p cprista 461nistr:tive actis te ;.r6.unt recurrence.
, c. The provisions of Specificat n 3.0.3 and 3.0.4 are not applicable.
SURVE!LLANCE REC'J!REMENTS * - 4.11.3 SOLIDIFICATION of at least p repr antative test specimen from at leasteverytenthbatchofeachtypeofwetrhioactivewastes(e.g., filter , sludges, spent resins, evaporator bottoms, borig acid solutions and sodium sulfate solutions) shall be ver,(fled in accordan with the PROCESS CONTROL PROGRAM: !
- a. If any test specime/n fails to verify 50L !FICATION, the SOLIDIFICATIO !
ofthebatchundpftestshallbesuspende(o)untilsuchtim test specimens gan be obtained, alternativ SOLIO!FICATION parameters i can be determined in accordance with the PR ESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. 50LMIFICATIONofthebatch r say then be/ resumed using the alterr.ative SOLID FICATION parameters determine 'by tt.e PROCESS CONTROL PROGRAM;
- b. If the ) itial test specimen from a batch of waste falls to verify L 50L10!PICATION, the PROCESS CONTROL PROGRAM shall p vide for the collpdtion and testing of representative test specime from each ,
consecutive batch of ttut same type of wet waste until least 3 codsecutive initial test specimens demonstrate 50L10!FIC 10N. The l ! P40 CESS CONTROL PROGRAM shall be modified as required, as ovided i n Specification 6.13, to assure SOLIDIFICATION of subsequen batches
- l of waste; and j With the installed equipment incapable of meeting Specification 11.3 or declared out of-service, restore the equipment to operable sta s or provide for contract capability to process wastes as necessary '
satisfy all applicable transportation and disposal requirements, t 8RAIDWOOD - UNITS 1 & 2 3/4 11-18 w[. , . f
- - , . . . - - - - - , . , - , , . . . . , - . . , . . . + + - - - - - -
\
\
RA010 ACTIVE EFFLUENT $ 3/4.11.4 TOTAL 00$E L ITING CONDITION FOR OPERATION 3.11.4 he annual (calendar year) dose or dose commitment to any MEMBER F THE PUBL cycle sou due to releases of radioactivity and to radiation from uranJ6m fuel body or any shallbelimitedtolessthanorequalto2$eremsto}Mewhole an, except the thyroid, which shall be limited to less than or equal to 75 mr s. APPLICA8tl!TY: A all times. ACTION:
- a. With the ca (ulated doses from the release of rap cactive materials in liquid or baseous effluents exceeding twice Ahe limits of Specification ) 1.1.2a., 3.11.1.2b., 3.11.2.26., 3.11.2.2b.,
3.11.2.34., or 1.2.3b., calculations shoyId be made including direct radiation gntributions from the un)ts and from outside storage tanks to determine other the above linjts of Specification 3.11.4 have been exceeded, f such is the case, creparo and cubmit to the Commission within 30 d Report that defines the s,orrective pursuant acttp' ion to be taken to reduce sub-5p sequent releases to preve recurrp6ce of exceeding the above Ilmits -" and includes the schedule acpfevingconformancewiththeabove limits. This special Report a includeananalysisthatestksdefinedin10CFR20.40$c,shall es the radiation exposure (dose) to a MEMBER OF THE PUBLic from urpnt fuel cycle sources, including all ' effluent pathways and direyt radi ion, for the calendar year that includes the release (s) esvered by is report. It shall also describe levels of radip(ton and con ntrations of radioactive material involved, an4/the cause of th exposure levels or concen-trations. If the esj,imated dose (s) exc ds the above limits, and if the release con 4ftfon resulting in vio tion of 40 CFR Part 190 has not already be6n corrected, the Specia Report shell include a requestforavfianceinaccordancewithth provisions of 40 CFR Part 190. Submittal of the report is nsidered a timely request, and variance is granted until staff tion on the request is complete
- b. The provi ions of Specifications 3.0.3 and 3.0.4 a not applicable.
l SURVEILLANCE REQ EMENTS 4.11.4.1 Cu ative dose contributions from liquid and gaseous of uents i shall be d termined in accordance with Specifications 4.11.1.2, 4.11 .2, and ; 4.11.2.3 and in accordance with the methodology and parameters in th 00CM. 4.11.$.2 Cumulative dose contributions from direct radiation from the u its y and rom radwaste storage tanks shall be determined in accordance with th ' me odology and parameters in the 00CM. This requirement is applicable on er conditions set forth in ACTION a. of Specification 3.11.4. ! SRAIDWOOD
- UNITS 1 & 2 3/4 11-19 [
s 3/4.12 RADIOLOGICAL ENVIRONMENTAL MON!TORING
\
/4.12.1 W)NITORING PROG' TAM L T!NG CON 0! TION FOR OPERAT!0N 3.12.1 e Radiological Environmental Honitoring Program shall be/tonducted /
as specift in Table 3.12'-1. APPLICABILITY: At all times. ACTION:
- 4. With the R iological Environmental Monitor Wg Program not being conducted as pecified in Table 3.12-1, prH are I and submit to the Commission, i eAnnualRadiologicalEpironmentalOperating Report require reasons for not ySpecification6.9.1.f.adescriptionofthe nducting the progra as required and'the plans for preventing a recur nee,
- b. With the level of rad an environmental sampi medius ctivity 'at .athe result oflocation specified plant effluents in exceeding the reporting levels of leg.12-2whenaveragedoveranycalendar quarter, prepare and su!::: jtt the Co=1::icn withit. 3; c.t.ja, pursuant-to5pecification') 72, a Special Report'that identifies the cause(s) for exceedin ( limit (s) and defines the corrective actions to be taken to re) duce N dioactive effluents so that th a
potential annual dose jio a MEM8 R OF THE PUBLIC is less than the calendar year limits,4f Specifica ong 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of t radionuclides in Table 3.12-2 are detected in thf sampling medium, this report shall be submitted if: concentration (1) , concente . tion (2) report hg level (1) reporting i el (2) + **'>- 1.0 When rap onuclides other than those in Table .12-2 are detected and are the' result of plant effluents, this report hall be submitted if the % tential annual dose" to A MEMBER OF THE P LIC from all radio-nuqTides is equal to or greater than the calendar ear limits of
, Sp6cifications 3.11.1.2, 3.11.2.2, or 3.11.2.3. Tit s report is not equired if the measured level of radioactivity was et the result of plant effluents; however, in such an event, the condi on shall be reported and described in the Annual Radiological Envir naental Operating Report required by $pecification 6.9.1.6.
"The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
BRA!DWOOD - UNITS 1 & 2 3/4 12-1 V M{ / l l A
\
I 4 I { WLOGICAL ENV!RONMENTAL MON!TORING >
! TING CONDITION FOR OPERATION
/
ACTIOW(Continued) ,
- c. th allk or fresh leafy vegetable samples unav34 able from one or no !
of the sample locations required by Tab e'3.12 1, identify I spec}1iclocationsforobtainingreplaceae samples and add thent within days to the Radiological Envif ntal Monitoring Program ' given in e 00CM. The specific loc tions from which samples were unavailable y then be deleted f the monitoring program. $ubmit controlled ve ion of the 00CM y4 hin 180 days including a revised figure (s) and ta ;e reflecti the new location (s) with supporting information ident ause of the unavailability of samples andjustifyingthe%ingth se oc 4 n of the new location (s) for obtaining samples,
- d. The provisions of pecificat3 ns 3.0.3 and 3.0.4 are not appilcable. !
$URVE!LLANCE REQUIRE 75 4.12.1 The ~pStological environmental monitoring sampT shall be collected pursuant tVTable 3.12*1 from the specific locations given a the table ard !
figure (y)'in the 00CM. and shall be analyzed pursuant to the quirements of ; Tabl .12-1 and the detection capabilities required by Table . 1. d i i y b i I 8RAIDWOOD - UNITS 1 & 2 3/4 12-2 : l
- . _ , - . _ _ . _ . - _ _ m ,.
i 3 TABLE 3.12-1 . RADIOLOGICAL ENVIR00st[NTAL Mh !TORING PROGRAM sameER OF
- REPRESENTATIVE U P05URE ATHWAY 5AMPLES AND SAMPLING AND E AND/0R SAMPLE YPE AND FREQUDICY SAMPLE LOCATIONSI3I COLLECTION FREQUDICY OF ANALYSIS -
4
- N
- 1. Direct Radiation (2) Forty routine monitoring stations Quarterly. -
" Casuna dose quarterly.
- either with two or mere desleeters
" or with one instrument for seasur-ing and recording dose rate ntinuously, placed as follows:
An\ inner ring of stations, one in each meteorological sector in the general area of the SITE 80UND ; w
} An outer ring \afsstations[, one in y each seteorologicais socier in 7 the 6- to 8-km range' free the g site; and
'N The bala of the station d to be p ced in special 7 k inte st areas such as popu \
1 tTon centers, nearby estdences, schools, ar.d in s\ N one or two areas to serve as control stations. ' '\ 4
^
I e TABLE 3.12-1 (Continued) l RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM E nunsEt Or k o SURE PATHWAY REPRESENTATIVE E 5AMPLES AND SAMPLE LOCATIONSgg) SEM M W m m quE
. OR SAMPLE C0ttECTION FREQUENQ OF ANALYSIS E 2. Airbo --
U Radiolodi and Samples free five locations: Continuous sampler Radiofod Cannister- ' l w Particulate operation with sample I-13 .alysis weekly. e- Three samples free close to collection weekly, or
- = the three SITE SOUNDARY loca- more frequently if tions, la different sectors, required by dust articulate Sampler
o the highest' calculated loading. Gross beta radioactivity i a average ground level D/Q; w analysisfollog filter change; and 1 One saapi ros the vicinity of ganea isotopic analysis (4 ' ) ; g a community ing the highest of composite (by location) calculated annua average ground- quarterly. i 1evel D/Q; and -1 f One sample from a contr . l location, as for example to 30 km distant and in the least prevalent wind direction. { p 3. Waterborne } Qh a. Surface I ). One sag le upstre . Ocepos e sample ever C=== isotopic analysis III j 7 One sample ream. 1 month pir.fod by monthly. Composite for j . veekly grab lamples. trittur. analysis quarterly. Gamma isotopic N and tritium I b. Ground Sample rom one or two sourc Quarterly. ont f likely to be affected , analysis quarterly
- c. Drinking sample of each community l Composite sample g) I 1 analysis on each drinking water supply within over 2 week peried compo te when the dose .
10 elles downstreas of the .when I-131 analysis calculat for the consusp-discharge. .is performed, sonthly Lion of the er is greater composite otherwise. than 1 eres per ar. (8) Com-posite for gross be One sample from a controi ; ganea isotopic analyses ) location. monthly. Composite for tritiese analysis nesarteriv. *
. - .,, - .,-. - . - - - . . - , - - - - - - - - . - - ~ ~ - - - - - ------- - - --- - ~~ - ~ ' ~ ~ - ~ - ~ ~ -- '
TABLE 3.12-1 (Continued) h . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM o NUMBER OF h o REPRESENTATIVE EXPOS PATHWAY SAMPLES AND SAMPLING AND AND/OR .PLE g) TYPE AND F QUENCY SAMPLE LOCATIONS C0ttECTION FREQUENCY CF SIS g 3. Waterborce d.Sedimenb(Cor.tinued) 3 One sample from downstream area Semiannually. G a Isotopic analysis N - y from N with existing or potential - lannually.
,, shoreline Nrecreational value. ,
** 4. Ingestion
- a. Milk Sampleqfrommilkinganimals 5 mimonthly when Gamma isotopic and I-131 in three locations within ailmals are on analysis scelmonthly when 5 km dista' having the highest p'esture, month y at animals are on pasture; dose potentia . If there are other time / monthly at other times.
none, then, one emple free allking 1:a a animals in each of b ree areas between 5 to 8 km distant g where doses are calculated be 4 greater than 1 area per yr One sample free allking anima at a control location, 15 to distant and in the least pre (alent wind direction. hm b. Fish and Inverte-Representative sample of commercially and re eationally T%ree ines per year (;pring.hr and Gamma isotopic analysis on edible portions. P brates important species /In vicinity 4D of plant disc ge area. f.s i l ). 7@ Representa ve samples of N ' commercis ly and recreationally impor Ist species in areas not in enced by plant discharge.
- c. Food epresentative samples of the At time of harvest. Gamma i atopic analyses N Products principal classes of food products on edible 'hertion.
from any area within 10 miles of the plant that is irrigated by - water in which liquid plant wastes have been discharged.
k l ! ~,
- i TAttE 3.12-1 (Continued) I E
RADIOLOGICAL ENVIR0000 ENTAL MONITORING PROGRAM NUMBER OF itEPRESENTATIVE : EXPOSURE PAT SAMPLES AND SAMPLING AND AND/OR SAMPLE TYPE FilEquENCY [ $ AMPLE LOCATIONSIII
- COLLECTION FREQUENCY ANALYSIS
$ 4. Ingestfo:(Continued)
- c. Food Samples of t different kinds I 'I and I-131 i Monthly when Gamme isotopic
- s. Products of broad leaf we'getatfon grown i ee (continued)
. available. analysis.
nearest each of two different ; effsite locations of highi q predicted annual average gi;_n_- i level D/Q ff alik sampling is not performed. ; One sample of each of siellar M:nthly when
% Gamme isotopicN and 1-131 broad leaf vegetatjan grown a.allable. analysis.
M 15 to 30 km di dat in the least ' j prevalent w direction if alik 4 E sampli d s not perfarmed. ! i { r i
# i
- e -
i i m- 1
\
t i I
\ -
l 2 l
\
f TABLE 3.12*1 (Continued) -
\
TABLE NOTATIONS ( Specific parameters of distance and direction sector from the cente ins f one unit, and additional description where pertinent, shall be ovid 3d f each and every sample location in Table 3.12-1 in a table a igure(s) in e 00CM. Refer to NUREGa0133, " Preparation of Radiologica ffluent Techn a1 Specifications for Nucle 4r Power Plants," October 1 , and to ' Radiol ical Assessment 8 ranch Technical Position, Revistun . November 1979. 1ations are permitted from the required samp1tng chedule if specimens re unobtainable due to hazardous conditions, asonal unavailabil ty, mal,' unction of automatic sampling equip nt and other legitimatethsons, If specimens are unobtainable du9 to sampling equip-ment selfuncti , every effort shall be made to comp tte corrective action prior to e end of the next sampling perio All deviations from the sampilng sch yle shall be documented in the nual Radiological Environmental Opera ing Report pursuant t2 Specification 6.9.1.6. It is recognited that, at mes, it may not be possiiple or practicable to continue to obtain sa es of the media of chpice at the most desired location or time. Inth{gseinstancessuitablespecificalternativemedia and locations may be chosbQ for the partic Tar pathway in question and appropriate substitutions stade within 30 ys in the Radiological , Environmental Monitoring Pro am given J the 00CM. Submit controlled , revisions of the CDCri witnin u days ncludfr.g a ra ised figure (s) ' and table reflecting the~new lo atto ) with supporting information identifying the cause of the una i bility of samples for that pathway and justifying the selection of t new location (s) for obtaining samples.
" (2) One or more instruments, such ap ssurized ion chamber, for measuring and recording dose rate conti vously y be used in place of, or in addition to, integrating d meters, gr the purposes of this table, a thermoluminescent dosimet (TLD) is conkidered to be one phosphor; two or more phosphors in a ket are conside d as two or more dosimeters. .
Flisbadgesshallnot/b used as dosimeters for measuring direct radiation. The 40 stations is no an absolute number. e number of direct radiation monitoring stations y be reduced according t geographical limitations; e.g., at an ocean te, some sectors will be ov water so that the number of dosimeters na e reduced accordingly. The fr uency of analysis or - readout for TLD ystems will depend upon the chara. eristics of the specific system used an should be selected to obtain optimum ose information with minimal fadi . (3) Airborne n rticulate sample filter: shall be analyzed for ross beta radio- , activity 24 hours or more after sampling to allow for radon nd thoron I daughte decay. If gross beta activity in air particulate sa les is great than 10 times the yearly mean of control samples, gamma isotopic anal sis shall be performed on the individual samples. (4) C a isotopic analysis means the identification and quantification f amma-emitting radionuclides that may be attributable to the effluent from the facility. BRAIDWOOD UNITS 1 & 2 3/4 12-7 Ap/ I t t i 4
,w--
4 s TA8LE 3.12-1 (Continued) TABLE NOTATIONS (Centinued) (5)The"ostreamsamole"shallbetakenatadistancebeyond):gnificant influe of the discharge. The " downstream" sample shal be taken in an area beyo but near the mixing zone. (6) A composite samp quot) of liquid sampled is proportional to is one in which the quantity (3) d in which the method quantityofflowingliqujean of sampling employed r Its in a specimen thpt is representative of the liquid flow. In this pro y composite sampie aliquots shall be collected 6t time intervals that are ven short (eg , hourly) relative to the com-positing period (e.g., monthly) ordet' to assure obtaining a representa-tive sample. / (7) Groundwater samples shall be take/ n when s source is tapped for drinking or irrigation purposes in aress'where the h aulic gradient or recharge properties are suitable fora ontamination. (8)Thedoseshehecalcula<edforthemaximumorganand ge group, using the ; methodology and parameters in the ODCM. ' (9) If harvest occup/more than once a year, sampiing shall beedper during i
' each discrete / arvest. If harvest occurs.continuwusly ..auwlleeg *1 be monthly. Attention shall be paid to including samples of tuberous ar root !
food pro ufits. l P 4 S l i.- f. yh[b 8RAIDWOOD - UNITS 1 & 2 3/4 12-8
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2 TA8tE 4.12-1 b ' DETECTION CAPABILITIES FOR ENVIROW9 ENTAL SAMPLE ANALYSISIII LOWR LIMIT OF DECTECTION (LLD)II}I ) d WATER Al280RNE PARTICULATE FISH
~
MitK 3 A YSIS (pCl/t) OR GAS (pC1/m2 ) (pCf/kg, wet) (pci/t) F000 PRODUCTS SEDIMEN (pCl/kg, wet) (pc d g, dry) N Gross Be 4 0.01 e.
" H-3 2 Mn-54 15 130 Fe-59 30 260 w Co-58.60 15 130 k
Zn-65 30 260 d; Zr-Nb-95 15 I-131 I I4I 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.
& Ba-La-140 15 150 18 15 80 180
,4 If no drinking water thway exists, a value of 3000 pCi/t may be used.
1
TA8LE 4.12-1 (Continued) E TA8LE NOTATIONS (1 This list does not mean that only these nuclides are to be consid Gi. her peaks that are identifiable, together with those of the ab e n Env lides,shallalsobeanalyzedandreportedintheAnnualRaffological onnental Operating Report pursuant to Speci.fication 6.9. 6. (2) Require detection capabilities for thermoluminescent dosi ters used for enviro tal measurements shall be in accordance with th recommendations of Regulat ry Guide 4.13. (3) The LLD is de ned, for purposes of these specificati s, as the smallest concentration radioactive material in a sample t t will yield a net count, above sys background, that will be detec with 95% probability with only 5% pro 111ty of falsely concluding t a blank observation represents a "real signal. For a particular meas rement system, which ma include radiochemical separation: 166 s D LLO = E V 2.22 1 Y exp.(-bt). -- - c Where: LLO = the "a priori" lower .eit of' detection (picoCuries per unit mass or volume), s a the standard deviat, on of t background counting rate or of the counting rate of blank sample as appropriate (counts per minute), E = the counting ficiency (counts per isinte V's the sample ize (units of mass or vol N),gration), 2.22=thendberofdisintegrationsperminut per picocurie, Y = the f etional radiochearical yield, when appl cable, A = th radfoactive decay constant for the particula radionuclide, (sec 1 ,4N At the elapsed time between sample collection, or end o the s le collection period, and time of counting (sec). ypical values of E, V, Y, and at should be used in the calcul tion. BRAIDWOOD - UNITS 1 & 2 3/4 12-11 l l
5 s TABLE 4.12-1 (Continued) (. TABLE NOTATIONS (Continued) It sh y be recognized that the LLD is def)fted as a before the f act i limit re nting the capability of a medsurement system and not as an after the f performed in su limit for a particulpr'asurement. Analyses shall be a l a manner that the stated LLDs will be achieved under ; routine conditions. Occasional)f,backgroundfluctuations, unavoidable small sample sizes, A pres ce of interfering nuclides, or other uncon-tro11able circumstances render these LLDs unachievable. In such . cases, the contributin ora shall be identified and described in the Annual Radiological vironment) Operating Report pursuant to Specifica-tion 6.9.1.6. (4) LLD for dri ng water samples. If no dr ng water pathway exists, the LLD of gamma isotopic analysis may be used.
/
4 I l I BRAIDWOOD - UNITS 1 & 2 3/4 12-12
s RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS L ITING CON 0! TION FOR OPERATION 2 3.12.2 A Land Use Census shall be conducted and.shall identify wi in a distance f 8 lun (5 miles) the location in each of the 16 meteor 61ogical sectors o the nearest milk animal, and the nearest residence / For dose calculatio.1 a garden will be assumed at the nearest residege. APPLICABILITY: At all times. ACTION:
- a. With a La Use Census identifying a locp ion (s) that yields a calculated ose or dose connaitment greater than the values currently being calcul ed in Specification 4.11'.2.3, identify the new location (s) in the next Annual Radiologica1' Environmental Operating Report, pursuan to Specification 4.9.1.6.
- b. With a Land Use Ce us identifying a location (s) that yields a calculate <
dose or dose commits t (via the same exposure pathway) 20*. greater than at a location from wh hs les are currently being obtained in accordar with Specification 3.12. add the new location (s) within 30 cays to the Radiological Enviro ntal Monitoring Program given in the 00CM.
- Thesamplinglocation(s), ciuding the control station location.
having the lowest calculate dose or dose commitment (s), via the same exposure pathway, m4y be dele d from this monitoring program after October 31 of theMear in which this Land Use Census was conducted. l Pursuant to Specification 6.14, bmit in the next Annual Radiological Environmental O' p erating Report doc entation for a change in the 00CMincludipdarevisedfigure(s) d table (s) for the 00CM reflecting the new logation(s) with information pporting the change in sampling locations ' 7
- c. The pr isions of Specifications 3.0.3 and .0.4 are not applicable.
i SURVEILLANCE EQUIREMENTS x 4.12.2 e Land Use Census shall be conducted during the grow season at least the best resu1%pnces per 12 months using that information that will provid loc 4f ag,riculture authorities.such as by a door-to-door survey, aerial survey, or by co ultin The results of the Land Use Census s 11 be included in the Annual Radiological Environmental Operating Report pu uant to ecification 6.9.1.6. wh BRAIDWOOD - UNITS 1 & 2 3/4 12-13 .
s l RADIOLOGICAL ENVIRONMENTAL _ MONITORING 1 N4.12.3 INTERLABORATORY COMPARISON PROGRAM -- LIM CONDITION FOR OPERATION 3.12.3 Analy s shall be performed on radioactive aterials supplied as part of an Interlabo tory Comparison Program that hag /een b approv,ed by the Commission, that trespond to samples required ~ y Table 3.12-1. APPLICABILITY: At al times. ACTION:
- a. With analyses not be g performed as required above, report the corrective actions taken ,te prevent a recurrence to the Commission in the Annual Radiologici Environmental Operating Report pursuant to Specification 6.9 1/6, The provisions of
/
- b. ecification 3.0.3 and 3.0.4 are not applicable,
/
SURVEILLANCEREQUIREkNTS 4.12.3 The In laboratory Comparison Program shall be scribed in the 00CM. A summary of'the results obtained as part of the above requhed Interlaboratory Comparison' Program shall be included in the Annual Radiologica Environmental Operati Report pursuant tc Specification 6.9.1.6. BRAIDWOOD - UNITS 1 & 2 3/4 12-14
__ __ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . _ . _ . _ ~ INSTRUMENTATION i BASES 3/4.3-3.8 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to-detect loose metallic parts in the Reactor Coolant System and avoid or mitigate damage to Reactor Coolant 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. , w a vir b 3/4.3.3.9' "A010ACT!"E LI^U!O [irLUENT MONITORING INST ^UMENTATION radioactive liquid effluent instrumentation is provided to moni
~
and contro , licable, the releases of radioactive mater 1 quid effluents during actu tential releases of li uents. The Alarm / Trip Setpoints for these instru,i a . culated and adjusted in accordance w!:h the methodolo aram the ODCM to ensure that the alarm / trip will occ to exceeding the limits FR Part 20. The - OPERABILI se of this instrumentation is consistent w uirements Jg'. eral Desian Criteria 60. 63. and 64 of Accendix A to 10 CFR Part streesow sks 3/4.3.3.10 RAOIGAClivi 6A5E003 Erf t'JE"'$ MONITORING INSTRUMENTATION The radicactive gaseou: Offluent instre entatien it previded te eriter and control, 20 :pplicable, the r:le:5 : Of r:d!000tive : tee 4&l i^ g;; Ou;- Of'luent-s-dur4ng-actual-ar-.petential releace: cf g: ecu: ef'luents. The Mem/%-Setpoint: for these-iest+vments :hal' be ::!culated and adjusted 4" accer4ance 'ith the ethedO!0gy-and par; :ter; in th: 00CM to :n;ure th:t th 1;rm/ trip will : cur prier t ex::: ding the limit: e f 10 Cf Ps P;rt 20.+ The instrumentation e4ee includes provisions for monitoring.( nd centrel'ing> the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. TAa CEEDABILITV tad uee of + hie 4act""=antatian ie cancie+=n+
^
with the requir ::nts of Oeneral 00:ign Criteri: 50, 53, :nd 54 Of ^ppendi te 10 CFR-Part 50. The cen itivity of any aoble ga: act!"ity -caiter used te she" ce=pliance '4th the g:Escus effluent release require eats of Speci' ice-tica 3.11.2.2 thal' be-such that concent"ations as !ce as lx10 6 uCi/cc 3*e i *estur:blc. 3/4.3.3.11 HIGH ENERGY LINE BREAK ISOLATION SENSORS
-The OPERABILITY'of the high energy line break isolation sensors ensures that the capability is available-to promptly detect and initiate protective action in the event of a line break. This capability is required to prevent
~
the potential for. damage to safety-related systems and structures in the auxiliary building. I l l BRAIDWOOD - UNITS 1 & 2 B 3/4 3-6
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3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 GONOiWTRATIGH be LETED ( , This specification is provided to ensure that the concentration of radio-fl acn materials released in liquid waste ef fluents to UNRESTRICTED AREAS wp1 be le n the concentration levels specified v 10 CFR Part 20, Appenq M B, Table II, n 2. This limitation provides additional assurance th,Vthe levels of radio D result in exposures ivematerialsinbodiesofwaterinUNRESTRICTEfREASwill ithin: (1) the Section II.A design objec Appendix I, 10 CFR Par 0,toaMEMBEROFTHEPUBLIC,and(2),fvesof, the limits of 10 CFR Part 20.106(e) to population. Theconcentratpfflimitfordissolved or entrained noble gases is edupontheassumption) fiat.Xe-135isthe controlling radioisotope and its PC in air (submep1on) was converted to an equivalent concentration in water ut g the methods described in International Commission on Radiological Protection RP A'ublication 2. This specification applies to the releas of radioactive materials.in liquid effluents from all. units atA,he, site., . . . . , The required detectio apabilities for radioact e materials in liquid waste samples are tabula d in terms of the lower limits f detection (LLDs).
. Detailed discussion,4f'the LLD, and other detection limits n be found in HASL Procedures, Manual, HASL-300 (revised annually), Currie, . ,, " Limits for Qualitathre Detection and Quantitative Determination - Applic n to Radioch t offtry," A_nal. Chem. 40, 586-93 (1968), and Hartwell, J, K., tection Limps'forRaditanalyticalCountingTechniques,"AtlanticRichfieldHanfo j
;yeepany R3 nort ARH_iA-215 (June 1975).
3/4.11.1. 2 -00Sf- bELETE b h4 cification is provided to implement the requirements of Se - tions 11 d IV.A of Appendix I, 10 CFR Part 50. The tion for Operation imp'Tiiment u be guides set forth in actin ~ymit II'.A ofng Condi-Appen-dix !. The ACTION statements prDue-4htrejuin operating flexibility and { at the same time implement the guidtsaet'TdPth
- Section IV.A of Appendix I to assure that the releasei a f7 sdioactive material id effluents to UNRESTRICTED AREAS A i'lfe kept "as low ss is reasonably ach ev Q." e dose calculaticfmethodology and parame.cers in the OOCH implement the requite ,
me n'Section III. A of Appendix I chat conformance with the mirin J 3/4 . ll . l . 3 DE W h BRAIDWOOD - UNITS 1 & 2 8 3/4 11-1 I
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s l RADI0 ACTIVE EFFLUENTE i B ES DOSE ( ntinued) of Append I be shown by calculational procedures based on modp s and data, such that th actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is u ikely to be substantially underestimated. Ther equations specified in the ODCM for calculating the doses due to the actual relase rates of radioactivemate(alsinliquideffluentsareconsistent/ththemethodology ' provided in Regulabry Guide 1.109, " Calculation of Annudi Doses to Man from RoutineReleasesofleactorEffluentsforthePurposepfEvaluatingCompliance with 10 CFR Part 50. Appendix I" Revision 1, October J977 and Regulatory Guide 1.113."EstimatingAquaicDispersionofEffluentsffomAccidentalandRoutine Reactor Releases for the urpose of Implementing pendix I," April 1977. This specification app ies to the release pf radioactive materials in liquid ef fluents from each r(eactor at the sity. When shared Radwaste Treatment Systems are used by more than ne unit on a ite, the wastes from all units are mixed for shared treatment; by uch mixing he efflurnt releases cannot accurately be ascribed to a specg fic unit An estimate should be made of the contributions from each unit baseo on input conditions, e.g., flow rates' and radioactivity concentrations, or, sf not practicable, the treated effluent releases may be allocated ~ equally to sch of the radioactive waste producing units sharing the Radwaste Treatment stem. For determining conformance to LCOs, these allocations from shared /Ra aste Treatment Systems are to be added to the releases specifically attr buted each unit to obtain the total releases per unit. 3/4.11.1.3 LIQUID RADWASTE TR ATMENT SYSTEM The OPERABILITY of th9 Liquid Radwaste Tr4 tment System ensures that this systemwillbeavailableforusewheneverliqui effluents require treatment prior to release to thefnvironment. The require ent that the appropriate portions of this system be used when specified pro ides assurance that the releases of radioacti 4 materials in liquid effluen will be kept "as low as is reasonably achie le". This specification implem nts the requirements of 10 CFR 50.36a, Gene. I Design Criterion 60 of Appendix to 10 CFR Part 50 and the design oc fetive given in Section II.0 of Appen x ! to 10 CFR Part 50. The specified li ts governing the use of appropriate po ions of the Liquid Radwaste Trea nt System were specified as a suitable fra tion of the dose design object es set forth in Section II.A of Appendix I, CFR Part 50, for liquid efflu nts. This pec4*ication applies to the release of radioactive ma trials in liquid fluents from each unit at the site. When shared Radwast Trea tment System are used by more than one unit on a site, the wastes from 1 units are mixe for shared treatment; by such mixing, the effluent releases ca ot acc ately be ascribed to a specific unit. An estimate should be made of the co ributions from each unit based on input conditions, e.g., flow rate and r4dioactivity concentrations, or, if not practicable, the treated efflue eleases may be allocated equally to each of the radioactive waste produci. ( l BRAIDWOOD - UNITS 1 & 2 83/411-2 %
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RADIOACTIVE EFFLUENTS BASES tttHfMLRA0 WASTE TREATMENT SYSTEM (Continued) units shari ree stem. For determining conformance to LCOs,-these allocati shared Ra573rt atment Systems are to be added to the Jrel Ases ecifically attributed to each un ain the total relsests e per unit. 1/4.11.1.4 LIQUID HOLOUP TANKS , The tanks listed in this specification include all 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 radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part.20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
- 3/4.11. 2 GASEOUS EFLUENTS- ' ' ~
3/4.11.2.1 OOSE RATE bEtEmb ( This specification is provided to ensure that the dose at any time at and) and the SITE BOUNDARY from gaseous affluents from all units on the site I wi hbe within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED ARE , i The annu(1 dose limits are the doses associated with the concentrations -10 : CFR Part Zo q Appendix B, Table II, Column 1. These limits provide r onable assurance tha .will not
. result in the (o g sure of-a MEMBER OF THE PUBLIC in an TED UNRESradioacti AREA, either within or otttside the SITE BOUNDARY, to annual ave e concentrations exceeding the limits speqified in Appendix B. Table . 10 CFR Part 20 (10 CFR 20.106(b)). For MEMBEit OF THE PUSL1C who at times be within the l SITE BOUNDARY, the occupancy that HEM 8ER E PUBLIC will usually be j sufficiently low to compensate fo ny in- ase in the atmospheric diffusion :
factor above that for the SITE BOUND Examples of calculations for such MEMBERS OF THE PU8LIC, with the opria l occupancy factors, shall be given in the 00CM. The specified r ase rate lia restrict, at all times, the corresponding gamma and b< dose rates above bac ound to a MEMBER OF THE PUBLIC at or beyond t JTE 80VHDARY to less than o ual to 500 mrems/ year to the whole body o less than or equal tc 3000 arems r to the skin. These release yate limits also restrict, at all times the cor anding thyroid i dose rate atxive background to a child via the inhalation pathway less than or equaldo 1500 mress/ year. This specification applies to the release of radioactive materials in i - Qaseous effluents from all units at the site. 5 /4 . t i . 2. t- b et.e r d p . it , s. . V 't>ew@ ~ BRAIDWOOD - UNITS 1 & 2 B3/411-[I 3/4.d t.4 bEtrrch r--
s g RADI0AC'!VE EFFLUENTS ASES
?
DOSE ATE (Continued)
\
The required detection capabilities for radioactive materials in iguid waste s es are tabulated in terms of the lower limits of detecti (LLDs). Detailed di ussion of the LLD, and other detection limits can be ound in HASL Procedu s Manual HASL-300 (revised annually), Currie, L. ., " Limits for Qualitativ Detection and Quantitative Determination - Application to - Radiochemistry, nal. Chem. 40, 586-93 (1968), and Hartwell J. K., " Detection Limits for Radioartglytical Counting Techniques," Atlantic chfield Hanford Company Report ARH-D-215 (June 1975). 3/4.11.2.2 DOSE - NO GASES l This specification i rovided to implement the requirements of Sec-tions II.8, III.A and IV.A f Appendix I,10 CF4/Part 50. The Limiting Condi-tion for Operation implement the guides set fopth in Section II.B of Appen-dix I. The ACTION statements ovide the repu' ired operating flexibility and at the same time 10plement the ides set f4rth in Section IV.A of Appendix I to assure that the releases of ra ioactive material in gaseous effluents to UNRESTRICTED-AREAS.will be kept "as lowf f s is reasonably achievable " The Surveillance Requirements implement requirements in Section III.A of Appan-dix I that conformance with the guide of Appendix I be shown by calculational procedures based'orr models and data'suc that the actual exposure of a MEMBER OF THE PUBLIC through appropriate / pathway is unlikely to be substantially underestimated. The dose calculation meth ology and parameters established in the ODCM for calculating the 4cIses due to th actual release rates of radio-active materials <in liquid effluents are cons tent with the methodology pro-videdinRegulatoryGuideJ(109,"Calculationo Annual Doses to Man from Routine Releases of Reactor Effluents for the Pu ose of Evaluating Compliance with 10 CFR Part 50, App 4ndix I" Revision 1, Octob r 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transpor and Dispersion of Gaseous EffluentsinRoutineffeleasesfromLight-WaterCoole Reactors," Revision 1," July 1977. The 00C0 equations provided for determinin the air doses at and beyond the SITE 80VNDARY are based upon the historical verage atmospheric conditions. This spec) ication applies to the release of radioacti materials in gaseous efflufnts from each unit at the site. When shared Ra aste Treatment Systems are sed by more than one unit on a site, the wastes f m all units are mixed for ared trLatment; by such mixing, the effluent release cannot l accurate 1 be ascribed to a specific unit. An estimate should be ade of the contrib ions from each unit based on input conditions, e.g., flow ates and i radica ivity concentrations, or, if not practicable, the treated ef uent rele es may be allocated equally to each of the radioactive waste pro ucing uni)5sharingtheRadwasteTreatmentSystem. For determining conforman to s, these allocations from shared Radwaste Treatment Systems are to be dded
/t the releases specifically attributed to each unit to obtain the total eleases per unit.
BRAIDWOOD - UNITS 1 & 2 B 3/4 11-4
\
l 1 RADI0 ACTIVE EFFLUENTS I' BASES 3 .1' . 2. 3 DOSE - 100!NE-131 AND 133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN ULATE FORM s specification is provided to implement the requirements of Sections \11.C, III. A and IV. A of Appendix I,10 CFR Part 50. The Lim ing Condition) for Operation are the guides set forth in Section II.C of ppendix I. The ACTION atements provide the required operating flexibility a at the ' same time i esent the guides set forth in Section IV.A of Appe ix ! to assu; e that th releases of radioactive materials in gaseous e luents to UNRESTRICTED AR will be kept "as low as is reasonably acht vable." The 00CM calculational met ds specified in the Surveillance Require nts implement the requirements in Sec on III.A of Appendix I that conforua e with the guices of Appendix ! be show bycalculationalproceduresbaseponmodelsanddata, such that the actual e osure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to e substantially underestima)fd. The 00CM calculational methodology and parameter for calculating the dose due to the actual release rates of the subject mater 13areconsistentwitf(themethodologyprovidedin Regulatory Guide 1.109, " Cal lation of Annual ases to Pan from Routine Releases of Reactor Effluents r the Purpose f Evaluating Compliance with 10 CFR Part 50, Appendix I,'" ReVis 1,'Octeb 1977.and Regulatory Guide '1.111
" Methods for Esthating Atmospher Transigsrt and Dispersion of Gaseous Effluents in Routine Releases from Light-Wate Coo)td Reactors," Revision 1, July 19D.
These equations also provide for dete ning the actual doses based upon the historical average atmospheric condi o c The release rate specifications for Iodine-131 and 133, tritium, a rad uclides in particulate form with half-lives greater than 8 days a depende upon the existing radionuclide pathways to man, in the areas 'J and beyond e SITE BOUNDARY. The pathways that were examined in the dev410pment of these alculatioris were: (1.) indi-vidual inhalation of airbor'nefradionuclides, (2) eposition of radionuclides onto green leafy vegetatiop with subsequent consum ion by man, (3) deposition onto grassy areas where (ik animals and meat produc %g animals graze with consumption of the milk and meat by man, and (4) depo tien on the ground with subsequent exposure t man. This specific lon applies to the release of radioact e materials in gaseous effluent from each unit at the site. When shared R aste Treatment Systems are use by more than one unit on a site, the wastes om all units are mixed for sha d treatment; by such mixing, the effluent releas cannot accurately ascribed to a specific unit. An estimate should b made of the contributi ns from each unit based on input conditions, e.g., flow atu and radioact ity concentrations, or, if not practicable, the treated e luent releas may be allocated equally to each of the radioactive waste pr ducing units haring the Radwaste Treatment System. For determining conforma e to LC0 , these allocations from shared Radwaste Treatment Systems are to be added to he releases specifically attributed to each unit to obtain the total r leases per unit. BRAIDWOOD - UNITS 1 & 2 B 3/4 11-5
t y t RADI0 ACTIVE EFFLUENTS f - BASES ,
-3/4.11.2.4 GASE005 RADWASTE TREATMENT SYSTEM TR
-The OPERA 8ILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATIO HAUST !
NT SYSTEM ensures that the systems will be available for use enever gaseou ffluents require treatment prior to release to the envi . nt. The-requireme provides rea thatble the appropriate portions of this system 2,e u d when specified assurance that the releases of radioac e materials in gas-eous effluents 1 be kept "as low as-is reasonably ac evable". . This speci fi-
- crtion implements reoutrements of-10 CFR 50.36a neral Design Criterion 60 of-Appendix A to-10 C art 50 and the design etives given in Section-II.0 -
t of Appendix.! to.10 CFR 50. The specifi imits governing the use of 1 appropriate portions of the eous Radwas reatment System were specified , as a suitable fraction of the dest objectives set forth in Section II.B ; and II.C of Appendix I, 10 CFR Par , for gaseous ef fluents. l This specification applies to the re se of radioactive materials in lSystemsareusedbymore gaseous effluents from each 1t at the site. When shared Radwaste Treatment an one unit on a sit the wastes from all units are f mixed for shared trea3 ment; by such mixing, the of nt releases cannot-accurately be ascr h6d to a specific unit. An estimat hould be made-6f the. _ contributions f each.un t besed on, input sonditionss e. .. flow rates and radioactivi once'ntration[s,o,,riif'not-practicable,thetre ad affluent j relecses= be allocated equally;to each of the radioactive was producing units ing the Radweste Treatment System. For determining confo LCOs nce to
- i
' hese allocations from shared Radwaste Treatment Systems are to added !
-t 4he releases specifically attributed to each unit to obtain the total leases ner unit. .
l-1 3/4.11.2.5' EXPLOSIVE GAS MIXTURE . This: specification is provided to ensure that the concentration of U
. po'.entially explosive gas mixturws contained in the WASTE GAS HOLOUP SYSTEM is
-maintained below the flammability limits of. hydrogen *rd oxygen. Automatie, i control' features are included-in the system to prevenc tne hydrogen and oxygen-concentrattens-from reaching these flammability limits. These automatic control ,
f1stures include _ isolation of the- source of hydrogen and/or oxygen, automatic 11 version to recombiners, or -injection of dllutants to reduce the concentration. below the flammability _-limits.. Maintaining the concentration of hydrogen and : oxygen below their flassability limits prevides assurance that the releases of radioactive materials will-be controllev .n conformance with-the requirements- { of General Design Criterion 60 of Appenuix A to 10 CFR Part-50. *
-3/4.11.2.6 GAS DECAY TANKS I f t L ' 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.
,- t 2- !
8RAIDWOOD UNITS 1 & 2 83/411-g ' i. r
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.RADI0 ACTIVE EFFLUENTS BASES GAS DECAY TANKS (Continued)
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncuntrolled release of the tank's contents, the resulting whole body exposure to a MEM8ER 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, .
"?ostulated Radioactive Releases Due to a Waste Gas System Leak or Failure,"
in NUREG-0800, July 1981. W 3/4.11.3 SOLIO RADI0 ACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a and G eral Des n Criterion 60 of Appendix A to 10 CFR Part 50. The process paramete'rs inclu d in establishin'g the PROCESS CONTROL PROGRAM may include, but are not limited ratios, w o, te waste type, waste pH, waste / liquid /50LIO!FICATION agent /cytalyst oil content, waste principal chemical constituents, and mixing and curing s. 3/4.11.4 TOTAL SE - This specificat n is provided to meet the dose limitations of 40 CFR Part 190 that have bee incorporated into 10 CFR Part 20 by f5 FR 18525. The specification requires t preparation and submittal of a Special Report . whenever the calculated do s due to releases of radioactfvity and to radiation from uranium fuel cycle sour exceed 25 mrees to the yhole body or any organ, except the thyroid, which shal Me limited to less than or equal to 75 mrems. ' For sites-containing up to four rhetors, it is highly unlikely that the resultant dose to a MEMBER OF THE P LIC will excpid the dose limits of 40 CFR Part 190 if the individual rea orsremaJnwithintwicethedosedesign objectives of Appendix 1, and if direct adiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in t, mitation of the annual dose to a < MEMBER OF THE PUBLIC to within the 40 CFR Par 190 limits. For the purposes of f the Special Report, it may be assumed'that the se commitment to the MEMBER OF THE PUBLIC from other urafiium fuel cyc sources is negligible, with the exception that dose contribytions from other nu ear fuel cycle facilities at the same site or within ay(dius of 8 km must be c sidered. If the dose to any MEMBER OF THE PUBLIC iyfestimated to exceed the req rements of 40 CFR Part 190, the Special Repdrt with a request for a varianc provided the ' release conditions r ting in violation of 40 CFR Part 19 ave not already been corrected), i ccordance with the provisions of 40 CFR 1 11 and considered to be a timely request and fulfills he l 10CFR20.405c,]40CFRPart190untilNRCstaffactioniscompleted requirements o . The variance oni relates to the limits of 40 CFR Part 190, and does not a ly in any way tp he other requirements for dose limitation of 10 CFR Part 20, addressed in Specifications 3.11.1.1 and 3.11.2.1. An individual is not
, cons red a HEMBER OF THE PUBLIC during any period'in which he/she is engage i arrying out any operation that is part of the nuclear fuel cycle.
BRAIDWOOD - UNITS 1 & 2 63/411-k
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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING I BASES
/
3/ 2.1 MONITORING PROGRAM T Radiological Environmental Monitoring Program required b his specific fon provides representative measurements of radiation d of radioacti materials in those exposure pathways and for those dionuclides that lead t the highest potential radiation exposures of MEbj8tRS OF THE PUBLIC result g from the station operation. This monitor program implements Section IV.8.2 f Appendix ! to 10 CFR Part 50 and thfre supplements the radiological off ent monitoring program by verifying t the measurable concentrations of dioactive materials and levels of /adiation are not higher than expected on the asis of the effluent measureewnts and the modeling of the environmental expo re pathways. Guidance for,<this monitoring program is provided by the Radiolo cal Assessment Branch T4chnical Position on Environmental Monitoring. The initially specifn d monitoring program will be effective for at least the- rst 3 years of commercial operation. Following this period, program changes y be initiated based on operational experience. The required detection cap lities, r environmental sample analyses are tabulated in terms cf.the, lower.1 ts of detection. (LLDs). The LLDs recuired by Table 4.12-1 are considered optim 'for routine environmental measurements in industrial laboratories. It shout e recognized that the LLD is defined as a before the fact limit representing he capability of a measurement system and not as an after the fact lim H for a rticular measurement. Detailed discussion of the LLD, and oth detection limits, can be found in HASL Procedures Manual, HASL-300 (revised a ually), Currie, L. A., " Limits for Qualitative Detection,and Quantitative Dete ination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), an Hartwell, J. K., " Detection Limits for Radicanalytical Counting Techniques," At tic Richfield Hanford Company Report ARH-SA-215 (June 1975).
- 3/4.12.2 LAND USE ENSUS This specjffcation is provided to ensure that changes i the use of areas at and beyond/the SITE BOUNDARY are identified and that modifi tions to the Radiologica}' Environmental Monitoring Program given in the 00CM re made if l- required the results of this census. The best information fro the i
door-to or survey, from aerial survey, or from consulting with 1 al agricul-tural thorities shall be used. This census satisfies the requirem ts of Secti n IV.B.3 of Appendix ! to 10 CFR Part 50. An annual garden cen s will l nota e required since the licensee will assume that there is a garden a the n drest residence in each sector for dose calculations. l /
)
BRAIDWOOD - UNITS 1 & 2 B 3/4 12-1
t \ l RADIOLOGICALENVIRONMENTALMONITORI.$ i \ 3/4.12.3 INTERLA TORY COMPARISON PROGRAM The requirement for pa i ation an approved Interlaboratory Comparison Program is provided to ure that independent checks on the precision and accuracy of the measure of ra tive material in environmental sample matrices are perfo as part of the 11ty assurance program for-
- i environmental monitoripg' n order to demonstrate for the purposes o ection IV 8.2 of Appendix ! to 10 the results are valid Part 50.
j I i I e . BRAIDWOOO - UNITS 1 & 2 8 3/4 12-2
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l ' l ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- b. In-Plant Radiation Monitorino A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
- 1) Training of personnel,
- 2) Procedures for monitoring, and
- 3) . Provisions for maintenance of sampling and analysis equipment.
- c. Secondary Water Chemistry '
A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
- 1) Identification of a sampling schedule for the critical variables and control points for these variables,
- 2) Identification of the procedures used to measure the values of the critical variables,
- 3) Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,
- 4) Procedures for the recording and management of data,
- 5) Procedures defining corrective action for all off-cont'rol point chemistry conditions, and
- 6) A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action,
- d. Post-accident Samplina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
- 1) Training of personnel,
- 2) Procedures for sampling and analysis, and
- 3) Provisions for maintenance of sampling and analysis equipment.
c. _1.U5EtL7 3,
- 4. I BRAIDWOOD - UNITS 1 & 2 6-17 l
ADMINISTRATIVE CONTROLS s -
; s REPORTING REQUIREMENTS (Continued)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT \ 4 h 5 g< ~6.9.1.6 5 0utine Annual Radiological Environmental Operating Reports T he operation of the Unit during the previous calendar year shall be submitted p for to May 1 of each year. The initial report shall be submitted prior to Ma of the year following initial criticality. , Th Annual Radiological Environmental Operating Reports shall inct de . summaries, nterpretations, and an analysis of trends of the results /f the radiological nvironmental surveillance activites for the report pp/tod, including a co arison with preoperational studies, with operati al controls as appropriate, d with previous environmental surveillance r orts, and an assessment of the served impacts of the plant operation on he environment. The reports shall al include the results of the Land Use ensus required by Specification 3.12.2. TheAnnualRadiologic1EnvironmentalOperatingyportsshallincludethe results of analysis of all r iological environmentM samples and of all environmental radiation measu ents taken during,t'he period pursuant to the locations specified in the table and figures irythe ODCM, as well as summarized and tabulated results of these an ses and measurements in the format of the table in the Radiological Assessmen BranchJschnicalPosition, Revision 1, November 1979. vidual results are not available for inclusion with the report, the repoIntheeventthatsom,ind)shallbesubmitted explaining the reasons for the missing ye its. The missing data shall be submitted as soon as possible in a suppleme tary report. Thereportsshallalsoinclude/the follow : a summary description of the Radiological Environmental Mo'nitoring Progra at least two legible maps ** covering all sampling locations' keyed to a table g ing distances and directions from the centerline of one reactor; the results of 1 ensee participation in theInterlaboratoryComparjionProgramandthecorrect e actions being taken if the specified program is,40t be'ing performed as require by Specification 3.12.3; reasons for not conducting the Radiological Environmental onitoring Program as required by Specificat'lon 3.12.1, and discussion of all dev' tions from the sampling schedule of Table 3.12-1; discussion of environment sample measure-ments that exceed,4he reporting levels of Table 3.12-2 but are et the result of plant effluents, pursuant to Specification 3.12.1; and discuss on of all analyses in wt't'ch the LLD required by Table 4.12-1 was not achieva e. l *A si 'le submittal may be made for a multiple unit station.
"*O sap shall cover stations near the SITE BOUNDARY; a second shall include [
e more distant stations. \ ! BRAIDWOOD - UNITS 1 & 2 6-19
4
@MINISTRATIVECONTROLS REPORTING REQUIREMENTS (Continued)
S TheAnnualRadiologicalEnvironmentalOperatingReportshallalsoinc5 a6 nnual summary of hourly meteorological data collected over the previo year. This annual summary may be either in the form of an hour-by-hour g listing magnetic tape of wind speed, wind direction, atmospheric st&bility, and precip tion (if measured), or in the form of joint frequen distribu-tinns of wind eed, wind direction, and atmospheric stability This same report shall inc an assessment of the radiation doses d o the radioactive liquid gaseous effluents released from t it or Station j during the previous ca dar year. This same report I also include an assessment of the radiat doses from radioactive uid and gaseous effluents to MEMBERS OF THE PUBLIC due o their activities ide the SITE BOUNDARY (Figure 5.1-1) during the repo eriod. All,a sumptions used in making these assessments, i.e. , specific activ t , exposufe time and location, shall' be {
. included in these reports. The mete st[ical conditionu concurrent with the time of release of radioactive mater,Ais i n gaseous effluents, as determined be used for determining the by sampling gaseous frequency pathway doses. and measurem,efft, The asspssment of ra sha (dth ion doses shall be in accordance with the methodafogy and parameters the ODCM. f The Annual Radiologt Environmental Operating Report to be submitted prior to May 1 of ea ' year shall also include an assessmeh of radiation doses to the most likel. xposed HEMBER OF THE PUBLIC from reactor leases and l
other nearby u um fuel cycle sources, including doses from p
- ary effluent pathways and,dfrect radiation, for the previous calendar year to s con-formance[with40CFRPart190,"EnvironmentalRadiationPrctectionSta rds for Nuc) ar Power Operation." Acceptable methods for calculating the dos contribution from liquid and gaseous effluents are given in Regulatory Guide 1,d9, Rev. 1, October 1977.
y SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTM 4 f.9.1.k[RoutineSemiannualRadioactiveEffluentReleaseReportscoverin I Weratio,n of the unit during the previous 6 months of operation shal,1 tre submitted within 60 days af ter January 1 and July 1 of each year he period of the f Wst q port shall begin with'the date of initial cr i ality. , The Semiannual R'sMeactive Effluent Release R ts shall include a summary of the quantities o'DT dioactive liquiA4nd gaseous effluents and solid waste released from the un outliatd in Regulatory Guide 1.21, "In lieu of submissior, with Annual Radiologic nvironmental Operating Report, the licensee ha e option of retaining this , ary of required meteorological data site in a file that shall be provi to the NRC upon request.
**A single ,s ittal may be made for a multiple unit station. The subm1 should A mbine those sections that are common to all units at the station; h ever, for units with separate radwaste systems, the submittal shall specif e releases of radioactive material from each unit. w
! BRAIDWOOD - UNITS 1 & 2 6-PO
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued) __ _
./
y
' ensuring, Evaluating, and Reporting Radioactivity in Solid Wastes and /
Re ases of Radioactive Materials in Liquid and Gaseous Effluents from Mght-Wate coled Nuclear Power Plants," Revision 1, June 1974, with dataMnaarized on a qua ,For solid I wastes, th erly basis ormat forfollowing Tab ~.e 3 in the format Bofshall Appendix Appendix B thereof. ,d with be supplemente threeI additional ca ories: class of solid wastes (as defined by-10 CFR Part 61), 1 type of containeN .g. , LSA, Type A, Type B, Large Quantity), and SOLIDIFICA-TION agent or absorbe e.g., cement, urea formaldehyde). k ' The Semiannual Radioaccw(Effluent Releasedeports shall include a list and description of unplanned reTwases from the' site to UNRESTRICTED AREAS of radioactive materials in gaseous an quid' effluents made during the reporting i period. 7 The Semiannual Radioactive Effluent Rel aae R changes made during the repor}ifig period to the%eports pursuant to shall include any Specifications 6.13, as well as any majo anges to Liquid, Gaseoutw r Solid Radwaste Treat-ment Systems, pursuant Specification 6.15. The SemiannuaF
\
dioactive Effluent Release Reports shal M iso include , the following: effluent moniT,Mfn oring explanation instrumentation as towas whynot thecorrected inoperability of liquid within orhgaseous the tin pecified f in SpecjMcations 3.3.3.9 or 3.3.3.10, respectively; and description of 'th( even,ts leading to liquid holdup tanks or gas storage tanks exceeding the li Mtt i of'$pecjfication_3.11J 4 or 3.11.2.6, respectively. i- V MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report. OPERATING LIMITS REPORT 6.9.1.9 Operating limits shall be established and documented in the OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the operating limits shall be those previously reviewed and approved by the NRC in Topical Reports: 1) WCAP < 9272-P-A " Westinghouse Reload Safety Evaluations Methodology" dated July 1985,
- 2) WCAP-8385 " Power Distribution Control and Load Following Procedures" dated September 1974, 3) NFSR-0016 " Benchmark of PWR Nuclear Design Methods dated July 1983, and/or 4) NFSR-0081 " Benchmark of PWR Huclear Design Methods Using the PHOENIX-P and ANC Computer Codes" dated July 1990. The operating limits shall be determined so that all applicable limits (e.g., fuel thermal-aechanical 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 OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
BRAIDWOOD - UNITS 1 & 2 6-21 AMENDMENT NO. E
_.- _ _ . - ~
. . . . . . . _ _ _ . . .- - _. _ _ . _ _ _ +. - . . - . _ _ _
s ADMINISTRATIVE CONTROLS' ' h-x 4 RECORD RETENTION (Continued)
- c. ~ Records of radiation exposure for all individuals entering radiation control areas;
- d. Records of gaseous and liquid radioactive material released to the environs; ;
- e. Records of transient or operational cycles for those unit components identified in Table 5.7-1; .
- f. Records of reactor tests and experiments;
' g. Records of training and qualification for current members of ,the unit _ staff;
- h. Records of in-service inspections performed pursuant to these Technical-
. Specifications;
- i. _ Records of_ Quality Assurance activities required by the QA Program;
- j. -Records of reviews performed for changes made to procedures or equipment or reviews.of tests and experiments pursuant to 10 CFR 50.59;
^
, k. _ Records of: meetings and results of reviews and audits performed by
~
i the Offsite Review and Investigative Function and the Onsite Review and-Investigative Function;
- 1. ; Records of the service lives of all. hydraulic and' mechanical-snubbers required by Specification:3.7.8 including the date at which the service life commences and associated installation'and maintenance records; m .- - . Records of secondary water sampling and-water quality; An('
- n. Records of analysis required by the Radiological Environmental
- Monitoring Program that would permit evaluation of the accuracy of the analysis at a later-date. This.should= include procedures effective at specified times and QA records showing that these procedures were followed) M 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall-be approved, maintained _and 4
' adhered to for all operations involving personnel radiat4n exposure. t 6.12- HIGH RADIATION AREA 6.12.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the
^
" control device" or " alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/hr at 45 cm (18 in.) from the' radiation BRAIDWOOD - UNITS 1 & 2' 6-23 ;
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)
. .1 The PCP shall be approved by the Commission prior tc implementation, ff 3.13.2 nsee-initiated changes to the PCP:
- a. Shall b bmitted to the Commission in the Semiannual Radioactive Effluent Re h s Report for the period in which the hange(s) was made. This subm1 1 shall contain:
- 1) Sufficiently detaile ' formation ,t<f totally support the rationale for the change out benefit of additional or supplemental information / lf
- 2) A determination tAat the change did n - reduce the overall I conformance of dhe solidified waste prod to existing criteria)ot solid wastes; and
- 3) DocuIntation of the fact that the change has been iewed and /
ound acceptable by the Onsite Review and Investigative nction. I
- b. Shall become effective upon review and acceptance by the Onsite
,/ Review and Investigative Function in accordance with Specification
- 6. 5. 2.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)
, 4.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 icensee-initiated changes to the ODCM: f( i a. Sha e submitted to the Commission by inclusion in the Morit ly Operat1Qeport pursuant to Specification 6.9.1.8 withirtdf0 days of
, the date th hange(s) was made effective. This submiit'al shall contain:
j /
- 1) Sufficiently detaite( information to totally support the rationale for the chaft without benefft of additional or supplemental information, nferrqatTon submitted should consist of a package of those pages o 4he ODCM to be changed with each I page numbered, dated and contain the revision number, together with appropriattfanalyses evaluations justifying the change (s);
- 2) A determ tM n that the change will not redu the accuracy or reliabjl y of dose calculations or Setpoint de minations; and
- 3) ocumentation of the fact that the change has been re wed and found acceptable by the Onsite Review and Investigative ,ction.
Shall become effective upon review and acceptance by the Onsite Rev 'w and Investigative Function in accordance with Specification 6.5.2.
~~ -
- )
BRAIDWOOD - UNITS 1 & 2 6-25 AMENDMENTNO.tj
DMINISTRATIVE CONTROLS
/
6.15 JOR CHANGES TO LIQUIO, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS
- j -
6.15,1 L ensee-initiated major changes to the Radwaste Treatment Sy / ens (liquid,ga ous, and solid):-
- a. Shall e reported to the Commission in the Semiannual R ioactive
'Effluen Release Report for the period in which the ev uation was reviewed the Onsite Review and Investigative Fune fon. The dis-cussion of ach change shall contain:. .
- 1) A summa gof the evaluation that led to the etermination that the change could be made'in accordance with 10 CFR 50.59;
- 2) Sufficient de ailed information to tota) y support the reason.
for the change ithout benefit of add tional and supplemental information;- 3)- A detailed descript on of the equipment, components, and processes involved and the int faces with'other plant systems.
/
4)' An evaluation of the ch e which shows the predicted relsases of radioactive materials ' liquid and gaseous effluents-and/or quantity of solid waste tha differ from those previously o
. predicted in the License' app cation and amendments thereto;
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- 5) AEeTialuationofthedhange,wh h shows the expected maximum exposures to a MEMSER'0F THE PUBL C in the UNRESTRICTED AREA and to the generpi population that iffer from those previously estimated in the License application and amendments _thereto;
- 6) A comparisory the predicted releases f radioactive materials, in liquid stid gaseous effluents and in s '
actualrpieasesfortheperiodpriortowh(idwaste,tothe- n the changes are to be made(
- 7) An mate of the exposure to plant operating ersonnel as a res61t of-the change; and
- 8) ocumentation of the fact that the change was revi ed and found acceptable by the Onsite Review and-Investiga vs Function.
- b. hall become effective upon review and acceptance by the On te Review-and Investigative Function in accordance with Specification 5.2.
l Licensees may choose to submit the information called for in this specificat n i, as part of the annual FSAR update.
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BRAIDWOOD - UNITS 1 & 2 6-26 T8 1 l.___
e INSERT 1 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCH) shall contain the methodology and parameters used in the calculation of the offsite doses resulting from radioactive gaseous and 1ituid effluents, in the calcu t at ion of gaseous and liquid effluent monitoring stara/ trip setpoints, and in the conduc t of the Environmental Radiological Monitoring Program. The ODCM f'shall also contain (i) the Radioactive Ef fluent Controls and Radiological Monitoring Programs required by Sec t ions 6.8.4.e and f , and (2) descriptions of the information that should be included in the Annual adiological Release Repor ts requ ired by Environmental Operating and Semiannual Radioactive Effluen Sp p ec i f i c a t i on 6.9.1.6 a nd 6.9. i .7.
\EnfronrwowkAI INSERT 2 E 1.23 The PROCESS CONTROL PROGRAM (PCP) shall contpin the current formulas, sampling, analysis, test, and determinatons to be made to ensure that processing and pacfkaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State Regulations, burial ground requirement, and other requirements governing the disposal of solid radioactive waste.
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^ ADMINIST:tATivE CON?ROLS- i 3
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_ dir, Radioactive Ef ficent Centrols Program i
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A program shall be provided conforming with 10 CFR 50,36a for the control of_ radioactive effluents and for maintainirg the. doses to MEMBERS OF NE PUBLIC f er,m radio' a ctive ef fit.ents as low is reasonably , scrievable. Se progrim (1) shall te centained in the 00CH, i g7,g e2) inal1 te itD'erented o)yw; stocedures, and (3) still in-
- ..;e 7 0ecial sc*.i vs to :;e taten .cenever the progrtm limi'.3 3re enceeded. The o'; gram snali include tne following elements;
- 1) Limitations on the operability of~ radioactive siquid 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 8, Table II, Column- 2,
- 3 )_ ._ Monitoring, sampiing, and analysis of. radioactive' liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the _00CM,
- 4) Limitations on the annual and quarterly doses or dose commitment to a MEM8ER OF THE~ PUBLIC froeiradioactive materials in liquid =
ef fluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50,
- 5) Determination of-cumulative:and projected dose. contributions-from_ radioactive ef fluents: for the: current calendar _ quarter and current calendar year in accordance with.the methodology and parameters in_ the 00CM at least every 31 days,-
- 6) Limitations on _the operability and use of the -liquid and gaseous. -
ef fluent treatment systems- to ensure that _the- appropriate
~
portions of these systems- are used to reduce releases of radio-activity when- the projectid 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 P_ art 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 8, Table II, Column 1 en d 4
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r ADMINISTRATIVE CONTROLS 6.8.4 e. -Radioactive Ef fluent Controls Program (Cont. )
- 8) Limitations on the annual and Quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
- 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC f rom lodine-131, lodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix ! to 10 CFR Part 50, ao
- 10) Lie!-tatia-c er veetf g :-d pu ;ia;,ef the ":9 !! cent:! :mt thret;h th: St:ndt3 C:: T r::tr:.t Sy:te: te ::fntc h rei::::3-
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)() Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
p, Radiological Environmental Monitorino Program 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 ef fluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the ODCH,
- 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 Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance pro-gram for environmental monitoring.
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!N 3 E t*T~
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.14pThe Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT ** 6.9.1.X7The Semiannual Radioactive Effluent Release Report covering the oper-ation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The report shall in-ciude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in con-formance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. YlAct, os borro m f pao.s-M A *"% SHsehe m .ar 4. t. j,c n y to . 9. t. 7
*A 5 ingle submittal may be made for a multi-unit station.
** A single submittal may be made for a multi-unit station. The submittal shculd combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall sper.ify the releases of radioactive material f rom each unit.
e i
INSER1 5 ) f
- o. kicords of reviews performed for changet eiade to the OFFSITC DOSE CALCULATION MANUAL and the F'ROCESS CONTROL F'ROGRAM.
INSERT 6 6.13.1 Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2o. This documentation shall contain:
- 1) Suf ficient information to support the change together with theand, appropriate analyses or evaluations justifying the change (s)
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Tederal, State, or other applicable regulations.
- b. Shall become effective after review and ac::eptance by the Onsite Review and Investigative Function (Onsite Review).
INSERT 7 6.14.1 Changes to,the ODCH
- a. Shall be documented ar.d records of reviews perf ormed shall be retained by Specification 6.10.2o. This documentation shall contain:
- 1) Sufficient information to support the change together with theand, appropriate analyses or evaluations justifying the change (s)
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CTR 20.106, 40 CFR Part 190, 10 CTR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of offluent. dose.
or setpoint calculations.
- b. Shall become effective after review and acceptance by the Onsite Review and Investi; so Function and the approval of the Plant Manager on the dat, upecified by the Onsite Review and Investigative Function.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the Each report in which any change to the ODCH was made ef fective.
change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. 1
'TACWENT C EVALUATION Of SIGNIFICANT HAZARDS C0ltSIDERATION
{ Evaluation of this proposed amendment has resulted in the determination that it involves.no significant hazards consideration. According to 10CFR50.92(c), a proposed amendment to an Operating license involves no significant safety hazards consideration if operation of the facility in accordance with the propo;ed amendment would not:
- a. Involve a significant increase in the probability or consequences of !
en accident previously evaluated; or l
- b. Create a possibility of a new or different kind of accident from any j accident previously evaluated; or c, Involve a significant reductton in a margin of safety. l
- 1. The proposed changes only alter the format and location of procedural i details and administrative controls of the radioactive effluents. !
radiological environmental monitoring and solid radioactive waste j programs. The changes are administrative in nature and do not involve ! any change to the configuration or operation of plant equipment. The ! Radiological Effluent Technical Specifications (RETS) procedural details i are being moved to the Offsite Dose Calculation Manual (ODCM). the j Process Centrol Program (PCP), and in duplicate form to the Station i Administrative Technical kequirements. However, the contents of the ' RETS are not being changed. The, purpose of the RETS is-to assure that the proper controls for the radiological effluent system are in place. The programs containing the procedural details of RETS will continue to perform the same functions. Any future changes to the programs containing the RETS procedural details would require an Onsite Review and Approval. Therefore, the RETS will continue to receive a high level of consideration even though they will no longer be part of the ' Technical Specifications. All the current provisions of the RETS are
-being retained, so none of the assumptions used in the accident analysis s will be affected. !Jastd on this evaluation, we have determined that the i changes do not affset the probability or consequences of.a previously I evaluated accident.
- 2. The procedural- requireNnts of the RETS will be maintained in the 00CH, '
PCP and-Station Admints'trative Technical. Requirements Book. Operation
- of-the plant will not be altered by the changes proposed to the j admitdstri.tlon of the RE15. -This change will not place the plant in any ;
new condition or introdece any mode of operathn not previously ; analyzed. Therefore, this change w111 not c.vate-the possibility of a ' L new or different kind of accident from any accident previously evaluated. 7
- 3. The proposed changes relocate the procedural details and' bases of RETS !
from the Technical Specifications to the f CH or PCP. The RETS ! l procedural details and bases will be maintained by these programs. l l Changes to these programs will require an onsite review. In addition, ; i I new administrative controls have been added to the Technical i Specifications which assure the proper control and maintenance of these , I documents and provide an equivalent level of assurance that activities involving radioactive effluents, solid radioactive waste, and , radiological environmental monitoring are conducted in full compliance with regulatory requirements. Therefore, there is no reduct4on in the L , margin of. safety. ZNLD/651:23 __ _ i
AUAC91LNLD ENVIRONHLM1ALASSESSHLMI The proposed Techhtcal Specification amendment involves several changes. CECO has evaluated the proposed amendment against the critet ta for and identification of ,1 censing and regulatory actions requiring enviroivnental assessment in accordance with 10CFR51.21. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided for under 10CFR51.22(c)(9) and (10). The following is a discussion of the chani,es and how they meet the criteria for categorical exclusion. This amendment request meets the criteria specified in 10 CFR 51.22(c)(9) because the following specific criteria are met: (1) the amendment involves no significant hazards consideration, As demonstrated in Attachment C, this proposed amendment does not involve any significant hazards considerations. (11) there is no significant change in the types or significant increase in the amounts of any effluents that my be released offsite, This amendment is administrative in nature and involves only the format and location of procedural details and administrative controls relative to radioactive effluents. No changes to the actual methods of controlling and monitoring of radioactive effluents are made by this action. Continued compliance with regulatory requirements relative to radioactive effluents is assured by specific administrative controls which are added to the Technical Specifications. Therefore, there will be no change in types or increase in the amounts of any effluents released offsite. (111) there is no significant increase in individual or cumulative occupational radiation exposure. This proposed change will not result in changes in the operation or configuration of the factitty and, as discussed above, there will be no change in the level of controls or methodology used for processing of radioactive effluents, handling of solid radioactive waste, or radiological environmental monitoring. Therefore, there will be no increase in individLal or cumulative occupational radiation exposure resulting from this change. The proposed changes for RETS procedural detail relocation and redefining the OOCH and PCP are provided for in GL 89-01. They meet the categorical exclusion criteria as provided under 10CfR51.22(c)(10) - (i1) changes recordkeeping, reporting, or administrative procedures or requirements. The proposed change relocates the RETS to the ODCH or PCP but does not change the surveillances and limitations and all regulatory conditions are maintained. i ZNLD/651:24 _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ -}}