ML19276H799
| ML19276H799 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/31/1978 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19276H800 | List: |
| References | |
| NUDOCS 8004280412 | |
| Download: ML19276H799 (100) | |
Text
{{#Wiki_filter:. . . . . - . . _ . . _ _ . ._.. ___ s l if p, .L t re;enair THIS DDC!JMENT CD:!TAINS en7s. - POOR QUAUTY PAGES
. DEFliMTIONS f.. - -.
- TIC" 3IHIS DOCUMENT CONTAINS PME POOR QUAUTY PAGES 1.0 DEFINITIols.
1.1 Ac 10N............................... ................... 1-1 1.2 AVERAGE PLANAR ExF05UnE.................................. 1-1 1.3 AVERIGE FL ANAR LIN EM HEAT G ENERATIG: RA E. . . . . . . . . . . . . . . 1-1 1.4 CHANNEL CALIBRAT101...................................... 1-1 1.5 CHANNEL CHECK........................................... 1.- 1 1.6 CHANNEL FUNCTIONnt TEST.................................. 1-1 1.7 CORE ALTERATI0".......................................... 1-2 1.8 CRITICAL PCUER PT.TIO....... ........... ................. 1-2 1.9 DOSE EQUIVALENT 1 131.................................... 1-2 1.10 Pr,. I n,,m . . c _m. ... , ., . m 010.,x.,sn
. m- co m.- ,w. 1w.,...............
1,- 1.11 E MERGENCY CORE COCLIN3 SY STU' (ECCS' RESPONSE TIME. . . . . . . 1-2 1.12 FRfQUENCY N0TATION............,........................... 1-3 (' . 1.13 I D E N T I F I L D LE AM /2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.14 I LOL AT I ON SY STE M R ESPON 3 E T I"E . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.15 LIMITING CONTROL ROD PATTERN......... ................... 1-3 1.16 LINEAR HLAT GENERATION RAW.............................. 1-3 1.17 LOGIC SYSTEM FUNC110hAL TEST............................. 1-3 1.18 MA/.lMUM TOTAL PEAKING FACT 0P............................. 1-3 1.19 MINIMUM CRITICAL PCL.'ER RAT 10............................. 1-4 1.20 OPERACLE - CPERASILITY................................... 1-4 1.21 CeERATIONAL CONDITION.................................... 1-4 1.22 PHYSICS TESTS............................................ 1-4 1.23 PRESSURE PCUNDARY LEAKAGE................................ 1-4 1.24 FRIMARY CONTAINMENT INTEGRITY............................ 1-4 1.25 RATED THERMAL F0;ER...................................... 1-5 1.26 REACTOR PROTECTION SYSTEM RESPONSE TIME.................. 1-5 1.27 REPORTABLE CCCURRENCE.................................... 1-5 1.28 ROD 0ENSITY.............................................. 1-5 1.29 SECONDARY CONTAINMENT INTEGRITY.......................... 1-5
.3 s 1.30 SHUTDOWN MARGIN.......................................... 1-6 1.31 T H E RM AL P 0;! E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 8004aB04 ~
0 LSCS-1 i Octobe- 1973 N
..x._' s TABLE OF CONTENTS
i DEFIN!T10ftS (Continued)
SECTION PAGE 1.32 TOTAL PEAKli!G FAET0R..................................... 1-6 1.33 U N I D E N T I F I E D L E ARM E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6
- 1. 3 .i m a ca c o r.cn t - 0,
, , s p o r. r s , T r- resc C 4 ' c '* T""
-- w, .na s+e s.- s r-+ , . n wr r tx+v s s ' 'w n "f'% '
' . ' ' ~
l- v 1- u n SAFETY LIMITS AND LIMITIi;3 SAFETY SYSTEM SETTINGS _2.1 SAFETY LIMITS 2.1.) THERi%L PO'.lER (Loa Press ure or Low Flow) . . . . . . . . . . . . . . . . 2-1 2.1.2 THERMAL POWER (Hi;;h Pressurt and High Flo'.t)............. 2-1 2.1.3 Reactor Coo knt System Pressure......................... 2-1 2.1.4 Reactor "essel Weter Level.............................. 2-2 2.2 LI!ilTING SAFETY SYSTEM SETTlMS 2.2.1 Reactor Protection System Instrumentation Setpoints..... 2-3 & - BASES __ 2.1 SA ETY LIMITS 2.1.0 G E l l E R AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 2-1 2.1.1 THERIML POWER (Low Pressure cr Low Flow)................ B 2-1 2.1.2 THERIGL POWER (High Pressure and High Ficw)............. B 2-2 2.1.3 Reactor Coolant Systcm Pressure......................... B 2-8 2.1.4 Reactor Vessel Water Level.............................. B 2-8 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Protection Instrumentation Setpoints............ B 2-9 LIMITit:G CONDITIONS FOR OPER ATION AND SURVEILLANCE REQUIREMENTS r, 3/4.0 APPLICABILITY........................................... 3/4 0-1 j LSCS-1 i: .Gs4chtr2978x'
.~ ...i.____.___ _ _ _ _ _
TACLE OF CC" TENTS D ,- L]MITING CONDITIONS FOR CEPPCIO" A'iD SURVEllLANCE REOUIREMENTS (Cor.tinued) PAGE SECTION 3/4.1 REACTIVITY C0iGRPt SYSTEMS . 3/4.1.1 SHUTDOW" MARGIN.................................. 3/4 1-1 3/4.1.2 R EACT I V I T Y AN 0M AL I E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-2 3/4.1.3 CONTROL RODS ' 3/4.1.3.1 Control Rod Operability.......................... 3/4 1-3 3/4.1.3.2 Control Rod Maxinun Scram Insertion Times........ 3/4 1-5 3/4.1.3.3 Control Rod Average Scram Insertion Times........ 3/4 1-6 3/4.1.3.4 Four Control Rod Group acram Insertion Times..... 3/4 1-7 3/4.1.3.5 Centrol Rod Scram Accumulators................... 3/4 1-8 3/4.1.3.6 Control Rod Drive Coupling............... ....... 3/4 1-9 3/4.1.3.7 Control Rcd Position Indication.................. 3/4 1-11 3/4.1.3.8 Control Rod Drive Housing Support................ 3/4 1-13 3/4.1.4 CONTROL ROD FROGR'li CONTROLS ( '3/4.1.4.1 Red Wocth Minimizer.............................. 3/4 1-14 3/4 1-15 5/4.1.4.2 Rod Sequence Control Systcm...................... 3/4.1.4.3 Rod Block Monitor................................ 3/4 1-17 3/4.1.5 STAP15Y LIQUID CONTROL SYSTEM.................... 3/4 1-18 3/4.1.6 ECONOMIC GENERATI0" CONTROL SYSTEM............... 3/4 1-22 3/4.2 POWER DISTRICUi!ON LIMITS 3/4 2-1 3/4.2.1 AVERASE PLAN AR LINEAR HEAT GENERATION RATE. . . . . . . 3/4 2-3 3/4.2.2 APRM SETP01NTS................................... 1 MINIMUM CRITICAL PCWER RATI0..................... 3/4 2-4 3/4.2.3 3/4.2.4 LINEAR HEAT GENERATION RATT ..................... 3/4 2-6 3/4.3 INSTRUMENTATION 3/4 3-1 3/4.3.1 REACTOR FROTECTION SYSTEM INSTRUMENTATION. . . . . . . . 3/4 3-11 3/4.3.2 I SOLATION ACTUAT ION INSTRUMENTATION. . . . . . . . . . . . . . 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION 3/4 3-26 I N ST RUM E N T A T I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 3/4 3-39 fl) INSTRUMENTATION.................................. 3/4 3-43 3/4.3.5 CONTROL ROD WIT 4DRAWAL BLOCK INSTRUMENTATION..... LSCS-1 tii October i978 - - - - . - -____._..._m.._ . . _ . . _ . _ . _ . .
u _' - A"ENDq uT- 6 TADLE OF CONTE {_i
-d A$iU A r- 1979 LIMITING CONDITIONS FOR 01'ERATIC!1 AND SURVEILLA' CE REQUIREMENT 5 (Continued] ,_w SECT 10y PAGE 3/4.3.6 ym,e MONITr' RING INSTRUMENTATION 2 y-r e m W <H w B L ArJ K-3/4.3.6.1 A ReJ i et-4 cn- Mord cr._ing_.InctrumenM H-cM . . . . . . . . . . . . . 3/4 3-52 3/4.3.6.2 Seismic Munitoring Instrumentation............... 3/4 3-58 3/4.3.6.3 Meteorological Monitorir.g Instrumentation........ 3/4 3-61 3/4.3.6.4 Rcmote Shutdown Monitoring Instrumentation....... 3/4 3-64 3/4.3.6.5 Post-Accident Monitoring Instrumentation......... 3/4 3-67 3/4.3.6.6 Sou rc e R an g e Mo n i t or s . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-70 3/4.3.6.7 Traversing Incore Prcbe System................... 3/4 3-71 3/4.3.6.8 Chlorine Detection Systems....................... 3/4 3-72 3/ 4. 3. 6. 9 Fire Detection Instruner.tation................... 3/4 3-73 d. ,-
3/4. 3.6. / Q R.unoQ uisa L/G.w i D G r r: t u e . , r O ',O 5 T4
- rn rN m Ts c N 3/q 3_77 y 9 . 3 . (, . i i on n,e e cro c G0Su6 c rm e .<r asrm % % 3/4 3-3/4.4 REACTOR C00! ANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEN 3/4.4.1.1 Recirculation Loops.............................. 3/4 4-1 3/4.4.1.2 Jet PuTgs........................................ 3/4 4-2 p. ,
3/4.4.1.3 Idle Rccirculition i. cop Startup.................. 3/4 4-3 3/4.4.2 SAFETY /REL1EF VALVES............................. 3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 Leakage Detection Systems........................ 3/4 4-5 3/4.4.3.2 Operational Lcakage.............................. 3/4 4-5 3/4.4.4 CHEMISTRY........................................ 3/4 4-7 3/4.4.5 SPECIFIC ACTIVITY................................ 3/4 4-10 3/4.4.6 FRESSURE/ TEMPERATURE LIMITS 3/4.4.6.1 Reactor Coolant Systems.......................... 3/4 4-13 3/4.4.7 MAIN STEAM LINE ISCLATION VALVES................. 3/4 4-18 3/4.4.8 STRUCTURAL INTEGRITY............................. 3/4 4-19 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PR ESSUR E COR E SPR AY SYSTEM. . . . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION 5YSTEM................ 3/4 5-3 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS 3/4.5.3.1 Low Pressure Core Spray System................... 3/4 5-4 A LSCS-1 iv Jr - 1979
I Ih 0 TABLE OF CONTENTS U
.s !-
\'h pT' LIMITING CONDITIONS FOR OPERATInN AND SURVEI! LANCE REOUIREMENTS (Continued)
J l 6 SECTION PAGE t je Jp$ 3.4.10 SPECIAL TEST EXCEPTIONS b, >L, aJ , 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.................... 3/4 10-1
;/ 1 3/4.10.2 RCD SEQUENEE CONTROL SYSTEM...................... 3/4 10-2 2
' JF ii 3/4.10.3 SHUTDOWN MARGIt! DEMON ST RATIONS. . . . . . . . . . . . . . . . . . . 3/4 10-3
[ 3/4.10.4 R EC IR CU LAT I ON L00P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 n .,.s
,C ';=~-
n 0 'd f
~~
BASES Q u
-n 3/4.0 APPLICABILITY........................................ B 3/4 0-1 2 -- j 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHU T DOW N D' A RG I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-1 7f>
- s. y N B 3/41-1 mm , 3/4.1.2 R E ACT I V IT Y AN 0'i AL I E S . . . . . . . . . . . . . . . . . . . . . . . . . .
3/4.1.3 C0rlTROL R0DS.................................. B 3/4 1-2
- f. .) 3/4.1.4 CONTR0' RCD PROGR/.M CONTR0LS.................. B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM. . . . . . . . . . . . . . . . . B 3/4 1-4 3/4.2 P0'.!ER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION R/TE. . . B 3/4 2-1 3/4.2.2 APRM SETP0lNTS............................... 0 3/4 2-3 3/4.2.3 MIflIMUM CRITICAL POWER RATIO................. B 3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE.................. B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.......... B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.............................. B 3/4 J-2 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION IN STRUMENT AT ION . . . . . . . . . . . . . . . . . . . . B 3/4 3-2 3/4.3.5 CONTROL ROD WITHDRAWAL BLOCK I N STRUM E NT AT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-3 s
LSCS-1 vii ect be 1978
. . . . . ~ . . . . . . , - - - .
TABLE OF CONTENTS CASES (Continued) g _S_EC T I ON PAGE 3/4.3.6 MONITCRING INSTRUMENTATION Radi atio:. Monitoring Instrumentation. . . . . . . . . B 3/4 3-4 Seislic Monitoring Instrumentation........... B 3/4 3-4 Meteorological Monitoring Instrumentction.... B 3/4 3-4 Remote Shutdown Monitoring Instrumentation... B 3/4 3-4 Post-Accident Monitoring Instrumentation..... B 3/4 3-4 Sou rce R an ge Ibn i t ors . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Traversing Incore Probe System............... B 3/4 3-5 Chlorine Detecticn Systems................... B 3/4 3-5 Fire Detection Instrumentation............... B 3/4 3-5 n.0es.,% ii>c va,.o a=r ac~r mv s 1 c. ,.wrnr,- 3 - C-an-o s a n er
- n Grsceu c %c .n -ca sre n, <.,, ma,, Gg 3/9 u
y+ .% 3/4.4 REAC10R COOLANT SYSlE}' 3/4.4.1 RECIRCULATION SYSTEM......................... B 3/4 4-1 3/4.4.2 SAF ET Y/R EL I EF VAL VE S . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 p. 1 3/4.4.3 REACTCR COOLANT SYSTEM LEAKAGE Leak ag e Detec t i on Sys t c::s . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 Op er a t i cu l L e a k 2g e . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.4 CHEMISTRY.................................... B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY............................ B 3/4 4-2 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.................. B 3/4 4-3 3/4.4.7 MAIN ST EN1 LINE ISOLATION VALVES. . . . . . . . . . . . . B 3/4 4-8 3/4.4.8 STRUCTURAL INTEGRITY......................... B 3/4 4-8 3/4.5 EMERGENCY CORE CCOLING SYSTEMS 3/4.5.1 HIGH PR ESSURE CORE SPR AY SYSTEM. . . . . . . . . . . . . . B 3/4 5-1 3/4.5.? AUTOMATIC DEPRESSURIZATION SYSTEM............ B 3/4 5-1 3/4.5.3 LOW PRESSURE CORE COOLING SfSTEMS Low Pressure Core Spray System............... B 3/4 5-2 Low Pressure Coolant Injecticn System........ B 3/4 5-3 3/4.5.4 SUPPRESSION CHAMBER.......................... B 3/4 5-3 O. LSCS-1 viii -Oc4ober-19W
_ . . - . _ _ . ~ _ .._ TiBLE OF CONTENT 3
- f. C?If^.jContinoed[
t.r SECTION PAGE 3/4.6 COMA!N"EyT SYSTEMS 3/4.6.1 PRIMM Y CONIAIN".ENT Primary Containment Integrity................ B 3/4 6-1 Primary Centainnent Lcak5ge.................. B 3/4 6-1 Primary Containment Air Locks................ B 3/4 6-1 MISV Leas?ge Control System.................. B 3/4 6-2 Primcry Conteinment Structural Integrity..... B 3/4 6-2 Primr.ry Containment Internal Pre:sure........ 53/46-2 Prim ry Contcir. ment Average Air Temperature.. B 3/4 6-2 3/4.5.2 DEPRESSU112ATION SYSTEM 5...................... B 3/4 6-2 3/4.6.3 FRI"lSY 20NTAINENT ISOLATION VALVES. . . . . . . . . B 3/4 6-4 3/4.6.4 VACUU", RELIEF................................ 6 3f 4 6-4 3/4.6.5 SECOND/RY CONTAINMENT........................ B 3/4 6-5 3/4.6.6 CONTAI M ,ENT 'JMOSPHET E CONTROL. . . . . . . . . . . . . . . B 3/4 6-5 (..\ . 3/4.7 PLANT SYSTE"S 3/4.7.1 S E R V I C E W AT E ::, S Y S T E M S . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.2 CONiilCL ROOM E",EP,0ENCY FILTRATION SYSTEM. . . . . B 3/4 7-1 3/4 7.3 RET.CTOR CORE ISOLATION CDOLING SYSTEM........ B 3/4 7-1 3/4.7.4 SEALED SOURCE CONTAMINATION.................. B 3/4 7-2 3/4.7.5 FIRE SUPPRESS 10" SYSTEMS..................... B 3/4 7-2 3/4.7.6 PENETRATION FIRE BARRIERS.................... B 3/4 7-3 3/4.8 ELECTRICAL POWER SYSTEM 5............................. B 3/4 8-1 3/4.9 REFUELING CPERATIONS 3/4.9.1 R EAC T OR MOD E SW I TC H . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 I N STRUME N TAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 CONTROL ROD POSIT 10N......................... B 3/4 9-1 3/4.9.4 DECAY TIME................................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................... B 3/4 9-1 () 3/4.9.6 CRANE AND HOIST OPERABILITY.................. B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L......... B 3/4 9-2 LSCS-1 ix October 19/8
^
i 9 TACLE OF CONTENT _S. s N F '. O b n EASES [Cc:tinued)
.-- )
p ' SECTION PAGE l-
?
- u 5 n # 3/t. 9.8 and 3/4.9.9 .ATER LEVEL - REACTOR VES^EL
~; F AhD WATEh LEVEL - SPENT FUEL STORAGE FCOL.... B 3/4 9-2 L
d5J d 3/4.9.10 CONTROL RCD .EP.CVAL......................... B 3/4 9-2 9-
;3 3/4.9.11 REACICR CCOL/ST CIRCULATION................. S 3/4 9-2
'U : 1 ( kd 3/4.10 SDECIAL TEST EXCERT:CNS E ~/ ' 3/4.10.1 PRIMARY COWTAIh'ENT INTCGRITY............... B 3/4 10-1 o n-q -I $ 3/4.10.2 RCD SEQUENCE CONTROL SYSTEM................. B 3/4 10-1 s' , a e, if 3/4.10.3 SHUTDOW.N K EIN DEMONSTRATICN5.............. B 3/4 10-1 J q) J 3/4.10.4 RECIRCUL; TION LOOP 5......................... B 3/4 10-1 m
')
. , DESIGN FEATURES _ _
w , --
~ ~
. s 7?U p
-s s s s 5.1 S IT..t* .0
~/
0' "' ' ' 5.1.1 Exclusion Arca....................................... 5-1 5.1.2 Low Populaticn 2:ne.................................. 5-1 5.2 CONTAINMENT 5.2.1 Configuration........................................ 5-4 5.2.2 Dcsi gn Temperat ure and Pres sure . . . . . . . . . . . . . . . . . . . . . . 5-4 5.3 REACT 0n CORE 5.3.1 Fuel Assemb1ics...................................... 5-5 5.3.2 Control Rod Assemblies............................... 5-5 5.4 REACTOR COOLANT SYSTEM 5.4.1 Design Pressure and Temperature...................... 5-6 5.4.2 Volume............................................... 5-6 5.5 METEOROLOGICAL TOWER L0 CATION.......................... 5-7 ("s ,
.)
LSCS-1 x -Gettben-lW C
LIST Cr T~4C1."t n _D_E F I N I T I 0S 4s NUMBER FAGE 1.0 der 1NITIONS 1.1 Surve il l anct F req uercy Notation . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.2 Operaticnal Conditions................................. 1-8
. SAFETY LIMITS AND LIMITING !!. ETY Si3 TEM SETTIt;GS 2.2 LIM! TING SAFETY c. STEM SETTING S 2.2.1-1 Reactor Protection System InstruT.entation Setpoints.......................................... 24 BASES .
2.1 St,r e n .. v ' '.."u'~n c ( B 2.1.2-1 Unccriair.tiet Usec' in the Cetermination of the Fuel Cledding Safety Lirait....................... B24 B 2.1.2-2 Ncminal Values of Paremctccs Used in the Statistict) Analysis of Fuel Cladding I nteg r i t y S a f e t y L imi t . . . . . . . . . . . . . . . . . . . . . . . . . . . B 2-5 B 2.1.2-3 Relative Bundle Pct,er Distribution Used in the GETAB Statistical Analysis....................... B 2-5 B 2.1.2-4 R-Factor Distribution Used in the GETAB Statistical Analysis............................. B 2-7 LIMITING CONDITIONS FOR OPEP.ATION AL SURVEILt MCE REQUIRE'ENTS 3/4.3 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3.3.1-1 Reactar Protection System Instrumentation.......... 3/43-2 3.3.1-2 Reactor Protection System Response Times........... 3/4 3-7 4.3.1-1 Reactor Protection System Instrumentation Surve il l ance Req ui rement s . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-9 3.3.2-1 Isolation Actuation Instrumentation................ 3/4 3-13 I') 3.3.2-2 1 solation Actuation Instrumentation Setpoints...... 3/4 3-18 3.3.2-3 Isolation System Response Times.................... 3/4 3-21 LSCS-1 xii October 1978
. . ewe e w ger- we.
LIST OF TAELi1 LIMITING CO'lDITIONS FOR TERATIO'i /J;D SUR'!EILLANCE RECUIRE".ENTS (Ontinued)
-A NUMBER PAGE 4.3.2-1 Isolation Actuacion Instrumentation Surveillance Requirements.......................... 3/4 3-23 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation.................................... 3/4 3-20 3.3.3-2 Emergency Core Cooling System Actuatien Instruuentation Setprints.......................... 3/4 3-31 3.3.3-3 Emergency Core Cooling System Retpense Times....... 3/4 3-3" 4.3.3-1 Emergency Core Cooling System Actuation Instrumcntation Survcillance Requirements.......... 3/4 3-35 3.3.4-1 Reactor Core Isolaticn Cooling System Actuatico Instrumentation.................................... 3/4 3 40 3.3.4-2 Reactor Core Isolation Cooling System Actuation Instrumcntation 5etpoirls.......................... 3/4 3 41 4.3.4-1 Reactor Core Isolation Cooling System Actuaticn Instrumentatien Surveillance Requiremr.ets.......... 3/4 3-42 3.3.5-1 Control Rod Withdransl Slock Instrurentation....... 3/4 3-44 3.3.5-2 Control Rod Withdravtal Bleck Instruaentation (,
Setpoints.. ....................................... 3/4 3 47 > 4.3.5-1 Control Rod ',lithdrav:al Block InstruT.entation Surveillance Requirer.cnts.......................... 3/4 3-49 3.3.6.1-1 R adi at:cn Mon itoring Instrument ct ion. . . . . . . . . . . . . 3/4 3-53 4.3.6.1-1 Radiation Monitoring Instrumertation Surveillance Requirements........................ 3/4 3-56 3.3.6.2-1 Seismic Monitoring Instrumentation............... 3/4 3-59 4.3.6.2-1 Seismic Monitoring Instrumentation Surveillance Requirements..................................... 3/4 3-C0 3.3.6.3-1 Meteorological Monitoring Instrumentation........ 3/4 3-62 4.3.6.3-1 Meteorological Monitoring Instrumentation Surveillance RequireTents........................ 3/4 3-63 3.3.6.4-1 Remote Shutdown Instrumentation......... ........ 3/4 3-65 4.3.6.4-1 Remote Shutdown Instrumentation Surveillance Requirements..................................... 3/4 3-66 3.3.6.5-1 Post-Accident Monitoring Instrumentation......... 3/4 3-68 4.3.6.5-1 Post-Accident Monitoring Instrumentation Surve il l ance Req ui remen t s . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-69 3.3.6.9-1 Fire Detection Instruments....................... 3/4 3-74 ('N., w LSCS-1 xiii October 1978
-.'.,-.1,-..- - . - - . . - LIST OF TACLES LIMITIN3 r.ONDITIONS FOR CPER ATION /ND SURVEILLANCE REQUIREMEt;TS (Cov inued[ NUMBER PAGE 3/4.4 REACTCR COOLANT SYSTEM
~
3.4.4-1 Reactor Coolant System Chemistry Limits............ 3/4 4-9 4.4.5-1 Primary Coolant Specific Activity Sample and Analysis Program............................ ...... 3/4 4-12 4.4.6.1-1 Rcactor Vestel Materici Irradiaticn Surveillance Schedule......................................... 3/4 4-17 3/4.0 CONTAINMENT SYSTEM 5 3.6.3-1 Primary Containmcr.t I sol a t i on Val ves . . . . . . . . . . . . . . . 3/4 6-19 3.6.5.2-1 Secondary Contair.. Tent Ventilation System Automatic Isolatien Dampers...................... 3/4 6-31 3/4.7 PLANT SYSTEM 5 3.7.5.2-1 Spray / Sprinkler Systems.......................... 3/4 7-15 3.7.5.4-1 Fire Hose 5:ations............................... 3/4 7-19 (A BASES . . _ _ 3/4.4 REACTOR CODLA.NT SYSTEM B 3/4.4.6-1 Reactor Vessel Toughness....................... B 3/4 4-5 DESIGN FEATURES 5.7 COMP 0ENT CYCLIC OR TRANSIENT LIMIT 5.7.1-1 Component Cyclic or Transient Limits............... 5-10 ADMINISTRATIVE CONTROLS 6.6-1 Special Reforts......................... ............ 6-26 (~3, LSCS-1 xiv October 1978
r , x 1 E ! \ t
.i . L, .n. r. .., . .. ..i. m.
c
/
CH a ?mO. C ?J.
- M. " T !"V!
/
/
/
1.9 A CHAta;"L CALIERATION shell be the adjustment, es ne:essary, of try' vhannel cutput su:h t'.a t i s respor.c; wi th tne ne:essary range ar.: a:;c'r ecy tQnce velues of tre parreter wn:cn the channel monitors. Tre CM'dE'. CALI W 'I% rna'! em r po a t N cn'i e O m nai i :i;c t .: '.n e a' al a r - b.f o r trip fum tiers, and shall iaci sce tre CH N.iL y.[sMr
^TIOGL
. TEST. ,
The CHA!n.E!. N . Q ' !EF.;TICN may oc perf omed by any series cj 'secuer.tial , over- .
, lapping or totcl channel steps such that t.9e entire cgnel is calibratec.
ICH A!D'E'. CliECK i
'l.10 A ChA!P:EL CHECi sha'l 4 th? Cual i a ti .e a ss e:s: en c f :hannel b e- t havior during ocer3 tion t;v obs3%a'i,c[. Thi s de te r ,ina tic 1 snail i r c l u d ,'
wnere tcssible, ccccarisor of tnMnannel incic atior and/or sta tus ai th 3
.otner indicatiens and/or stat"/derN.d f r:c indor " <' nt in;trunen ta ti: n channel s mea ,uring tf e sama d r ane te r.
CHLUNEL FUN TIC!W. TEST l 1.11 A CHAN!: El. FUNCTIONAL TEST shall be: fh / af Analog channel s - the injection of a sinu'.ated sigh 1 into the channel as c1ose tc the sen:or as pratti:able to fy OPERAE:LITY including alam and/cr trip functions. g\s
- b. Bi stable channel s - the inj e: tion cf a sinu' ated signal ints ' N the sensor to verifv~ OPER ASILITY incWdinc alam and/or trlp N y / function:.
~
N N - x
!SCURCE Cl:ECK
- l . 3 X-WE9 A SOURCE CHECK shall be the qualitative assessment of channel ,
response wnen the channel sensor is exposed tc a radioactive source. q ' t g s 4 '\ iPRDCESS CONTROL PROGRAP ,'
/
- L20 A PROCESS CCNTROL P902AM (PCP) shall be the r.anual or set of /
ioperllingocedures detailirg the program of sampling, analysjs,'and
' eval ua tiva with h SOLIDIFICATION of radioactive waj'(from lice d s *e assure . equirements of the PCP areypdced in Specifi;3-iBWR-STS-1 -J-- -
N x 1,
} ~ lo L9
- x. s
.a .- .'..-. . - - - . -
,1.0 blF i t.1 T I Ct!" ( C o a t i nu e d 's g~
lj . ._.
., SCL H IFIL AT10'!
, I.
a- ~~.___ _ 51.31 SOLIDIFIC ATICh' sheil !4;.the Enversior cf radica:tive wa stes f ro-
~
i
'Ilicuid systems tt_2 ho .spinetus, menefithicy ir7:tili:ec solid witn ce- !
i j' finite vcatr:t inc shape, beunced by c s%Lle surfs:e cf-clietin:t % outline y- , ut.. it il sicts ( free.st anding). s ' ._l, _ i. __ o It i
; 0'T51TE DD5! CELCULLi!OP. t'.A!.9 AL IOD;M) t ,3 5 !
I' 'c h .: ; An OriSITE DO5E LAltULtT10N MAtJU.L (C E M) shall be e ranuci contain- ' l{ing the re thodelc; end pc-mete's to be used in the calculttien of o f f-
, sitt dcses due to recion:tivt gaseous a.7d liouic ef n uents and in tne
'!cciculation of caseousReevirenents an: licuit ef fluent Of theronitorineOZM are provice instrunentatier in cl erm/ trip setnoints.
. 5peci fi c a tion E.15. C. '/, l .
- !. i. .# . .
i . ? (,
' 9 A G A SE QU.: Rt.D '.ETE TREt.TMEh'i SYSTE" i s any syster cesi ned end in-
' s.t611ed tt reau:c riMic a:tive gesecus c f fluents t'y collecting primary cool ant syster of f gr..;es f rte the prir.arJ" s.yste and providin; f or dei c.v t
.or bolcup for thc puiTMe cf redu:ing the 1021 racioa:tivi ty pri or tL ;
.reiecse to th; envircrrent. _-
N. f*% V[L'TILtiRMrutUST iPEt,T"El:T SYSTEl', \ I.37 'N . : %p 7 r .v. .r. t;1 t. v. .: T r P. i5 er .2*..r_- d r c i . o. . en3 l
- 2. _... . c. A yr_ v..i n. .,a,7 . n. i r. y,.; r .,.
' installed t reas;E ta secus rel'it 40_di w or rj.P. c: live rete'ini in parti- )
I CUl f .e fC ' 4" C'G b t! t v Ce!! 4 nc Dr TN ' r 0" vert erhau!! c ? !- e !- triccuph ;har cci ersorMr! ' c n c.' t;MEIA # ilD ."'^ - the purpt se N rEn0'v i r - ! I itdines or ctrtituittes frj M h'i g e se ce s e x ha u s t s '. r. --- -i rior to t9e ,
, reie8sE tO tot Envi"Jr=~61. Su;n c syster i s fety n0 t creet on sre i t (EEr t re,,
- Q' .c '2 c steri:e E ry c'fect on n e t ' r'ed c f fi u a . Encinee ed\. .5?
- h. . .4 u s 4 L .,. :..K ri . u;
, , . . le:.r. e.it i. h.r.s-%
Cl e f fluf J.#~SP.s dr e fi:1 C C ELi 0e'"eC *C bt . : N' 5 Y SWc on o ne r t_f . , 1-i e l I i 8
! -Bi&9~ri- -+-E--
' LS C S -l l- G o n
- e. e 46
---pp m,
m 5 ._ TABl.E 1.1 SURVEILLANCE FREQUENCY NOTAT10,'l it0TATION FREQUENQ S At least once per 12 hours. D At least once per 24 hours. W At least once pec 7 days. M At least once per 31 days. Q At least once per 92 days. SA - At least cnce per 6 months. R At least once per 18 months. S/U Prior to each reactor stcrtup. P C o m en. c,a u Rwa ,o cn < " 'W' " O" N.A. Not applicabl?.
/
LSCS-1 1-7 October 1978 i
** * *~~*"*** w c w -eg.aers.g w. m .-..-.e e .% . -.=g===.--..-e- w---..- ~ * - -
. . s ~7 1.--........ .. . _ _ _ _ _
r= , TABLE 1.2 OPERATIO!;AL C0';DITIO 5+ f40DE S'.' ITCH AVEkAGE REACTOR CONDITION POSITIOff C00LA':T TEMPERATURE
- 1. PCWER OPERATIC!; Run Any temperature e
- 2. STARTUP Startup/ Hot Standy Any temperature
- 3. HOT SHUTD0', n Shutdown > 212 F
- 4. COLD SHUTDO.-:M Shotdtn- n 1 212 F
- 5. REFUEll%* Re fuel *
- 1 212 F
,~
4With no fuel in the reactor vessel, the requircments of these operational conditions are not applicable. A
- Reactor vessel head unboltcd cr removed and fuel in the vessel. '
**See Special Test Exception 3.10.3.
1-8 October 1973 i LSCS-1
- AtiENDMENT +P 'IO eAi,t AW 19D T ADLE 3.3.2-3 ISCLATION 5 /:TE.ti RESTO'OE TIPE TRIP FUNCT103 RESP 0"SE TIME (Seconds)j
- 1. PRIMARY C0!! Tali,"ENi ISOLATION
- a. Reactor Ves';el ',!ater Levc1 Lcw Low, Level 2, except MS1V's 1 13
- b. Drywnll Pressur:- - flich < 13
- c. liain Steam Lirie
- 1. Radiation - High'* 1 1.0*
- 2. Pressure - Low ~
< 13*
- 3. Flow - High 1 C. P
- 4. Reactor Vessel Watcr Level -
Low Low, Level 2 1 1.0*
- d. Main Steam Lint Tunnel Temperature - High NA e, Condenser Vacum - Lc t NA
- 1. liain Stcam Line Tunnel a T - High NA 9
Reactor Yessel Watcr Lrvel - Lou, Level 3 NA l
- 2. SEC0hDARY CONT AIN.ET ISOL ATION
- a. Reactor Cuildir:0 Vcnt Radiation - High** < 13
- b. Drywell Pressure - High 1 13
- c. Reactor Vessel 'eter Level - Lo,.', level 3 1 13 l
- d. Fuel Pool Vent Radia tion - liigh'* 1 13
*ls'olation actuation instrumentation response tirc.e.
** Radiation detectors are exempt from response time testing. Response time shall be measured at detector's output @the a, t first electronic component in the Cnanrici,
# Times to be added to valve movement times shown in Table 3.6.3-1 to obtain ISOLATIO!1 SYSTE!4 RESPONSE TIME for eacn valve.
O . Ta s a 3. 6.5.7 -I LSCS-1 3/4 3-21
## 2 I*
.=p ,gg, .m e q ,e,,, , . ,_.gmm,. m, p ..y g , , , , ,
- * ' 4% ppt & PM*6gew Sa w
AMEiC"ENT 41 JANUARY 1979 TABLE 3.3.2-3 (Continued _), ,_ ISOLATION SYSTEM RESPONSE TIME TRIP FU"CTIO" RESP 0"SE Tii'.E (Seconds)
- 3. REACTOR UATER CLEANUP S'rSTEM ISCLATION
- a. 6 Flow - High 1 13*
- b. Heat Exchangcr Arca Temperaturc - High NA
- c. Pump Area Temperature - High liA
- d. Hect Exchanger Arec Vcntilation a T - High NA
- e. Purp Area "entilation a T - High NA
- f. SLC5 Initiation tiA
- g. Reacter Vestel Water Level - Low Low, Level 2 1 13*
- 4. pef.CTOD CORE ISOLATION CCOLING SYSTEM ISOLATION
- a. RCIC Steam Lir.e Flow - High 1 13*
li. RCIC Stcan Supply Pressure - Lc',' < 13* OT ..
- c. RCIC Turbine Exhaust Diaphregn Pressure - High NA
- d. RCIC Equipment Room Temperature - High NA
- c. RCIC Steam Line Tunnel Temperature - High NA
- f. RCIC Steam Line Tunnel a T - High f4A l
- g. RCIC Equipment Roca '. I NA
- 5. RHR STEl" CONDENSING SYSTEM I5OLATION
- a. RHR Equipment Area L T - High NA
- b. RHR Arca Ceoler Temperature - High NA
- c. RHR Heat Exchanger Steam Supply Flow - High f1A
- 6. RHR SUUTDOWN C00LlilG SYSTEM ISOLATION
- a. Reactor Vessel Water Level - Low, Level 3 1 13* .
- b. RHR Pump Suction Pressure - High NA e
- c. RHR Pump Suction Flow - High flA _.
LSCS-1 3/4 3-22 January 1979
IllSTRUMLI1T AT IC:1 O . StlRVEll tAflEE F.EMILEl'ErlT5 (Continued) 4.3.3.2 LOGIC SYSTEM FU CTIO:DL TESTS and sirr.ulated at tomatic operation of all charinels shall be pcrfarrred at least once per 19 months and shall include calibration of tir.e delay relays and timers nec essary for proper functioning of the trip system. 4.3.3.3 The ECCS RESP 0tiSE Tli1E of each ECCS function shall be derronstra-ted to be within the limit at least once pcr 18 months. Each tcst shall include at least ene logic train such that both logic '. rains are tested at Icest once per 35 months and one channel per function such that all channels are tested at least once every fi tin es 18 months where ti is the total number of redundant chanocis in a specific ECCS function. m. e, O: LSCS-1 3/4 3-27 October 1978
I
, , l.
i , ! ?- I ! r-3 TABLE 3.3.3-1 u
~
EMERGE!:CY CORE C00LIf1G SYSTEM ACTUATION INSTRUMENTATION MittIMUM ':U'1BER APPLICABLE ' OPERABLE CliAtitiELS OPERATIONAL PER TRIP SYSTEM ** CC!DITIONS_ , TRIP FUNCTION l l 4 l i 1. DIVISION I TRIP SYSTEM i 4 A. RiiR-A (LPCI MODE) & LPCS a' 2 1,2,3,4,5* j a. Reactor Vessel Low Water Level-level 1 2 1,2,3
! b. Drywell Pressure-liigh 1 1,2,3,4,5*
- c. LPCS Pump Discharge Flow-Low (Cjpass) d,to
- d. LPCS Injection Valve Differential Pressure-Low 1,2,3,4,5*
i
! Dh (Permissive)
LPCI-A Injection Valve Differential Pressure-Low 1
'f3 w e. 1,2,3,4,5*
l, (Permissive) 1 1,2 ,3,4 ,5
- i 1
- t. RiiR Pump A Start Time Delay Relay 1,2,3,4,5*
l t; RilR Pump A Flow-Low (Bypass) 1 j m 9 2 1,2,3,4,5* I h. , Division I Bus Power Monitor , B. AUTOMATIC DEPRESSU9IZATICN SYSTEli ( ADS)*** I a. Reactor Vessel Low Water Level-Level 1 2 1,2,3 l 2 1,2,3 I b. ReactorVesselLowWagyLevel-Level 3(Permissive) 2 1,2,3
- c. Dry'eell Pressure-liigh 1 1,2,3 R d. ADS Timer 2 1,2,3 g e. LPCS Pump Discharge Pressure-liigh (Permissive) 1,2,3 2
Rl!R Pun'p A Discharge Pressure-liigh (Permissive) { f. G j M
'e
.3 v
) b
~~-
] \ s'
-LIST OF FIGURES m LIfiiTItig, CONDITIOT 5 FOR OPEPATIOi! AND SURVEILif,7lEE REQUIREME;;TS PAGE glB E R 3/4.1 REACT IVITY CO'iT_R_O_L SYSTEMS 3.1.5-1 SBLC Tant Tempcrature/Cencentration.. ..... .... . 3/4 1-20 3.1. 5- 2 Saturation Temperature of Sod .r: Pentaborate Solution............ .............................. 3/4 1-21 3/4.2 P0i!ER DISTRIUUTI0t! LIMITS 3.2.1-1 Maximu0 Average Planar Lir. ear Heat Generation Rate Versus Average Planar Exposure................ 3/42-2 3.2.3-1 Ccre Floe., Percent of Rated Core Flow.............. 3/4 2-5 3/4.4 PE/fTC1 C01L ANT SYSTEi' 3.4.6.1-1 Minimum Temperature For Mechanical Heatup or Cooldo.cn following Nucler Shutdwn.............. 3/4 4-14 3.4.6.1-2 Minimum Temperature For Core Operation (Criticality).................................... 3/4 4-15 i,
3.4.6.1-3 tiinim:ra Tempe eture Fer Pressure Tests As Required Dy Section XI........................ 3/4 4-16 BASES 3/4.3 INSTRUMENTATION B 3/4.3-1 Reactor Vessel Water Level.............. ..... B 3/4 3-7
' 3/4.4 REACTOR C00! ANT SYSTEM B 3/4.4.0-1 Fast Neutron Fluence (E > 1MeV) As a Functicn C 3/4.4-6 of Pov.er Service Life..........................
B 3/4.4.6-2 Effect of Fluence and Copp2r Content of Shift For Reactor Vessel Steels Exposed to of RT.,Uy B 3/4.4-7 550' P Temperature............................. DESIGN FEATURES t9 s.1 SITE 5-2 5.1-1 Exclusion Area....................................... LSCS-1 xv October 1973
- ~ ~ . . - . , . - . ~ . - , . ~ . . . . - . - . . - . . . . . . . . . . . . __
LIST OF FIGURE 5 U[5IGN fLATUDIC ({vit i nioid '; fiUMBET PAGE 5.1-2 Low Forulation Z0ne.................................. 5-3 ADM IN I STP. AT P.'E CONTkOI.5 6.1-1 Offsite Organization. ......... . ... .............. 6-12 6.1-2 Unit Organization.. ... ............................. 6-13 6.1-3 Itinimu, Shif t Manning Cha rt. . . . . . . . .......... ... .. 6-la f%. .
)
m s. LSCS-1 xvi October 1978 - - - - - - - . ~ . - . . -. . ~ . . _ . . . . - - - - _ - . - . . . . - - ..
/JiEND"E!ii al JANUAfD 1979
% TABLE 4.3.5-1 (Continued) CONTROL f_00 WITHDDA'..'tJ. P. LOCK It:SiiT:'ENTTTION SURVEILL ANCE RE0 fl0T Ec -
- a. fleutron detectors nay t'e excluded fron CHAhNEL CALIBRATION.
- b. Within 24 hcurs prior to startup, if nct pcrforn ed within the previou: 7 days.
- c. When chargirg frcm CONDITION 1 to CONDITICh 2, perform the required surveillance '. i thin 12 hours af ter entering CONDITION 2.
- d. When THERI'.AL PCWER cxcech the preset power level cf the R':M and RSCS.
- e. With any control tod withdrawn. Not applicable to control rods re. roved per Specification 3.9.10.1 or 3.9.10.2.
- f. Physical inspr ction ar.d actuation of position switches.
i i ! O January 1979 LSCS-1 3/4 3-51 ~- - -. - . . - _ . . . _ _ . . . .
I f1ST_P U_ '1E NT /.T ! M
\1/4.3.6 f'.ONITCP lhG INWU' r' it,iION . \
R/S! ATION l'.'"i! TORI! G INSir..T;T AT!M f'e g'/ rf' .h&C _'a
\ 7 N
Lit!!TI.;G CONDITION f M GPET:ATION e [m .x c r. a ,- 3.3.6.1 Tbdvadiation Tonito-ing instruir.entaticn channt',s shown 'n Table 3.3.C.1sl shall be OPERAELE with their al;rm/ trip setpoint within the specified limits N APP L I C A C I'. Il Y : A's shun in Table 3.3.6.1-1. ACTION: t* R
- C M '
- a. L'ith a/rediak'on monitoring instrumentation hconel alar-'/ trip setpoint exceeding the value shown in Table .3.6.1-1, adjust the setpoint to Nitnin the limit within 4 60urs or declare the channel inopc}elle. \
p v eg. t ',
- b. L'ith one or rncre/;'adiation menitoring. channels incperable, take the /,CTION required by T &'e 3.5.6.1-1.
The provisions of Specift
/
N aticns 2.0.3 and 3.0.4 are not c. applicable, g r, SUR','FILLANCE REQUIREMENTS
\ _ , _ . _ _ _
4.3.6.1 Eachoftheaboverequircdradiationvgnitoringinstrumentation channels shall be der..cnstrated f>PERABLE by the grform:,nce of the CHANNEL CHECK, CHANNEL FUNC110hAL TEST'and CHI!,NEL CALICTi.TIO,'< operations during the OPERATIOM;L CONDITIO*iS a,n'd at the frequencies .ho<cn in Tctie 4.3.6.1-1. A
\
LSCS-1 3/4 3-52 Ac4cbedW , . , . . . . - - - - - . . . . - - - . . - - - - - - - - - - - - - - - - ~ -
~ ~--- :
') ')
'- b _ _
l / *$ i '
/ t l
r-1ABLE 3.3.6.1-1 } M I T
~ PR.0< E5 3 RADI AT10i1 MGT1TTOR:t;G IttSTRUMEriTATIOTI i
' Ml"?MUf1 APPLICABLE CH.GilELS OPER ATIOTML ALARM / TRIP MEA %9EMEriT ,
/Rf!;3E ACTIOT; .'
i DPERABLE C0i;D ' T IOliS SETP91tJT It4STRUME!1TATI0tl
-1 6
[ 10
\ 1
* -10
~~~~ cn
- 1. L vaunt-6 Effluent Monitor 1 6 S1 All I N tLcu
- 2. Service Water
% C ittor j
/ __
10-I-10 0cps 51
; 1 3. Reactor t?uilding Closed 1 All Cooling Water Monitor '
10'fcps
. ~L n Nm ervice Water 2 'Y 10 l
Effluent nu ;ter Y 10-1-10 cps 6 S ' 51
/
- 5. Station Vent Stack 1 ~
Radiation Monitor i All
' 6. Stan@ySmii eatment N ein Rad. Monitor 10 -2,;g rR/hr 2
51
' 2. /. Reactor Building Vent 3 All Mon itor 2
3 All 20 mr/hr 10"R0 rr.a/hr 51 %$
$ 3 X. ruel Pool vent Unitor SU d 5 pi E' _3 e.
2 . I l t,, l t c G
, '52, N-i Cx 1.
/ .
r- ', M TABLE 3.6.1-1 (Conti.ued) f T
~
- Prto o s s RAnlaTIO: MoNIT0"tNG INsTRuMEriTarte:1 NIfilMUM APPLICAPLE CliArtilELS OPERATIO :AL ALAR 1/ TRIP MEASURG1ENT OPERABt.E C0t:DIT IO 15 SETr01:1T 4ANGE ACTION INSTRUMENTAT f0!l I Off Gas Post 2 1,2
-I
-105cpg 37 4 P'.
Treatment R0d Monitor p l
$ Iff. Control Roor$ liVAC \3 All [ 53 Intake Pipj Monitur a
l 6 }4'. Area Monitors 2 G R a. Refuel Floor liigh 1
*' 10 -10 mR/hr 54 Range Monitor ,
Wo ' 2 E b. Refuel Floor Low 1 **> 10 '-10 mR/hr 54 l' Range Monitor
- c. tiew Fuel Storage Vault Monitor 1[ **>
N -1 10 -10 mR/hr 54 l 10~ -10 mR/hr 54 l d. Control Room red 1 All Monitor <t.
?
G K, l .-- i 'f, ' '. . . t . . , . m i i m c. ; t i , ; .;st: t r -J .y 'c c nm-ebehag.w!-f-rem-We-redieaet4e-1-iqu ; j u% vw wcnw
" Witti fuel in the new fuel storage area or the spent fuel storage pool.
Q*/ s C
$ m?x I 'cA
(
* /
/N s / /,
\ f/
0 /S Bl P TABLE 3.1.6.1-1 (Continued) P5'CCCSS R ADI ATION '",N1 TORIN3 INSTRU!'ENTATION ACTION
~
~
ACTION W' 4 required monitor inorcrable, ta M .d.m
'twa4thdhq_05i indep cnt-seplqs_ni_ ccc4Me dischap g @e tcnk to beg.charWTi& to 7elns%~W.i_t_h the [equired NET ~ter incperable f or > 72 hours, suspcE 01+csc.nf'
- \ liquid rad taste. -
~~
N ACTION 51 - With the required proccss monitor bl inc; p/ e, obtein and analyze grab sampics of the monitored arameter ct icast c.nce pet 24 hcurs. ACTION 52 - With oncs of the rccuired monitors .noperabic, operatien may continue provitd that the ir,o;e able monitor is placed in h e tripped conditio dwithin one hour. With both of obe required mo4 itors inoperable, be in at least HOT SH'JTDC'.,N within 12 hours. ACTION 53 - With cne of the rcquired / N monitors incperable, operation Ih may continue ;'roviced Ihat the inoperaDie channel is j placed in the trippc]J's condition within one hour, restcre the inoperable chtni.cl'\to OPERAELE status witt.in 7 days, or, within the nc>( 6 hNrs, initiate and maintain cperation of the/ con'rol 'rton y emercency filtration systEn in the (press .zation) mod' of cperation. With both off the required ec . ors incperable, initiate and maintain r cration of the de, trol room emer;cncy fil-tration pistem in the (pressurih tion) mode of operaticn within one hour. ACTION 54 - < he required manitor inoperable, perform area surveys With,he of ,t monitored area with portable r.c'ritoring instro-mNitation at least once per 2a hours. O
)
LSCS-1 3/4 3-55 October 1978
/ .
l
/ -
r-3 M TABLE 4.3.6.1-1 7 Y'
" RADI ATIO!1 M0tilTCRIf;G ItlSTRUPErlT ATIO:1 SUR'/EILLAt;CE REQUII'EMEf4TS OPERATIO:iAL CHA!itlEL CO?;DIT10i15 Iti CHN! lEL FUf;CTIOiAL CliAi; tie W!!!CH SURVE!LLA:;CE CALIE MTIOTi j
FUt4CTIOT:AL TEST \ CHECV TEST REQUIRE 0
~
1 n : r
- 2. Service Water D '1 R N
- . . u. e n Menitor _
{ All i i /. Reactor Building Closed D M R j R' Cooling Water Monitor M R A C ervice Water D
$ Efflu h te ! 5. Station Vent Stack ( M R All Radiation Moriitor l
vn Rc !! r +o _ D M R All {* 2 7. Reactor Building)'c fionitor b S R All E 3 g. Fuel Pool Y nt Monitor D M 1 5, 1 I 5 s c A3
%NA i }*h
- 1. ) .
o
) -
1
e 4 }Go TABLE 4.3.6.1-1 (Continued)_ L P g. CC 5 RADI ATI0tt M0filTORIriG Ir;STRUMEllTATIO!1 SURVEILL A!!CE REQUIREME';TS t OPERAT101AL 4 CHAll.JEL CCriDITIO :S It1 ! FuriCTIO;lAL CHA!;tiEl K!!ICil SURVEILLAriCE
' CHNi?iEL REQL!1rD CHECK TEsr CALIBRAF 0.l FUtCTI0 rial TEST /
f t 1,2 D M R y/f. Off Gas Post
- Treatment Rad. Monitor
/
} M R Al1 D
', 5 16. Control Room IIVAC Intake Rad. I'onitor I
! (o 6. Area Monitors I
E M R
- W*/
a a. Refuel Floor liigh ' D
; y Range Monitor C M R *t <)
l* b. Refuel Ficor Lovt 1 Range Moriitor M R t .
- c. r;ew Fuel Storage D
- Vault Monitor M R All J D j d. Control Room Rad.
Monitor SU
\ E5 4 Si n_t4_.-1-m,.m ,1- ~,-- s, -a c,.. c;
.:._. t. :tcc a 1 , . t < ; n , eee.c < r_-te-
!2 2 .z c.;:. ..u NWithfuel -
the new fuel storage area or the spent fuel storage pool. w n qY
! %\
IN STRUtiE!.'I AT ION SEI SP,!C f'01 ToiING I!!STRUENTAT 1_0N )
-LU1ITING CONDITION FOR OPERATION 3.3.6.2 The seismic moni'.oring instrumentation shcwn in Table 3.3.6.2-1 shall .e OPERABLE.
APIL I C. . ITY: At all times. ACTIC',:
- a. With one er rr. ore seirr,ic monitoring instruments inoperable for more than 30 days, in lieu of any other report requi ed by Specification 6.6.B, prepart and submit a Special Report to the Comissico pursuant to Specification 6.6.C within the next 14 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERA 5LE status,
- b. The provisions of 3pccifications 3.0.3 and 3.0.4 are not applicable.
SURVEllLANCE REOUIRO/,rNTS A 4.3.6.2.1 Each of the above re;uircd Leismic monitoring instrumenti shall be demonstrattd OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL Ct,LIBRATION opcraticns at the f re-quencies sho..n in Table 4.3.6.2-1. 4.3.6.2.2 Each of the above required seis:.ic monitoring instruments actuated duririg a seisr:ic evcnt shall be re:.tored to OPERASLE status within 24 hcurs and a CHANNEL CALIBRATICN performed within 5 days fol-lo. zing the seismic event. Data shall be retrieved from actuated instru-ments and analyzed to determine the magnitude of the vibratory ground motion. In lieu of any other report required by Spccification 6.6.B, a Special Report shall be prepared and submitted to the Co mission pur-suant to Specification 6.6.C within 14 days describing the magnitude, frequency spectrum and resultant effect.upon f acility features important to safety. A LSCS-1 3/4 3-58 October .978
N' , N -
/
.x.x. s ,
/
\ .
[-
#'S J
T A5l.E 1./ I rOeveiunum FREPUE!:CY NDir.TIDN I REQUE r:CY NOTAT1Cr?N 5 A . east once per 12 hours. D At least once per 24 nours. W At least cr.ce per 7 days. l'
\
At 1 ast oncc per 31 days. Q At icest .ce per 92 cays. (, , n ., v 4 s SV At least ontt g -H - c+y w R At least on:t per le ths. S/U Prior to each reactor str4.
~
P Completed Prior to each releast'.s N en
'~
f?. A. liot applicable. N
/ s
\
~ . _y e...
- - - . . . . . . . . . . . . . _ _ - = . . . - . . _ _ , ,
a.,...---. - - . - .
/
li It:5TauMENT ATICN c FAD 10tCTIVE LIOUID E ULUENT INSTRU"ENTATICS LIMITIMG CnUDIT!ON IOP OPEr'AT!CN 3.3.G>.10
--3 : 3.-35 The radio ac tive li cui e f fld'f.3.'c.10- 1 instru:,enta tion uent noni toring
. channel s shcwn in Ti bl e -3r -lVshall be OPEPACLE with their alarn/ trip setpoints set to en ure that the linits of Specification 3.11.1.1 are not exceeded.
APPLICADILITY- As shown in Tabl e -Br3-11 r-3.M.10 -l ACTICU: a. With a radiccctive liquid effluent nonitoring instru-menta tion channel al at.r./ trip se t;cint l ess conse' va tive than a value which will ensure that the lin ts of 3.11.1.1 are net, immediately suspend the release of radicactive liquid ef fl uen ts monitored by the af fected channel or declare the chanre' in-cpern,le.
- b. Uith one or ncre rsdioactive liquid effluent nonitoring instruocntation channcis inoperable, take the ACTION shown in
. Tabl e 3 r3-llr 3a/o.a-i
- c. The provisier.s of Specifications 3.0.3 and 3.0.4 are e not applicabie.
SUEVEILL ANCE RE00!"Et'E"TS (,10 .1 4.3. Sit- The 9:t;oints shall be detet ined in acccrear.ce wi th proc edur c s
.as dcscribed in the CCC and shall be rcccrded in the T station}---it' r nrse.os, C. . I o, 7.
,4.3.erbf Each radioactive liquid ef fluent monitoring instrunentation channel shall be demonstreted CPEPULE by perfomance of the CHANSEL CbECK, SOUPCE CHECh, CHA%EL CALI3 RAT!0':, and CiCNNEL FUNCTIO!:AL TEST operations "Ju'iny tH-U0C S-endJ at the frequencies shown in Tabl e ~~r-4-ilr--
6.10.3 4.3.(c.10-l.
~K '4.3.9:Br-3 Records - Auditable records shall be maintained, in acccrdarce / ge r ' O ,_. with proceduresRin the CCCM, of all radioactive liquid effluent b0 ,conitorir.g instru entation alarm / trip setpoints. Setpoints and setpoin:
{'Speci calculations fication 3.11.1.1 shall beare available net. for review to ensure that the li' nits of
-l ;
LSCS-) 77 "l" E T L1- 3/4 3 A g t
- - ~ ~ , .. .. .-. .. --...- .. ...--. .--
- i t s
r
; .2 .
I s
?
I j - t TABLE +-M 3 3.6,to-l ! I RADICACTIVE LIQU!D EFFLUENT FONITORING INSTRUMENTATION N'h ; in .
! ~ !
I. T+ta. i M IM! t.'Usi p
' # CliANNELS APPLICABILITY ACTION It:5TRU. LENT OPLRABLE l
t
- 1. Gross Racioectivity !'.onitors !
Providing Autunatic Tennination of Release
- a. Liquid Radwaste Effluent i Line (1) At all times 18 1
- 2. Gross Radioactivity Monitors '
Not Providing Autoc atic Ter- i
$ mination or Release 4
t,s , n
'lq. a. Service Water System Effluent l
~Line (1) At all times 20 i 2c ,'
L. DiR .sa.:..catae. w 2cn_ % t.y, A Ol Ar r.u ri ~ zs
-L. C sireent-GeoH ..; '..L.:tu Cptro-Eftdunt L , .- -(4-) 7.', ali t h , 2G- - l, go
- c. CM Sc.ev. c a U rma. G a twawt bwS g) g, m y, ) l l.
- 3. Flow Rate Measurement Devices ** r t
Liquid Raduaste Effluent Lin-@ At all times 21 s l
- a. (1) 4 21 8
) b. eh e4eg. : _.'. 4 (1) -
At all times
- S cou oc~~ P,- c
} I'
, oit v cn.v : r'n / n o ~
i (
" Pun.p curvesa m ay be utilized to. estimate flow; in such cases, action statement 21 is
,j. not required. r i i'.. , I
i C ,C /~ , _ j. o / ,
" &nC - t I
i 3 3 G lc -; l
}i U' bO TABLE ~>.:- R (Continued) .
e V, , e, . i l, F.ADICACTIVE LI'"JID EFFLUCt;T MO:11TORING INSTRU:/ENTATIO:1 ! I i
- f tIrl!MUF1 .
CH ANI,'E L S i APPLICABItITY ACTIC:1 INSTRUME.,'T ' Ot>ER.8LE
.. hfic2Qivity Recorders
/ s. .
" all times 23
- a. Liquid P W.f.sie-E M M .ea^^ (ij
~
l E Tank Level Ir.dicating Devices *"a ' u *nks outside plant s ildings) a t u At a!! tiries 22 , T[,j a. (1) A all times 22
- b. 1 {
At all times 22 ,
- c. (t) '
At all times 22
- d. - (1) 5
~
- l
' i
*** Requn w o.., ' >rr.4- m ;;TE5 int is based on I p ' M .IioIier. ~- - '; ^
^^ttDN1W1Q.s v:hich have alikes or retention ponds - '-l ;
,. c a p a'a i e o f pre ve n t i nf7tma--t--4 % o r a t ank ovar t l ou - and have prov ision . f or sei:pling co11cc htFJTT ;n_te==,u LrcurT2 9 s __
, . . gthe.u to a 1 niu i<! r a d .. 39,,t au.en t-g s t en , ~ I
- . . . . - I
- i. ,
%._ )
t-WC 7 ht>-C t/C i-5-154nG-
.:s :e .
C' -- asca ta; t en2 0t Cu;;np sancy.4- 8
,;ad acuo'TtrDl'1CJ PP'JG r> Si lo^0t /; t ^ n 30 M PC:L W 'fDyT~
pap t Acad sit p 'g1 og dn .Tc;--snu tspogl;;u-leq1 Ed'pa;3aj;v aqq eta 5 as t a to; *,uan t,;ja, ' .w.r-r.rtiiLa; 3137Ody-G p uuna guL U tW aya./g pD; pba;-veqi s;0L 31EVS3dC Stauuey) 30 Jaqanu aya yrtn--fg-_n011;y_ X;eq - i ~~~~~~_ . l te Su;;np poicq2sa si l a ^a L p i nb 4 t - aya zutao; suo aya t;pappo;d tppe p tnb.t sitp tj'E2 01~ 9ElCJ Anu purM5~huca s tyg
~~
og suo t; }ppta tr.bi -t-SunELTh a 37tyt3d3 s tcDucy3 anct u np.__ . _ _. i / q pa;tnba; ceu; scat 3 h'3 1 33 3 s tauueya jo s.o;;t.r.u cy; t,q tn 22 noligy --.________ 1.___.cq; s asca to; 1 t enlae 6u'.;np s;ncy t ;3d scuo ;sec t ;c ps;e.apsa S t a;ea not; aq: popt asad slep ;I c; dn acj anu t;uca AEa AE".qqed s ty; e t t, sane ta; avan t;;a ';usuo;;nta; 370lb3do s tauutyg anqu ta 041 lq pC;tnbc; uey, ssa t 37eyt330 s puutqo jo 20q:nu ay; ya tt; 12 t,oI13y
-ts/.;;n.7 m-acce t-;;--3cwopeatep 4c-a. tut {_.JDv.0;-lW e- '( cud C J O c;ag ) /; p p De o L pc J ss0;$ Jof per/ tet.t pue pa;33t;ca 0;e saidces ge;6 san:q g and 00;c ascat ge acut paptr.o;d slep ;I 0; dn aoj anu puo le u / E v.y; E d s t yl , ,
( tLA sasta to; ;uan tjj a ';t s'.a;;nbt; 373;3330 s tauucy3 cnqc ta 04; Aq paa;nba; uey; ssa t 379yy3do s tat.ucyo Jo saaq nu 041 yllM 02 N0110Y lenga ed sty; e p s;uant;jo at.pocotpe; jo asecta; puadsns 'asts;ay;o 16u p tea a5;Py3 sip pue
*suo tae in; teo air; este te; ey; 4) L;or, i ;uapuodspu t t ;;ets
/; t (t as3 cqq 30 s;aq20 pa tj t tenb A tte stuyse; c".; , seal it *2
!pue 't I 1 II r uopect; toads y;p acucpaoace ut pa:At eue a;c sol ues d quapuadaput ce; ; sea t ay 1
- Oseata; e 6uttetitut c4 Jotad ary2 poptroad 'slep ;I ca dn Jo; pacnsa; og leu sasta ta; quan tJJ a ';uace;tnbDJ 310133d0 s tauuey3 unqu ty ay1 /q paainba; ueys ssa L 37erE3 0 s tauucy3 jo aagenu ay141 LM 8I N011-)V NOI1110N 310V1 (panupuo3)
-H-EM E- 37SV1 l- Ol3 T E ,- U
- ------w~__ . - , , , , , , , , . _ , . . . . . _ . _ . . , . _ . , _ _ . .. __ ,. . . _ _ _ . . . . . _- . . . . ,
l t
+
a 1 i 6 1
'Z. 3. L. 8 0 I , l T ABL E -&.-3-i+
RADICACTIVE LIQUID EFFLUENT !40NITORING INSTRU:qENTATION SURVEILLANCE REQUIREI4ENTS oa I~ TV l*
- a. p", CHANi;EL v .
,y .
l FUNCTICNAL
, ,1.1 CH/-l.NEL SDURCE CilANNEL I
INSTRU:*ENT CHECK CIECK CALIP. RATION TEST ( f Gross Beta or Gama Radioactivity l. lionitcrs Providing Alarm anJ i Autcmatic Isolation
- a. Liquid Radwaste Effluents Lir.e D* P R(3) Q(1)
- 2. Grots Seta cr Gam a Radioactivity f lionitors Providing Alana But !!ot t I
Providing Automatic Isolation (4) u
; a. Service !!ater Systt.m Ef fluent i u
Line D* li R(3) Q(2) , k N d $ MV3 CE V E TDQ l*'N A 4 Uh/ f Q l 4, x( b. Coapsnent-GwH nt4yshr- . 1 -ET f l uc.c. L i c.c D* a R(2; Q(2)
- c. c u a : s. s ,e a a:,r :,z c-= m ur u.~ aav m ,
- 3. Flow Rate fleasurement Devices d(0 I
f
; a. Liquid Redwaste Effluent Line D(5)* N.A. R Q ? %wne ,n R e,s ! b. -[Hschege-Cend- D(5)* ft. A. R Q 4
I i I 1 : I -r . i y 3 ') g Y i
-) .-
i ..k < l ! l \' N '
.t ! 3.e..'c -1 -
T/MLE '. 24 L (Centinued) ' l , .s f, RADJ,ACT!i.'E LIQUID EFFLUE!;T m :iTCRit:G I :51PsU::.!;Tr,TIP:: SURVEILLA :CE REQUI.REf'Et:TS - 1 D' ii 'N
, CHAICE -
)ih If:STRUMENT CHA::t'EL SOURCE CHAf:::EL FU:::Tk.HAL ! CHEC% CHECR CAllIMil0ft j f5T , 6 / i 4. Activity Recorders (6) I
! a. Liquid Rad > taste Effluent /
Line D( }*s fl . A . (V Q 5. N N
/
N Tank Level flonitors (for tanks side the building) (7) i
- a. D* .A. R l 1 b. -
ft. R Q
- c. '** fa Q
- d. D** fl. A. R Q I O .
1, n 3 .
.c A m
i. h xs \ j 's .)
.- 1 y,3, r,,10 -l T AB LE ' +1 (Continued)
TAELE 1101/T!0!!
*Dori ng rel e 3 Z s v i a thi s pa th'..cy.
Eurir; liquic additient. te the tant.
(1) The C: ?'mEL Fl%TIONI,L TEST shall also cemonstrate that autonatic isol ation of this pathw crd centrol rocr alarm ar.nunciation eccurs i f any of the fo'ic.,ing ccaditions exist:
- 1. In",trer'ent indic ates neasured level s above the al am/ trip sc t;cin ,
- 2. Circui t fcilure.
- 3. Instrurer t indicates a downscale failure.
- 4. Instrument centrols not set in cperate ecde.
(. (2) TW 'CHf.:.!.EL FlR CTIO!at TEST shall also dencn! trate that control rcen alam annunciation occurs if any of the fclicwing conditions exist.
- 1. Instrunent indicat . neasured levcis above the alarn/ trip setpoint.
- 2. Cir cuit failure.
- 3. Instrtnent indicates a dern cale failure.
- 4. Instenment centrcls not set ia operate ncde.
(3) The initial CHAN!:EL C All3 RATION for radioactivity measurement in-strumentation shall be perfon cd using one or nere of the reference standards certified by the 11ation31 Eureau of Standards or using standei ds that have been chtained frca suppliers that participate in ncasurment assurance ac tivities wi th ISS. These standard should pemit calibrating the system over its intended range of energy and rate capabili ties. For subsequent CHANNEL CALIBRATI0il, sources that have been related to the initial calibration should be used, at in- , tervals of at least once per eighteen months. This can nomally be accomplished during refueling outages. (Eri stir @ct-s-esy- s ub , stitute.-pcc.v._icusly enat4-ishee--t:el-itetton preeecs o fx this r.o qu i+(m e n+r}- , N34T-5 3/43-ji6 L SCS -l e M69e $" ' g9,
... . . . ~ . . . - - . - - - . . . .
G. -' . (.. IO -I p T AE LE 3-11-- (Continuec) (4) This requirteent is applicable only to sysica: s. tere the service wa ter sys tea or cce., . :ent cooling water systtm is discharged to an ef fl uent strecs , sucn a s cociing tov.cr bicocuven. (5) CHA!!!:EL CHECE sn?ll conr.ist of vcrifying indicction of flow during periods of rele m . CHAfEL CHTCK sh:11 be mace at lec t on:e daily on an./ day on which centinuous, periodi;, or bat;n releases are made. -_ . _ - - - _ _ __.~------n o _,.--.i c.--a ,_. - - -- - tr c_ a n r , = n t _u.. ap;Her.Mronly t_o sys t<.ms wnere an -l arn/ tri p
'L',i e n 157hi TT C d - by r t .Td c r :T critM ' cr- ; n 5 ttener.;,a.ti r r. .N. . . .-.... ~ .
r e cai r cnu.t i s nc t ap pl i c 61 e to ta nk s whi c h b a . e d .i t e
- c r- re U.1._tent T h_i s_ i . n~pa r A s a :::hle_o f rr cvjn tircr= ' f -ir5JTv. ent cf a ta.nl ted liquids and oEiting v .-e r fi thn c s .a tenad.liquid ht v e-trreni rcd .c Uste r.1trcet.
n r t vrent
+t iz syst
.._ ;.c11
- - . ~
C c e.i. . --- -
,r, ,
Y' BWR-STS 3/4 3-5I ' O LSCS-I
. w eesge g ad . Gee m. .pheg e.w . ems
. __.--es.m,
.. ._-.a. 1 I t!5Tc"E UT AT I ON
- P A010/ CT1'/E GAc EO'r EF R t'EUT INSTRU"ChTATich L!t'ITl'l" C0!;DITICt! FOR OPERATIC':
. . . _3.3.t . n ~3. 's . c.. n ~ s
. W3-3 ra - The radicactiveingateous procesjs n.d cf fluent nonitoring instru-Tenta tion chanrel s sbo.e. Tabic 3-1; shall be CIEP.AELE wi th their alarn/ trip setpcints sc t to ensure that th; linits of Specifica-
.. I tien 3.11.2.1 are not exceeded.
a
/
!rPLIEG_ILITY: A*. shcwn t n Ta bl e -3r3-12.-- 3.3.6. 81 - 1 ii
.f. TIC"!: a. Wi th a radioactive gaseous procet; or ef fluent nonitorin; instrucentaticn channel alarm / trip setpoir? less consnrv;tive i, than a value which will ensure that the linits of ^+.-il.h are
'j net, declare the channel in:perable.
h
- b. Wi th ene or nore radioactive gasecus peccess or ef fluent monitcring instrumentation channels inoperable, take the ACTICM s hov.n in Table '2r3- H r- 3.3.0.ll -l
/
- c. The provisions of Spccifications 3.0.3 and 3.0.4 are not a ppl i c at i e . fm sun'.T " !./.NCE F ECU 1P E t'E NTI 4.3. L .st . I 4: r3 9rl The etyints shall be determined in accordance with rrccedures as described in the OIN and shall be recorded in thc istation7 leg,.r m.s es, ii .3. t . u. :'.
4r3r379.-2 Each radioactive caseous process or ef fluent nonitoring instetrer.- tation channel shall be dtnenstrated OPERAELE by perfo' nance of the CFAUNEL C HE C S. , SCLRCE ChECE, CH/C;EL Call RATION, and CHAh!.EL FUNCTIONAL TEST epera-
. tions during--the4*Oi 5-a rd a t the f requencie s shown in Tabl e 43-ler % ?..L.ll-l 4.3.0.H.3 44r3r3:9.-3 Auditable records shall be naintained of the calculations nade,
]in acccrdance wi th procedures in the CCC",, of all radicactive pro:ess
'. and ef fl uent noni toring ins trur.enta tion al arn/ trip se tpcints. Setpcint:
and setroint calculations shall be available for revicw to ensure that the ilinits of Specification 3.1:.2.1 are net. U i Q jBmSErr 3/43-J'l L 5 c S-1
- - - ~
i
, 3
.s .
O ... ') . .a j : *i N . h. i i -
- i ,-
f ln
- A 3, 3,r,. r ! -l I
TABLE 9-3 .J. RADI0 ACTIVE GASEOUS EFFLUENT M9t!!TORING STRUT'EtlTAT I0'1 a
'E
- MINIl1UIl 7 CHANflELS APPLICA3ILITY PARA"ETER ACTION t _IySTRUMEt1T OPERitDLE j Smee b mimur
- 1. -t' 5 0:-enser f i n Tmatet :ys'em Effluent l'cnitcring System
- a. floble Gas Activity Monitor (1)
+ Radioactivity .': ate 27 I-te.1surcmcn t i
; b. Iodine Sam.pler Cartridge (1)
+ Verify presence of 31 cartridge i
- c. Particulate Sampler Filter (1) *- Verify presance of 31 I filter lu2 i d. Effluent System Flow Rate Measuring
- System Flou Rate Measure- 26 iw Device (1) n:en t l
- c. Sampler Flow Rate fleasuring Device (1)
- ScTpler Flow Rate ficasure- 26 I mant f-s j 2A. M A Condenser Offcas Treatment System Explos .eGas Monitoring System (for l
< systems designt.mN withstand the effects '
of a hydrocen explosica}
~
** ,. lydrogen 29
, a. Hydrcgen Monitor , t. _
j */ a gggp n ., y, ,. - ,, "L { t-
't t,,
., 7
^ .
* * ,- j a 7
, r))
0"< 1 . ,. J x ..
l 'l f - 3.3.E.H-l '. , P- TABLE 3.1 (Continued) !
- u .
'.' .,, 3- .'en RT,DIOACTI'!E GASC0 tis EFFL'jEttT t'Oli!0 ll!!G I::STP'/:G;TATIO:1
+
') Mlf!1:!UM -
{1 CliAC:ELS . It;STRU. E!:T AUPLICAI>lLITY P AR A!'ETEP. ACTIOil OPEM01Q I - 1 -
' 'Dmrr-Eendenser Of fgas Treatnent System Explosive Gas h ing E!J Q (for _ X' -
system not designed to wit'istanCTE effects of a hydrogen explosion). . . l My'!rogen 20
; a. liydrogen Monitor
+* % liydrogen or Oxygen 30 dr _ , or Oxygen Monitor (2) i su~na, e s remr-cur
' t 2 /. Inir Etti4tMnHent&t-ien/fttree-
,j tionitor System
- a. foble Gas Activity Monitor (1)
- Radioactivity Rate thasure- -EP 2 7 ment l
', b. Iodine Sampler Cartridge (1)
- Verify presence of 31 Cartridge i ,
- c. Particulate Sampler Filter (1) Verify presence of filter 31 i .'
- d. Effluent System Flow Rate
; !!easurem.ent Device (1)
- System Flow Rate iteasurement 26 l
- e. Sampler Flow Rate Measurement
! Device (1)
- Sa pler Flow Rate tieasure- 26 nent i
' T )
a ) -'
.s s .
~'\ ' 3 ) - l.
/
b ? . ',. n - I l TMLF % bit- (Cori!in ndl
- r. Fly T r ,;; 7m;!" , !--- ",:T AT im.
I PADICTCTIVE CAST P!3 I'. * ! c', - g
' fiitilM'J:: -
! Ej , CHAI!::EL3 lL It! STRUT'ErlT I:PF%CLE APPLICABILITY P A",t^1T T ER ACTION
~__..__-
l
~
- 4. Condenh@terJLMi^cc ' ivi ty l'onitor (Prior to input to HoidUp~
** .ieMo,-ga-gac t i v i ty 25
- a. f:oble Gas Activity 2 niter- (1) rate aeasuren2
, 'N . (See List Below) ;
- Radioactivity Rate Measurement '?
' a. ' ble Gas Activity Monitor (1) t"
- Verify presence of Car Wi ge 31
- b. Iodine k., er Cartridge (1)
/
I 4'
- Verify preserc d f Filter 31 Particulate Sample (1) ilter lpT c.
I
! d. Effluent System Flow Rate heu tring * .,ystem flow Rate Measurement 26 Devices (1) l 26 3
- Samoler flow Rate Measurement
- e. Sampler Flow Rate Measuring Device (
l (1) Main Stack Monitoring System j (2) Auxiliary Building Ventilation iitoring System (3) Fuel Storage Area (Buildi g) Ventilation Monitoring System (4) Radwaste Area (Dni- ) Ventilation Monitoring System
! (5) Turbine Ba nding Ventilation tionitoring System (6) Tid Gland Seal Condenser Vent and i'echanical !acuum Pump I 4 haust renitoring System f
. . - . _ ._..4___._,
'>.,.' . G . H - !
T/& E -E-95 (Lontinued) TI " E YTATICH
.c
,. u. . . j e
, u r, ..,.
.~ 'N cce r o f f ._:- tret tm t sys ten operation. y
./'
N 's' .f :i< ^ t) : in cerer.ser air ejectcr. - ACT.,. _, (.t .cr ,.f C Ean.. 's CIER AELEJess-Than requi red by thc s el s CIEi ?LE requircecfit, cases f rcm the rain c - . *
' .+; ..e t".? r '.-sys tc-' nay be rel ca sed to the a i mrr . . ft t. R
.- - M' hourt N., r.covided:
..- m c:<...a...s ., w qn w m_
1 ,T! ;~p s del e- sy s t c" is b .~byisssed; and
. r t. . o n: am c:wusirp3tc M '
in < vuf :f-sjs t:e't-noi;+c-ges ac ti v i t., miter
. , . je_ c -
.a.r.., s
,/ , - ':w- . bc in at 'eart HOT STAEY within 12 hours. N .N A..
' , - i u-
"r c,,
.1 .- CFEF'd cha i s Ce..r u. m.
rcouire
,. , . . l e s s .,u n r e cu i r e a, by .J'e ent, effluent releases via k
.i. , t .
r . cc.tinu:- for up to 28 days provide: the fi c.< r t_ is.% N a t l e n t o r.c e pe r 4 ho u s. AC' . 27 ' .' th v ' r of ci arnel s OPERABLE less than required by the
'u - rr w.ci : erE' , LE requi rcrent, ef fluent releases . ia
' '- pet j 1 ccntinue for up to 2E days provided ario
- ce taken at lent once per 8 hours and these samples s ..n '. .: '. for gress ac tivi ty wi thin 24 hours.
. . _ __ . ._ AU ' .__
- , . t: . > nu mr c f channel s CFER AE LE l oe.s4.hm-rcc0W66 b_y___the 1o - ii._ u r w e:1 s- fGd31T'i Eduirc.cn t , irmediately suspend
- _ . . _ . _ . _r el_ (.._. r c c f r a d i c a c t i v e e f f i u e n i s v i a ti i Ifab.r.'r--
~
.~
~.J.C W " ?.~ .
ti,e .ecr of channcis OPERAELE les: t h a n ,- rg.cai r ed- t9~'the
' ; m - '- Nvci s CFET 7 LE requi renen.t.,-c; PTtion of the main
. ~ treatae:.t3ff,Th may continue for up to 28 days c; .ccidee
- rAnsc n.T?- r ci?@swpl cs are collRt6a"at4can%per once 4 hours an
..u i vre d wi thi n thr. en sui rm ,+ hours.
~ . . - -
.:._. __- . . . . . . . . . . - - . - ~
ih tha number of channel s OPERABLE one less than_recaire c cm ti rN ~t o r u to ! <* -da.vs __.Xi.t.h.. b.o..th c ha nnel s i n- .
' _ . . _ _ _ _ . _ _ . - i.c'perabic, n at l ea st b h0T STANDBY wi thi n 1 houf . - ------ --
~
A
.m..( . 5 ; c +. . 3/4 3-h.
L c, C. - l
.-.agsi..-.qD __ L . ,O. TIM 4 g g
a
. TidiLE 3. 3-12 (Co n ti r.ve d )
ACTIC!l 31 Wi th the nu" ;r of che.rnel s CW.* PLE lcs; than requi red by tL - Minimun L v el s CPU TCLE req 'irer.,ent, e f fl uent rel ea ses v ia thi s pa thway nay c ortii.uc for ce to 2E , js , p: oviced sar.pi t s are contincOL-'y coll ec t 'i wi th auxiliary sanpl ing equi pmer.1 for periods on the order of sever. (7 ) dcy; ar.d analyzed wi thi r 48 f.ours af t.:.r tiie er.d cf the scnpling peri;.d. e e e a
@ -BW R-ST S - P 3/4 3-57 L SC. 5 -- l e
'e 6 m e
~- . . . - . . . . ....n.--....--.- - - . - .-. -- ;
o i i
. . l.
i j. t
- u. 3. s . " - r j TABLE '.2 " - !
,,er 'tADI0 ACTIVE GASEQUS EFFLUEf1T f'0:lITCRit:G If1STPI'.*1Er:TATIO:1 SURVEILLAtlCE REOUIRE!:ErlTS ; i i:' D i . v, ,
- CliA! ::EL . f
} ~.1 1
- iL CHAi!llEL SOURCE CHA!!:EL FU::CTI0f AL CliECK CitECK CALIBRATIO:1 TFST I' STRU"Et1T I
1 S ra. von \)evr G w 1T
! l. Min-C-endeese< C f fys-Amt~nt Ey: t m-- ! Effluent Ibnitoring System I
- a. I;oble Gas Activity I*aniter D* l1 R (3 ) 2.- Q(1)
D* II. A. R Q j
; b. Iodine Sampler Cartridge D+ fi . A. ff. A. fl. A.
- c. Particulate Sampler Filter D* tl . A . fl. A. fl . A.
T q ., L ., d. Effluent Systen Flow Rate fMaccring
, Device 0* fi . A . R Q
- c. Sampler Flow Rate f*casuring Device D* T1. A. R Q l' nim 2A.A Cendenser Offgas Treatment System Explosive Gas l'o'iiiterino System (for systems designed to
'f withstand the D eete of a hydrogen explosion)
- a. Ily<irogen f*onitor D**' II. A. Q(4) !
n .___ ...
..u.,-....__p...__ , _ _
v
. yr ., _
p
- u. .
- c. O se on-1e v ,s. m o i
?
l N~ ., : l > ~ . s~ 3
, 3 !
j ,- _f
) ,
, i
! t.
6
' a.3,G. Il-1 .
TABLE :.1 '2 (Continued) 1
~M RADI0ACTI"E GASECUS EFFLUE !T f30r!!TORit;r, li:STRUnEf:TATIC:1 SURVEILLA !CE P.E001REf;Ef:TS ! ')'a CHArmEL
- ') CHA!mEL SOURCE CitA?;!!EL FU::CTI0t:AL
*y (!!ECK CAli r".AT I0tt TEST CliECK Ir:STRU"Ef!T
~7Nain Condenser Offgas Treatment System Explosive '
Systen (for systems not designed Gas hr4(he GTTestsJ'f to ,sithstand t a hydrocen explosion N' ft
- a. Hydrogen I*cnitor N F* fl . A. -(9
- b. Hydrogen Monitor (alternate) f!) Q{1Q Il C* * ?! . A. Q(5) .
w c. Oxygen l'onitor ' 1: ff
- fl. A. 0(5) !! N_
..ygen Monitor (alternate) __.
E'r.w.m o y G 4s Emm a:T
-2.7. --r.cector-Building-vent H at-icn/ Purge tieni-tering Syste, L
D* H R(3) Q(1)
- a. ficble Gas Activity tecnitor fl . A. 'J Iodine Sampler Cartridge D* fl . A. fl . A . '
i b. fl . A . fl . A . l l Particulate Sampler Filter D* fl. A. i I c. !
- d. Effluent System Ficw Rate ficasuring Device D* fl. A. R Q l Q Srpler Flew Rate f;easuring Device D* fl . A . R
} e. I l i l !
l . .
?
. 4.3. G. II - 1 l TAELE 4.1 12 (Continued) .
RADIOACTIVE GASEOUS EFFLUE.*tT l'OT:ITORI !G If!STRUtiErlTATIO : SURVEILLAf:CE REQUIREfiEr:TS t iP jil CHA?lt:EL T CHAfi!!EL SOURCE CHAT:t:EL FUNCTIQUAL I '-- If:STRU:1E'lT Cl!ECK Cl!ECK CALIRaATIO:1 TEST ". 9ecic Q ioactivity f!cnitor g (P r i or to i npu t to the ci Ur2+ -41 m of
- the n5in condenser offgas treatrent sys:.;i.
- a. floble Gas Activity Moniter D* *
- M { a ,c ivity Recorder D **
- it . A. R Q N i
j ,, h jSee List Below) . '. I N ITGMc Gas Activity Monitor C* M R(3) Q(2)
'{
'-) floble Gas Ac i'ity Recorder D* fl . A . R Q f
! ledine Sampler D* U.A. fl . A . t ..
Particulate Sampler D* fl. A. fl. A. fl. A. i
; Flow Rate lionitor '*
fl. A. R Q Sampler Flow Rate lionitor D* .. R Q i i i (1) Main Stack Monitoring System (2) Auxiliary Building Ventilation Mr oring System (3) Fuel Storage Area (Building /entilation Ponitoring Systen (4) Radwaste Area (Cuijan lentilation Monitoring System 1 - (5) Turbine Bui1Mffo Ventilation Donitoring System - (6) Turbj nd Seal Condecser Vont and rechanical vacuum T I j ,,rerp )aust wisiy ',,mn '
m - Ll . 3. G . II - 1 T ABL E -4. 3=1t-(Continued) TABLE fiOTI.ilon
*During releases via this pathway. . . _ . - - . . _ _ .
A s **During main condenser of fgas treatment systen operation. ,/
. -N'During operation of the main condenser aic ejector. ,/. '
N (1) The CHAM:EL, FUNCTIONAL TEST shall also demo;st~ rate that autcmatic isolation of'this, pathway end contropuom alarm anr. uncia ticn occur s if any of the folldwincqondi tior.s exi st: 1. Y Instrument indicatcs mea 3ured levels above the alacm/ trip se tpo i n t.f'
- 2. Mr/ cuit f ailure.
- 3. Instrument indicates a dcenscale failure. N N
- 4. Instrument controls not set in operate rede. N.
(l) (g) The CHAtiNEL FUNCTIONAL TEST shall also deconstrate that centrol roc-alarm annunciation occurs if any of the folicwing ccnditions exist:
- 1. Instrument indic ates measured level s above the al arn/-V-i;-
se tpoi n t .
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
[2.) R) The initial CHAN!;EL CALIEP.ATION for radioactivit'y neasurement in-strunentation shall be perfomed using one or more of the reference standards certified by the National Cureau of Standards or using standards tha t have been obtained frcm suppliers that participa te in measurtnent assurance activities with NBS. These standards sheuld permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHAl";EL CALIBP.ATION, sources that have been related to the initial calibration should be used, at in-tervals of at least once per eighteen months. This can nomally be accomplished during refueling outages. -{Eri-sting _d ants may-subst-i-
-tute prwicudy-est-abM&hed-tM1DntMrqn ccedures--fr ni s cequirwcn -)
1NR=tT5= b- 3/4 3- R t 5 C.5 -1 .
. .-.-.---------.--.-~--.s-- -
N
/
A',
- 1
- 4. 3. (c. Ii - 1 y
TABLE t3:17 (Continued) (4) The CHA :!;EL C AL IBRATIO!L,she indtd the use .f standard gas sa.p l es containing a nv3jnaM'
- 1. On /e volume percent hydrogen, balance nitrogen; and
- 2. Four volume percent hydrogen, balance nitrogen. Ns N~. _
'~ (5) The CHA?;t;EL CALIBP.ATIO!1 shall include the use of stancardjas--se.'ples
~ ' -- -con 11i ni nc a nca inal-
'N.' N One vol ume pg rcen t-cW. a.cny bal w<a nitrocen; and 1.
' p
. Four volune percent oxygen, balance nitrogen.
~~---- _. _
- R 4
-Mt M TC-1 3/4 3-62 m
*W " *** W N FY*NN
*M M eeute m Mem>M Mmw M- NMa -e- W Mew-r***e *w *. *M wappee mew
6
~\
I
-) -
6 a
,a s E- TE'_E 3.6. 3-1 n
F'il!GRY Copr;IEN T IS'.'LATICN VALVES l ISOLATION TIME VALVE FUNCTI0ri AND r;Ur'EER VALW G?O"P(II (Seconds) 3
- a. Automatic Isolation Valves l
< MSIV(b) 1 3-5 ' 1821-F022A, B, C, D l 4 1321-F02CA, B, C, D Main Steam Line Drains 1B21-F016 1 5 15 l 1 5 15 i
R' 1B21-F019 . 1B21-FC67A, B, C, D 1 $ 7.5 S' G Dry. ell Equipment Drains 2 5 20 1RE024 1RE025 1RE026 l 1RE029 i
! Drywell Floor Drains 2 5 20 1RF012 1RF013 E;-
1 5ee Specification 3.3.2, Table 3.3.2-1 for isolation signal (s) that operates each ' valve group. 8
= ,31,
*May be openend on an intermittent basis under administrative control. MM b, x .:
< priot subject to Type C leakage tests. "9
-a Ul 'ot a primary containment isolation valve. Listed for information only. i.
$= 0-b See Specification 3.4.7. for MSIV Action Statements.
s i
I
. ,8
- I
.; . . ,l - I l' U, IABLE 7 c.3-1 (Continued) hG PRIMARY C0riTAlt;fiEfiT ISOLATIO!J VALVES ISOLATICri TIME VALVE FUi4CTIO1 Arid f;'JMBER VALVE GROUP II) (Seccods)
- a. Automatic Isolation Valves (Cent'd) ,
' Tip Ball Valves (a) (#) 7 Following Auto ' Probe Retraction 2 <1 l Containment Monitorino Valves l ICI'017A ,3 ICM018A.B ICM020A,B ICM019A,B R - ICM028,30,29,31,33,34,27 i ICM022A,B ICMC22A,B ICM021A,B(c) T ICM02SA,B ICM025A,B(g' g ICM025A,B Drywell Pneumatic Valves 2 "'g' __ ! It:001A, 3 140 1:1001/ 10 3
- Irio74 <30
- II
- 075 <30 j I.O31 N (a) (#) 51 ,
' 1 i
I See Specification 3.3.2, Table 3.3.2-1 for isolation signal (s) that operates each valve group. l' E> { E
*May be opened on an intermittent basis under administrative control. y ,]
9 4 #iiot subject to Type C leakage tests. $N
<s
~
i
! $ u;ot f a primary containment isolation valve. Listed for information only. rj j b See Specification 3.4.7 for MSIV Action Statements. Mi C
0 pens on an isolation. I I e
. _ v
- e . sa m s . . . ,. . . . . . ~ - --
... e . - - .
.4 %
. ttApjL tr** d* 6,'.f*. li s.lt a4 1 dM,7fAfd 1979 LJ I C.
- 3 3 -- e s O e '
*i U t's O C
*-a C t '
h- to _-
< CJ
_J L'l O* -- 0 w hI () rs ( )
.' )'
<3
.)
C. ' .1 (r, 7 <; gj O .
, C .< .) ~
~, C) <3 O P .
L e<
'-; L t,.3 L
ss C D J r~ C: c; s
- c U O ,L > - -
C g e- O O g', ~ =- C t n 4> O g,' ..- m
,-,' LJ si L w' .>
H, 1* e e8 - u - r C. j - e m -- a s .-
* ". '3 E
@ e- *D
- L,
, .) C M t1 g.. -
LSI L. J (t ,.e
.,p y - U 0- Q G
# 4- B F- &w '
e A w c..- .- a ( l O C CY d 0 a Q r ') M C ( ) C) e- 4a JJ M CL' <J - M Lu v F- 6 M LO O' O L M T: > c
- C1 CJ I' - > C a 43 0 4s R C C :=
1c f1 - e -- U C") M L~ C- 07 C := 0 rd O c c1
- o
.r-
- e M >,
2 +1 ; C U F-p , O ej m Q Q
>-a e-e *) .c o
>-- C t1 m u +1 O V O o c.)
- - m -
C 'C 4i D 4- CJ O U LL. - - CL - 'J a C L 4- r> La j ;1 c)
' O
.,e i .O 3* C p C' e D J C
- c o L.,L .o ge g <g > 3, e.
u o X o
. . c ,a :c to n
' D U 4 LSCS 1 3/4 6-25 A*"? I979
_ - @3,mq De59 ,My ea,neg gw e geg g g, gg,
- ~ - - - - " * * * * *= = . . . . _, __
" - - - - _O*
- JOW. MM*
AMENDiENT 41 JANUARY 1979
- r. ,. L, .in 2/1 f.4 '/Atti RELIEF Sin'Pi T S51t"; r" 'nE R - D'r'N' ELL VACU.'M DRE AKE RS t .I.M.' T Y. .C.D'r : T.i r,': FCR " ER..fti!C1 3.C.".1 All suppression chnber - drywell vacuum breWrs shall be OPEROLE an ' indicated to be in the fully closed positic, with:
- c. A to'.a.1 leakegs bet..'ecn the supnetssion chacher and drywell of le.,s t!.an t:ie equivale.t ie3L :": throu?. a 3 inch diameter orifice at a differential pressure of 16.7 psi, and
- b. The cedundan'. position indicators OPERA 3LE.
- p. m. i f. ' i., T. '. .i l y - .
- c. r...n. ' i l R, S 1, 2 , a nd
. .1. .
ACT!C:.:
- a. With I drywell sunpression pool v?cuun breaker inoperable operation nay L. ntiNe pre /id^d the ranual isolation valves on both sides of the v;cuu~ LU -Ler tre closcd. Restore the (,
incpere.ble v:, cur L r <wt cr to GPER,",LE status wi thin 31 days 3 or be in at le 6t HOT SHUlDO... witnir: the f;110 wing 12 hours - and in COLD SHUTC0ii in the next 24 hcurs.
- b. With nre than 1 drywell-su:' ore'sian pool vacuun breaker inoprable ce in at letst HOT SHUlDur.N witnin 12 hcurs and in COLD SHUTC0WN 'iithin the felicwing 24 hours.
- c. With all position indication en a vacuum breaker inoperable close the car ni isolatien vc1vcs on both sides within 4 hours and d:clare the vacuun breaker inoperable.
SURVEILtf.T E REJU UEMENis 4.6.4.1 Each suppression chamber - dr:,well vacuum breaker shall be demonstrated OPERABLE:
- a. At least once per 31 days and within 2 hours af ter any dis-charge of stera to the suppression chanber from the safety-relief valves, by cycling each vacuum breaker thr,ough at least one conplete cycle of full travel and verifying that each breaker is closed as indicated by the position indica- A tion systen.
L Sc.s-1 3/4 6-26 January 1979
. . . . . ~ . - . ,
's / 4 . 0 PETULLIt:G CPEPATION5
~
3/4.9.1 REACTOR MnDE J,.' ITCH (s LIMITING r.ONDITION FOP OPEi:ATION T.~ ~ ~ '. T.' 3.9.1 The reactor raade switch shall be OPERAELE and locked in tho Ref uel position with at least the Refuel position one-rod-out int erlock OPL'.<LE and ' tith the folloviing Refuel position equipc.ent interkk , OPLt 3L: whcn equip;..ent associated with the interlock is being et er:ted for CORE ALTERA110NL.
- a. All rods in,
- b. Refuel platform position.
- c. Re f ur: 1 platform hoists fuel-loadcd.
4,- feel-grapple paci-tion-d E. Service platfora hoist fuel-loaded. t APPLICABILITh CONDITION 5* ACTION-
- a. Wi th the reactor i ede s'. itch not locked in the Refuel pe",i-tion or the one-rod-out interlock inoperable, immediately
[,, ' suspend all C"M ALTERATIONS.
- b. With any of the etove rcquired Refuel prition equipmcr.t interlocks inoperable, suspend CORE ALTERATIONS with c';ii? -
ment associated with the inoperable Refuel position equipment interlock.
- c. The provisions of Specificatico 3.0.3. are not applicable.
SURVElLLANrE REGUIREi'EiilS 4.9.1.1 The rcactor mode suitch shall be verified to be locked in the Refuel position:
- a. Within 2 hours prior to:
- 1. Beginning CORE ALTERATI0fiS, and
- 2. Resuming C0F. ALTEkm ION 5 when the reactor mode switch has been unlocked.
- b. At least once per 12 hours.
O.
'See Specia) Test E>ception 3X3.
LSCS-1 3/4 9-1 D O'"~ # "
. -~ - - - - - - - - - -
- .E FU E L ' " , Up E F.f,1 ! 07.,
f ' SU!>"r IL!.A!;Cr pgmilRD'.'J NT S (Conti r.ned) 4.9.1.2 Each of the above required reactor node sw'tch Refuel ; osi-tion ir,terlocks shall be de.monstrated OPEP,ABLE:
- a. Withir 24 hours prior to the start of and at least onco per 7 days during CORE /'.TERATIONS, and
- b. Prior to resuniirc CORE Al. TERAT 10N5 folicwing repair, raintrn-ance or rcplacec: cot of any component that could affect t h e-Refuel position interlocks.
(~' . J rs
)
1 LSCS-1 3/4 9-2 Octobe. 1970
~ ~ - . . . . - . .. . .. - ..- ~ .. .-.- . . . - . . . . . . . . . . . - . . . . - - _ . . . . . .
?s h , y.pta _ qo ~. n : r .e r ' ] iir, : r r L ". r ". T. "a
;i. 3,
. . . /.. .i11 L ,.o,, .J y.o,r...
r r t ,.d ; i ., e C:'CE"!'fM 3 ,II * ~
.(
L l!!!T!'$ C00' ilff N Oi'EP'TIO"
-- u . . . . . _ . . .
--.y.__...__...__.. _ . . . .
23.11.1.1 lbt cer.c c c :. e ti: cf radica:tiec naterial reira3e at any ti- , frt the si te in ut.rstri;t^d areas ( sce Figur eO ly-;q shall se i ici t. ' _ to the con:2ntr,2tior.: S:ecified in 10 CIE b.rt 20, A;penh (: , lable II,
. Colt. m 2 f e r rajicr c-li& s oth, than di: sol ved or entrair..* r+1 e c ' .
4 Fcr di st.al v e d or en tr ai ned not i . cc:e s, t he ccr.c e".tra ti on shi.' l be l ir1
- t d -
t a -2 . -l '.h :7 i-/ t.1-'.1Gi--- ac t w i t:r. ul r. Co N'c.c:en't a w t " 5 m ,'e.c m ' O 1
;f's 7 * ) U r . .I (! , / j - l a. ,' - j. , l 1, ! , [ - (
.l'._P L I C A C I_L .I._T.5 ~ 5 t i'l l t i-' e s .
_A C T I CD -
'eli t h the ce! . tn tr c '.i v cf radicac tive n;terial rel e a ser' f r r.:- 14 sit < it ur < estricted areas etcee:'ing 11 ab cve l i-i ts, irredia tely re .t re c on-cc .tra tion wi thin hc able lirits en f ,,rovide pec mpt nc ti fica tion to &t Cu' ai ssion v . suan + te Speci fic atic n f: %-la 6.G. S.s.. O, ' ' S U n. r.. f L ' A ". ". p. r M. . I '. r. ' t. '. i c 4.11.1.1.1 The ccnccntrr.tien o' radicc:tive :r,aterial at any tine in liquid effit.erts relee:ca frcn the site chali be ccntinuously e,,iturt '
in ac corderic e wi th Tabl e -3 d-14. 3.M. / D-l
~~'-~ ----
-4 .1.1.J...l . 2 The liquid ef fluert continuxs coritors having p.rc'/isic.ne fgC autc.u tir3 iin2tio ns> fli cyi d rei e s eq s ,_.r;-i-htrc' iii'Ilbi e 3. 3-11, s h !' 1 be ust d to iini t ice. ce-Wy-0W6Erdiactive na terial released at any..-timr~fr?.516 si te to unrc str ic ted creasYtuwt,e ; . ;i .yn 'i 'n : ,y . i -
fica tion 3.11.1.1. -
'2.
4.11.1.1./ The radioc:tivity centent of each batch of radica tive licoid waste to be discharaci sScil be deternirc.d. p,rior to rel ease by sanpling and analysi s in ac; erd 2 ce s.i th Table tj'. ll-lb) The resul ts of pre-rel ca
- analyses shall bc used vei th the calculitic'IIaTfetnods in the W1 to an'..:re ,
that the cor. centration at the point of relecs is limite{~to the valt,"- in
\
d Spec i fi c a tio n 3.11.1.1. ti. . ld*
- i. 1 4.11.1.1.d' Post-rel ease a".alyses of sanri es frcn ba tch rel t a sc e shall -
bc re r fo rr.ed in ac c ordanc e wi th Tabi c d . Tf'l L'}-.The resol ts o f the po s t - ~
, release analyses shall be wi th the calcul'ationa ne thcdr. i n th ' OCCM t o
' assure that the concentrations at the point of release are limited tn I the vclues in Speci fication 3.11.1.1.
; L\. U * \ 'p..\
. i p l N 545 3/4 11-1 i escs -/ .
4
'**~.ms -..o.a,-.. .~ - , . .-s- '-w* ' - * * ' * * * ' " * " * ~ ~ ' * ~ ~ ' ' ' ' ' ' * '
- . . - _ . _e. .p.,. , s. .. , .
*' D.\\,\.\~~'-
{ SUR VE I L LI.':CE iTCU!i'EPE!'il (Cortinuedi / I I ty
,i4.31.1.1.2 T he rcdioac tivi t3 c e r.c en tr a ti .n o f l i cui d s di #r ha rg ed f r c:- '
l,mjcc oti nuaus y rel W ' -fr ints sh1]J,po d
-e n . ,' t-
~ .nd analveis c , l ec t r. - a s l a bl e e, t e.r-. ll..l L #i ne e sul ts o f the anal'v7
. sanpl e gi n eu oca,rn.c e eil th .-
hshall le used .ii th tt e calculational dst:U[s in the OZ:1 to assure that
}'the concentrations at th point of release are limite. to the values in
! Spe;i fic c tion 3.11.1.1.
! 6
.- !!4.11.1.1./ P erc rts. The ser.irnu-l Radicactive Ef fluent F.electe Rct: t '
. shall include 1:.. i n f o m a ti o n spe ! fi ed i n Spe . ;i c ati e n 4 4 . ,4 6, (c, c ,
i - OT TH E U d tu o Gr= p u gg g
!l . 0 , . w, e ~~
P o r ru r p3 " c" " g "' i d l'd F9 G W 2,ll- j 3
~'
.~. -
2 3 it . I . ) -l ,..
.i -
I e i i i i 8 i WMil-L-- 3/4 11-2 L 5C S-)
-w ,, i I -I Tn'o,.a 'I.11 - I a N "'p , .
r~. fi Y i s ms , Pe n u,, s s i o te Corr.<,,m2 u ie n ,c b t'I5oLVE D oC b N TR Olig t: D }\ 0 CLE hq',c3 I?e tc. n sco Fream rne S.w ro U n e e s wic u o A c., ,, ., . Nuct ne lhPC CuCcA,,d
, ~,
Kn 86 m '4 E -5';
'2 E '!
B5 I E -L,L; Q q. , t l B ': \ Gl5: <! E - CU 1 E /- S 9 E '; li i
/ i
/
1 An 41 f iG~5 7 r. . I 1 :
/ ,
I _,.. ).'c 131 u n \ l' E 'I : 7 e 'l l33 en 1 ftE-9 . S E 13 ', ! o
/IG-4 /
'I 6 E '!
13S in ' / 5' E - S
/
. 2E 'I I3S ij 4 G-5 / /
2 E. - "
'. ,/
C
' l\ ,1l,1.I ~ l TABLES.....11-1.3 RAD 10"CiiVE L10'.!'D WASTE SC'LlcG AND ANALy;I; ppo;; -
; 1.0<.er Limit i Liquid k,tilease .iype
. Sampline Minimur i"pe cf Activi'.y
' i cf L4_ t c t i o r.
FrequenEy Analysis Analysis % (LLD' Frequency (u'1/nl)a -
+-- t ., f,,
A. Satch Uestt Re , [ach h tch Each Batch frincipel Ga.m 5x 10- ' l" l e t s c T cnk s"'- Er.iticrs" / x 10-I '. 3 I x 10-'
+- .\ .
Grie-C a tch/M - fi-- -liss01VGd ar.d l(x IC U in t r a-i-n&G e s es \ I t-- 11-3 1 1 ;- Ecch Catch M - Coreositee b -se x -
, -,1, 7 t
1 >\ _n, ] ' eq _ 1xJg-6
- p-Each Batc.n Q Sr-69, Sr-00 5x 0r -
Ccapesitefb A g Tc-;;. 1y l3-6 g ' O! B. Plant Centir u: Continuous ~ U -P r im-h-e-i G r- 2 - ,1 Re l e ct e s L'. e Ccmposite . f6 . u.11tter p n
.s
-- I '. : .
L_f 1 x 10d x 107
~
1r
.-at-SamNe--
", -Dissohed and
.-En t+e-br-d-Ge- s I ). 10'
~4 II-3 1 x 10-5 Continuous di- M c Compositch 4 7,3 _,._3 1x 19-7 \
-p.g E.- 1 x 10-6 Sr-89, Sr-90 t
Continuous # Q f5x10-E \ 9 Co.posite k ', I'
.p.E 1 x 10 -6 C'..R - S T S - 1 3/4 11-3
Mnenn r.s e g t o 7,, e r- -r a c c o a w r " <.i. ~ w cc c , . , .n
- m lo c r it ro <a 2.o , %. ,,,, x 8', 7 ,, ,x,,_ 1r_ , C . ,_ , , , , z ,
1ne ~~m u .n r v- o a r c t. r , . ( u_ cn , s t., , , , a ,, , , , , T ncn.a. N wr n - u ~ n.. w Ta o e c; % t2p n S w.,c,n,w ~ . Lh 11. l . l ' T A P L E b. =.,-) t.11.U-1[C on ti rum) TABLE NOTATION
~
- c. The I c..e r l im i t of de tt c ti o n ( L L D ) 'it--def-i-WMat.1<--;ui ta t i o n a , o f I Ta b i c-4 .-1-E c f--Sp ec i fi e s t i o n- 4 2 12.1.-l . l N b. For certain radionuclides wi th 10.. carna yield or lon en.yrqie- er fe ' '
certain radicr.uclide mix tures, i t r ay not be possitle__ te, ret sdi radio-LLD. _Under tiEse circur,tantes, diTcl-ians..j[n the LLD na B?'--irercased cencentra tions inver e.ly nearprTo~rtionally tbt to ti e e aani t us o f the ganma yie' d ( i .b ,4 r~Ih;l LI, where I i s the photon abune;ance ex pr es serl.a s-s-dEE5m al f rac ti o n ) , b u t-i-r%c a se sha l l the LLC, ar sciccT'a ted in thi s manrc e f o r a spec i fi c rac ioi.U~i-ice b e a r ca tt r
~
than 10; of the l'PC val ue speci fied in 10 CFT< 20* Apper2i.i B, l Table II, Colcnn 2. ,'
,_ -["
b g. A c capo si te se :'pl e i s o ne i n v.hi c h the cua n ti ty o f l i gt,i d sannl ed i s proportional .o the cuantity of licuid waste dissharned and in whicn the method of Sa ipling employed resul ts in a spec 1. men v.hich is repre-sentative of 'he liqJids releasCd. A v s re n : --
. c f. To be representative of theaccantities and ccncentration:. of radio- A active-- nater m.i. c i s--i n l i c'li d e f f l u. e_,n t s , s a pi e s shal l b ee c ol l ec te d f,o_n .tlrtp s ty . n pr e;o rti on . 1.._,e, 0 c ra .e c; tiow of tf~e e f fl ue n t :. te c am .
Prier--te c-clyr* c-ell-segle-taken-for-thc-c-crt%i-te--@a 14..rm t he reug Hy-r i x ed-i n-e M- -feHhe-c c~ es-i-M--s sy4ta- M--rep r e se o t a - ti ve-of-thee f Cl uent- rel ea se s el ,pf A batch release is the die, charge of liquid wast;.:s of a discrete vol ume. 3
/' C A continueus reic.ise is the di charne of licuf d ostes of a rnn-di sc re te volcne; e.g. , f rom, a volure of systen that has an input flow during the continuou , releasc.
- g. The principal camma enitters for which the LLD specification will g/
apply are cyclusively the following radionuclides: Vn-54, Fe-59, / Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-1R - This list does not mean that only these nuclides are tcyc'de tec ted l 4 reported. Other peaks which are treasurable anbidentifiahic, ! toqel.her'wi th the above nuclides, shall al sc inddenti fied and ' rep' o rted '$ glides which are belcw the lj.D'ior the analyses shcul d j not be reportc' dyeing present at,tht/LLD level . When unusual , circumstances resul t%LLD's Ipr:hJr than required, the re00cos , shall be documented in tiiNc6iannual Radioactive Ef fluent Release . Report. N W. BWR-STS-1 3/4 11-4 N .
,,,y.g,e y. g g w we * * - - -- + M 8 -N yWpg
***~'"N.* e.e , e mog y me 6 e _
*h gog g w e. . . .e ,.
. s. . ..
9.. ..
.i . -* l .', . .-, w .r ,-. , ._; .
.. .yg l
{ - l '. :g.-{.4 .. l l ,,
- , , .. . . .g i ,
. ) . , , . M.. ,.m a. 4 '~:. , : .i ' 1 l
< . , . . , .. f .. . ~ .7 . i. ; , i
.r . .
..__- t i
, ._ .- - ', n- l m -
\ s' ; ,
.[. .... _. Jf ,.r,_r -. i. ' ;. . ;.I s
- I
. s .'e, - ,e, . <
. ' . t i
.~f .
' .. i ,
. a ,,.
. ~ .
s e,. 'p. .- - - , . t- _ > n-t.l . J :i I. s
. - \ u. .
1 :
.l
.,9....
- -p ..-i i.
- . - -y
;i .
.L .- . j _ . . ,
i r g 3 g..- m ,, .
.4 .4.-_..
_.c xe . lu_.. t. >
. I . ., _ .
. a j - y.r . .
.,~. s ~
3
, .. ., . ,i n. . .-l
,. .. s_., ,. . .c
.-.._. . .,_ a -. _
e' r 6-;-< - .;.
~. .
._... . p ~ l .~ ,
. i
,t y., _
- [ ,.;, . . i
; :- , , , _ ; , , , . . q
. 1.'. ,
.. '.J f . -. 3.
g
,;J ' G..,, -
. r ,.:.1, .. *,, l . . . . . t , . .; .
. . v ' / ,
- a.
- r. ., ,
~,.
..' ., s a
<. I. . , , , ~w.j
'j ' ., . . i. *
- *1 '
- e. .!
- t , ..s' ~ s
" / i,
- ei --
(
..l_.,.. l , _ . _ _ _ , _ _ _ , . c,,,i_
.. g ,.
...t. ' 4
**~. . ~f . #
~
l., . .W, .. t
'\
' .j, - l i- - . . , , .
_ .e .. f.,., ,, _ . . , ,v s 5% - !eR", ; l .' ' .
.l .s - M. ,.'N.--s,,,.
, . ;j, ; . .
.'. ,t..,
..s
. s. . e a .(. , ,
. . . . . -. l' 3
- .. ,y. .M .g ., l. [ .
- r. s .,.,\,. . _ -_..._._8__. .
._./'__..,__,,1%,,
p., g ) *'( , ,. i b,. Ii
.t' j _ ;. . re : {, g j
-) , ' , ,
. _ A '.t'cs.
, j '- : - ;.r ~ * ,. . .
'I ' r-1 .'.. ... 9 l . ,, .$ 8
.~
r
. g g
u.
.- ,t '-
1 (' ' , i'
,~ ' j '*. ! {:f.:.,- -[' ["
* ' ;/ t, -
/- y
~ '
li t
-(!
'-- .l
!,._a -
._..-..-.4-. i--
r _. \n ,< _-
--.i L. ; *. . . . . . ,
,/- ., /~~ '
i .-' k .e f
, , , .;f *
! ^; ','y,,.
. . \' . . ., c. , *
-{ :. > . ' .- ',
,e t e
., . , ~
( ,i
'.- ; c 1 ., A r . . s. .
,',1
*y-]
,,4, ._
- I,_,. . If' , ,
l
.. . - . . . - : .- 0_ i .c 4.
i
.,,..Jf ./ ,, 2: - _ l 7
~* .
- s t ,
b
-i
.z g
. ,i l i
' ,f _
u,.
...i I.
Gf."s'-- /,.,m._, , a,
. (,
- i .-
.I;-
.s, J . ,
q' , M - I t 1
' I l
,9 , )., .,
i l7 -j, /,.t . ,) .. l I
-.m.
- s. ,
,- "N;9. . , . ' , ,r_ ' ' M, . ~~- I . ' .- _ . -.
' s Ii - i i, .: l
... s ."._.._. -.... ,
_ 3 . ,. ,
,.c ;
- I,,(('
. - mme eres m.e.~
. .... p i:
i
; - . , j .
.t. , .. . _ . . . i , .
.a' g - -- v .m .
6 _;,,_i _ _!. _ _ _ , ..t. - l _ _ --: i i
;._r}:.! _s:.. .. i ; 1m l uo ,_
- 5. ,f o. 0,.;. :i. % .__ H_ __._e; 1-r. i v, . i. . . I
. . is
>. p a. a., ,;, i, n. e. .h, , . ..
i . l-
. m ., i . . <
.t;. ;; .
. . I. ..-
J,. . .n. - i ,, .. i,. i,
. m lq . . .- . t
.V -
I al' * . i. - t . . . e - .. t . -J
-6 4
* ,a, . .-
4 .- I c}* -]f. - . f.n. L, . . . . f,
,I .
l . .
..r. e l-l g
..}1
' .lt:- .
___.1._4 no_ , _ _ _. l k;. ._ _ _. __ I __ __i . _ . _ _I.i i _ . . [ sk '
.l '
l
), ..
.J , . -.f .,
E.. e j a J - t l s
- t
.l l
i I.
.i
,. . .t -
_. , .% . - , '. . 6..,;- -. --- I
,i I ,
- l
. ,) . ._.
- ,t . ' '.
I
.s [ . ,
I l' l l e
$ r ). .
4
'88-. * " * - *- - * * *
* * * * *
- r .e ogw.gg , .ee-.M- **N . * . * *
. .-. ..~...... - . .. . . . . . ~ - .
\
N' ,
\, ,
, , ,/
/
f*\ ' i i -
/
/
/
/
/
/
/
/
/
/
/
/
Thiqfigere shall,'/consi:t oi t.c.1p of the site crea'shouing the vr"e- . area ,b'oundary for ii c.:: d seffluen tr ic th(t* c ,6t ri r.;d i n 10 CT T ;. t
~
(* 20. 3(a ) ( b3 <'
- t. .
.. N Figurc 5.11-1 i . \ s
, \ () ' BWR-STS-I 3/4 11-5
\
s
. _ - . _ . . . . - . . . ~ . . - , . _
.._. ...s. . .. -. . . - - . - . - - - -
=
,. r PIDICACTIVE EFFLUE!!TS
, DOSE
. - LIMiill:3 CONDITIC'i FE.T.1PERAT10N 3 a. bu c 6 <.h yi-c. '. 3 3.11.1.2 The dose or dgse comnitncntato an indi'.; dual fron radio.::tivt ma terial Lia liquid ef fluents released to unrestricted arcas ( s. >
Figurcd. ll-1)I shall b[ea lini ted: Oc,m ,r, . mrr-" . 3 . W.1X- 1 c cotA. x.f,
- a. During any calendar c.uarter to j 1.5 mrem to the totcl Lody and to j 5 nrcq to any organ, and
- b. During any calendar year to j 3 mrem to the t:stal body and to i j 10 nrca to eny organ.
1
!APPLICAEILITY: At all .1jmes,
~
i .. ACTI0'P I' a. Wi th the calculated dose fmm the release of radioactive rateriai s in l'<1uid ef fluents exceeding any of the abc.e limits, pr( Nee and submi t to the Cormi ssion wi thin 30 days , pursu3nt to 5;eci fic.5- , , , ti o n:S-o 't , a {pecial Report which identifics the came(s) for c/- ' I h,.
'Gding tFe ljoit(s) and defines the corrective acticr.s to be taken to reduce the releases of radioactive materials in liquid ef fluents duripp the remainder of the currcnt calendar cuarter and during the subsequent three calendar cuarters so that th;-
average dose ore dose ccmmitment to an ir.dividual frca su:h re-leases.3 d urin; these four calendar cuarters is within 3 r.rca tr the
/ total body and 10 mrem to any organ. Thi-s-Epec-iM epn e t-sh a l l e aho-i nc i t. d e--fM-th--res t+M s--s f- ra d ? Aog i cat-a r,s i-y s e4 - o f- t h e-
,b -drinki ng-w teF- sourtcra w-R-)-the-d ei-epiec 2--%ec t- or p/p)'- 0:
fi n i shed- d r i n!+i no-we-t wep pbi c s-*i-th-r+;.yd--tc 2.he--r e ut i r een t s
' F y# V o f-- 40-CfR-141 ; 45 f e-Eri n kimg-we te. --/ e t , (44pi-ice &16-oniy-i t
, -d rinki ng te'r Isupph-i.s4ei errfwo--l -r+c+i+ing-wa-t e r-W441 b . GO.nc:.w.ti:n -
c,K Tiie provlsions"of Speci fications 3.0.3 and 3.0.4 are not [ applicablc. SL'RVEILL ANCE REOUIREf'E!n S 4.11.1.2.1 Dose Calculations. Cunulative dose contributions f rcm licuid ef fluents shall be detcrminea in accordance with the Of f site Dose Calcu-lation nanual (ODCM) at least once per 31 days. I 4.11.1.2.2 Renerts. The semiannual Radioactive Ef fluent Release Report i shall include tne infoma tion speci fied in Specification .6ert-M (c. (o.C.3 %
^
-FWR > a -f' 3/4 11-6 i L. b C S -l 9
-. g go . . e,.. --*=-e= Wamt M- 9 " * " -*N'- ** NM"**' '
)
(f. axtt.c. J-
-- )s N -s_.-, .
/
O..f- k A & cpr.- y. dm
~ s o.,x.mLLJ A 4> A sr 2.0 7 l -
h
' . prepare and s o!m.. i t a S p .z r. i a l Report to t he Co"t"i s s ion pur'uant to Specification 6,6.C.f end limit the s u!'s e tpic n t releases such that the dose or d'i .e conni t"H n t t o c. real l
i n<i i v i d ua l f roci all uranium fuel cycle
'on:ces i s lID:i ted to G 25 rirem to the total bod / or er:y organ (e y.c .p t thyroid, which is l ir,i t ed t o 75 ruroi) over 12 co n s ec u t i v.' e oths. Ihis Special fie n o r t shall i nc l u<'e an ana l y",i s wh i ch dewn-s t r a t i" tha' rad ie t ion e>:posures to all real i nd i v i Oj a l s f rcra a l l n r.in i u 3 fuel cycle seu:ces (including all effluent p a l l r. . ' y s e n - direct ratiation) are less t !'a r t'i_ 'i O C r r, f5 r t 190 M onde rd.
Otherwise, t.htain a '/ationce f ro:n the C<.uwn i s s i on to permit releases which e>.ceed the 40 CTR Part 100 Standard.
/
't
\
weg .,,, , ,,,, , ,
~~*'N""W' _wew m penggue%-
- r. . . . . . . . . . . . _ . . --.. _. < -
I :> . e . f r ,,a r ,, 1,.t- - -
- rr t. i. p i -i.r i
.s
. t.
e ...\,
.e*
y 7 t_. * . v . ev i i t,1 ' il i'- 1, : ! (; TI r GD((T ![': i 1.11.1.3 i tt licuid r:@a ste trcatment systen sh311 be OPb' ARLE. The s . '. L - it.11 be U 1 to red'. the radiocc tive raterial s in liquid v:a stes
; r i:- to*- ir di v'erge v:ht a tN proje : ted dose due to lit;uid ef fluent r el t ,ec *-
u'.rer ::.ted arc's ( see figure 3.11-1) vener, everar:ed ever 31 m c-j ,f . , - vo . , e e,; rrET to tha total body or f R,nrcc. to any organ. e
?-
' - - * -%u g 4,
- .w. . s t ' '
'f, m!C?' '
At cll tim e s . O,d 1*, ~ .4, .. . e
- a. ',l i . rar'n :c tive 1 iqu' d we stt being di scha r 'ed wi thout treat" ent r 1 in c- : ef thc ab 'ee linits, prepc re sad submit to the
' Co rissi, r7 i Sp...ial ' .d-titwhic in ?' da vs, pursuant h in'cludes to :pu.ification-6:M[,
the foiloeing infornation:a.. -- (c .U .C' l i ). l<icnti fica t ~ en cf coui pmcr t or sub syster:: 1:ot OPEP.ACLE and th: rea wn .; r r.:noper;hil i ty. l
.% !! 2. A: tion (:) tder ta restorc th: nonoprshle couipcnt to
! 0E P. A . '..: states, ij 3. Sur- j d:r:ription of actien(si ta(en to prevent a rccurrence.
h I
- b. The prcv < sic e; of Spec i fic a tior. 3.0. 3 and 3.0.4 are no t applic 81 e.
'l
__1. t. '_" N n ' i ]. . _ _ _ _ _ _ _ _ ' . .r ;; e i 1,_...._ . s u m._ _ __ _. .- lI:4.11.1.3.1 Doces due to lieuf releases to unrestricted areas shall be !
. pr ej :'. t ci' c t I c a n t o nc e p.- r 31 d a;, : .
j 4.-l h N 2-- T he-1 : qui d--r+1-v i.:-sy:. tem -shal-ba-d e:aenstrate d -OPEP. Ai> L E e t 1 c es t-e nU- pe r--9e , yi "lc:. t h--4i qu i+vei.e sit--sys temh at- b een- u t i l i ze d i I te-prc c-es s--rediMe ti ve '-iquid-c C fl-uen t s-deMng---th _--pre eious-92 day 5. l 1
- i. i
. i i I. 1 . ' I I I
. Fn'R-S T S-1-~ 3/4 11-7 t'
' L 5C.5 - i 1, O) t 4 5 d I e
-. . . . - . . . . - . . . - - . . . - . - . - . _ . - - - . - - - - - ~ ~ - - - , -
s-. .. . . . . . . - -
's . ,
\
/*
/
x . .
./
'!PI,D U't Ci I VE EFF' "r' T t /
/
L 10 O Eo'."d';' i t L c L I M! T '. f:", CC'D !i i P. FCT: F :T'4
's s
\ /
3.11,. l . 4 > The quantity o' r: die :.<e m- mial contained b each of th
' folli',-ci na tanks sh'll be 19 i tc; i <
s - curies excluciss tritiun and
. dissolvrd or entraincd r, t e. n '. .
\
.- c. N
- b. - - ,
N
, c. s I. al1 t' s.
[, ' "tl I r f. r. l L I T.y': -
~~ ----
ACTIN: I
- a. Kith tl- c'an'tj', c f ra';ccti 'r % rial in ary of the ahcVe l' listed t r';s ei .;uir., .
x c t ~. e l ir.i t , ic.ediately su , rend all l i add i ti e n s o f r c . .;.,; c t . . c'.:ri.'l to t!.e ta r' and wi thi n 4' hr! either rcdu;; :. r.1 c ont , is te wi thin ti.e lini t or previde [ rorpt n0 ti fi c a t i >rft' C' . .;ic n pursu;nt to Spec i f . c a-
! tie n G . 9.1.12. T r ~. r r i ' '. . felic p report shall include a fs
, sc hed t-1 e an d cc '.' -i r t . c f a:ti i ties pl ant.. d and/or tak en to redt:( thc ta ra. c c 'C' \
wi th i n t! e abo'. e i ini t.
/
/ 's
_. b. Thc prc 1.icns of acc' . i '.: : : ., 3. 0. 3 a r.d 3. 0. 4 are no t a;plicatie. / ' \' l.
! n ,, ,
- . S 6.., o. r ,d ,o. u. . . -.t-- 3,.r....._
/ \
4.11.1.4 The twcrti t., c f radic :tive natori:.1\contaired in each of the abcVe listec t:.nks shall be det - ir-cd to be '.<i thin the cbove lini t by a n al .y z i n o a r, A, r e :,e r. t a t i s e m rl ., of the tanh's c'tntents a t least once iper 7 days , hen radio;;tive nair. mi s are being ad5 <d to the tank. I I
/
l , l_%7isincluded in thi s Speci fic ation are those outdoor tanks, tha t are no t surreunded by liners, dites, or v. alls capable of holding the tant contents and that do not l' ave tant. overfi uws and drains connected to the l-(quid 1 radwa ste treat. men i. sysicm. 4 i
- BWR-STS-1 n
3/4 11-8 e-s
\
\
. \
.'..'..'.,. ~~--._.- --- . . . . . . . . - . . - - ~-
'S RAbl0ACTI'VE EFFLUEt:TS-l3/4.11.2 GASEQU5 EFFLUE'!TS i
'D W RATE
[f iI!11 TING CD'!DITIGH FO? OPERATIO!J
/ r a\ ./ '
The dose rate at any time in the unrestricted areas ( see
-n\,'3.11.2.1
[(,/ ).( 3.iiY- ffd:T Ge site shall Ficurefn-1-:-) due to radioactive materials released in casecus ef fluents l i be limited to the following values: ' l h.. N. a. The dose rate linit for noble gases sball be < 500 nrem/yr to I the total body and < 3000 nren/yr to the skin, and {: , t' Y
- b. The dose rate limit for all radioicdincs and for all radinactist h y$" 't naterial s in pa-ticulate form and radionuclice: cther than ncble ;
,, p lj gase s wi t% bd ,'--l-Ms-grecter tr.are-E-dv shall be < 1500 rrtc/yr 3 to any organ.
- u. j, j.
fA / DIllC AF:lt ITY : At all times. I. oyc
,f d s AC T 10'1 :
{
' t. LJ e Wi th the dose ra te( s) exceeding the above limi ts, immedia tely dec recse the i
/ p rcicare rate to comply wi th the linit( s) given in 3.11.2.1 and provim x t t' 4 g,; y j preg t. noti fica tion to the Corni ssion pursuant to !?eci fic ati en 9-M1.-*J^ . .
b (h t o G.G. B.D 0.k i ec 2 - SUR',EILLANCE RE0UIPEFEMTS l y ; h _._ . U ~1 ' h, k "hg,
))
?
4.11.2.1.1 The rclease rate at any time of noble gases in gaseous < filu-ents shall be controlled by the offsite dose rate as established abcv: 'n . 2 6 n Speci fication 3.11.2.1. , O w . . . 1/ f )< k { 4. l' . 2.17 2'The-nsMe g3 s ef fl uent continucus meni tors -E hav.t.ng .previ s1 n: TiTtc
~
d i n T a b i e 3. 3 - 12 , 2fG2 pJ f o r t he a u t e m I.i c te rii n3cli'UM eet u ud r.a ce Vf- shall be used to 1ini t_o.f.f si-td5iG thin'tliel.h:cs-est&l.i shed in j
.3 ydN
,a Spctifica ticTr 3'TC271 v hen moni tor se tpoint values are es ceeddiT -_ .. ,1 j ...___7 w 4 6 l
f j '#g v" 4.11.2.1.X The release rate of radicactive naterial 5, other than noble ; d b 'g Mh O 6', , semnies gases,and in gaseous ef fluents perfomins analys.es-shall be detemined i.n accordance wi th the sa=r'ina byand obtaining ana'rsi: repre i I . program, spec i fied in Tabi c(4.11-2. )4 .11.2. ,1 -1 '
~
!} 4
! 4.11.2.1.R The dose rate in unrestricted areas, due tp radiccctive nitcri-y al s other than noble gases released in gaseous effluen ;s, shall be
. detemined to be within the required limits by usinn the resul ts of the sanpling and analysis program, specified in Tableg,% D in perfoming
. the calculations of dose rate in unrestricted areca.
, 3' - 4.3. I k ; 4.11.2.1.5 Reports lhe semiannual Radioactive Ef fluent Release Report i
'] !~shall include the infomation specified in Specification M-1-434(o,6.C.b ljBWR-STS-1 3/4 11-9
_,,-.-wMW.P**mu88W1d D .Wm.'-* . n s 5 -=a .
\
J
,/ i
-1
.l
/
/ .-
i
/ i
,/ ,
, - ' l s TAILE 4.11 2 i 'c \ RADI0 ACTIVE GASEOUS WASTE SAilItlMG AND A ALYSIS PROGRAM .' ,- N ! I Lo,.er Limit of :' Minimum Analysis Type of Detection (LLD) Sampling (uCi/ml) l ?s Frequency Activit', Analysi Gaseous Release Tyce Frequency _ I 3 P l P
! c Principal Gina E-i' +.crsh 1 x 10-':b A. Containment Purge Cach Purgec ,d Each urge '
~
Grab
}l-3 ,
1x 10-6 Samele h 1 x 10-4b B. i(' ' I (List other release orab TIC \ p 'r'incipal Gama Emitters P points unere gas- ,e ' \ti-3 1 x 10 l ecus efflucnts are San ple e discharged from the i ?- facility, e.g. air
!. ejec*or, equipment T vents, ventilation exhausts,etc.) '
3 , l x 10-12 f C. All Release Types Continuous 9 'b0 Charcoal
,/ /
I-;31
\ -.- ,
4 as listed in A and Sarrple I-133 1 x 10-10 j B above. Principal Gama Emitters" Cobtinuous9 UO - 1 x 10-11 Particulate (1-131,Others) 1 Sample -
~
Gross a b 10-Il
~
Continuous 9 M
' Particulate Sample .
/ / ~
s
/ --_
Sr-89, Sr-90 1x 10-II N f ,/ 3ontinuoud Cr'c ,osite C Q N
! /
rar'ticu1 ate , ,
) ,,l .s upic , .~ #
x i ,, ., . 2 / , 5
. e..,- p t I i
,'1 s
l t,., e
*; ** cs s se e
.I g E A L.,
" I e e cg
.. i n .
- v. ca, t 1 *J (4
- .- c- p e,,
. . . . . . - . .-. _n . -
C I e a. I U U v v f. 6' r >= *J
. '.. ~es n s.s o C f.' O & "& w u-
-s ,
., ~.1 --
m m .- ~:
, o
*
- C-i # u a.,
'. atx s O ".
u- -r . is ... N C a-8 - J k. I _
*s *J C6 C.
V ") O t V F 6 4 i i O r L .i . :- 7 _3 P 'I ~~ C . 12~ t o e t-- C i C. L' C U r". L^
.',~j 6
e i 8 r ... , , , _ , _ , , , , . . , , , , , , , , , , , , , , , , , , , i i 1 I
** -1 1 6
i i
--9 1 i l
'l 1 j Fi l
- f. <
l ,
- s. } 1
{ p t i g/* k' ! i .' 1 I
'f 3 ti L9
. n t.
s'. s e r c. o .
\i +-.
- Z. q
L y g: e
/
.I N . .c .c
^
*e .* u
) . C f: C l
; l l - o e c w
' L> v u 6
( =, \. s
.,, j --- - . ! -- - -
I
- c. l -
e 3 O T
..d e 1 r .;
f
;} }
t
._3 i. ,-
i i i p b- j i'
~4 q r
I . c. .-
- 6, t,
., t
' c; u
- i ',(# p 11
+4 s
* . 4s
.- - ' e.. e!
g .; .- gy (3 .
- 9 l - .
- r. , so es .
. .- ve L s p'. t ~ C L,
- "- a - La ,o
'3 0 s; Q R
. .. K .) -
s' ' G 'n
+g C; +4 I- O e ti.
V .*
- a 6
*.--... -~.. - ....... .
e
/
g ,e C ,,. ) .-. . . _ ,
i 7 t ri !. P.- 7 ( r on t i n u.: d ) Tl r ti?TA"10"
- c. 1h l o < .r 1; .i t c; ' detecti.n (LLC) should t.c < 10's cf the cc - -+ , t i -. - .occi' led in 10 CFi' Pcrt 20, ,'<pper. dix E,.
l T. f. l e II, c ol u 9- The l o..c r limit of dctcctibn (LLD) {
.n ichl; le.n n .i c,r. a. of .at, e *._; c,. S p e r. .i-
- e 'i i m.- n l
fir: tion 4 -- C ' '. - l I o. l 7. . l e I. h)\ <g A \ -
- b. i n -' W. . . , s t :I r
- 3, or sii.ilar o; rational occurrence g
- t. ' . i c
- c<. i altcr tb n i >; t u .- Of radionuclides occu- after
?. . l i n .: , - _ * '. e r . : lysis thall be perforr.cd prior to
<,c, ret
- c. I n i ! ,- t c : ; c!! al- Ec perfom.;d at Icest cr.ce per 2h hours for 7 ci , : l i c. : ;. cach shardc.sn, s t r. r t u r, c; r si.ilcr m e m aticoli occtrrcrce v.hich ccold lecd to significa.
i.creu?cs er teciccits .i n rc g. i s i c _ i r.c relceses, o
*
- p i
, ._ .e. e e
e 4
- e
" ** * * * ,,,, , , . , , , _ m we
^"**MM M
ememe+ 99 +--h er *e. e w e e e'*-u-*-***N*** - V eww m- pq,g y q,,. ea
.\-
N P N , ' TABLE 4.11-2 (Continued! -
/
s ~~~ TABLE NOTAT 'ri; /
\ /
- a. The lower limit of detection (LLD) is defined in Table f.sdation a. of Tabl e 4.12-1 of Spec i fic a tion 4.12.1.1. /
s b\ Fcr certain radionuclides with icw ga ma yield or ice / energies, or fer l
\ certein radionuclice mixturcs, it may not be possible to neasure radic-knuclidet in concentrctions ccar the LLO. Under these circu stancas, l
,. th" LLD nay be incrcastd inverjely pro;ortional)'. to the magnitue of .
tht , car,' yield (i .e. ,1 x 10* /1, v here 1 i s the j photon abundanc e exp?qued as a decimal fracticn), but in no ,cese shell tre LLD, as calculated in this menner for a specific radionuclide, be greater than ID*., of the IU C value specified in 10 UR 20, Appendix D, Table II;xColumn 1.
\
- c. Analyses shMi also be perf0med folfowit.; shutocwn, startu;, or sinilar operit,ionci occurrence rhic cculd alter the mixture of radieruclides.
- d. (Deleted)
/
- e. Analyses shall also be perf,bcd at least once per 2* hourt for 7 days g following ecch sbutdahg piartup or siniier operaticnal cccurrencc
/ which ceuld lead to Sigdfic;nt increases or dccrcases in radio-iodine releases. Sarp,iIr(shcil also be cnanged and analyzed at t! e ir terval s in Spec i fic6 tiors\3. ii .2.1 and 3.11.2. 3. When sargles
._ collected for 24 hofs are anc,1yzed, the ccrresp;nding LLD's nay bc increased by a factor of 10. N Tritium grab san / shall be taken 's
- f. ples at least once per 7 days frcr the ventil;tien exhaust from the spht fuel poci area.
/
- g. The ratio ff thc smpl e ficw rate to t.se sanpled strean fl ow ra te shall bejtnoon for the tine period ccred d by each dose or dcse eci fications 3.11.2.1 I rate calcul ation made in accordance wi th 3.11. (2 and 3.11.2.3. I
- h. Thp principal ganma emitters f or which the Llosypecificatien will apply are exclusively the follcaing radionuclideq- Kr-37, Kr-88, Ae-133, Xe-133m, Xe-135, and Xc-138 for caseous cr.;i ssiens and !'n-! 1, Fe-59, Co-58, Co-60, 2n-65, h-99, Cs-133, Cs-137,\ Co-141 and Ce-l M for particulate emissions. This list does not rear. \he t only the< <
nuclides are to be detec ted and reported. Other peakb which a e rneasurable and identi fiable, together v.ith the above nuclidc , sball j also be identified and reported. Nuclides v.hich are bel nw th" ll.D j for the analyses should not be reported as being present at, ten LLD ' l evel for that nuclide. When unusual circumstances resul t in LLD's higher than required, the reasons shall be documented in the teni-annual ef fluent report. B', R - S T S- 1 3/4 11-11 'N,
\
\
\ '
i
/
- - - - - - - + - - - - - - ~ ~ - ' " * - - - * * * ~ " * " ~ ~ ~ " ~ ' ~ ~ ~ * * * * ~ " '
~
**a-*==- - - - . ..._..-......e. - . . - - - - -
U.0!nt.r!Iyr EFrLUT4 s E5 GI
- g. -{ -j I, LO E , ti.O_CL_T i L1:'!T :'? CND! TION FOP CPErtTICU D L*',11 --I >
'3.11.2.2 The air dose in unrestric ted areas ( see Figure -t-t-l-) due to ncbl e cases rcl eesed-.ij._grJss..cLf.luents shall be limi ted to the
'follcaing: :,,
, o m uwr- -%g,,
- a. During any calendar quarter, to j 5 mrad for gamm.a radiation and < 10 mrad for beta radiation;
.. l i c. During any calendar yea: , to j 10 mrad for genna radiation ar.d i
-< 20 n. rad for beta radiaticn; G he- d or.e-de s i g n-etj ec-ti v es-shel-i--else -br c-red uc ed-b a s e d -on- c o -- :
yet t d -pubi-i e--ec ce;-eney-e he r . . , . . - . , bec hes-and v i si to r - i -cente +-w W - th+- e m M M M- . '. a . g4
'ADillr ett:Tv; At all times.
y.,~
- c. Vi th th: calculated air dcse fecr radioactive noble gases in
'g.v.ec.2s e'fluents excecdin; an;, of the abcve lir.its, trcpre cri sub ,it tc the Cennission within 30 cays, pursuant to Specifice-m tion +M, a Special Perort which identi fits the caust( s) for
'kSgJRieding tPe limit (s) and defines the corrective actions to
; be tRen to reduce the releases of radioactive noble 93ses in casuundfluentsydurir; the rcmainder of the current calence
#._ quarter anIdDFEg the fubsecuent three calendar quarters so thit the avera':e dese durina these four calcnder cu rters is
/.' -[rF 0,'+i
{v wi thin (10) -Ed for gamnar 'adiation and (20) nrad for bet 3 ra di a *._i o a._ ..__.___._._____..s
\D'Y, ,
P b. G _= ,2 g3;L__ _X~ , / cl>'. Th9 prcvisions of Specification 3.0.3 and 3.0.4 are not appl ic abl e. ISU'"!EILLA!EE REQUIPEMEt:T5 l 4.11.2.2.1 Dose Calculations Cumulative dose contributions for the total time period shall be detemined in accordance with the Of f site [Do>e Cal cul ation l'.anual (OCC:1) at least once every 31 days. i jl4.ll.2.2.2 Reports The semiannual Radioactive Ef fluent Release Perort '
!'shall include the infomation specified in Specification 4-Ale.
i~ 6.L.C. o BUR-STS-1 3/4 11-12
-m.* p Ne M gmO g weO.uia g S -g-@6 ** .'
. ~ ,.. > _ _ _ _ - . . -- - -... . . r %, p td S C l?-T 3 5 I' E C ' # ' CD b Ob lith' I it'i t r i are exceeded by a f actor of 2.0 ;)repa re and sub:iit a Special Report to tht Ccor r:isslun rio r s ua nt to Specification 6.6.C. c r.d 1init the sutisequent releases such t h.. t the d. ses or dose co nitriant to a real ilad I V i tle t.* l f i U! a l l ll r dil i t!"1 fUuI Cy r. I t* sourc es is l iini ted to < I'5 nr en tL the t St il lW ' / or eny Organ (except *hfroid, which i r, liri ted to '; 75 raren:) over 12 c o a e c u t i ve l'.un t h e, . This Snecial Report shill include on analy!,i', viich demen-3.ti..tes that radiation exposures .o all r e,il individuals f ren all uranium fuel cycle :.ou r c e s (includirc all effit'ent pe t li . iy'. ond d i r e c t r.rdiation) are less t h.n: the 149 CFR l' art 199 Standard. w Otherwise, n'at e i n a va ri ance f ro.a the Co'n-a s s i on to peinit rel ea se s u'.ii c h c>.c:uJ the 10 .fD. Part 190 Stande -d. 4 w wM e
m
/
~ ..-
' ' s (' t r F-l' D Fr G D / C
.. t vos '
- .u prepare
, ta p. 3 + t., t! .
.. to 5; .ification
'. t,t :' . . t. ot r I rose . c C o ,. ,-, ;,1 t r . n :
; i .. I._ 11 uranium i e. 11 ! ! . - <t to <25 mren
.- a- y in ( *r XC ep t 1i: i t t > 'e75 r -a d I r u.
l il i ', $p*!C i a l
; . an . 1,'i- v.h i c h
,U f t? 5
- r v ! i . ' l '. r' t y p'
- i
. s } c. f ot' .t l I UFdMIU9 I i 1 ; C } t ? 'i '. l l' <1 } \ t: ( f } L! t* ft !
r%
.4 g .- i.. . ', - i - .) a r+: 1ers i
. t"T ' i i.1 d a d .
,, r i . i n c . . ( !' D U [IlE r , .
,* r. .,t';
' \l 'kCI g , - e-* } '. ] , ', . : 9 8 } < 5 F d r i i I
I e 9 h 9
- -4 . - - . . . . . . . _ _ . . _ _ , . .
D i '
'rt.r> ;:,r rrr t.. tc . .....,u,..
- .. ..--u,.,.
P_.I D !- . .__! .t .'- _.- j L i r",1 : v tr '.: a ,r. l 3.11.1. '. Thr - i m. , , r a. ' -
... i a c: -
lr:.at-i..\r;r.., <
.c
. tb t
.',19 ,. .
l'
;wi.ti ' 'f li, . s re. .
i t u . r e. tr c tt d e ' _
'. . :o t. f el: .. --
i
. ~ . . , I f
- a. Dur u .: -
! .W. g I L. Dur m . "-
. . c. ', ) !
- v. .
;a -t r h - . : .
,. -v. . % ;
- l _.w 4
;. . ._ : f - 4. 3, ;. 1
' l,
.,.,r+r i
. 't..
i _2 i m...
.,l . .. I
! i
' ACilC': ;
i . Vi th tv. c:1 ~~ el e: c f r a c i u i c d i 'v s A ' t.' n
- a. ' -
I, r60iO *
--f ' - ~~ OT-T ? d i ' ". U ".1 i ' C T g,s i .
Oth"- no' i.* f'i t' stecdir an. t f , l, - e c. , . ' . C c - : i u w i " - c'.6.C.I
.! the c' c. e iir ' : c, ;- t t- -
'} ,
i n d. %: . p- : .a -- ' ' .t_; . . :
.- , a S; : 13i uc.pri - - + -
i i wh i r. l . i cnti.. -
.' r:c:.' : t' r lim t ard l
dcficcs th ; c. ct i t ao ts'.:c" to reduce t!.c rele" s of
- P -ti'.; m_ ' - ial; i" ,'o r t ir -
lat .' .r-c
; t. s .
thc r: ic ccccs with-M1'= iivc r -te .
- ir,":::cu eff -ts curing the i rcmi n : e f '. . co- . . ' ..' . c.u a r t ,d durir.3 the sti' sri..nttH. cri - 'c: tds 50 n. . ; t' r 3ver a , dose .c - -
i dos- ce ii tm. tV ' ' 2 ' .> i - 11 f r' r .n rel ea se s 'd. --e-crino~ 'x l s.t.h. s c _ f c u r c d u d : r
. r te s i: ,,i thi r -{ 1 '.Q mrt<r, to any o r":a"
, b .C <y...a I%
- c. -L i liis pi c. i siere ef C; -ifi:3ticr: 3.0. 3 c r.d 3. 0. 4 c r e no t
^
appliccble. t g#,
. x 4..~
cp~ . A.
, . , ' ,' s
; S.U_R V.E I.L. L M. . .C E...P. E C U..i ".D D n.3 - -- -.----- -- --.
1
!4.11.2.3.1 Do".e C alcul ti c r - Cirul ative dc:e contributions for the total l I time period shall be dett e n u, in 0:cordar.ce wi th the ODZ a t lea st ok:r-
! cv e ry 31 day s .
I i
,4.11.2.3.2 Renorts The scmi r. mal Radioactive Ef fluent Relea',e Report , ,
'shall include tr.c infe n.a ti nA sp.c i f1 d in Speci fication 971; 9. (. . C, . C . .
("% o
*w*
UR-5 TSTI- 3.4 31-13 L.S c.S -l . . - . . - . - -
---~- - - - - ~ ~~-- ~ ~~ ~ -~' -- - ~-
i.,_t.._--...-_
.. t \ -
,1
\
REDIDACTIVE EFFLUEhT5
'J *\ \ . ' l
,,..~ ,
l GILE 0US p/D'.MTE Tij *.T!TM .
/
i Lif'lTING C0hD'T10E T O V I.'ICU .
/
/
*. O s- t= - G n ,, o? E c.:,rn n ,~ r. c n r,- r: c. . n L \ ,
~~
i 3.11.2.4 The gaseco:-redeaste--t-ce W t s;. .ttm and : eMi-; .' U c r. . L-. c -
- m. t r eet,mtnt-sys tem s hall be C' ET. ABLE. Ibe es : 0 0. .s-< c : . * ~hr e e t -- t . - .
i
.r e 4 A ,s .?-shall be used to redu:e radiccctive rat 2 rial; in ca: .. ; s (s t e -- , i:r .
( M * "#' '" g...j ' to v - . : - their discharce wher, tre pr ojccted gascour ef flueEt ^ , c.o g : - . n rt c ,c O.
,_ ,.e-f f.l ue.nt. p- -rel - ene r. >tc un rec t-ic ted arca s ( se e Fi g'.ro
. -%f, - e. : r rl- - _ ,( -I . y.. ,
3 e s p., ' ' ; cv .e- r. a. -., caa--- y s v c. ul d e v.c ee d -i . . .- rra d f o r g ar u r aG ; a t c r ,. a+ ,_+: . .W.. t c~ ' . n ac i a ti o n anc tit-v er t h-stion-ed v.it t--tre e'y n t-sys t: - : L- U- h ustJ t i
. rMe:Mbe-edic ac t i v e r e tericl e -in-c,a seeus '..;+ts edc e--tc.--th i ci ,: h g['y ! when- the proj ec teo-ga s<eus- e f fl uentuhr.-:-htt a a ::-+f fA.c.LV.a -
- . to-un reW i : ted- e r c.n s-tse <- F i g ure--Grl-1 )-.W.re-e rr:; . '-ce sy c 5: . ' - .
og . e. c e :v, :, e, i .: .nrc<r ,.o any o rc a ns reg 3497 3% ;q-nm
- m.,c., e ,;, -
I l .'. .}.
.I I AMi !ClYIM TY : At all tires.
' ACTION:
~
, c. k'ith gase'as wastes being di charced fcr more th:' 31 das with -
t
?*< 't v treat:nt and in e ce: S of the abcv? l iri t:,, Drc a rc an- W - '
of cA' to the tcmissier withir 30 days, pur: art to 5;ecific: tier 4 .h 3 a Spccial Rcrort which includes the folici. irs ir.forcatic'.: ' . < ' . C. c> r-
- 1. Identi fication of ecuirr ent-o -rsubsys tc s r.ct CTE' l '. ' c d the recson for nonoperablii' /.
- 2. Ac tic r( s ) taken to res'e. e the ner.-cperable ecui;ncnt tr CFr t'. 'r'. %' ~ ! " ei ' n' T 'w' ~ .
- 3. Su:reary desc ri pti , of action (s) taten to reever.t a re-turrence.
- b. The prc.'isiens of Speci ficatier. 3.0.3 and 3.0.4 are not arr licab1<
i _S_U:'NE I LL td:CE D E OUI R E!'E N T S __. 4
.. i
; 4.11.2.4 If Deses due to catecus releases to unrestricted arte; shall L'
! projecte 'at least once per 31 days.
f 4rl hih4r?---T-he-epp-epm a t:- sytte' e-shel l--tMerer.Stn te<' OPE AL E - a t I W t
- 1 o rc e--pa& 92--days- unl es t-the-1.ppropr ie te- sys ten-bas-+een- utili zed Au- prn".e' c.
, , ' radioae t-i ve-pa seews-eMhn ts--duMng-th--pr-ev-ious-n-<'ay+
. p.
i M-545-t-- 3/4 11-14
. I L.S C S- l ,
.o..
4
. , , . _ , _ , , , . . . . . - , + - . - - - - - . - - . .
=
/
/
. /
r N j h,, :rr .t.e.r.
- -.- - r. rLo.re...>
I * / e /
\ /
/
. :' m ',!TICM F"' f: E U,T I C U
/
3.;:...E Ti due or do;; connitnent to a real individual f rc, all u -' f u I cycle sources is limited to < 25 nrcm to tne toiial body or i t r. ( , tpt th. t t ;. ro i d , wh i c h i s lim i ted to < 7 5 cren ) ov e r 'a i- : .. ccn;ccutive nonth',. I' JP - I.t all times.
., ,r., \
y
\
- a. '
.. . t h th3 calculcted dese frcn the release of radioactive r Mrial- in liquid er ga*, ecus ef fl[nt , exceeding twice the l ir . t s o Nee c i f i c ati o ns 3.11.1. 2.A , 3.11.1. 2. b , 3.11. 2. 2. a
- s. ll . ?. 2. olN3.11. 2. 3.a , o r 3.11.p.'3.b , p repa re and sut ri t a '
Sn.;ial t tpoht to the CctrissicX ;ursuant to Specification 6.9.2 A n'! l ir 11 thc ' tut':.equent rel ep$c s such tha t the dose or dcsc c c.~ i tm - t t e a 'g e al individal frcm all uranium fuel cy:le ,
/
se :rcer ( c ,: - .t thi fcid., i mitt.y wit ch(to < 2 5 i.rcn is'1inited to < to 75the rrem) total bcdy ever 12 or any organ l consecu-tivt nenth:- This Special Eeport shat 1 include an analysi s i v.n i c h d;-nc r : rates th$.t radisticn exposures tc all rcal indiv - i daa's frcm all uraniy6 hel cycle sources (including all i e'D u:nt ra tha /s an; direct radiatic .) are less than the 40 Cri' f a rt l' 0 5 tan'fard. OtM' wi se, obtain a variance frem the Cc ni:sicr. 10 ;m ni t rcl ea st's whicn excecds the 40 CFR Pa r t 1EL' Stand; Ld.
/
\ '
- b. il" recvicip/ns of !pecification 0.3 and 3.0.4 are not appl ic at ' y '
/
/
/
. .Cl l *' [ F I 8 . :,, *l _' f r.
C f f.Y. ' I T r j 'c hi]
~...--. _... _. . x .
4.11. 2. 5.1,.d t c e C al cul a t i ons Cuaul 3tive dose contrat.utions frem liquid N ! anc g.n. cop ei:iccnts shi.ll De detensined in accorcanct\ wi th Spec i fi- j c e t io n , ) .11.1. 2. a , 3.11.1. 2. b , 3. ll . 2. 2. a . 3.11. 2. 2. b , \ 3.11. 2. 3. a , a nd 3.l!.2.3.b, and in accordance wi th the Of fsite Dese Calcuhation l'anual ( G ; . J. 4.11.2.5.2 Pe m t* Special Reports shall be subnitted as rechired _i u.4d e r 5;)e c i fi~c a t i o n 3. l l . 2. 5. a .
/ 'g
/ \
,- . \
' B;.P - S TS -1 \
/ 3/4 11-15
\. s N
y y s
/
. . . . . . , - . . , . . . - - - - - - - ~ = --~-~- ~- ~ ~ * * * - * * - - ' ~~^"~*~~~~"'**;
. . .c-... __- __.
R APIN Cil'.'E EFrLt'EUTS E'PLD51'.T
/ GAS tilxTUTE (Systcns designed to withstand a hydrogen explosiod i
L l!11 T i.tici COND I_T_1_.0.!1. F0R 00 E P ' T 10!! j - 3.11.2.h The concentra tion of hydrogen m y.--7 in the main condenser o f fc as trec t:nent sy sten shall be l <ni ted to- ---rt-%-vokne--
- ey ~ nnvish n Rw-cm., cuss (> p5 p g, [- g g ,, . , ,.
IPPLIE ABil.lTY: At all tir'es. q g a n a, ,s , g g ,,,,.m,. g Pec c 3s u re c. a u n w,. p ,,v.s ACTiF!: oao pris,
- a. Wi th t he c or,;en tra tion o f hyd rogcn .v-. cry :-N in the rain con-n____ denser of fg;s treatnent system exned@9--tH-int;-rest:m u.c Li e n M-L IN'c,. . ,, m, the-cwerOcr'< ernr+ t io r-to-iti-ty.7-.4hcdsm+ pi tni n J.S hour s .
m n e u tc _C.W~
;p p c.
g ,, .-$ s. cc.n cr F1O n*h; '= q , ,, c , . . a ~ %:ifications 3.C.3 and 3.C.4 are nct
,Ci #[36."'UEapp fr~c'i'ilo 1icab e. ns~5f 5 i.::SUP'T ILL A!!CE REOUli.E!Il_lTS N.
.4.11.2.6A The' enc +ntr.3 tion of hydregten or cxygen in the main _cend a ; ' r.
!o f f g e s tr ea t~e n t sys ten sfiU ht+de *gp' i nc d to he Uby cc,tinuously nonitoring the wute ;i'w<J)j !Mdi~5bove nair condenser offgasi ni ts
,ttrea t ent syste wi th tM 4Eydr@M or c7ygen) tch.-r+:dryd CPEE A?i.E N
llby Tabl e- 3,2.&-e t-Weii fi c a ti o n 3. 3. 3. 9. w
~_
.i
.t b.
I t. [i i
/" '
j BuMTE-1 3/4 11-16 I c Sc 5 -l e , -e -*."."P* * * **-'*9
- " * * ^ * * * * - * - - - = ..*weee*=.-< . ,=-a.
. _m . _ t_ _ _ _ - _
e e .
\
\.' ('
o$tF
,~, 'N
\ \
'!PtD!O/ CTIVE EFFLt!EtiTS-EXPLOSIVE Gt.5 MIXTUN (Systems not designed to wi thstand a hydrepe-)'c. pl osion)
! LIMIT!!!G C0hDITICU Fh? N ER ATICM a _
/
I}3.11.2.60 i The concentration of hydroger, and/or oxygen in thd' main cct:- derger of fgas treatment system shall be limited t0 < 2% by olume.
\
IM L IC/,P I L I T Y : . all times.
~
/CTION:
- a. Wix th the concentration of hydrogen and/f,r cxygen in the rain coridenser of fgas treatment system ) 27 by volume but < 4% t'y volub.e, restore the concentration of r.ydrogen and/or bygen to wi thin \the linit wi thin 48 hours.
\
- b. Wi th the\ to 'ntration of hydro, gen and/or oxygen in the main s
j condenser 0( 90s trea*nent sy;ttn > 4% Dy volune, irnediately i suspend all Edditions of wa ste gases to the systen and red cc i the con:entrat'en of hydro' 6n and/or oxygen to { 2S wi thi: 48 hours. l c. The provisio".s of pec(fic ation 3.0.3 and 3.'0.4 are not a ppl i c abi c . Y l l SUVEltt /HCE REQUIPEugn73 i __-
- -f
^
/ \
1.11.2.60 The concenp/ations of hydrdgen and/or oxygen in the main con-der.ser of fga s trea tspnt system shall be Neternined to be within the abe'.'e limit , l'y continuously rv nitoring the waste cases in the main condense l' o gas trea tacnt j.'vsten wi th the hydrogen a'nj/or oxyeen monitors rcauired 0FERAFLE by Tab 6 3.3-12 of Speci fication 3.3 3.9. i
'\ \
N, N N i s DwR-STS-1 3/4 11-17 Ns 3 ,
. .- - \
/
/.
/
- .. - - __ . . . _ _ ,_,.y.--p.--. .e, .. ,
.m_ _ - . . . t
'\. ,
N , N
\ /
-~
,/
\ ,
/
\ RfDl0 ACTIVE EFFLUE?:15 fp, M.' 1 !: CGTE!1EER /
L1MITI1:G C0!:D1T10" FGi' OPERAT10?l
/
\
3.11.2.7 The gros ; radioactivity (beta and/or gmna) rate f nobic gases neasured at the nain condenser air ejector shall b^ linited to
, (100 uti/ sec/!Mt).
\
AHLICAi% 1TY: At all tiraes. ACTIO?i: \ ! r N IWi th the gross'redicactivity (beta and/or gamz/) rate of ncble gases at lthe nain cordenser cir ej ec tor exceeding (100'u'.. sec.'!'i.t), restore the gross a t leastradicactivity'(rate HOT STA!k' wi thinto thewithin next 12 itsh linij urs. wi thin 72 hcurs er be in NN
, SURVEllt A?K.T REQUlFE!'E?G $
N / N4.11.2.7 The gross radioac t'i3 ity/(beta and/or ganma) rate of noble gases [f rem the rain ccr&nser air ejtcier shcIl be deternincs te be v;thir. t4 /~' liabeve linit at the follcwir.g ff tpuencies by perfm.irg an isetcpic
.analysi s of a rcpresantative,' san;A e of gases ta- n at the discharge (prior j
!to dilution and/or dischcrrf) of th nain concenser cir ejector: I
/
li,l
- a.
At least' onc/e pee 31 days. ij b. Within 4 hadrs follewina an in\cgase, as indicated by the l' Condense ,' Air Ejector l'oblc Gas ytivity f enitor, of
- greaterj&an 504, a f ter factoring tut increases due to changej in THERMAL F0WER level, in hc r.cm nal steady sta te i l
fiss'4n g2s release fron the primary oclant. I I i l
/ \
3/4 11-18 P' BUR-STS-1 g N
! \
-"'"I"** I** *
""*"*******% .ww. . ' on **. **N*e ""*<***'*%89emM + f vy-P -
%% _gm....
/
\.
\
D - grl , 9/ b/
\/
CADICfCTIVi EFFLUENTS D 4' U P' RV. -i " 11 COUT Ai:H'ENT - s b,Jf11 TING CO_N_DI T 10t1 FOP. OPEF ATION ___ ln
\ /
3.11.2.8 T he l' ark 4-e 11 containment drywell shalf be vented /purced ~
,throylii[i4 tithe Sta nd by Ga s Tr r einvc i., t:pr;t, 5y.s ter ._-
(>. M '
i rn v. tv i ~r o e o O. T H 'd 0%
,rne cr .
APPL IC AE lbliY : -- T '. I M' Wheneve r theedry <- /.?fr'31deg, "'W" y--- pc.1. % wv .; . i.4.cliet_ i s TJ5 p y tid R entma su Lim, p i r n a h(;, D, q,m 4 *
,g g , \
N
- a. Wi ths the requirenents of the a>/:ve specification not sa ti sfied, suspenbgli ventin9 'rurging cf the drycil, ,
- b. lhe prov 'sions of Spcci fi , ions 3.0.3 and 3.0.4 ar e not a ppl ic abl e'.N
\
.. \
. :5UP.VE ILt.UIE REQUIP.El';f.hT5_'N_ _ .
r, !: 's 3.11.2'7 The cont 3ir. ment ~. . ell sh?li b. deternined to be elioned fo'- F~l ivihting/ purging throughyth. 5hndby Ga s Treatnent Sy ster, wi thi n ~a hours 4 ior to start of and at least \nce per 12 hours during venting /purrir.;
,!vi the drywell. \ -
p _ x _s d 7/)ir ._et /rn t ra m s <v v i rNT rb a t> o w m 6, e
~ - - -
s , , r ry ., ea rn n a ,, t, 8 3 d . I i b BWii-515 3/4 11-19 ' 4.-,5 c S- ) N
- -. \
\
s
, ./
~* e**'***"*.'P"* ~********-******
***me g. - - , ... .._. .ww . - - - - . - . - . ws e *- =..+-.s%
/
N N ' NN .
\
lR AD10'CTl'.'E Ef rLUENTS I 4 [f g 'I
. 3/.* 11.3 SOLID R AD10t.Cil'.'E WASTE ilMITING COMP!TICN FOR OPEr.ATION x .
H '\ / I ! 3. 11 . 3.1 The solid radwaste system shall be OPERABLE and u;,t>d to providc
! for tt]e SCLIDIF IC ATICU of we t solid wa stes, for the SOLID'71C A110N and j j packag%g of other radiocctive wastes, and to ensure thejd eeting of the p reguircq.nts of 10 CFR Part 20 and of 10 CFR Part 71 pr er to shiprent
- -
- c f radic3htive wa stes f rco the si te. !
- b. \
.APPLICABILITi> At all times. .f i
I ACTICN: , I a. With thehequirenents of 10 CFR Part 20,10 CFR Tart 71, and i I, ' the PROCES5 CONTROL FROGRAM of S 4cifi:ition 6.1 A, not i ti s fi .: d , ! s suspend ship;er.ts of defective /ontciners of solid radit a.+ive , I wastes from tb si te ,' i
- b. With the solid r d'.ia ste sys,.em not OPERABLE for ncre than 31 days, when rc auir$4 to nc4t 10 CFR Part 20 and 10 CFR Part 71, prepare and submit k tid Comission within 30 days, pursuant n
, to Specification 6.9.1[ a Special Report which includes t:c '
follcwi ng infonaatiojd.
- 1. Identification of equiva:nt of subsystems not OPERAELE and the reason /s for inoperability.
- 2. Action ( s / aken to resto\re the inoperable equirner.t to t
OPERABL status.
/
- 3. A dgscription of alternitive us d fer 50LIDirlCATICH and ackaging of wastes.
! p/ '
- ' 4. utnary description of action ( s) tak~ n to prevent a re-
!; currentc. ,
i-l c. The provisions of Specifications 3.0.3 and 3;.0.4 are not i i appl ic able. ' I j / I jj S_UEEILL ANCE REOUlPEPENTS I
;; s !
e
' 4.11.3.1.1 The solid radwaste systen shall be demonstrated OPEP.AELE a t ;
least once per 92 days, or there be the capability for SOLIDIFICATIQU of wa ste by r.. : ting one or more of the certions below: BWR-STS-1 3/4 11-20 s /'s N
' N
/
x
/
/
/
s 4 J.tr N .. t
,. } '
xs
\
SURV E I L13!:U EEOUIPEFhTT (Continued) /
\N a. By perfomar.ce of functional tests of the equipnent _and pontnts of the solid raduaste systen.
cn-
\
, b. by crerating the solid raduaste system at least once in tne I p' evious 92 days in accordance wi th the PROCESS C"hiPOL Fr09./".
Verification of the existence of a valid contract for SOLID!c!- ;
\ CATION to be perfomed in accordance with a L 'OCE55 CONTROL
- . I' PRLGP M.
, 4. !!.3.1.2 xThe FR00E55 CCNTRDL FROG
- LAM of Specifi ation 6.14 shall be used i s l
' to from verifyat leastthe SOLIDIFIC e) cry tenth batch AIlCNofofeach at least one type of rep /et ac radior/ser.'.3 tive wa ste ( c tive
.1. , test spe jw filter slu4 M,1. rent resins, evarorator bottyns, boric vcid solutions,
, sc s' m sul fete soluticns, and filter media)./ The test specimens shall be ;
! prtressed in tbt ratiochenice.1 or waste prc[essing laboratory in accordance !
wi tn procedures of thq PRCCESS CONTRCL FRr,3qA;;, j
\
- a. If any test s're,ciren f ail s te verify SCLIDIFIC ATION, the SOLI-DIFIC AT EN of the batch ungdr test shall be suspenced until such time as additional trst specimens can be obtained, al-ter: tive 50LlDIFIC(TON (arareters can be deternined in ,
acct.rdence wi th the ERCtESS CCNTROL PRCSRA",, and a sut Rouent test veri fim 50LIDIF/( AT10:.. SOLIDIFICATIOU of the batch na;.
, then be ~esened usiph thn al ternative FCLIDir!C ATION paramett es determincd tu the TROCES$' CONTROL PRC R A :.
If the initial iest / specin\
- b. ens fren a batch of waste fails te verify 50 Lib![IC ATICN, the PR%ESS CONT?CL FRCGRA!1 shall pre-vide for thg collection and tes\ing of representative test specir.cos ' rem each consecutive tNtch of the scme type of wet waste /until 3 consecutive initbl test spec rens de on-stre te ,56LIDIFIC AT10N. The PROCESS'$0NTRCL Fis03R*M shall be rodified as required tu assure SCLIDITJCATION of subsecuent battk s of waste.
/
4.11.3.1.3 brorts - The semiannual Radioactive Ef fluent Release Rerort shallincldd int iolicwing information for each type \f solid waste d of fsi te during the report period: shi pp/ .
- c. container volume, 8
/
/ b. total curie cuantity (determined by measurcaent or estima te) .
l
/
l/ l \ s[ \ N
\
l BUR-STS-1 3/4 11-21 \ N I
/
/
./ -\
\
/
. --- -- - -- - " -"*"~~~ '"
. ... u ._ _ _ . - . -- - -.
s * ,
- x. /
y
\. (v
\ .
) [
' ' C. ' 7
. ..l.l 5,' " } * ) ,' " f. /> T f '< ' p ?_ t 'T_ ' : ! '. ( P. ( y *. j ..n g p p )
/
N\ 'i I c. princi;al 92- .3 radicou:lide; ( determined by nea succ. or .e 7:
\g!. + 4 ! i t c t r.' ) ,
u i
- d. type c f *.a s te ( e . g . , s pe r.t rc -i r. , c omp e: tec d ry s.? .e ,
I cvapora tor cottoms), x type of ccntainer (e.g., LSA, Ty p e A , Ty ;:e B , 6 r g e C u a ^ ti ty ) , e\ anc
. -l
- f. \ sol i d i fi c a ti e r. a p e r.t ( e . g . , c c.cen t , u r ea a r .ai ce rj'ie) .
\ ,e . M.
N
/
^
/
/
/
/
/
EUR-STS-1 3/4 11-22 x P' I \ N
.-.p.
/ .
/ \
/
*-M * * * . . , . . , , ' = + ' * * * * * " * " * * * " * * * *
- 5' * * * * * * " "' ' ' *
.wwm . ..
e t c.
- t. .
e, t) e. U [/ ()I'n
/
- . - - ', C C s ;,
.- O p e -
y s~ q
~
W Dl l C*~' sn y
- - . . . - c <- e c2 e .
_ e V
-- e lr--
L.. ** c a. M &
.'5 '. < aC
- -U L
- - o ,
c . r c c . ( . e
^
C: 7'm;% C > t 's V ?
~
g- .J :- . ; ,. oy w . 6 . - (sj
. n .' .- .- &
j R O [3
**) Q 1 y
-,- 'C ~ .:
/
/ il 6 e- a-E e-L
- 1
.. < _r C C C c.
/
/
t
/ O %B h N
/ !% ?.. L C c e cT
,/ *C 'V
/ V%
- ^J G C en c,.-
U C' L L C F.***- C' t' o '. C. C. ** *J 'T C" L' C C' C' '~.J U U L Ts y
/ C L C- C O O C T c-u rs c.
M M "* C /
@ tn C-c C B { 1 O f. 8 T L '-
- - r,1 *. C y o.>.'
f,_ ' s 4.* CC *_. t
< r,. * *T .
e 9 e g - C i
\ C C-J i
i Aji t> .- - G C CJ > .
' L O- m ey r* )
E.' t-
\ --
O y L oe aeo e, xs CC o L i- - L
* ' 'N e L O rJ *7 O t .-- % e- O% C) C .: c y .- y Cj r. N a .-
- L. ' t e C 4J 'O f" L I'i ' '
\ C C C 15 L C8 C
., E .C..,. c1 - O
.- ! O L- , - e E e v4*
r', 5
- U
\ c .D g . O C
L
"] D T C
y
, N sJ "3
. C
- 6 C. (4 v C T 4' O
. J\ C- C C n L - u.* y [- O rJ u sn
/
P.) i
/
L l m r a
=== L s (*
H O
,/ S. 1
.r-t' < \ r m s'
/ e -
l c c C'
- O j
/ _
.1 - -i e q g g U
O 4' 1 t ' r-- e-
/ 90 L K= y W
G. t c t.; o v C. O a c5 c> y .- W 'e C.! (1.* 3 {
,/ :
t- ~l U - e.
~
O m c: n', (a ' N c I . e LJ l e- N
- f-
/ I ll - SI'i- ! . in 1;;.3
. _ . . . . - - - ~ _ . - - - _ . ,
, e, ,
, N -
i N , i a TABLE 3.12-1 (Contin :ed) ,
,- ?
> RADIOLOGICAL E!171R0f:MEilTAL I'0"!Tnit:G pr0W" - y; Exposure Pathway Sampling and Tyne'I1nit Fre7: enc . . i and/er Samale Sama > N Loca ti ons" Collcc'. inn Frec'iency , cf in', - . /
- 3. '6'ATER30PJ'E i -
l a, Surface (Locations 9 anno) ' Cc posite* s rple colled.cc Gw' i't r 'c -
' Fit over a perica of<wd>,- -,
. c ' - '
i / 1r.tiua a.a ) ,, . /_ -
- / I .- et ir r;t
/ pc s i .e -
crce per 'T la ec .. i
- b. Ground (Locations 11 and 12) Avleast once per 92 days. Ganna isotcpic and triti'ra 2.' / 'N ainlyses of each e.n i;)1e.
\
Ccmpoc.i te~ sar7 'Scellected G c. Drinking (Locatiens 13-15) 1 I-131 anilysis of each 1, over a period of <il sdays, composite samp!t>;
; if I-131 analysis is per-and for,aerl; or Cnmposite' sanplo collecter Gross heta a"d gama o.er a perio1 of < 31 days. isotopic analysis of each l t qposite sa.mple. Iritium i analysis of cenpos i te i s.vi.p'1ha t Icas t once per
'J2 days.
t i d. Sedi.ent fre (Lecations 18) At least once per 184 days. Garr.ma isotopbnalysis Shorelin/ cf each sample. 'N I \
' q Ctr,asi;e sa:miae, snall be collected by collecting an aliquot at intervals not exceeding , hours. 34
" 5: icca tions are sho'.m on Fig' ire 3.12-1. 'Q
/ ~
x
/
,- ) .>
~
N. w ..'/ .
.sh xx I
T,'".;. E 3. l ?__l_.T C.c n_i
- - . H_ .i N , , - -
o u ; g ,. cs
.;r, . c. . , . ..,~.1 2
. ~ . , , , ,,,.
=
n.
*P
& eh
';' Exposure Pathway ..n,
' lire and .~ -i - - ,
of,>
~
and/or Sa-ole Samele tocations** Col tr Fre' :r * - i
- 4. IllGESTIOT \ N
/
- a. Mi l '< (Lecations17-20) At least cnce per l ~'da.s -' ot--ir r.: 1-131
- t. hen anir'als are. n pa-turc; r :iy s i , i . enh' ,i"
! a t leas t ence tier 3! da'.s
! at otner twes.
/
- b. Fish and In- (Locations 21 and 22) sjmble in seasen, o at r3 ,,3 ; m n; c -- 1;q i 3 vertebrates i c u'ep:c e pe r 'M days if on e ne portions.
ndt s cib.ona l . Dr.e r. ample o f 4 w /each of tF follcuirg .neciss:
~
s l r
~f tj1 a
- c. Food Products (Locations 23-2.>) At time of harvest Ofis Grn.a isotopic analysis
! sa mic of each of the fol- en edible Tortion.
I l o.:i nc; classes of food 5 p:ofucts: 1. { 2.
; 3.
i
- 3 (location 26) At time of h.'.rvest. One -131 analysis.
sample of brovl lelf v ege ta *. i c n . \ s N i N
' Sr.ie tocaticr.s are shown on Figure 3.12-1. x y N
, / x f .
l - f' .
. ./
/
/
V
/
, ,/ ,
/
/
/
/
/
/
/
/
/
/
/
/
/
/
/
N
/
/
N N / x
\
\
'\
\
\
N
\
\
\
, N,- r' -
/\
p/ 's
/ \
/ \
\
/
/
/
/ .
i
\
Figure 3.12-1 '\ \ N
/ Radiological Environmental Monitoring Sample Location, .\
(Except f or these locations subject to change based on s rg unu:.ual census resul ts. ) ', ,
/
f.-, [G -STS-1 3/a 1?-G
--- . ~. . . _ .
._ , ., , e . . . . - . . - .
'\
h
\
e t . - . . . . _ . . . - . .
/ \s
.t j
N y 9
- e.
I J # (* . c s
.C & CL
=
Q L C : ua' o e ss s> .'- o c2
.- u t s. C C C n .-~
Q e- C *o L *J. G e *'.' O L C
-L c ? c j C c *J L rs u r. '
m ,/ L C ' "C I t *i G' 'O F e r) f: .* U LOl! N L. C *s e >.c. D. OO C-L
-G.o. cC / O S
.J - .
c ej >- 4* r; -* U .s C C c
- i. C C O V O * .7 rw e G C , F-L (- L - 0-
.- c- t:' c .L %
2 o O Q C - C t- L L .= - .C c' C - Y.,. C"1*= J.' f tu \ oo + *a C *~ C C 0 LJ C J * O O .C- 6 C E r - L c o .. rJ O c c C C C L u u L -)' M, c,4 =-
- O C U ifG "c U*
t: o C = ,a =
- U
> - t H o rn rq L L
3 0.. c's u a
- C .* -
CO
.T c2 t
- - - q. m - - . . . .. ,/* s
.-.. i -- . -
t' > c.1 o. c, - . .- ---,N i C 0.J r. .:) .f* 0 *J m Cs N
;' . m L r;( w e- t E e > 0 -- C 0 t *
+ *J C*. .U
-- - Q L' = - - - L - CO L
- t. O V r0 0 5.O - U J ..G. I r- L L .> ..- O . Q .% * ' ,
o *- C *1 U C. "C' .C -- L L '. *'.- U 0 i ;. U- T* c F'
/
+ s s. . *s ci r- t,i u 6 O L .O e o c c c - 0 t- L c-
.- .- O L r. O ;- -
e e, - eae,
- c. . O C . L :.a L r6 o .J 1
- a c; a
- r. . C C e o .7 C o ..o c t. C Cso :.- n - y.
OO .e J O a f6 u - C ' t C v .o. -(:> Q C O "e ": *- ;, L g .O C e J
;- /;.,-;
i' C1 C r O O c c0 t- O ; c0 L O t -- U oC E< - 0 (J P 4 o e, i t. J- t. O L :* L C o 0 o O v c ri > J H .- a' < > *s 4s O .
- r.- i c1 . a ry L o e,* >. O m r z., u \ y c r . .f cm C. 6 0 ?) L O C 48 e m -- C C;
-b o c- Lo 4.
C g . .- 0 .
+s o o ;$ . rJ cL : c . f-ceoC :- r . a .C- o es C > J e
C L C N c cn = .7 ' O O f- O
..C. 7
- L. O.-- C < *l e- - - L' a 0O CC e r C .O . u t ! T - - .
E y
.- .-- l
> t1 ? .c
.-.J G
t. oD- 6 L.
.* s) ; . G- - UO -~
u ') ss c *. L C fJ ). f* u '- I- D' C (> c-'.C t. f C as -* *- - ?' O .' O CL . ~~ > M E Ik - V .i.d a oO O r*s L (: u oe U .O. O C U C cd i; .- O ./ t f
.O. r, r O
- t d
L t, .a u a u ooe E r o..' D r
- 6. u
- s. - .- o a ca ci a - o uoL ct '- n. c o es ca v. C 0 L. ..Q ca
. \. - >
t e - C .c. 4.. u C O > C U C O C D C f. 4 C 48 C * * * - W - E L O "- c. c- C ". .as
- c u .a k- O .- o o o .
- r.
L C o c/ u - E epL o > cO C O L U U co. o e . c e' u o o - -
..h v : U c u L-C. - 2g 'f
- ow.
*s C c- '
u, r - o ecH r ct <
.y .r- u. . L.t -t.. e, s.
un. r> c L. ? .s vC c c v-
.:.3
- s. . L -'o u cc
- f. ~
L 6. I t.' rg c .o . - t, c c c- t. a . _ -e E s 'o c .o o 0 - .s e v t- r ") ; e *
.u-- .o o - 2 e to t. o> a o o w- rcO ' - O
.r/- \ .D v c N, e -. . .a o L.e oe .C, -
n e
- r. .a m .. o e o
- L t. ..
a :. o e 3 u j n - co, on
.o a t
,u e
. ,ok o . . ri.- - L-o c.
0 a a . . .- :. -a -- .v. s- e -
.. > c uu *../. " w: (g <; n; L t.;i.a u C cd ~' r
} L C
c. O Ci O
.O
_C o r*'% o .c- u. o.o e V a c Om e L n c .3 14 4-u O 3-c .7- y
*1 .C fy o-c: .> m ov->
r O L
-- 7 0 ./>-".o s ri r. -
y u t. u - o .- u t s .:- r~ ;- C ot sem --- o c c c. Us m r-c a .n L L o
.c u o ue t.
+> a.
u o.\ . co
- U et ".
o o.. .a o o - L. < e o o a' .u
- L oo>
u c o + ' 'e 'c; .C O ' v a C
- oau -w C O
-) I :. ' . - '.'
** c / cs S ed
." t tg
.e o
a l o La r en u .c - o .o o ri > vo u- o v. w - - =u . - a r n .r's v
.- ei o u c .oF -y e& u o -. > .t- oo ac e a C ct
>.s u c a, 3 o- - L m ' L .
' 6 .- p.
+> L I t. - oe >o t -
o s. O o . .c a - ;~ a - 3g
- l ra F. c. c -
*z E o o r:: w' o cu.c o . a a - w- o .o - c ci cn .2 mo u *.- 9 Em m .os g
( .u .. m o C O . . r j a
- 2. c _O s
[ N $ i- Q '[~ [ U
,/*
c
.O p-e* c .
-- C* -
.E. .
l 8
- 2 f.) #
to e i s'
,_4 .e.cem .m.T9r-*W"N* * ' ' .
e e, . . . . - . - - = . . -
....m.-.. I' ~*\ 43/4.12 pre:CtMitt.t EW,'!r n"rttr AL n'.'ITnmG
'3/4.12.1 l'3:!T0"l!!G pFMo t".
LIMITit:5 C001110!: PP OPEFl i!CH 3.12.1 The rcdiological envigrqntal monitoring prcgra shall be ccr-da: ted as speci fied in TabicQ.12-li a
' * ( 2' ' i
- 1 - l
' _A_P__P_!. I C t.E !:. ! Ati V : all tines.
,ACl10N:
- a. With the rcuiological cnviremental/r.enitoring prsgram not beirc conducted cs s;ecified in TableQ l.2-ll prepare cnd submit to t h e. Ccmrission, in the Annual Radicicgical Operating Pe; ort, a description of the re sons for not concu; ting th? ;r c g_r em . a s .__
required and the plan: fo r pr e v "n ti ne c_. r+c ur.r..e.c c.c . .I ( Dev i a ti e'\ n f are permited f ren the recuired samplinc schec l c_j.f .rpeciner s j
~
~~ O - are unobtailii.ble-dut to haza rdcus cor.dDons7ssa r;nal un avc .1-
'IN5crtT.L[- 7'_
cbil i ty , o r to mal f uncii4[1' Ufr69tC'~O c t a--I i n; cqui rmn t. If t hr. latter, evgy 4 f f#Cshall be nadetcuple.c corrcc tive a L.c t i ga pr itTGo the e nd o f t he ne/ t sar pl i n g pe ri c'c~.~ )'_N_ _s. _ . _ . _ . _ .
- b. tlith the level of radicactivity in an environmental sampling
',, i inedium at one er more of the locations specificd in Table 3.12-1 exceedinn the limits of Tabie-6.4d when averaged cvtr cn:-
k( _ _p,f'g, ./ _ ~~~~~E 30 desdar days frcrecua rter the end, prEMEan.1 of the af f ected sabnicalendar t to thequarter, Ccr.ni as Special si on wi thi n
'glc / Repor't which includes an evalut tion of any release conditiers ,
Q({f(*
~
i'7_-
' [~h(..A ) cnvironmental f actors or other a ,, ects which caused ti e lini ts of. iab.3<6+2-1 to be exceed 9. This report is not required if th.' measun d leml of radioactivity was not t he resul t of pl ar.t ef fluents; hcever, ir. such an cvent, tne ccndit;on shall be reportea end described in the Annual Rediological Environctntal Operatinq neport.
3.s % I.I-(
- c. lli th inilk or fresh leafy vegetable sampl es };nnailable frem any rp of the sanple locatien.: requi red by Tabl e'3_,,12d prepare and submit to the Cemni ssion wi thin 30 davs, pursuant to Specifi- ~
'f catic,nr,6.% 2;- a Spccial Report which ' identifies the cause of the . A'
[([CI'. _]
- _ _ _ _ . _ . unavailability of samples and identifiesq1 ccations for obtaininc repl ac cmen t sampl es. The locations fren s.hich sampl es i.ere un-
,B
- 6. /
avail abl e nay then be del e ted f roa (T'abl e 3.12'-D pr. ovide d tt e ._ , locations f rom 5,hich the replacccent samples were cbtained arc { q< added to the environmental rnonitoring program as replaccent ' locations, i f available. (f ' t.
- d. The provisions cf Specifications 3.0.3 and. 3.0.4 are not ^' / '
appl ic abl e . O y',,WS-B F 3/4 12-1
. ; L 5 c .S -/
. _ . . . o . . _
~
..--.---..__....n-... . - - ~ - ~ - ' - - - - ~"-~-"*"~~'***~*~~
. r~
St'PVLILL/tcE PE0nirtt 9;is
,s ,4 . l ? . l .1 Ti e riniiol cgical ent ireC cntal nonitoring ca.*ples shall be g 'q c oll K tt j.rucI t ua n t '.', Tabl t/.2.12.-F f n r the i ct ation; shov.n cn g' l figure <[.l?,-J and St.all- be an51yzed pursuant to the requirccents of p liabl g 3. l?-1 Sand 4.12 ,1,. g,g ,g,;..)
I N dy' I4.12.1.2 (;
' ci <'rt - The res t.l ts of analy;es pe'-femed cn the radic-lcgical en<ireretotal rnonitorirq samples shall be sumn:rized in the
, Il/ricual
' Radicic9 i cal Envirc:ntnt;l Operating Report, purscant to Epec i fi c a ti o n 6. 9.-l .-5.
(; . pI . (' 6 I! l ;-
-p.s t.
f I 1I o P I. I 1 A f. MiR Sis-i 3/4 12-2 L 5c5 -1
.g . -~- - - - . , , . , . - . . . . . . . . . . _ . - --.- - - - - . - - - - - - - - - - - - - - - - - - - - - - ~ -
e . *
. s Ga+
* ,s .
I~ (' Q -. me.
\ ->
o O
'l i c Ol
- o w
, e
~) s-m., n f ,
C a_. s. 3 t
., a k.
'. e. 3 E DD f t: i -
P. in
- e c- O O '
!; ;.a'.: O j-8
..-)
/.r - - - - -. - -- .
Q ('.'
/-
~1
.J e .i ..
6 . \ t> y g 2 ji , y_ 1 *- o tO
'/ .,
' s. en >~- m l **
Q-I t t.) c- (r)
- c. g ,
c' i l C.. O CE ef ' F 1 ' Li
*- c
[ , o
>i e v ;l u -
o , ,-- 1 1 6 l,
' ' , ' ,g, . g - l-- - I (i- ,- ) \ lg >- Zl J ,, f;
\ D
(> '.~.. ~ .
, .t-~ [,
g fj
,fl
, L_,' ' 1 9
O e ( lL l l w (1 C t.'
~-
oC6- LLI - i (. .. )i. J u __) e.- . M o
' 3
(, . .I' rt = y) U. f,
".U 4 l.t.)
s - y i (4 J
.. ,, i
/ / y %.
t
~
C U l .. . j r) I (/) i, c' o f a i
\
n Cr c, 6 o l_ L q
' ie .
.o. -
' t,
.- . {- li
- \ x. _c g- ,
r.1 (. j
'i ao
(-, . t;
$.\. ', -
)h I
5 SP *e
==
W e;9 6 no Lr J O l a. f g
.# a
)* , g I
L,t. . E o
- l. ' . c C
0- O O a) CQ n, _ e ". . - ef C (n u o us .-
*^ ( \ .) ( bI Ib (
.,J)
{n9 iU .-- y 6 O
- --- ..D u, a, ._
a .-io o fu _ c o
.> . , m c,,
.. u, o t, a oU3 o c, c
[.. t- .. k. .- k- r1) L' ) C gg g-- y e..', $ C3 (O .-(f) (1 ( ) U .1 C '- C' g y g .: y -1
* ( L) C- C (p C 0,1 11 6 O r'. i O . * -
-. .7n O (_) .i O Z (/) )5 C U) Z M Z O O i e i e N ro # tc) o r- co cn O - o_.1 to y i .i e i e i i a i a
. . - . - -. . . - . - - - - - - - - - - - --.--- +
e . -
. .r .; t. .. . . a ..
O I i9:
,/ e o. e - . -
kr , ,Iy g.. 3i ei,- ,s.'I
=, .t' rs t; e
,3.-
e e i s e i e ff
- f* i 1 1'
%s t t p .+ tt n ( . 7 g r j te e ert i .3 r, u I,t1 . ...
IL *
.< s e c ) ..c e n f.i .r i.i li li 'ttr
,, ..n -
g- s
- t L t
7 6
- l. e f f f ia.tI uf G 8' l' i
1 - i i , . e.' < < - t rat i r t - M T .a '
- I t I ; *
- 1r . . e 6. i ar 1, . tr t- r e
i !t .11 ' .... t, 9 51* t,t*tet' ..... F< i l' I I 4I I 4h9 ie
- r,6, .....
i f. 4 ti c , ei tf I -- ,l I AI i it, I+1 s e i .. t v t g I Is t t ar.
- t. t. ;'3!
e i .i < u te 1 i i+cs . It i w e ste 1 i I. i ti l. l . 1 .]- .I tt i .' l ' t+t: rr 4 . 't i t i ( s . } 'l , 8' I8 is! 1 it i k. . k !s ( s ,3 i? . 7.8 til' int. e Apt f1 1a '.I t. F i e r..i . L.3 - 1 % [a : l' " 8-'3**
(. I i ..;. e- .! lii - tie ,at (t-il7 f f*'l i t.1/ r *18 4 in o l'. it
, e , , if,r 1*k ini L 11 n efli 9 f a i
- i. , * . . . ee i
.t *
-1ei
.' s . l i s ,- s ii t ..
- a g , i i. 1 f .. I *b - e it f,ta e'1$st t 9 l' l' i eti t- s. I t.
Tt r e t t vt .i y e -i r f' - 1 1-. LI I't/., ..t
<t I a.-l II ; I l'J l I~ I
- k. e , 11,.]7I 1n f ", l ' ri. 9 1'I ie s *i -t
( s n = (at) " l $$ f*$[#5 b ' s I t e t 9 le Ia 1l. e ltr g.. ist g ff t r= l l e r 8 l etti
' ' i.t e i.,( 1t-6 y 'f.
It . ' 1
,_, , ,_ _ _ . . . . . - . - -. - ~~* -e*"'*W- " " * - * * * ' * * * -
e .
* '. 6fj
- % =
p .a ,r- i,. *
. i r 4-l; 1,. .Er' p .,, i i , . , < } 6: . 6 e. , b l . 2.i ' . iIi,i w=*.
I l. p.s l'- i?t.fli, (a, i 3 ;6 i - o f-
- 4. '. . + . l y i s-l b ,
gi f. '. - ) } I ; l . . 'g i l ,' # 3 r 2. I ! '. 4 . < 4 C 1 -l'J 1 1)1 C.7 t<irr 2 i * .* -1 '
- 3. mis,1y
- i . ,
%. t o
(t } I. 1 >s' r ;i 1. i. e . 1, ' n .c a. 1(a) w l .( s i
- 1. i are r Vr
; e , , ry. '
ri L1,
) i r of i
' .1 l ,1 - 1 i k.(et 1 )
> e. 'st I. t 7.
s 4 (. t (, asterly
). j! *i rc - ---
,oo,.,e m o s. e
,_pg, , _ . , - . . . -= * " ' - - * " '* a ~. _
. . , . . .. . .......e., e e--
- g., _ . . - .
% . . . . --t+-
.s. . .
- t. g li (a) 6 . ' l. . '1.
. 1-2.11: a l' I l ? i t t ' s
,. .* G,. n i v o.
rt.i le, Cs-1 M 00 SC1/12t r pw ..
- a a *.' n ,A
[c (*',, m .) ts (s-1)?: 70 * #11! t r b a -l.a - 14 0 ; 3 G g r. j j l l 2 F.ethis ( *.a s . te
/ r.r 11) 4/ o 4~.,,
i ' l I )
,., nn
,;gg. .
bet y Sc i> ecotori< 'l I I l 6 '* 194 I (a) s,', , w, ,
;'- 3 u .:x .....
(, /. s,.o , t 1' '" [i , s* \ . s mv ~. :. . A.a .1 ..... asm. , . . . . ,
- m. **j *-
'. f.
' ' " * , .' eO-' T, ' - 8 "rJ u r e 8 --i CC Ot.T NOT C-
- 7. p ,., pt a r. ,. . .;,
s
,, s
.L .,, t * ,u ._i t, 3 A F* 1 *. a * . ;i l v.j; ,
' ,rt i a t .' 't ' 'l f s t 1 os in a n er i, e js .- ej. lv jJg, i l' ( '. . ) t ] .. , , , ,g ,
I !' ""l* I
- d L 5 '.n . Our n 3 s in i I"' t i ' ' ' cf Am t, e 8.11, , [, .a l 3 ,
.r; [l . 'u t i .
. . 1 t.h411 he 1;a rateT r than n
- beii ter < i t i a - i . ... . ~ ,, ,g ,.
b ' '4 b 1% % e il a, { li ., [ 1, g, i s a r .- . t! g s., d Ir
- nit
- a I,,rCI /11 t i t , th, *
.! I .r h .ta le ,
le ..;. fr r In f at t i:1. .i t e. t ! it-A. I s i s 'a t s t 'I ( i ;> ply are H-3: 2hlO .L* l
- l t' t r_- t . /s'a', .r *s s , /' 4 x i .. .-1);
Pn-11-3 0, ]=l' . 1; C = -l b 3v; Ch- 13 7 . U>; suJ i
-{
I'. /p g3 vt. int,*rj IO r.' - S tor cbo~r* Jo'
-> V O 'f
- 3 (g,
- bb O I" t O ,* C ' I 3 9 ' 2' Y , g 3; c,_o : ; IO 3.
--e c,s -
*, e
- U'i
- 2 V ic [ S D,,
T - 2 0,
,, _ _ - .- . *g.es* * = = -m- -no.m..r..,, , .
,. ~
" O-' l re ; , f '* \
Li.12-I 1/al E ~4rE2 6' p P R A C T I C A L L C'.! *. LlHIT5 Or DE T E CT 10'! (LLD) FOR ST A'JD.".RD Ch'!! r.0*::' ENTAL P AD ICLOG I CAL MON ITCP I N3 T4.C '?. AM LLD (a)(b)(c) Scr.nic Med n Anniv;is (L.(0 ) Unit-Ai rborr.e "Pa r t i cul a te" Gross BetrA* 0.01 pCi/r' GarTa Isotopic 0.01 pCi/n3 S r - E') , 90 0.01 pCi/o' lodine-131 0.10 p C i /- ' Airborne 1-131 Milk t, Surface Water Sr-89 10 pCi/1 Sr-N 2 pCi/l 1-131 50 pti/1 Cs-134 10 pCi/l Cs-137 100 pCi/1 Tritiun 0.2 pCi/.I Gro.,s Detaf 5 pCi/l C a m.a Isotepic < 20 pCi/1/nu:1 i '. Grc:s Detar 2 pCi ' d ri Sedinent Gr-89,90 1 pCi/r dry Car .a Isotepic 0.2 rCi/; dry
.#'. F i :,h Sr-39,90 0.1 p t i , w t 1-131 - Thyroid 0.1 pC i, _ wt (s-134,137 0.1 pCi/n . ic
- Gress Beta < 1.0 pti/c .. c t
*0.5 pCi/l on milk samples collected during the pasture season.
**Re fe rc.n'oed to C s- 13*/
^< ^5.0 pC i / l on mi l k sar. pl es .
-1.4 %
I D. 1
.y Lscs _l
*W** **% - # %8 'N* E ' '**9- '-*e = en
'* ** . . . % y e . p - ee.. -. _ ..m. ,
e .
. i,i A I.,l. .
) j $.4.. 1,ar r, -s e- g. .
(~ . ,
. -. 7 , , .
i
- 3. The Lt. i *' .,
; : ,n of radioactive raterial i r, a t-
'r.,
~
i , . ,c- ,i-~ pe" prcb si lity with only ',' .' . J, u <' ' a i ts r resence.
- r t i for a r. : i!, . m + 0.. '; i :1, r ., y includc rcdio-h ,, I ', ' 5 i (- u
!. . r
(', [ .
, .e... M _e .g me,,
h*= e..
- t. CXP( ,. ;) . t
\ t."'.
[kD ta' r I1 *
* .2,[Cr 2! d{ I i r.c d Cd O'/ c (d$
p tr u --
- J l
*!.g ' **- ' . O F .9 'J P d C C. y N *_ Op Q[ (hC ,
ri I! C L -.'i t ' I -E- 'e ' "'; e I L ie (&. e Cottri* ) E i- t; t _
'c -
(c - c ou'i t ; per :. eforrc: ion' V a' tI '
'l '
(in ' i*' ofrme C,r VOIU~ y ) ,s
* - ~' *"t-#. -tion p;r Inir.ute N r I ')
2 . ' ,' it
;. : < . ; - i ,-
Y ie !;.c '[ :
- In P;d*'*' i;GIy[cId h,, ;' O r, L;' f } i C ; L c) s ' ' ' ' ' " 'd9 * , $ ", E r' ( Cr ["[ [ O f *. i C 9 ! ) I
/' I ; I-r i
- d t r. ' !!'
r it l ', lh ' ' ~ r';# 'i b.* ' l2 C O ) } C C { i C F. i' h d tr 4 1;-i< t i *., the a' 1" ,
,it i- f ; "c c . .un t Tlie vola: ef e,t in t!x c,1 elatien .f tF. '
LD for s
.?
di ( e t ; i < $ s, c (,
't.. }i 6s {,-* t h ,* t c t y i. } o p' r, c r y- j (; t, C t. -
0TOund c ; ti C, rf ?!. ;. . *7* e ' t lic !- I c r.i c. r. ' i e 5 (T cppf cpr ic:ic) r , 1: e o o," r ! ' i e 'J t her ret icc ! ! y predicte! sali in c.icalitin *
. LLo fc r a radici .c l i !'
de t e i r . i r, % :-r. ;r :t : . 'try, tl e bc-tcround
- hall .
incto6 : t.- < '
' i! it i- -
e l' ot: radic.u.c I i di , o r et , r t 5 fl ik .' e' f p I U . l?10 * . i l s ' *, l r s ' L . T ,' a ['I C f', ; . 'lti*y Cf / ly f r.* i el ie
- lu t , y:rit nich i- qr. tci th.n radio ic t iw LLD tri i. t l e.i , ' cr di it i: the least significant di ;i t <f .
LLD. ts 4 4= w
#T 7 4 **
)
e-. 4")"
. % r C3~
w r q @ +WWOe.g rwy hpg ee e p e eg a
. m ~ *M8* e
, - ~ .
\\
., / l'\ , m \ -
I t,CL_L.' -!r H . I ? -\ ,_ ...J__rn- ( r.o n t i n u e d ) l it.rLE t!OT/.Tlr/: l i
. b. T h e L L D f o r e r. v i r c. - entcl recsurements is defined cs an l a priori (Lefore the fact) lir.it rc;res enting the capcoility
! ef a n ea r ecem.nt system and not as an c,costeriori (after the f act) lir.i t for a pa r t i cule r c.2a sur ement .
- c. The definition of LLD is that centained in EML_ Procedures ILt.uct, H*3L-300, 1972 Edition, revised througn 1976.
i-11 d 2- 5 C S - 1
/
/
[
.- ,/
/
/
/
T ! E '_ t 4 . ! '. - l ( C o r. t i n .. ' d )
..,c c -
l s '. : *
._ _.or*v1 -1 L. .
I:_
/
' a '.1 - na i - , 'l t- , i t'. M rice-"1 underin suchcondi rcutine a runnertions.tha t [th0 sta ted C casionaliv
- 1: <
fi r
- ices , ur.c . oidably smt.li sannl/e'si re s , the' i
i t .. r ' a r i r.g nu-l i dc s , o r o tt e r unc 9.'it-ell 6Di c c i r-
- t. , '- the e LL!:s unachir v arl:/ I r, su; b c c st s ,
r
. ' - -: ,2 i t i ' c; t ors i ill t>e idt nti 'i e i ,[nd cesc rit.ed in the '
. , ;i r
- . .> 1 Env i ror-~;n tal 0,, era ti nef P,epo rt.
\
n - u. s
<a. .
- _l' i c? - ' ; n t1I l 0 5.
\
\ \
\
\
\
\
\
\
\
\
(*, xi
/ \
/ \
/ N
> s
/
\
/
/
/
/
/
,/
/
/
/
/
/
1
/
/
/
/
/
/ \
~/ N
,- \
/
'N
/
/ \
N
/
N
-- y
\
j
- . l". -
. - L. . 3/4 12-9 sN l3 . -Y \s
/ \
/ , . .
N
/ \
l
******M*****
, ,_ ,. , eowe e ~ =
i.. _- .- s i i. q ( J .,,.,. ( I.;, . y.- p s, -- . . . - - -- . . _ _v .- . .s.. ;,._ . l
,,'4 r ,
i
- t. . ...7.... .
,_ - .3 .,. l ; j a m .. .
. i 4. ). . -
, , .# r i
+ r.
- _r-.' .
- e. + I e.d .2 n . e.s. .n . . t } , r. p, . . a. -'l
,1,?
- t. . .n s,
.t7-.
_ . s.-cc yy.: , . - - . 3 ;, r. . .> ;..
~
w .
,,,i, ,
; . :. I' .- , _ - - . - - ,t * - :... .-
,f,T. 3- . e. ~ o. o '. f 1, <, r *, 'i < c.
. .- ,;. Ir i- . 732 '<
. c .. i. '. ._s 1.111, F' =. - . t. 10. ... .
~_. w: r. e. r . e r -
;-___. it. ., i si ...,i.- .
i;
- t. . .. .
I, ;; - . r, ..s. e. c .
- _ ,e r . . . . ; r. - %.-h s
1 -q , y 7
.t .
. .g-, . ,.,..
, ; . 3. la .- t. . _ .. , .. < nj.w'.....i
- g s. l . ,M. ; v-g -
0 ._
- I i
4 d; i '
.t. . . -
- e. ;; . i- . -~ .
. . I , .r. ; ; ./ ; r3- .- ; .~. .,. ; ; g n c e , ,, n ; . g. y.t c i. s ._ _
._ y .
...._;. :.. :.v., ...
.ny. . y ,. y.,,..,., . ..
i,., ; e_ . _
.r
-;4;, _.
.;c, . 1 ; . . . 2, , ; , cc;_ y n . .
q p.c, ... . .. i g -: g y, ,; . ., ; - 30 ca r s, pur t.ur,' to i tr._. e,.
, i .n i p. . , - ' .hl-n i .'c . t i f i c_ s t h e. '...
l . .. - I f
, e
- t. , =,,. _ . , . . _ . = - - - ~.s.,a r.$.-_ . _ c c_.a w ,,_.c. . . ,. 3 . . . a l
I y . < .;_! - e._ , , e r. .yc.;
,,c. ,
..M ._t 4 .:.i q.p.,.,r.
r:'_. - . . . ' _ - . i r,;c g ' c r~
' r. . -,.rs ' r, <. g - n 1 g y . c c.
l _ . _ _ _ _ .- s c, ;- . ,, -7 . .. . a r. ..ee m_.,u.q. .~: H ,.r; e , t y c,,,,a , l ..c p. m., ..
. , a4,') ' 3 r.
- e :. .; _3 ; r - . t .. .+ e i . ~... ~. -m . .- L _ ;_+ n b_ L s. . .. . -.- . . , -. e. . . - e . - -
, ; g ,f.,*.+-)
+
a, s- - - .. .e
- c. m y_. ..-a.:pa.-c, ; r : s .: .; .... , ,O r, m. i r- i v D ' ' ' ' r ,
; .. s e c_ .s. t.
~
.i ,.._ . , ..v. e> . c.. e .< : . ; -.. . ; . ,. i
. _ . . _ .3. . _ - . . t .
A o n, . 7 i.4_ y em .. , m.., ; ;. _.._..i, -' -;r. ,.. . ,- - , - ,;. .J
.-.. 3,s
,, a.. n, .
n
- g. , .;._ _ , , .. ; .
s_. , ,... .
, . . , . .u.. ., ,
v-
,.,c.
.. . . . c m. . r ,...;._,.
. 1 (V !6
- e,.' 6h3 .
I ~*- . b.) C.i l J T g d f - ( t' ? I; I "- rn J f . i - }
.."'9
; c m
. c ,. : .e .c er in J .,ch : ni:
r
. tc..r _- . 2 1 't Q.*,_
- 1. ,
I l m- e . .ce. - .: e c,n..a..,..,".
. ~ .. ,
. .\
t
- c. m.. , . '..v...
. ",..'. 'ic-. ':. .c. . '.r..' - .~ 3.0.4 a r c r. 4 ,. i
? i
' ;. - i.- i9
.: 0 s.
.,,1 o o i, a . , . . , -
-- - t i _ 2.1_ ._ - J2 _____ _ _ _ . . _ . . --
- __-_- u
- s. ,
i n, c . .1 T u. i.. e c,-e t o s .h s t te ec m c+<." at Icnt once y- i-c
.- t h t<*- en 1: da t. ' cf -TJune 1 cnd Ocich - i f, 4W<-e +c-c~'
w.y s ., ,o ; . . m_ , .,. . o a. . . _ n. ._,, . . , ., oi ;. < . .
.,__ a.,...- , ,t m - r
.e -
m , ~ c.a. : .:. e 3.. . --
;m s o ', y Jr .,_, ,_ l...
. 1, , ,nc re: - ts o thc and use cenc;s 3 2 1
,c
.. i rc. u.2 4
. - i .c.. .c.,. i .
P%
.in M.e .nu i - e :;ei:g;ca Em irvnen ;; Operatine g ee y ,._. a .. ._ ,, . .,.-;._ _., a -_-,.____ %. %. m.__y. m.
1 .. , . .s . . , , in
. a_ . u , . . . _ . % - _ .. ,, _.,. ; .. .. g .
,__;4 _; _;__.._. : 4,o_ g ..,:.. , . . v . u P' -9~
- 3/4 12-10 i o
-- w e - -
'I.*I'E5Li(}}.h; FN.
' 3 . I ?. 7, , /l e. c.o r. u ; of A Na..nts e c o o vf. i N G mitg r o ca numoN C O f 4 5 'i m t* T i t : 1 G /f t)L t. if r- c c,N D t4 t T r- O 4NNttnLLY D tt lR I N 4 T ll C: G (~; A *d. Il ) h S G Ti53N TO 05 TC2 crooNG 'i ll G I (2 L C' C_ 0 '1 I t t I rgt-I D N u m G cat av r 14 G t- ;, re c- c. 7- T t> THE S e T G .,' I h Cc N5't s
_ _ . ~ . . . . , , S/ / rg 4. L IS C C4 N D tt C.7 C~- D La rJ D cre TJ4 G F:t t. L w a N Gi C4 N D # T10 N S *- [ll 5 E C. .T. ],[ - R. b iTfI1// O 1 tn : L r- (J e4 D i (A S r- (2 o m T H n ('f. n N 7 5 t 77: 3 ti 1/ tt to F- r. A 710.*.! G' y A DC:p LW D D DR oR C-614 I t/ () LG:;T Cov IV TirJ 6 T G c t ' t.' l G e a ,
- b. b.! T pli PJ (i 3- mi LC @t O l u.S E rd ti rn tr' A y ns.s (.'y u si:19, If r.- P 15 R t+- Sic e i; I tJ rte in & T) odi FI?.orn cou N -r y O Is t'd.l Ct i L T tt f2 m ( A 6IFrVT 5 < > (2 o W CDI (2 E t- I /) f.I LE S cited c_ t2 5.
,1**- . . ~ . . . - . _ . _ . . . - . . - -
m l P" _ ': 'intt ra ncm:nc ,
- .7re - CC : '/2150'1 PPUMM $,i.*II~
2 , ii.' 7 ' err.r .TIO;
) .
8' #' .,,,,,..i.- sr.-.- w <, 1 . W ~ c' r
'r rf f 1 E Jh TI 't $'
g rfor ed on,rgediceeti w'[m e-tch' *,m[s t ur pl' v. f f as," t I/" I 'I O #
,; , spil ti.
ire ' . ca t r j 4 t q.nr 4teri-i-rv.;re whi&h Merc P'rav e'i -b
- ,. .. -> c.,> ,., Vae 1:ct. r a z ,.. Ifc.ovev'
- C L~ Pi? 's ') G r.wo n'ev m n' "'
- , 1r c.1 r
,, t,.ri n v L ,s rc ' ,
- .<s- m e nn e coe> S 'D r a o s a 3 (C < r -M ' t< .% i
'n t.t a'1 tir E.] c A utPaecy.v,,, u-w r e ,e < , n , g ,.c i,c
,nas Pon a f)v>r o e=n r.s y nsc c= u= p);
;~'
Sisyy t u 'rs a fin A L 1 P:ED t) 'J e n W ' t '
yses rot t eing pericmed as rcquired above, report ;
the zu ._tive a:ticos taken to prevent a r(currcnce to the , Ct ::icr in the Annual Ddiological Environnental Operating l'.. , l T-< cvitien , ef specificatior. 3.0.3 and 3.0.4 are not l i; , itc 1 e.
- r y '. c g ri;- ,
I Tb r. 1.1 + of a , 'yscs perfor ed as part of the above reccired : Int c .: * , r.c :rir- recerm shall be included in the Anacal ;adic-1r ~,v- - .~ t . i C ;.. ' tine Rewt, pursuant to Specification :.: .12-G.tc.C. e
- 4
-e 4
- t
.i i
i I
,**r f e g
, ; f'., =-STS-1 3/4 12-11 si I-em
- 88e6 e - wee-. 4 .M.= -- - - O M %% M @'y q gg,,, g p om M
p ._
, l_.e r . . _ . . _ ..
CI. ' '
--(d e (- .. .... ,
r .-
- /t[o u . q > / Lyre , .,i s
lhe ric >
' ' . . . - -*t-^.;-' ' ' . , pr . t i d t.:! tr) rr e - 1., r ard .1 , - ' *
-at. rf c 6 d i c e.: -i s e r,a t<f r i, I s !
i n I ' ', 21 d C # - ' ' al ' . : .; ; Of 1i';id OfflU- l
'- c' 'l DO C al c ul 319 d
. C n '. ~ . IhC .'
, ', . i -1: ,
j r.. n,.cc s 4,... .r , t . -
.. c r <_. u. ... +5,.,m.*.
s e
*t i . e.
21 e r'/ tri p . ' c.- : 1. : o f 10 C F R Pa r t 2. . Int CM.RA" .
.' cce. !: tent wi th 'be
.,O -; G c,f Ag ewi x A tt l receircntnt- .nt 10 trt Nrt '
.i w.
6., - - , , -
- r :. . . ,.
...,.-.-.,7 1 p t . p . . .
-a . . .
- e. i . - ,. c . .
.ll _.__/_n._.._._..
. . _ . _ _4.. . . . _ ._s ..
I I
.-, ,n> . _ .:,. , . ;5 , ..c. 1s.c.J ,.,. f
-i - ,, r s.c. ....
c' radioactive natorial s poni' .'. 'c,t it-' : l in oa:ce :' .i- . t :, i c: . n '.i ci reicasEs of acccous < f fiu-cnt , The rl: --
- , 'r ' -
irst t - t shcIl be c al cul c *.ed in v,, ,.. ,. r t c. 4 ,-. c ... , . ,. -. c ..
.).
., r. .
s..m C.,.. .
. c , ,. , . .,.
. o. .u%. . +.. i n c.
alai. ' ' , l' r e. . : - -- of 10 C 3 Cart 20. ,-- De ~ ri' + 'ir i .1 - 5lir '_- ..::i .l ::l .)-' 3 - f t t.r. ,.n i ' ; r i . g {.t.f11 '_fcr C- ,
..t! , ,
. c, . cL .,a A.S .r.4 ; . . ; r.. i y. + i,;:: c. , . !
g r r. ,- . t. L :. i i c f .c L. c. c.
- e. l6.- r. v.
. i n . 6. .. , . ... . . .
2 - c. O f ,s . .o- i ri e* -, -.'.s. . .s
. 'c. '. r. r.. . i-c r .- c. . . '. c o f. re. n e r - 1 De si jn Cri t; < ' , fJ. , 5
- r. i* ',
to 10 CFF ?ar* SL. i L S C .S - l n c,.. , ._w 3,, . a-
-(.
. . . >- 1 . L,
~ . . .
'/' ' 4 Rrf CTR CORE ISOL ATION CCOLING SYSTE / CTA'!ON INSTRL. .t... ATION The reactor corc isolation cooling system actuation ir,strteenta-ti," is provided to initiate actions to assure adequate core cooling in tte e /ent of reactor isolaticn frco its primary heat sink and the lors r.1 f : ;i. ; t o r f l ew t o t h e r ea c t o r v e s s e l, w wwnt-.gw @.g.e+4 sn-e f--
, y~; - ti . ,.taf<-3+r.;.> ace e 1irg equi n at.
's ./ 4 . 3 . 5 r 0 ' c n.g' p~' p u. . t. T u. . n pja. n t n i.o c y. I n 37 m. ~".,F Ni t 7. . "
iii e control rod Lleck function; cre provided consistent viith the require: cet; of the specifications in Section 3/4.1.4 Control Rod r'ro-cra- rentrols and Section 3/4.2 Power Distribution Linits. The trip i r, . i : is arrcnged so th;t a trip in any cne of the inputs 5:ill resui'. in a control red bic;k. L 5 C f,- 1 83/4 3-3 -@Mo!or l 's ? '
l' " LlC';T/J ! 0's
?- .,
L/2 5
- / i '. 6 FON!10 RING INSTRUlENTai10N
% ra 7ner1;".' A L L 7 F1LW K
?. /; .1 r, ,1 ?m! A7;n i Myi! TORI"3 INSTR'"ZNTATIOR
~~
/ ~ ~. ,./ '
Ine Oi EPOILITY of'the radidon monitorina instrumentation the radl5Gocolevels are csr.tinually reasured in the [ ensures ere:is served that;by-th (1) findividu61 chaiii:,15,Jnd (2) the alarm cr autonatic (tctior.is-i'nitiatedwhentheradiationlevettrQsetpointisexcceded. 3/4 3.6.? SEISMI" "5ITORING INSTRU"ENTAT ION The OPERADILITY of the seismic monitcring instrumentation ensures tnet sufficier.t capability is available to promptly determine the magni-tule of a seis.nic event and evaluate the response of those features i: 1por tar.t to safety. This capability is required to perr.it comparisen of tha r.casured response to thst used in the design basis for the unit. 1 3/1 - 3.6.3 METEOP010;ICid MONITOPING INSTRU"ErTATION The OPEr/SILITY of the :rctcorological annitoring instrumentation ensures *. hat sufficient 7cteorological data is available for estimat-ing potential rcdiation doses to the public as a resuit of routine or Ucid? val relcase of rndioactive traterials to the atmosphere. This cepability is required evalutte the need for initiating protective treasures to protect the _ alth and safety of the public. 3/4.3.6.a RE!DTE SHUTD0'.-lN MONITORING INSTRUMENTATION The OPERA 31LITY of the reirate shutdo'an m nitoring instrumentation ensure; that sufficient capebility is available to permit snutdown and raintenance of HOT SHUlCO..'N of the unit from locations outside of the control roe:a. This capability is required in the event control rocm habitability is lost. 3/4.3.6.5 POST-ACCIDE"i MONITORIM INSTRUMENTATION The CIERABILITY of the post-accident instrumentation ensures that n sufficient information is available on selected plant paramcters to monitor and assess i:1portant variables following an accicent. . L Sr.S- 1 O/4 3-4 _gc.t4ar l G 72-
g l3/4.11 R ADIO;',T I VE EFF LUE NTS E
,Bf:E5
,_-_.-~ __ _
l' l' 3 /4 . l l .1 LIDW D E ILpENTS h D, 3 /4. l l .1.1 CONCENTP* TION j This SV;cification is provide 1 to ensure th?t the concertraticr cf
.. J radioactive raterials released in liauid waste ef.'luents f rc the site to j urrtstricted arecs will be less than the concentraticn level s specified
;. in 10 CFR Part 20, Appcodix F, Tale II. Thi s limitation provides aNi-g tional assurance that the levels of radicactive n3terials in bcdies of
'wa ttr cutside the si te will not resul t in e> posures within (1) the i Section II./ de: pn cbjectiver of Iprendix 1,10 CFP Part 50, to an indi-
- vidual and (2) .ne linits of 10 CF R Part 20.lCC(e} to the popul atier. Th.:
*: cor.:entra tion limi t fo r r.oble ga se s i s ba sed upon th assv ption t' 't Xe-135 is tFe conteciline radicisotope and its MP; in air (submersicn) was converted to en ecuivalent ccncentraticn in water usinc the methcos described in Internatienal Cornis; ion on Radiologic;l Protection (ICrF)
Publication 2. 3/4.11.1.2 DOLE
<m t <
Thi's speci fica tic n is provided to it.pl erent the recui rcTents of Sections II. A, Ill. A and IV. A c Apreniix 1,10 C FR Pa r t 50. The Liniting Condition for Oper:tico imolcrents the cuices sct forth in Section ll. A of Appendix 1. The ACTION state-ents provide the recuires
. cperating fle(ibility and at tht same time impl er ent tne guides set forth in Section IV. A of :ppendix '. to assure that the releases of
. radioactive naterial in iquid ef fluents will be kert "as icw cs is
.reasenchly achicvable*. - ' , for f resh wa ter si te s wi th drintina wa ter
, supplies which can be potentially < Ifccted by plent operations, there is reasnn:ble assuranc e that the oporation of the f acility will not resul t iin radicnuclide cor. centr.>tions in the finished driri. inn water thct are ~
in excess of the reauirements of 40 CFR 141. The dese'calcM ations in the ODCM inplcnent the require'ents in Section Ill. A of Aprer/ix ! that ( confomance wi th the guides of Appendiy I be sho. n by calcul ational
); pro edures based en models and data such tha't tie actual expo'ure of an y individual through a;.p opria te pathways is unlikely tn be substantially ji un dc re: tic.a ted . The equations e.pecified in the ODCM for calculating :
'l the doses due to the actual release rates of radicactive rateriali in l liquid ef fluents will bc consistent with the metl edcicgy previded in l 5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man f r en Routine Releases of Reac tor Ef fluents for the Purpose of Evaluatinn Compliance j wi th 10 CFR Part 50, Appendix 1," Pevisian 1, Octcher 1977 and Recul a torj
- Guide 1.113, "Estima ting Aqua tic Di spersion of Ef fluents f rce Accid'.n tal and Routine Reactor Releases for the Purpose of Inpiteenting Appendix I,'
April 1977. NUREG-0133 provides methods for dose calculations consistent wi th Regul atory Guides 1.109 and 1.113. 7"} B'. R -ST S - 1 0 3/4 11-1 l
- - - ~
- . - ~ ~ - ~~~ ~ - ~ ~ - - ---
tr - '"?"T VE rrFL UE'!TS i. i l l-: i i o ! s em:! f icc 'icn epp ? ies to the ra t ease of liquid effluente frcr
- re;:t:r :t t5c site. For un!'s with shcrec radwaste trectment
!' . tr . liqu!d ef f luents frc" the sharec system are prepertioned ne t. r. : ' : shc-Ing ihet system.
I
.. ...' - - Ll.." U ! D W r TE TRE AT"E NT
.!i y Tr (.R E J .' E ! '. l T Y c f the f louid redaes#e treatment system ensures th;t h se *cm <.!Il be esailable fer use wherever licuid effluents recuire
-nt p lc- to rcicas: to 'he env ! rcr. ment . The requirements that the jl - - r --1 2tc p M !crs cf ++.;s system be used when spec lfied prevides assu -
l-tt t' c ret e: se cf radicact ive materials in liculd effluents wili
- r. r ' "es to es is reestma*..ly achiev;ble." This specification imcle-i-
ro; i t- < 't s c f 1C CFR Pcrt 50.3Ea, Gencret Desien Critcrien f*
j- .',d!- tr 1r CFR Fert 50 and design cbject!ve Secticn !!.D ef l' --
'x I to to CFR Part 50. The specif!ed limits gcverning the use c'
,, - : iat- :rticn; cf it e !! quid redwcstc treatment system were speci-
!' c so;ttlit fracticn cf the cuice set forth in Section ll.A of 10 C P F:rt 50, for licuid offluents. O
[: . , I,
- l .-
h
.. . ~ . _ . . .
t . t i r~'i 'i n ure m e 7;'. q yy
- b. i . 'Fa s ^- i t' l n - iM'h 0 :, t ! !y%of radica:tIve nater!*"
ed in the
;: - . l < . t r < s pr ev i u s a s sur anc 3 't %t..t re. -evcit cf en unccntrolle:
[ m. , _ . 9 cf h ta os' ccr,t nts, fRQ- re.Wr at iens wou t d be
,j i - Nr uc l lr i t s c' .10-CFr."pe Fart -re u20, Append!x A, T M gmr 2,
.M '
u near5 f.:c'2Jia eter supply ar.d the neerest surfece water N ._ ' - O . T .WbGnres tr Icted c' ea.
,_,_ . 11.> . c.u r. cr i sa - cret'e.. r m~
.* [?"; RATE
...__ il.2.1 his siecif ;cetien is provided to ensure that the dose rate ci eny-
'lne at- the exclusien arca boundary f rce. gasecus ef fluents f ree all units en ! ! .0 sItc will be w!ihir, the annual de,e limits of 10 CFF Part 20 fer ev o:1-ictcc c ecs. The anr!ual dyse limits are the doses associated wii'
-' crcentr:.tlons of 10 CFR Part 20, Apper. dix B, Tab!c !!. These limits rrc. !de re :aneb !c assur ancc that radicactive natorial dlschargnd in C n 33 eifluents wiII not result in the expcsure of en IndlvIduct in an ent - trlcted area, cliher within or outside the exclusicn arca beundary, te enr.ual avercy concentrat ions exceeding the limits spec lfied Ir AN ndix E, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). Fcr i n 2 :v i dual s wt.o may at 1:r es be w it hin the exclusion area beunda y , the O e::.cancy of the Individual will be sufficlently ICw to cceper. sate for Dg g80-) - . . ss 4 A.=6
.-e. .. . . . _ . . , . . . _ . . . , . . . . . . . . . _ , , , , _ . , _m. e ,., . - . . . - ,,,,.,
,hl_
i t'"2 , t peric di f f usion fac tcr abcve that for tiu e r. - odn _ The spec i fied rel c;:e ra te lini ts rr.str ic t, a t
< vre;, jing gr . an ' t:et; ds'. retes cbove b.ictg ound
.(. ..se o. c. -3.,.,; - 3 n,.i
,- , +, /
,, . , ~,.,..a. t c.,, .
,,.s,I.,
..so.
v ., .. ~. =n r. , i St: , cr to 2 ( 3 '. c ) - < m '.ve to the siin, lhest
.o L: O. ._ st r ic t, a t all ir <., the cr rres;c nding thy rcid
, , 'd t, cn i n f a o '. ' la the c cw-mil t.-in f ar t pc tba,
/ g :- ic the nea re:t (.c., to tre pl ar ' .
;: : fi . tir a; ri ie r, 5 the relco se e' gasr' us c f fl u.nts f rc~
i t._ -; Fcr un its sei th M c ru rc r's.: s t<. tr e a t" : n t i _ . .. . .t..... i .. f . ,.w. , . p.c.
. s ,s i. n.sr . _ &. ; ' +. v_ e r e - .. n. ~, r '. i o n.c. e.'
. - h . A r '. " - (nsi sy ; t c.~'
- v. r - .
- c.:ce- .
.e.,
(d w e ., , . _ , ' , e. . , .s g .. , \. e:sis. a4; , , , ) 4. . p
,,c.,.
w _.-
.> . c ,. .. . :.t, .-.ll . w 4..,., .%qJl I w .., ns c 6
. :.4i. . t. r I V . ; . o . t ., ,. , . r. . d i x '1, 10 r ur. .?, c. a . _m. . lhn -
- in f;-' r ation i- ;1U nts t'r e guies set ferth in l' 'r, ji. 1. The f.CT:CN sta tr :nts ;,rovice the req .i rc d
. '. 1< . n f c t the !~ ~ ti .c i.: ni c :q: the guidos sci
- 5. - ! /. A c' .br:r.uix ! assu c tra t the releas?s c f rcdic-
- t: i r. <; ; ' . s ef fl uer.ts will oc kc ?t "a: Ic. e s i s rec: r:bl .
i~ 4. 5- il l e c c Recui r e' eat: w R c t r.t the requi rc ce ts in
. ~
l3. ! ';1 . th 1t cer 'ancrc e .,i tt tra guices of /p;;<..;ix '
; ' c 61 iUl e tiChal pr0C edu r c . L' 2 9". d on "i0 del s a nd di t3 Su:h i- e- p s: er an individual t" c.
tbc apnropriate F.tn-
- l. .e
t: b( r ub - t a n ti al ly un dere s .i'" s ted . The dcre cal cul a-in ti.e OL .". f o r c al cul a ti n.: t hc doses due to the ac tual !
. rf'. .c tive nchic gases in gas ous e f fluer.ts will b<.
i '-- ;b ' t:.edcl tgy pro.'idcd in Regul atory Guide 1.109, t'. ' leual DO:c s to "an frc 1 Reutinc Releases of Reactor j!' .c ".
- a.- Pur; c.' o f Eval e:i ting Corgl iar,ce vi th 10 CFP. Par t 50 j :< i ... ' !. 0;tober 1977 ar,J Regul atc ry Guide 1. Ill, "l'e theds 9' ' ir r "lue ., wric irans; art and Di s ersion r of Ga seous Ef fluc r ts I h i: tr is". f rv Light '.a ter-Cool ed Reac tors ," Revi sien 1, Jul f l!
o i li r (r a ti ns prcvidej for determning the air dosc: i: t t h-U :io. .. laun:.. / will be bar M opon t! e hi storical average ainos-h ;c cc liin:. I:t. LG-0133 prevides mct! ds for dose calculation: i s t ._ n '. . th Ecgul a tory Guides 1.109 and 1.111. ii .2.' I F/AT IC'H AT E FOPM D.? ~ r_~. AM 0 i. r l. l_m s..,_ _P t P._I O/ r.il VE KAT E R I A L R .. .
.lu, ,'t uiH 1 1EN h t.L GIM.S
, i lhis s;. .i fic a tion ir provided to impl emen t the recui rceen ts o f
! %; ti, ' !!.C,111. A and IV. A of Appendix I,10 CFR Part 50. The Lirii ting i
3-1 0 3/4 11-3
. .e .' e eew m ..h * * * '
- OU'* O* 8'O'
I
!, l'.10 !' f/.l l'!E E F F L pE M R l ;' E t. r '
'Conditiem fer Ci c . tion are the guides se t forth i n Section ll.C of Ap pe n e. i r. 1. The ACTlUM staten(nts previde tre recuired operating fle 1-bility and at the sa*.e tire implement the guides set forth in Section JY.A of Apperrix ! to assure that the releases of radicactive raterial s
'in accous ef fl ucr will De kc pt "as 1: <. a s i s rca st nably achievabl e. "
The CE.M c al cul a tional er
- Feds spccified in the surveillance requircne-ts inpltrt nt the recoircrents in Snction Ili. A cf AppeMix 1 that confom-ante with the guides of Pppendix 1 bc shoen by caiculational precedures bc:ed on nndel s and dr,t a such tha t the atual exposure of an individual throenh arrrW iatc :a t6 , s is unlikely to be substantially undcr-entirm ' .d. The fC c cl cul ational retbers arcroved by NEC f or cal cul 3 tim the de:ns dut M the act' al rel c a r.e r a te: cf the subject natcrials cre ret uired to br u r.si stc nt wi th th. re thccci cgj prcvic;ed in Regul ate ry CLide I .lM, " Cal cul a ti r of AnnJal Dcsc s to I.an frcn r<cutine Fel ea se s )
of Pr atter f f fluents for tre Purpcse of Evaluatirg Corpliance with l 10 Cr; part EG, tpre di7 1," Rcvi sion I, October 1977 and regul at ry Guidt 1.111, " F^ th.c.i s f : - Estina tinc Atensp!.eric Trer.spert anc Dispersi of Gareas Ef flw r" in Reutine Leieases fror Lignt ',le ter-Ccoled Dac tnes," Pevi sion 1, July 19 7 7 These equations also previce for cetermining tL e ac tt.cl dDses ba: ut.0" tha hi stori:al average at* c spheric condi tic rs ' e , The rel<.ase re'e sg i fic ations for radioicdincs, radioac tive mc te riz.i in re ct icul ate f orr, and rc dionuclide: othcr thar r.ctle cases are dcrender t on th existing radionuclidc pi hv.cys t te nan, in tre Unrestric ted, area. The p;tWys which arc- telmincd ir, the develcpent of these cal.rul-tim are: 1) individnl inhalction of c irberre radicr.u lides, 2) dcpesiticn of redionuclices onto c cen leaf;. vegetation . tith subsecuent censu,ptirn by nm, 3) cerasition onto grassy arca: whcre milk animals and neat s' producin; aniral s graze wi tn cen:, ption of the cilk and meat by E.;n, s/ end 4 ) deposi; ion en tbc around ;i th subsec.uent expcst:re~cf nan. 3/4.11.2.4 Gt 'E OM '!?.c TE iPE AirEhi The OPErtBlLITY of tb: g .ec cus radua ste trea t.nent sys ten -so4-thc--ven t il e- ;
-ti';n cx haust-wea tmen t _9 s tem s ensure: tha t the systems- will be availi 'l e fer use. v.hencyc r ca secu, e f fl uents requi re trea t; er.t prior to rel ea se to the environment. ' The reevi rerent tha t the apnropriate portiens of tW%.
systc s be used when sp:cified provides reasonable assurance that the
, t el c a s t ' of radioac tiv e r..aterial s in casecus ef fluents >:ill M kel' "C ilco a s i s reasonably a<.hicvabic." Thi s speci fica tien impl ements tb- l requirments of 10 Cri! Part E0.36a, General Design Criterion (20 of Api "- j
, dix A to 10 CFP. Part 50, and design objective Section llD of fprendix !
to 10 CFR Part 50. The specified limits coverning the use of apprcpria'r por tions of the sys tcmd.E."speci fied as'a sui tabl e frac tion of the
~
' guide set fcrth in Sections 11.D and II.C of Appendix I, 10 C fr. Pa r t 50,
, for enceus ef fluents. , /~'
; DWR-STS-1 B 3/4 11-4 4
* " ' * -9 *"*"**OW 9OW
' *
- e% -pl. s ye 4 4 ,,
p PIh!MCT!'!E FIFLUE NTS B
-_A_S._E 5 3 /.". . R. 2, E - C0 5 E T h i s--s pe c-i-f i e e t i on-i s-prov-i d ed--to- me e t---the--rer.n c-t ia g- requ i r cr.1 c o t s j % y ) pf-4CrCFE-190.
,J p i 5 .- ~
p (d:/ J /4.ll .2.h EXPLO31'F GAS MIXTURE
, s
/ w D This specification is provided to ensure that the conccntration (C' f of potentially explosive gas mixtures contained in the waste cas treat-
['] ! men t sys tcn_ i s.mc in ta ir,ed- bel ew thc-- fl er abil-i ty l imi t9- o f hyd rogcq - ge - aan.-e jge n , - Hu 8 e' tt ie-con t' ci- fe tu re a r+--inc-10. 3.--i n- + d systtm-- lj Of to- pr ev en t - the-hyd re.y er-end-c+ygen-c erc en tr+th. .s f ro n-ree chi ng - the se
. fli maHi-i tv4imi ts:-Tntst-cut.enatk-centrobfe&tures-incl ude-i sol atic .
[E lo f-i.t+--sourc e-o G hyd regen-and/-or-o+ycenr -a utma-tic---diw:r:-ion- to - re - a9 ' c cc.iri r.erv s or inj ec tien- o f -dil utan ts-to- reduc e-tFe concen tration bel ow 2d ! the-fl ar,a ab414 tv --I ini t s,) Ja ir t-a i rnr,o -U+-ceneg utes t-io n < f-hyd ree t g[ 0 ! a nd on.yg e n- bel cUsth9 i r- fi ammc h il i tpN.i ; ;--pr-oW o s- amr-ar.05-tha I. ' - (, l t he - r el e a se s--o f - r ad i o ac t i v e-mater-i a ls - wi-I l-be--c o n t-rs'.-l+d- 4 r.--con fo m cec e jui th the-requu enent: -of- General- Design -C -i-ter4cr4G---of-Appe. dix A O -
-to-K 4T-Tv-Par t-60.
3/DhB,L M/ IU CONDENSER
. .N Restricting the'gress_radioactivitv rate of n'.M e acS ; >r,on tb-nain condenser provides resicimH c. a sc ul'anc e tha t.Jdtal bed;. expo
- urc
'to a individual a t t he e x ;1 u r. i r. n a fi.'M c. :t ' #wi l l no t e x c e e a sn a l i f r action of the limits of 10 CFE,.de6[LO in'hty.gnt thi s ef fluent i s i n ad erten tly di sc hargst -difI'E51y to the envi rcr entT'i'tM.Qtrea tnc o t.
Thi s specifica. tion'inpl enents the requi re ents of General Desi; r. ~ Crity ia-6 fand 61 of l;'rendix A to 10 CFR Part 50. - 3/4.1~.1'22 -! ;DLi-e? I I CONT AIN".ENT - (CET ICNEA-- Thi s speci~ fic ~~----.. a tion provides iTac. n' e neb' tha t relesc ca se/s/,,- f rc-' drywell purging operatices-will~T:5T'ex cced the arir'I'& doQai ts o f 10 CFR Par 120-fei" unrestricted areas. xW
'---.~~?- - ~ ~ . . - . - . - J.
C'.lR -515 -1 B 3/4 11-5 9
'9. * * . - .o ge . gag n .,p.,_ e. pp p - = - +- *w- *e- ********^*******"'*'~~- '# * - ' " " ""'*
=
e A \
~.-
,,/._
s-1.
+
s r g,. , . -.,
, , , - +
. y s . c .- .e p..
+ w.
, . . p g .,>#w u ..
, ,a.
3,. 7, A_a . , ... , ,)
'c. ,
'^r 5 " i 1,. rdt. C'r S ./,,.'F0'..<j.i:-7 r O c e s ",10 3"d .
' 1 ., "; ) *. ' .
_ I n i S. ",: C i 1 1 C d t 10 r. i r' D i C 0 ' 15
.S- > ,,t,n... f. t i nw .u. e ,. .- ire t.1.v c r.12. c.wvr, O.c rr- - -
1- _-
.pDr :2 cg ihcludec in e taclish-
~.
.. . i U , a c,. .. N. . . . l ,i ... ..eu .a s, s.
to w , ,3 s .
. e
, b L. +. .
i i $. i i c . '.' 0 0 5g Pi t/ C a i 21;.'S t f ? ,ig5, w 3 5 *. e r i: . . cor -ti tuerts, nixinc and cuFing s N N. .. r I l 1 t. i i 1 i e l 1
- 6. 't
^
- J -!
B 3/4 11-6 9
- . . - , - - + - - - - - - - ,.
f
O I g 3 /4.12 R At !N. OGIC AL E_N_VI_Rr"M'iT AL !$HITP !NG i EA
-..S.E-5 3 /4.12.1 IONITC.Rl!M PCOGF AN The radiologic al runitoring crogra- recaired by thi s specification pre-vides reasurments of radiation and of radicactive materials in hose '
cALosure pa th.ays i.nd for then radionuclides which lead to the nighcst pctential radia tien exposu es of i n'ividual s resul ting frcm the sta tien Thi s nc ai toring prcgra" thercby suppi c-rents the radiol ogic?)
~
o pe r a ti o n. ef fluent monitorin; prcger, by verifyinc that the measurable concent-a-tio'.s r$f rediccttive materials and level s of radiaticn are not higher thar ty pec ted on the huis of the ef fluert mcasurtnents and medeling of t h< . e i ron t.n tal expo: crc paiheays. The initially specified r,onitor.r3 yi prt.-c:, wili be ef f ertive for at least the first3 '9eeFyears of ccmmercial ope ra ti e n. Follcwi P this pcricd, program changes may be initiated ba ed on operaticnal experien:c. Thc de tes tien c ?r milities required by Table 4.12.-l are sta te-Of-the-irt for routin- envi-ormen t31 rea surcncnts in industrial l abor a t;<ies.
-LLD's for dridina e ter teet the requircaent of 4C CFR 141. - l' 3/4.12.2 LE!C UN C D!'"3 T his sr:ci ficatic r is provided :: cnsure that changes in the use of unrestricted arac are idcr.tificd anc that :nocifications to the racnitoring pr.:gre, err: r.ade i f requi rco t;;, the resul ts of thi s census.
This census sa ti sfip the receirencnt s of Sectior. IV.E.3 of Appendix : to 10 LFF L;rt EO. ' Pe ' ic ting the census to gardens of greater than M squart f cc t rrr cices ' .s'r ance tha t significant en.osure pa thways via f leafv vegetrics will : e identi ficci and renitored sirice a garden of this size is thc nine a rccuired to produce the cuantity (2f kc/yca-) of leafy ,
. vegetables assumed in Reg 0 ctory Guide 1.109 for ccns'nption by a child.
g To de tctrine thi s ininic.n garden si ze , the foli cwing c ssu,ptions we re j u u. d , 1 ) that 2G cf the garden s.as uscd for gro..ing broad leaf veget3 tie-(i.c., sir.iier to lettuce and cabocage), and 2) a vegetation yield of
'I .2 Lg/squa re ne tc r.
3 /4.12.3 I M E'<L ABO A'. P COPF An 15 0" PT 0rMM lhe requircent for participation in a Intericboratory Cc"mariton progrc, is previJcd to cnsure tha t indeoendent checks on the i rccisien an? accuracy of the measurcoents of radioactive raterial in environraent.ii sample r.atrices are perfomed as part of a quality assurance prcgran for enviretriental monitoring in order to demonstrate tha t the resul ts are reasonably valid. C'n'R -S T S -1 0 3/4 12-1 0 -
.m****eng+M.WW **esr * **ei.w % . .,
"*em - - *ww g egg, e. , ppg %p
* *
- aM . ..es--y., eee @6..+.r=m- -
gs ANilillW ATIVE CrNTROLS proceduras, or instructions having nuclear safety s i gn i f i c a r,ce.
. 6) Signif icant operating abnorm.tlities cc eviations from normal and opected performance cf plant equipment thct af f ect nuclear safety es referred to it by the Onsite re/ica and Investig tive Function.
- 7) Reportacic cctorre ccc rcquiring 2f-r.our notification to thc if.'.' .
- 8) All reccgnized indicetion of an ur. anticipated defi-Ciency in 501 > espect of design or operation of safety-related structur.a, Systr.C , or CoCponcnts.
- 9) Revitu .nd repcrt finding and rcto.mendations regarding all char g.: to the Gcnerating Stations Emergency Plan prior te in plctentat ion of s",h change.
- 10) Revice rnd report findings and recom endatiens regarding all ittt,s referred by the Technical Staff Supervisor ,
Station Sui.e- ntcrdcr.t , Divi'. ion c'.anager - i;uclear ('N Stations, and M >g;r of Quality Assurance. I
- 11) C o n o c e . ..
,o To a Oor G r e. D o s e C m.c m e ~ m m ,. m
- b. Audit Function ( o oc.cyl The Audit Function shall be the responsibility of the Managc of Qua'ity Assurcncc- independent of tne Producticr.
Departmcnt. Such rcspcnsibility is delegated to the Direc-tor of Quality Assursnce for Operating and to the Staff Assistant ta the ,"an?pe: of QJolity Assurcnce for mainte-nance quality assurance activities. Either shall approve the audit agenda and checklists, the findings and the report of each audit. Audits shall be perforned in accordance with the Company Quality Assurance . Program and Proceduret. Audits shall be performed to assure that safety-related functiens are covered within a period of 2 years or less as designated below.
- 1) Audit of the conformance of facility operaticn to pro-visions contained within the Technical Specifications and applicable license conuitions at least once per year.
- 2) Audit of the adherence to procedures, training and qualification of the station staff at least once per e9 year.
- 3) Audit of the results of actions taken to correct de-LSCS-1 6-3 {,et @ . W'a -
3
~ _ _ . . . _ _ . . _ _ _ _ . . . . . _
, '. ir fic ility ectiprc.er t, strutttres, "f< ation that affect nuclear r . . n 1. . z_ .
4 .: , c c' cc.icities required by
^ i c, _
.~ ta tr.cet the Criteria of 1, '. i. .! c./ P'. cn and i:n, l emen t i rma
', ~ '
.; -"e- :tj Plar ar.d imple: renting
~
/ o r e v i t .. , . .
~ to I' ";.ctico h o; ram cud in;lemcnt-
' 'itc per 24 7enths.
r' cf r .;c~ oli;r.cs :ith !.'P.C reauire-a.:nr.. , ., a
.is . c_ . ,J . . -1.a .. u.
i ,,..s._. vie 4,
- d : P. the Divisier. 'M r. a g c r -
< r. n , . c.
i . , .c.,u,
. .,.c_,
... +. t.c p
. Et cT . J. . ,, ion 5;is t sms An c ly: i s , 1 n
.. o. ~
ic,'.c!
--,a.
3 ConEt ;ction, Product'er.,
-z..
c,1 i u i ,, 1 y , t
'7 ' : ur ce repcrte to the Exccutive
' ,t i - , .,.c tr.c C,i! site ceo ew c,
, , ,.ie '.irce
., , .-a
+ c:
- + r, r ,.,;.
.w.%.. v c . . _ O1 .c q.
. . ,' . r i r1 -
~
tt
,i . 9..' l',r : I ys i s . Eitht: the Panager of .
the 5'g m iscr of the Offsite Revie,. ct
- i. .a m.' n i .' tne authority to crder unit s: a.A '
ethu. -ction ..hich he decm:. ncces-s' ._
.- ;' . cc iiticns.
D e u
' 'i 4' r tt u .n 'atiCns shall be dcco-i;
- 1) '
'?_'it' 1. tii - '
, L '. ; d d ., covered in 6.1.G.I.a and 6.1. r. 1. b .
- 2) fc'i.. v .~ doct auta' ion, r: ports, and correspcndente sl.cl i l t , L. "'p t c r file at the station.
- c. P r o c e '!u r : ', ^
h r i
- t c n c ' , i n i t, t r a t i , n procedures shall be prepared and .-
L S S - 1 t'- 4 -Oct&e -4 975
j.w 5 i) tit al l ugy r.. ;i ne .. 'c c"eduate or equivalenL with at least
; y.;rs oT experience in the metcliurgical ficid.
J) iht sum:rvnte cf the Offsite Review and Investigative l ur.: ira sh >ll he' e experience and training which sa-t i t i .,- 51 ' n.1-1971 requirements for plant mcnagers.
. IV .: :e In ics aad Investigative Function shall be supervised by - Ji 4,en .wpc mtendcnt.
- a. f- .ite Revir, aJ Inv00tigative Cuncticn i; '
5tct i ca u; ( r i nte.ndent shell : (1) provide direction it t: . P. t . i e .- . n . .' Investigative Function and appoint the
- crl.o ;cel 5t-Jf Sq ervisor, or other ccr;arably quaiified ii 'i.'^.:1 as a s:r.ior particircnt tc p ovide appropriate dir . tix ; (2) errove participants for this funtion; (3; : s s i." - that , tc- 1erent cf more than cr.e participarit who cellectisti) pcsscss backgreand and qualifications in tha sutjrmi r. iter under revice/ ar_ selected to provide con:r oers n .' ir.t rdiscipiinacy revia., coverage under this functicn; U ) ind mcndently re'.it.v and arprove the findings a r. recom e datiurs de.>elcp.ed by personnel perforning the Revicu ar.d Invctigative Function; (5) report all findings of nonctc :licrce .cith I;r.C reqairoments, and provide recom-n.en ce.t i on s to tu Division l'.anccc-f;uclear Staticns and the Supervisor of the Offsite Revie.. and Investigative Functirn; and (c.) suLmit to the Offsite Revie.. and Investi-gative Fur.ctic: fe concurrence in a tirely manner, those item:, described in Specification 6.1.G.I.a which have been approved by the Onsite Revie.. and Investigative Function.
The respnsibilitice. of the Personnel performing this func-tion are stcted belo..
- 1) Revi.w: of (1) precedures required by Specification 6.2 and changes thereto and (2) any other proposed proce-dures er changes thereto as determined by the Plant Superintendent to affect nuclear safety.
- 2) Re.iew of all proposed tests and experiments that af fect nuclea: safety.
- 3) Review of all proposed changes to the Technical Speci-fications.
- 4) Review of all proposed changes or r.odifications to plant systems or equipment that affcct nuclear safety.
LSCS-1 6-7 Octobar 19f'
'. i t , . '. no r 'l ner.cc4 p l . a n c e- ' ' n NRC r er.;u i r c ren t 's
.: . * .pa e :.d f or.. .rd a report covering evalua-o ac. rr rp - i c o s t t ; wcnt rccurrence to the
'.'.' v..r ~ ~h:710; St ?! it and to the Super /isor
.r. C. .1 :' "ec.t. nd Investigs 1 e runction.
..C ilit;' L, cr3tir,sig t9 detgct n,otestia) $a ety t
- 'f spum l revie.3 and l'< stigatiOn: -
and t . ..an as rcr:c 'cd by th "..D rvisor of the
- t
.. and Inva: getivt :- e. i : t i on .
' 't l' C ' 3 ?. '
5 (' cu ity plan cid shall subli t
. . '.N n <; :. 5 to the Divisicn " .nsger-t'ucicar 1,*
.. g.r 3..... 4 c ~. . r. . .. n. r. .., .D 1. i .* , 's d e a'. m ' 'i v e.
q 4 . -e i n_ e n . e. p +.. i. p. g-i s. . d ,i - C: d slt . I 1. U hn i 1. re C ?'i ..C n d t. j Ch a "C., C s t o
'. .i . I'. ia ].' - hC l t : ' 51Stic:is.
' \
- i. OI FC j. "t-b'- ccCJrrentSs cru artign; takcn
., ty.a . r r . .~n 1 ..... ^
. p-.
N t - 7 t I!- c"? i _ l 3(ffF Sc%:' 1 ;.o r is resprnsible to the 51ation E , : r i . .i t : . and slall rde roccT^Trdati "s in a tiMly 0 tas OT r i v it..., i n ,' e 3 4ga'.iCn, and QU3tity
- C ,i ct l p h : . '., o f p i t n t ra i n t.; q 3 r :6, cperrtion, and acr.,ini-st- ,.m ; 'me, rel?tir.g to .~;cility cperations a':d
,: ,ce Lhc 3uthcrit., '.o ricocst the :.ction necess;ry to c . c '. . . l i : : ..ith rules, rigui3tions, and pro'edures
- v. h ' - i' his cpini.n such action is necessery. The Station S m ' i n t .:q ient shall folice. such reco::Tendations or select a ccw r,e of Ntien that is rere cer.servative regarding safi c.. ration ci th? fc-ility. All such disagreemenU ciell e rcported imct: .t ely to the Division M nager-Nu-cl' 'ctr ion: and the Sopervisor of the Offsite Revie',.
aM i t,cc s t .y t i'. c Funct iLn.
-1 Lo c_ ,,~(<-
- 1) Rcrects, revies.s, investigaticns, and recomendations shall be dccrented with copies to the Division Manager-Nuclear Stations, the Supervisor of the Offsite Review an InveM igative Function, the Station Superintendent, and the Mcneger of Quelity Assurance. -,
'5-1 6-8 -Oct ob er--1970 ~
_i_. . _. . _ _ . _ _ _ _ . _ . _ . . al u r:r d: "
'~c'2 .aticr shall De i.,_pt
! +
. +; .
e! ,cn.
., ,: - '. r . ' '
,.-r,. . . . < > ' ' . '. .,'1-. ' i. '
,s r .
.. +. , , . , . -
. . . . .: o .
.. ,. . - u;.a
< - ...s m... . .....<i-
- i. - < s.- ,,
i.
> ,7 ;.
.c.. , . . , ,
m., ;r.r.'i' d e- 'uIc r
#. t. 'i -
1
.la7
. g . . - 1
.> t. . .a
, . c
, s ry....,,D
.t 6 6 t ';
n' c n m; r _ *. uc l e. c r ue
~
in 5, -
'n visi n 5:
ar ' .
- c. - of tne Of';ite Recien
,.+4 F .;; ,
.w _ .. '
. ,1.r ....,i..
i... .. ...
+, *%r., .1
~
t_..
. .2 3 i _ta i '; d 1ist1:ig of it- . t: b e r e v i c ,. ._ ;' .
., r. ,) :.s, 4. . '. 6 '. 1 O.#
- h *~_su ' ' .-
. i i 'u '.' C , '. '. r r '
r r
..-. e. , . . .
activt_,
'ssi i .a t :' * ; ' p a r r, i b . I '. t i e s .
t, . n ,cc.
- 1) The c :_. :en :el pc f er . 37 1:. OnsitE Review ar.d Investiga-tive Cancti0n, in cdJiti. .0 the S';a' ion S cerintendent, shali cc - i: t of per; tid ' " , .3 egertise in:
c) r.tmicar powe: plant +=chnology, L) rcacter cperatiens, c) rer '.or tng i n?er ing , rdiological 52fety TJ chemist, d) e) in:trusent3 tion and cc.'.rol, and f) c'e ch an i c a l and electri: systems.
- 2) Icrsonnel performing thc' P.isite Revic, and Invest ig::-
tive F.nction i.h.ill meet r:inimum acceptable levels as desciiiicd in A.151 N13.1-1971, Scctions 4.2 and 4.4. H. Fire Pro'.ection Program An ine:penJent fire protection and loss prevention progr u ir,pec-tien and audit shall be perf onr.ed at lec.st once per 12 month., utilizing cither qualified offsite licensee personnel or an outside fire prottctien firm. LSC5-1 6-9 October l'C"
/ [r" U 3 rit!' ' ' n Cf;*n ROL S a
An ircpectien and audit r.f the fire protection and loss preventien p r og r.' s r.h ,l l t,e p c e f ;r.me d b; a qualified outside fire consultant at Ic.1:.t cnce per 36 mcnths, r'
,' i e
LSCS-1 6-10 October 1978
, 1
,,;..m, 6 .e ;
. r c, - _ 7..r.
.. c. ' c..tor "r r -
A. 8. > e ' '
' i t t e. p'ocedurer includin; tcplicabic chect:off lists c o'.t r 1 itu us list r d belca sh0Il be pr epared, anproved, and ad-he d
'.. 'i 1 n *- t e, , c: ' rc t icn , and shutda:n of the reactor, and o' - s sic : e ' cc..J,.m. a t s invo lvi ng nucl ea r saf2ty of the s
4, s . .
'. f. . .- i: : cpw: L i er. s .
A. tin tc be in co to corrcct specific and f areseen potential U O t ' , tiw:, < f systcn:. or ccrpcrcnts including responses to c: ~5, ser.per ted pr; . cry system leal:s, and abnorn.al rea' '.ivi'.y chy .? ._ s . 4 En .g.. . coVit icr.s in'.olving pniential cr actual release c' c.aic.cti ;;y "Ceocrating Stations Emergency Plan" and s.M u e erg ec. cr.d a;nornal pro:cdures. E, In-t .m . n t e t i c: ,1cr:;i.:n .shich could have an effe t on the ssf'tv of the itcilit',. C. P. e- . ive d c.crective n.aintena .ce operations which could h ree an c f f t '.1 en the s:fcty of the faci'ity. 7, Sure il' Mca cod testin; req ui r cn.un t s .
- 8. Test: cid expcri~ cats.
- 9. I'r o c c d u' to ensuri saf e shutdu :n of the plant.
lu. St : tion :ecurity Plan rnd iTplementation procedures,
- 11. Firc Protection Froaram implementation. {
i .
'"; r : ,4 c- O ,. . a O . .
. n , . .~ 0% ,% .L m c Lc m e T o w -
l
.. . adia: on centrcl piocedures shall be maintained, made available to all staticn f.cr sonnc.1, an:.' adhercd to. These procedures shall sh:.w permissibic radiation exposure and shall be consistent with t'e require:.ents of 10 CFR EU. This radiation protection progran shall l'e organized to meet the requireirents of 10 CFR 20.
C. 1. Procedures fer item > idc.ntificd in Specification 6.2 A and any charges to such procedures shall be revie. zed and approved by the Operating Enginece and the lechnical Staff Supervisor in the areas of cperation, fuel handling, or instrument main-tenance, and by Maintenance Engineer and Technical Staff Super-visce in the areas of plant maintenance and plant inspection. Procedures for items identified in Specification 6.2.0 and LSCS-1 6- 15 -October -WT:
/
' . ocNm e r thill oc reviewed and 3pproved i
Su: .sor at'd the Pedioicnical Chc:aical _1 - '"
, .sen pr usir.g each c' the abc',e
' senior cporatcr's license. in
.. ' Jstt" '
chin' , thereto, must he.vc N' ' . .a'. >> ' upcr int er-6._' t bef o: e being
*r ; : '. .'s ccdure.r. .Aich i.mpic z t approvcd r' i.. 11 i p a:U- : r <. S Shnl) DC apprOVCd dnd he " tc - E n g i r.c. wnere t5c writt<_n cuther-
;6 Ly .. < ' - t i on S upcr i nt enc.ent . The it
;n -acciure" utiliz(d for safety-t
- 1' :,,,~. ; d o r. ' ', if procedurcs referenced
": ;'it ien Prcc.Ture" have becn approvcd
,- 4 Pr. c ' es wh ic h de net f cil wit hin r; *: !.L./ cr L.2.B mcj be apprCVed by the Cc-
- n. i -
. ta .
- *;rre r.2.A and 6.2.3 above city be n dc o
- 1. i' ' th. ' 1.. rc ; 0.<'are is not iltercc. n ci - ,5 ..,- .1 t.^ M . .f <, cf tr.e plar.t managem.nt
~,
3! i. . . - hC'.d5 tl $OniCr $6 actor OpGr at :t ' S o 3 c. _ s - ...-4+.
- u. .
,.s,. .t .
7 'b- "
- A . r.1 j, ri.eia.s?d by the O' site i, .iew and r
u- . ,m 2n
- p. roved by the Station Superinten-c, - - , in e r.tation E. ir c' - "
r nu ; :: dcscrn';d in 3 ecification ( s '- -
.3 c.te? c te ly. 1best drills will be planned
.,- , .nc cra:rce of t. year, cv:mur.ication links are
'. a- '
. r;. /.ci . cru ccat::cted.
A t !.0 5- 1 6 16 October 197E
- , . . . - _ . . - . . . . . . . ~. - . . _ .
- g. . . , , . .
o< . r. , . . . . < in v 'i ' u' ,.- t :: - cer uirewnts of Titie 10. Cooe of i 'rt i ic m. .er.tified reports shall be sub-mitt- to * ' t- ' - te Regicncl Office cf Inspection a n . ' r r , r t.c 3 i. n' nrtu A. f- . 9< 1 'A. , A 'N ' .t t cte, 2nd ';.n..er escalation tes ting (.,t(cuipt of an opecating license, t' : .
';1. in- !;
i, ti ic ms. : :vol- ng a picnned increcsc in
. 1+ il i: 1 ' ct.tn cf fuel thct has a different
- d. ', - - ~ a c tu"d bj a d if f er.ar.t fuel supplier, vn: (1) . .. Lir - .tv. he ee sigr'ficantly al tered the nut i. ar .
t .eaali; pcrf ormar.ce cf the plant. The r e . . r c ., H . cf P . test: identificd in the Sr en" .. i r. l u a e 'ic':ripticn of the r.scsurtd nit .a r. ' -
- c neit;cn: er characteristics cbtained c- acriscn of these value*, with dc -i m '
*x ' - 4'.d
- - t,4ci,gic.e, Any cc.-. ec tiVC dCIiCDs
/*. d ., _ .y . - ,g ti .1 v. - . - t-t:in .=tisftctory op:retien shall also be "
/% ;ir oal : ecific etc.is required in
' lic; cc .ior, t..ed < c.the. ro m tz;r.ts shall be included in thi. t.
Str t u;' - '- shr'i P su'critted tithir- (1) 90 days following
- c. m W . -
.; s. : t t progren, (2) 90 cays follo<;ing rcar,' :- .... .it c: ccr r.ecial co.cer operation, or (3) 9 1
..; initial criticality, hici.ever is e9<liest. .
If tne
- g. 't d v : r"t cc eer all threc events (i .e. ,
i nit i al '.17: 11t., c raleticn cf stertup test prograra, 2nd re u. , t - car. . r s nt cf cc:percial power cperation), sup'O lu rcs e n ; I l l' u suhitted at least every 3 r.cnths until all et esc 't; have L:Ccn CGpleted.
- 2. A t W"1 ' ' 211 i- ;ubritico on an annual basis of the num-h: ef '
n, utility , .md other personnel (including con-tracter ' '
.e i vi n evosur .5 greatcr than 100 mee../yr and ti'e ir c- '1cd r r u- .'> psurc according to v.crk and jcb functin.-
', th:- t : Su l .' t i en sunnlcnents t he recoironen';
e.g., reactcr crarctione and of Sect. . .'. 4... P i l M- -.lu-(,Th. 20...), runeil ., . . in.c vic. irepcction, routine maintenance, spe-cial c n'nra (d' scribe maintenance), waste processing, and refo:lii.q. Thc do:a assian..icnts to various duty functions ( l may be e.tio tM t.c .- d cn podet dosirt.eter, TLD, or film l"i h mosure.cnte Sn.11 e).pesures totaling less than 20% of the individu :1 t ai..sl J v need not bc accounted f or. In the ag- . ts31 6-21 OctoN.r 1W
f.9,vpa]. U ,-', . cregs'< t I <. . ' t 3 m c' , t h._ tot;l .+ ole l;ody dose received fren r : :1 < m: r u - M11 te ,* signed to specific major wor'< functi m , w'
- 3. W nt hl.; ' cr o'
, m, F. =, '
Re.utin- _ i.t r ' c o.' cp .iing stati'. tics and snutdown expericnce shall ' '.'N i' tud o . M bly L ni, to the W rector, Office of non-
- i ,rcer ,nd Pr w c- Ccrtrol, US .1uclear re-g;1et: : > . _ wn , ;' ,
n , ton, th^ 20555, with a copy to the spr , 'e r ' m .1 ' ne, to cerive no later than the 15th of ea? / a 'elloc .T, tb- c;1end,.'r month ca.>ered by the t<por' . . , . . nt i . ,6.v c a n , .. c. r s rn T, v Dry ',1,- Co'. C. , c 't av R<>~ s r v. ms in.' B. ~I!Ur t d ' ' '<m 1 r-
;c.1" .a On <,, n..".
c.
/h,'
e .~nnc 90 o o v; s . c. .
}!
g~ m :. n c , >>s ;>n rc w rn. c n n, c
)
z Eerort.b! c, : . . i . r r ., ir.:ieding co rective actions and me35ures to prt.e:' . Ji vs, sh 'l' Fe reported to the hI. In general, L L. . . , . . , ' -.' xce, rm with reruect to safety sitnif icance delcnoine- '; ; ,
.dia:,. of reverting required. In scme cases, la.. vc e
. 1: - sin i.t m of an event may not be obvious at the tite of i t- c c <. .. . r _. I, nut h cases, the f6'C shall be informed
'~'
pror t i.v - a^ it.: ' jd ;ipi'icanct in the licensce's esses ment , of the F. '. 1:e .'d:Li ., supplwcr: 31 reports m?y be re;uired to fu!)y d :: rib '
; " 11 -
.;luticn of the occur ence. In carc of cor: cc' li- - .~" 'm -tel rcDcrts, 3 licensee event repcet shall be cc ilct- x r- 'cc_'. ihull te rah to the crigin21 report date.
- 1. Prorr' : n t i f ', .. .: , i ith citten Followup The t ,;, < - V t> "ts listo! telow shall be repcrted as expedi-tiou.ly C ; i b '. ; , t;u t within 24 hours by tcicphone and ccn-f irr 9 b,, t t '. . .c.h, w ilgram, cr fassimile transmissicn to
' ' U _ rpo t. riate re-ional of fice or his desig-the direde: .
nate tu lat - t) : the first ..ortir.o day folicwing the evont, with - v iti n f<lle a,- tepcrt within 2 weeks. The written f olic m rcp / ' EMll include, as a minimun, a completed copy of a 1it.m 9 . vtat r.peit form. Informatico provided on the licen*u ev d. rencet fcim Shall be supplei..ented as necdcd by addititaal narreteu material to provide complete explan3-tion of the circumst m es surrounding the event.
- a. Failuir of the reactor protection system or other systom subject tr. li',:iting safety system settines to initiate the ret;uii cd prot tetivt function by the time a monitored par neter reaches the setpoint specified as the limiting safcty system setting in the technical specifications, A or failure to co.tplete the requircd protective function.
L5CS-1 6 22 -& t obe r - 19.L'i
, . - . .. .. .. . . - - . -~ - - - - - - . - - -
s .
/O!'."ii ST' i.l IVE CUH ROLS p - .
liot e: lnerumcot drift discovered as a result of testira need not be renarted under this item but rw/ be rcocrtable urider items ]. .e., b. [f,, CE E,.2.0. be l nv.' .
- b. Operation of the unit er affected systems when any para-meter cc operation subject to a limiting condition is less conservative than the least consetvative aspect of the limiting condition for operation established in the tech-nical specif ications.
I'r.t e . If specified cction is t.a. ken v.hr.n c.svstcm - i s f e.md.- to he oper i:tinn he' . ten the i.mt conscr n ive er.u ine k u.t con; .ative ;.nceis ci a iim.t ano cor.m ticr f cr ener t at wr
9 . .~.
- b. .
i<. not ccnLi &rea to nc-/c t- en vic- _.ditien t o' egerat ..m
" lated an ' r.va rat bn rcnerted uncer tr. ~ itc", but it raay !' rep d EI" un9r I t r.m B , 2 b . t e , 0,; .
- c. Abnorr..el de ,radat icn discovered in fuel cladcinc, reacter coolant pressure bour.da.y, or primary contaircent.
Inte: Le9 3ce of_ valve . cac'r '~+ '"n or can ets w tn i- the limits l i- r o v
..10. '.n *' i t i .'" =1.u:. ;1..e . s a ** ' ' ' n i n '-r-to-"tra'e
<%. nr ' -
-for -
~
<1 . _ne d nct De reportec under tnis item.
- d. Rtectivity ano"alics, involvirg disagrecrent with the crc-dicted value of reactivity balance under steady-s; ate co" ditier,s during pc..cr operation, greatcr than er equal to 1% t.,k/!. i a calculated reacti,ity balance indicating a shut-dovin rcargin less conscrvative than spccified in the tech-n kal spccifications; short-ter. recctivity increases that corresponci to a recctor period of less than 5 seconds c ,
if subtritical, an unplanned reactivity insertion of rr. ire than 0.5% ik/k or occurrence of any unplanned criticality.
- e. Failure m malf unction of cre or rtore cor ponents <.hich presents or could prevent, b;. itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.
- f. personnel error procedural inadequacy which prevents or could prevent, by itself, the fulfillment of hte functional requiren.cnts of systems used to cope with accidents .ialyzed in the SAR.
Pote: .e. and B .1.f. , reducea redundancy-. For I t e_ms.. I'_._1, that do.x not .resul _ int a leu 01 "vste'n function F '1 O not be reported under tnis section but may e rcportiible under l i t m ii . 2. b . and 0.2.c. belo .. LSCS-1 6- 23 October 1T^
f f _'T* _ . . . . . . . . _ _ _ . _ . . _ . , 11 . 1; < -
,r ef n-tural '.,r ac made events that, r/ ,
; .;1' t' c tver.t , rer,Jirc pi cnt shutdc.m, t, M '. ..ti:.s, sr ethif protective aca;ures
- r. ,
wical e trificatit,:. O i; i r ,
-'in ,e Nr. sic v. or accidert analyses
, , (: '-
fy such coalyses 35 de s cr i bet' in
,, e , ; a fo* the tcchnical specifications i b t: n -
,, , Der:ritted reactcr eteraticn 'n d .
r s,it than 3; sum 2d in the analvses.
,J
; .. .f /. J ';, syst. n, or components that
> . r al . . or c^rrective measures to prcycnt i- , n- !c a cen . vative thcn assumed in i
t' . ir r i n '. be W- or technica' specifica-
"isc e >
,. u i r.g p l i n t life of conditions c '. A ed in t he S/-? cr technical spe-
. y: ; r- *
. .cc:.cc ru edici action or corrective
..t' o.ister.:c or develcprent of an
\. V ,.. .
t
,J
'l > f. & i. !s .
. . ' t. p r. ide r reper t i r0 of poten- ,s
,,0 L
i
.. . ....n..
< i O; ' L
. rr - . i . c 'c : ciscus M belc . have lesser iTme-d i .. . :. .. /, 1: <
t sc -ite' urmcr 5.1 a' Ove. Such i' of witt r repcrts tc the director 11, ., _ e .L t.c . : '
., c c Li . effice withir 30 days of occurtence y1
s De
<< - r p't shall includc, SS a mi n in.um,
'. 7 '
c ce "' . ; lic m E event report forn. Information f ,' l , cv. s '!. w- . ' , ' rcport form shcll be supple-l 2 5'- : su ,i..u t, ,;1 narrative mat.ri;.1 to provice c
!g '
cr... 1
'~ ' of ti c circursttr.ces surrour. ding the event.
- f. l l ~,' 'I !
Re:. - -o - ' i .: - syt;en or er.<;in0ered safety feature
; !l in < '-r '
' P. ;5 .t i d th are fm.ad to be less conserva-
! hjl ti; r, . oc estallis!'cd by the technical specifications 1 -
l b' ._h d oct pre',cni. the fulfilirent of the functicnal
.l J' >5 t l
- r. m t of a' .,cted systems.
u - o'
. U e, I b. Ct' : ; lcMin' to operation in a degraded mode permit-IV T { t e,i : ., .' l i:. : ting conditinn fer operation or plant shut-de m r;uir J b. a limiting cc,ndition for operation.
._D Not Reutine surveillance testing, instrument calibration, s._,
, / er m e,x ni c', i ve r . int enance which re . aire s.", stem cont iq.ura-tic"' n devriwd in liens B.2.? cnd B.2.b. need not lie re;:N :td ex 2pt where test results themselves reveal a -
LSCS-1 6 24 -O W + +-
III i ij-x
,e .
-e
- s. 4
+
~
D' s
\
,o sil t d a -
n ai e r r
/ d
- dd o r o
o h s t o ei n u l f t f oa e _ cm - ,
/
t . n n b g f r 5 e i e d ah es t uh < irNc n oc cd r h t e k t e e c; - s ef r a n. c!
'e e
f i ew h h n n a t a n 2_ wsy s s i n g a r fe. of di v i ri uut d o n u' a e n o r a t Ni o t c d l on r o s e t e i qcc 5 o a
/er : mih u t n5 d l s n** r hb t i a s t
0i i i t t 0 oi c a2 nt e e n .d n r - ec v t e i 0 a f d '-
'i' ist sNd l i o g r 6 *c. r -
n-i . '
" n r
o c e P d o c e t b i a l n f o sk a af w "r l d . - - '. . y n s f s e i. i n' ar i a i h o u c y n o t a d r n . - h e r t y_ - u e e hd',_b t e r o4 r
,r o -
i 5 'm i . t t i i a t n . d e d r c" t o 1 e. t l rd e n t a r or ,a es
, t nt
. ~ u s
t
- .t c
+
i . c p
-e
-e 2 n oc r a C
ert dii nf o r r i e o p . m uis v) r t - r .
%'f oif a r2 d p r e t i i3 aSM r s i
}
e n r e,h d n t p c r s ,. t ot p es n - i o vo r '. on i s s t c r t aoi
-r o r qa a a ,
o e i i dd i rS' t uc . t i. e ne ui r e o s -- c ,f
, nst- in " vd
- i et t d n ,i . i er nd > o n v i e o c d d sf t f - e - - h s - s on . t d d r nu1 at o an o nc t i ii - ai e p i f " r n i o
- rr i en t
t t r v i ed ii t o f n t sd f u : d t e t r o ad s . et c - 6n ri e + r p o o r .- . b' e i s r p i o ci et e nit ol n f n d e min r e ecM+ pc n s mr ef a v i wr n : b s! u h r t
- i i
l r' ' i y o" s ei o i el l o r e ut c r o g ac < mc si r1 p r us n p
rf uc a "
+ oi e - aa o e ec o 0c;:ihM s e sh i s cl r nt t dh d s t o yd: s n t f n ob : t e I cn 3 t l J n es ou h
- c b s a t c a ea r n n n
. inn a g' f i d t l
ef s f dl u t n o a t
- t e .
iof l '.
no o - e e5 t >
o a r s! or oh o h p s vasu m D,hal n a sl i b ,
r a t r i s q -
i t f hf a r st n i
t n i t
_ i . e a o ,. n u c
> y ni - n vd e r e a d . c t b
e o t
et n db it r t r g o e r s oa q 5 n I wS W[c e l
mp n s e r n i s e o ep ,
. - N r x s u ad
,e '
1 e ut ei t t n msa .: r r
o *. . v' d oe o a r . d l
e es r of st e.f r
,h
.. nr e
n c'
- i -
crgy s
- s h t t l ous rk s b s n
)
I g
er m n e
I r
t u
d e
bhi -t
- i ii -
e io "
h - t t n ot u t f pd s e i a o d r
+
1 dt t . r e n nq s n - n . l gi f l Tf n
t e p o,,a l e f o
'o e e o.
t c i
T, r c u mr e
a cr a t ob o i n
e n e
t l sD i o n - -
r n o,t i r t
an e 3 e
h na t t 1 s r. r oc i s" s g n . v e
n a
ns v
a n
c '"e af t n l c r : t oe yi o gf '
bt - n hs - cr oe i t v s; '
t t -
e w ec pd
- r. t -
a s . nt if sr e si c ni l
eon es uy e e p n
u r
e r
~
n ,
sd "i
t s vI ot u
' y s c ic u t' f t oa cc p r e' '
't e
t s
a c oh l
sd e n r e s if 1 f o s - * ,i i o a e.
i r '
c Ndh. f n e p e
c n
e ~
f i : r -
o' s
- n v a ai t t s g*
e o vr rih i r a c
ef s
n oe i v up o
s -
l e
erf t u
- c e4 n o
r t
n e
o s
r e r C i. s r m n e c rf i :
nn i a u ;
s '-
u a e us4 t i at dl i
" c fO-e s s o -
- r. c e
rk u aa c e t t c " h e o. pl e r e, q u a
d c e a l a ?
v5 f S . .
eie :
t c
t n c n e ot r. d c e r o a c .s i
's; ' ,
. c o ..i a csi a l
i t c o t pre t c h. .
e v
e n on.
;i
"..d S ot ef - de :
nh - .
g ds d s
c e c'
- vc e r r s n ui it I d a :.
's s
- o - :, ' e
- p s n ch . . r n t nc i i
- P. . e- ?. q d n : a -- c t n
r t e
lb 'a oM a n L
- rl e e - - l o.
'A, - : e t i o d
'n r. .
o t ep r
i t
- t. -
vt r ar r
r a' p r e n on A
- e.
t rI _ c _
c r d -. e e eo ot e ur e d 2
~
N '
' u pB e
e i rJ '-
p
, - i d t
" eo P ' n t
C c n e op t
4o s r bh r O t o r n b o A c t
N o n) o A2i 1 I 2
3 t.,
~ r r o1 i ,
r . - v r
- s. or i
5 hed ; nt 2 - a . . .
s, T T ue;p n a b c d 2
3j> r~ , ,' l11 i.f . il j l.!
.> - ,li l' ,'. o
e9 U
O a) -
f% .-
y s. .
p w .e-L C s> a.e . *)
. M O O r C .* *~ ** t' s.
C q- q. rs @ .U
- % vs-o C u s D ~U % L s a U O C O
- c. r - t) G
- s) FC CM L D O 0 CO e *O O .-
;e . U . - O as L. C H - O >
O re m y
- C - C C' ". e C
-3 *s t e w O V L Q L D O C) *
*) f D C .d
- O O C * .* PJ C *J W 7 r s > c *a 4e u i .~. C
- U
*C r.) (- Q > ss U t u M C to V ^ .
C y. .e 7 C . -- p .- e; i V .'.)- C- > C4 C q , C C L .- F 6 '-d i "U C-~ O '- -
u v s v a ~
L . :: .-
T .C- U
- - s r; .- c .- . O L- t' E **
O (. a > 6s e C "O *. ** V .- V
- y. u n. C *1 U C *
. es C ~. *C D L .. L e_ t) C s - *) *. :. C C r* ., n r) ~ .c- ss C L. es t ss C O- *~
~: * .C C -- .O :) - O r.
C s.o C
O C. C U
E t 4-- C C (L T - C L C N. 1 C ~ 's C' N *- ~ T L' O
, .. .C- C ej L. e] .O t *. - <*
~' C C U . O ~ O _f' >*J 'l ." t 4 .a* A ".
L +- U
- t. p O e fi e t
t c. e., C L I oF r *. N
*n
- C
'U s e- r a Q
- O s U ;; -
e.. .G - ( c: .- 6 L. L.
- O U N' O L *>
C ( w- u L %. C 0 %- - J *1 i .C r, L C .- Ci .O e C C C. ~.~,
*- >C e L - L O *$
J- te , c L C C .-
> cs4 wC UY CL .> >.F.' ~ M "J C ". -"
rj .-
- t. T C r; --
"U o c. - 0 L. C C *. *) C. -s C C ' ."., **- CL s U rj m -- t. 6 - U .s O s O .C.. O O C *U C . *s
- J.e .C X t' v> u .- y su 1. s O .- r c, L C U: *'
r; O C 1 C ? *- U r: CJ - U s' V- G O C C .- O ~' ~ L ~ ~ L' W *- *
. L t. t; O r. res *L. .C*
- - rj C -- C u
.r. c. O U t.- .C-.". 4 .- 4 '3 >
u : ".O- CO 4 0 .C * - L O -
. q, r. t O
>O t .O
~ . w- C D t.n e >
"' e 3J i- O ; r; r; r
- 3 C +-
L C O O L ; L' u es .s "j t-a E C >- i *.C
rs O "U .C +- C U t O s. . c.. rJ O L U. = *s U f % *- O :1 L. 0 r-
- O .- ' . '
s C- 01 O C-
*L
. y .r. y. En t . - O b- L - C U C C *e C uI L. i o r; O L C *s
*1 .- D rs ~
1; e e ti c' L L C O cc rf g
*s ej C .4 " . ,vt. *--1
.[ - .-y . a m as c6
".J
- .I L. C. OO T *'
D U L o . *D t : L *~
O w .'"o C. q' U. ~
*e cc "C ss T L . 7 O -
O
'I C.
- t. w 4; .-** L rj ( .I b. - O C 4, O t- .C- *) L C C' i C 1 - .C L . f.
t
- t. o a' - e 0 . /g j u e e X - C O J >; i o e ti , o
.O L e .s C b. O c-
*D - L
(. 42 +a . O c u C4. +J C C t. C O z , w C a .
V . .0: so L o =- U / *- ". - t C C I* C '*
- V Ib * *
"d =
C' O *s C
- v , * ~;
O r- D D s.* Q - t: 'n . l.J U "Q '-'
ss ; L. .:. ss O rj L
- es O <- C. t ~ . Ug JJ : "* CT O WO p V *1 o O > L U **O C '
L. C'J J C.' u r* - "- ** ,.
r* Q v
.s u - O
.L-
. ~ = - .C' s *1
'A - U D s' k O L
c es c. .: . e~ a. C ss L as t. 2 Y D*-<
- e as # ;s O C O rj (1 C *1 as - (*: C b- O
.- .:. e ,,
*5 o
e .- - c '. r c. c t
* .; t L r 0 a. .-. L% O C:
- C t' i' .*
8 Cn O C C -+ L -- O
- L) - - U **
C.' L l'
L O J.- ( s .C = *) O (1 O'. O of ] = U L {**
4J "U
[ s> *) C". PJ e- (. - L - O O O L rJ *J 7 1b O O ( e C ~O O
.'i .-C QO L- 2C c
_ L O C r.
L C 4 LJ rJ 0 **
~ U
- g. r .- g-. 4 .s [ ou Q .C ~
*)
. _ > f) *J, D O ^ _'" 4J *'.b- *'
.C .J L*- *- CD p - .t2 6. -- "C,1 r
O . v v r) u '
. 5 L. - C *s = >~%
C L. .- 'O -
c'. t CC p s. () < -
g r. (41 ..
e U O J. .L "O t
C e ^ "*'
U f} (1 ** d j L #'
7 .b
- e, =; v v *.*
t f. 4, a a 0 -- *' C V
.C- L L r) C 6a a> 44 9 C '" L c) e L o L. t .
C' c 4e -
O a. O > _ o L
r; n . C. C .
O t\ ' < Q eg s.
- Las r) g- .
L1 - N p%
/, '*)I - ~ - - - ~ ~ - - --
~ ~ ~ . .
e.- -
.m. ...
e a
I..
e ~,
S
.D OC }
u .s e.o Q) . e 3
^
L .
1 es 0 .( t.
o U ~ WN% \
f G C .~ Q . C f.
u S. C f *-. Cs
- T U L w D 5 L U m C . y s m 0 r: M L .
b 0 0 U .t-+. r4 .- u .*-
- O L. f.: .r a U -
rJ U L *s r3 D 0 C- c3 - gg QZ so to ss % % L 4 N,1 O- O > >: J C,
e.
L n. O .- C - L- C 6. -
y L. L .c- e Ci 1 O *O -- O 0 '*-
> L o " +' + r
- O C e 6 o o e r e_ i
./
O y rn
(*)
0-O .c o .^
e,*
i.
6.
c' Z -'. C.'
44 er d'
O rs ~; C .- v, e ', .*
r: .r: r p D y- w. .C-J :- ;
L- rt
*) r M L (1 -
r C;> .'. . OL Q 64 O Ci r
7 c;
.c .-> .: c. ',
o c..
%. con.C- a .
.- .. t. .
c: <x -
M .
c 7. T C C
** C .* "1
. O L L 7 L b C /.
r; .r, -. .O- -.c _i . ' L 0 1 *: 6 *-
.d f
C C .f u
ey es
.. O 4.
T c
C. C '. -
.O U
t- .t O.-
. t -. ('.
v u (s T .. L T - M - ,
L U u O Tm ( .C +> U e'** C
b
(
O .f : ** - t us ' C e^ G h t ; f% C t- .- ti e C +8 (L e .- O . .
.- C) rJ O . C (.
o L
.O ~*
-o .C c, - L' u c.^ ,
f.'
cc C 1. - .C ,
- . - e ro o - c .c i
t, n- i u .u-o ou o -
. i I
t.
C - . ei - *J *.Jv f. - 1. . % p)
.C- p r c Dt : 3 .- se U ** . g-3g .'-
g D *1 C C *- ss -
u .Y J. V C t.
.t n <
r: c L.v v ve : ~ .' O u .-
v, c e
e sn L. e ..,. .O . a r f.
i o
p-
- u c. o. , L .- c .c.
- u s. w n
.u F. rJ C F - t. I
\ (1 f: L - C3 U~
- C %
*J - 1. k 9 (.- l i C) u
.L, C ~%--
.C.
. t' a .
a
.. c . <t n. - u t .o .v
- U .CN .- d
- "U O { .- L 3 t C ** ,
7
-' H O t*1 > T ! -
u (.L u
c r% L. rJ e C O /> O. ~2 O ; t. J q oh 4 c L o - .. . - .,u .> - :
+
ei .D ,~ C O C C: 0 ts D c
) ', Q o cts.1. D L L *. u L .~ _ L '
[.
c t * .o w
p f) rJ C uP c .O-E w-cu *-
C U o c O-0 i. m O '
3 m.
.]h' J
o .c- C O (1 O? -'- U u -
- Ch ; 2 L. S OJ
[
*s L = L j eO ey -i 3 - . .+
> .c -O es . .: ss
. rc v
<> s-
. it s a v' L2 ce
(; C.
L m
U
*J 4'
.j.a q
~
C C ej r U i y r e.. g 4 rt }
6e H p i. s. - **-
L.J cv o .
.*) t O 7': . .. d '.) '- c 't ) ;
tb I O
'n
- O C S -.O~. f A C O i ., . t Y
Q V E O C D + u +8 ? O La L C O .
~; k
- j. a 4 b c u v t, e u o %-
- ~.-
o.. u s. ., o c u. . .>. .. u o O u. 1 . .s
.- g t
L c, *J u. >.r- [ > .. ' L. 6 .- (
(3 >. o C ()
O o ot. . p..: O L e--.--
e -' uv >
c r.
c L *: } ..
.: O .
- (t Oa % B C' d 3 g C CL 0 s* U U (L L ,1 L-y v .C. *< e
.O. u n e s. o u . .
t
. s.
;*i . . . . .c -
0r; V c O eO
.C l- O O 2 e-u (
. c L, }
o .- c i. anJ e L o vi > O O %
r; - o 65 (' . e - m V U tt.
C O I g.
- S L :)
t O 7 O Cl C: O'
.)
l.
C L
<J' C6 L C
*) t. J.
4.' .'.b f.' Q
*{ O 6-
- i. .-).
- d g Q c 0 '
3 tJ .s. o .J - ^ -
'{ < d '
I C C X r. . - -
.3 .1 y
.O U *U t' C
.C;- e c O -i s.-
O v v ss 4 6 .j m sc
- r . . , . sn s -
4e ea r } '.
u L
( O O N ,
(.. .s tu c 1 v L s
L ci L)
L M L D 2.
g - - T /)
t,. F L r rJ b
. .a. .- 3 o o 4 O Q p f
. c1 c. p s)y V
O I
(, . .' c
r:
/
T A P'.E (' . 6..1
_S_PEC I AL T.EPCP T3 SPECIrIC C IL'.
ARfA R EF E R E t.T E Tii77' T
- a. Reactivity Anomaly 3.1.2 Wnen di:cm.a.cc.
- b. liaterials Radiation Sur- 1.4.6.i.1 Afts _ /, T . m n '-
u_ _;c. '
veillance Specimer: rn < :1 -
an z. l y s . ;
- c. Seismic l'unitoring Instru- 3.3.6.2 44 day: ifice / , .o ; ,
rnent f ailure if not crerabic in I?
dcy,
- d. Seisuic Event 4.3.6.2.2 14 days 'tcr e/ert
- e. L tecrological Monittring 3.3.6.3 21 days dier discm ar.
Instrument failure if no'. C PEi: A3G .
7 days
- f. Fire Detection Instru- 3.3.6.9 44 cajn vice d.;U m l -
ment Failure if not C3ErGELc in ic days -
9 HPCS Inadvertent injection 3.5.1 90 cay 3
- h. LPCS Inadvertent Injecticn 3.5.3.1 90 days
- i. LPCI Inadvertent injection 3.5.3.2 93 days
- j. Abnormal Degradation of 4.6.1.5.4 Wnen disccecred Primary Centainnent Annt.al Repret !
- k. Radioactjve Source Leak 4.7.4.3 Testing i l ~
- 1. Fire Suppression Water System 3.7.5.1 4" days after discov:r;. I Inoperable if not GFERAo.T in 14 days
- m. Fire Suppression Spray / 3.7.5.2 44 days after discovery l Sprinkler System Inoperable if not OPER AE'.E ir.14 cays
- n. Fire Suppression CO 2 3.7.5.3 44 days af ter discnvery l System inoperable if not OPERALLE in m 14 days g 3I a' s 8
/ ... -L m.y i ,, l t o ..e FE5'.UAM d 197 9 TfsELF 6.6-l_ _(Continu:d) 5"ECIt.L REPORTS SP EC IF I C ATICri t .
REFERE! ICE SUE".'~TAL DATE o Ficc %,
- tion Hal )n 3.7.5.5 44 days after discovery '((
Lj ;ta ~ Ir.< tor nie if not OPERABLE ir.
14 days
l=~ r> t, .,,.,a. m
\
~
--r - , ,,,,,e.,,.
r W er n , ~ 30 an,. n re a a nu
, . . . . ,m. ..
, e i . .a ,.. . r. t ~ . . . . . > . .
o . Il 5 . I 7,
- 3. Thi, r. m ' i: rer:uired only if the tests reveal the presence of U . '~ . ; > c. . u - i . or mDr t of removable cont a'aination.
e f"hr * "V-I"7"-
inre.1 . _
- l. 17
s
> 3 )
/
t .?
I 9
5
.m s s e-m e r
- IAG.u .,see-n m s.v.o ei . ; ;
e e J<' e. . . a L : ._=)
i'
,F- 6. ~i . l 'Trt'.r.
.. '.".s~ r. t ' r. *. t. 'rT . l ". ". " M:n n '- ( r. ' r. .". ),
.n i w
FT -'e: CCC" sha'l dascribe the r.ethedo!c v and parc-etars to be used Ur- in the ca lc:;i c t ier of of f site deses due te radicactive ecsecus and licuid l f effluente a"d in the caiculc ien of carecus and licuid effluent renitcetne a
- nstru e"tctica aior-/ trip set;c!nts consistent ei th t' c arpli:able LCC's j contcinco in these Technical Sracificatic,s. "etbednice;es and calcula-tional procedures acccotab!c to the Cc-mission are cen tained in NURCG-C133 ~
---?
I , 7: \ '
! ~be CCCM shall be submi tted to the Co--issien ., P the ti-c of proposed {j 'y \
I 1
Fadiolog. ical Cffluent Technical Specifications and shall be subject to review and approval by the Commission pr'or to i.pierentation.
i:s s
M
* (C l
! k 6.7.0 Any changes to the CCCM shall be n,de by either of the fo!!owing ! *2Ls !
/
, re t Fec.s: s--
t\
t
-- I A. Licensee ini tiated c'nanges : '
{ GN I 1. Shall be submitted to the Commission by inclusion in the
\J l i l'enthly Oper' ting Report pursua,t to Seccification 6.6.A.3 \
d) witain 90 days of the date the chan;c(s) was r,de cFfective \~ /
cnd chail cortcin:
i
- a. sufficiently detailed inforr;; tic, to support the chance.
Information submitted sFeuld consist of a package of those pages cf the ODCM to be changed, tenether eith apprcpr!.ite ara!,ses or c;.,.co...uns just.fy.inq
. tbc c race (s), ;
g s
t
- b. c deter.mination that the change will not reduce the accuracy or reliability of dose calculations or setroint determinations; and
- c. decurent, tic, cf the fact that the chance has been reviewed and feund acceetah!c by both the Onsite and Cffsite Review runcticas.
- 7. Sha!! becene c?fective upon a date seccified and aerced to by the Ons!:e cud Offiste I,cview Functions folic.rina the review and l g
csse-t,nce of :P 2 cha'ce(sl. l
4
# l 'N f.-
t
\ s
- 9. f 6 l
_- [;-)
.- I r
9 4 s
t
(
".1 t
fI a
f e-J8 L e
% + )- F t'
l.
La .
ti r. r s
9 6, 2 )
/_ e .s , -
_)
* ^ *%9Mb* 9M66ge , ,y
-}}