ML20118A691
| ML20118A691 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 09/14/1992 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20118A690 | List: |
| References | |
| NUDOCS 9209240456 | |
| Download: ML20118A691 (17) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ = CNCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT STEAM LEAK DETECTION INSTRUMENTATION NUMAC UPGRACE PAGE CHANGE INSTRUCTIONS .VIlll.1 Removed Pace Inserted Paae 3/4 3-13 3/4313 3/4 3-19 3/4319 3/4323 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-28 3/4328 3/4 3-29 3/4 3-29 s 3/4 3-30 3/4 3-30 11N.112 Eg';"e Dm linerted Paae 3/4 3-13 3/4 3-13 3/4319 3/4319 3/4323 3/4 3-23 3/4 3-24 3/4324 3/4 3-28 3/4 3-28 3/4329 343-29 7 3/4330 3/4 3-30 E41 h P
et; ENCLOSURE 5 -o BRUNSWICK STEAM ELECTRIC PLANT, NNITS 1 AND 2 NRC DOCKET NOS, 50-325 & 50-324: OPERATING LICENSE NOS; DPR-71 & DPR 62 REQUEST FOR LICENSE AMENDMENT-STEAM LEAK DETECTION INSTRUMENTATION NUMAC UPGRADE TECHNICAL SPECIFICATION PAGES - UNIT 1 .va
~- F TABLE 3.3.2-1 (Cont inue() g E ISOLATION ACTUATION INSTRUMENT.AT_ I_O__N 'E VALVE CROUPS' MIh. MUM NUMBER APPLI CABLE 75 OPERATED BY OPERABLE CHANNELS' OPERATIONAL TRIP FUNCTION SICNAL(a) PER TRIP SfSTEM(b)(c) CONDITION . ACTI_O_N_ [i 2. SECONDARY CONTAINHENT ISOLATION a. Reactor Building Exhaust Radiation - High (1) 1 1, 2, 3, $, and* 23 6 1 1,2,3 20 b. Drywell Pressure - High (1) 2 1,2,3 23 2, 6 2 1,2,3 20-c. Reactor Vessel Water Level - ~ Low, Level 2 (1) 2 1, 2, 3 23 w 3 2 1, 2, 3 24 5 u 2. 3. REACTOR WATER CLEANUP SYSTEM ISOLATION 4d u a. A Flow - High 3 1 1,2,3 24 b. Area Temperature - High 3 2 1,2,3 24 c. Area Ventilation a Temperature - High. 2 1, 2, 3 24 l II} SLCS-Initiation 3 NA 1, 2, 3 24 e. Reactor Vessel Water Level - Low, Level 2-3 2 1, 2, 3 e4 5 -High-TimeDelayhhh(f 'NA 1 1, 2, 3 24. l f. A Flow = y, g L I Acr ery u d e. A g 1 G r vm m
oe TABLE 3.3.2-2 (Cont inued) -- to ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E ALLOWABLE TRIP SETPOINT VALUE TRIP FUNCTION E 2. SECONDARY CONTAINMENT ISOLATION "4 a. Reactor Building Exhaust Radiation - ;1igh $ 11 mr/hr $ li mr/hr b. Drywell Pressure - High 1 7 psig $ 2 psix c. Reactor Vessel Water Level - Lcw, Level 2 3 + 112 inches (a) 3 + 112 inches *) I 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a. A Flow - High gal / min gal / min b. Area Temperature - liigh $.50*F 150*F w S Area Ventilation a Temperature - High i 50*F 1 50*F l w c. NA NA d. SLCS Initiation >+ 112 inches (a) Reactor Vassel Water Level - Low, Level 2 3 + 112 inches (a) e. f. A Flow - High - Time Delay $[4/se9n[y s[ l 4 c[3 0 m;nks c,. 9;f q dubik /Ev)CK 2soms x jpo*f x jgo p o i ~ i U jfew %,u ra L cc. ~ // ig L l E 5 =
- c. -
~ TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUM NTATION RESPONSE TIME RESPONSE ' TIME (Seconds)(a)(e)l TRIP FtJNCTION -1. PRlHARY CONTAINMENT ISOLATION a. React or Ves sel Water Level - 1. Low, level I <!) <l. (d) 2. Low, Level 3 -713gf) b. -Drywell Pressure - High <!) c. Main Steam Line 1. Radiation - High(b) <l.0(II) d) {13 [ 2. Pressure - Low <!) } 3. Flow - High 10. 113 l d. Main Steam Line Tunnel Temperature - High $13 e. Condenser Vacuum - Low <13 t'. Turbine Building Area Temperature - High NA' Main Stack Radiation _- High(b) $ 1.0(0} c. h. Reactor Building Exhaust Radiation - High(b) NA l 2. SECONDARY CONTAINMENT ISOLATION a. Reactor Building Exhaust Radiation - High(b) g3 b. Drywell Pressure - High ,!3 i c. Reactor Vessel Water Level - Low, Level 2 $13-l 3. REACTOR WATER ' CLEANUP SYSTEM ISOLATION Mb l -a. A Flow - High lI b. Area Temperature - High <h I Area Ventilation a Temperature - High l-c. d. SLCS Initiation NA e. Reactor Vessel Water Level - Low, Levet 2 113 l f. a_ Flow - High - Time Delay NA 'l
- g. P@y AMeaca se~ -nsw,Ac -H+ HD e
8RUNSWICK - UNIT 1 3/4 3-23 Amendment No. 149
^ f-TABLE 1.3.2-3 (Continued) 1 k-ISOLATION SYSTEM INSTRUF.ENTATION RESPONSE TIME TRIP FLINCTION-- PESPONSE f1ME (Seconds)Id)IC)
- l 4
CORE STANDBY' COOLl'NC SYSTEMS ISOLATION a. High Pressure Coolant Injection System Isolaticn. 1 -HPC1 Steam Line flow - lii gh $13(C) I 2. HPCl Steam Line Flow - Hign Time Delay Relay HA -{ 3. IIPCI Steam Supply Pressure - Low $13 4 HPC! Steam Line Tu net Temperature - High 5. Bus Power. Monitor NA 6. HPCI Turbine Exhaust Diaphragm Pressure - High NA 7. ItPCI Steam Line Ambient Temperature - High NA 8. HPCI Steam Lire Area t Temperature - liigh NA l-9. HPCI Equipment Area Temperature - High NA l 10. Dryvell Pressure - High NA l' b. React or Core Isolation Cooling System Isolation IC) 1. RCIC Steam Line Flow - High $13 2. RCIC Steam Line Flow - High " lime Delay Relay NA 3. RCIC Steam Supply Pressure - Low NA 4. RCIC Steam-Line Tunnel Temperature High NA l 5. Bus Power Monitor NA 6. RCIC Turbine Exhaust Diaphram Pressure - High NA: 7. RCIC St eam Line Ambient Temperature - High NA 8. RCIC Steam Line Area a Temperature - High NA l-9. RCIC Equipment Room Ambient Temperature - High N A -' l= 10. RCIC Equi pment Room a Temperature - High NA -l'
- 11. -RCIC Steam Line Tunnel Temperature - High NA Time Delay Relay
.e Drywell Pressure 'ligh NA i BRUNSWICK - UNIT 1 3/4 3-24 Amendment No. 149 ... y e a
~t 'e TABLE 4.3.2-1 (Continued) E ISOLATION ACTUATION INSTRUMENTATION SURVEILL_AlCE REQUIREMENTS 5G CilANNEL OPERATIONAL l 5, CHANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICH l Q TRIP FUNCTION CHECK TES*1 CALIBRATION S_U'tVEILLANCE REOUIRE!$ E 2. SECONDARY CONTAINMENT ISOLATION G Reactor Buildin Exi.a, s t IE} a. Radiatir n - H e,h D M R 1,2,3,5, ared b. Drywell Pressure - High R(I') 1 2, J NA(a) NA Transmitter: Trip Logic D M M 1, 2, 3 l c. Reactor Vessel Water L:.31 - Low, Level 2 IN NA(a) NA R
- 1. 2, 3 i
1 Transmitter: Trip Logic: D M M 1, 2, 3 r 3. REACTOR WATER CLEANUP SYSTEM ISOLATION t$ R 1,2,3 w c. A Flow - High li ff.s I R
- 1. 2, 3 CD b.
Area Temperature - High NA Area Ventilation a Temperature - liigh NA R I, 2, 3 l c. d. SLCS Initiation AA R NA 1, 2, 3 e. Reactor Vessel Water Level - Low, Level 2 g(b) 1, 2, 3. NA(a) g3 Transmitter: Trip Logic: D. M M 1, 2, 3 $8 f. A Flow - High - Time Delay NA R 1, 2, 3 l 5. b tf'Aj 'Eb bN Mb IA [ / 2 ' 3 g ,q,e TampuSce - H:y s 1 E C 1 .a o g
u,: ~ ) . TABLE 4.3.2-1 (Continued) E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE PEQUIREMENTS E E CilANNEL . OPERATIONf.L CHAN1iEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CI:ECK TEST CALIBRATION SURVEILLANCE REQUIRED Ey 4. CORE STANDBY COOLING S'SirEMS ISOLATION a. High Pressure Coolar.t Injection System isolation 1. HPCI Steam Line Flou - High Transmitter: NA(a) 34 g(le) 3 7, 3 Trip Logic: D H M 1, 2, 3 2. HPCI Steam Line Flow - High l Time Delry Relay FIA R R 1, 2,'T 3. HPCI Steam Supply Pressure - Low NA M H 1, 2, 3 w U TA 4. H?CI Steam Line Tunnel w O Temperature - High NA Q 1, 2, 3 ya e 5. Bus Power Monitor NA R NA 1, 2, 3 6. HPCI turbir.e Exhaust Diaphragm Pressure - High NA H Q 1,.2, 3 5A 7. HPCI Steam Line Ambient F Temperature - High NA R 1, 2, 3 l 8. HPCI Steam Line Aree I
- t. Temperature - High NA R
1, 2, 3-l- E. 9. HPCI Equipment Area g Temperature - High NA H i E 1, 2, 3 l-2: - 10. Drywell Pressure - High Transmitter: NA(a) - NA R(b)- y 7 3 ' Trip Logic: D-H M 1, 2,'3 .g o .= > ~
.up T__ iBLE 4. 3. 2-1 (continued) ~ ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E x CHANNEL OPER/TIONAL -Q CHANNEL FUNCTIONAL, CdaNNEL CONDITIONS'IN WHICH TRIP FUNCTION CHECK TEST CALI BRATION SURVEILLANCE REQUIRED- 'E 4. CORE STANDBY COOLINC SYSTEMS ISOLATION (Continued) H b. Reactor Core Isolation Cooling System Isolation 1. RCIC Steam Line Flow - High Transmitter: Nt'a) NA R(b)
- 1. 2, 3 Trip Logic:
u M M 1, 2, 3 2. 9CIC Steam Line Flow - Pigh l Time Delay Relay NA R R 1, 2, 3 3. RCIC Steam Supply Pres sure - Low NA .M Q 1, 2, 3 4. RCIC St4_am Line Tunnel Temperature - High NA R .I,.2, 3' l y 5. Bus P.swer Monitar NA 'R NA 1, 2, 3. 6. RCIC Tarbine Exhaust Di aphrsgm Pressure - liigh NA M d I, 2, 3 7. -RCIC Steam Line Ambient Temperature - High NA R 1, 2, 3 l 8. 'RCIC Steam Line Area [ E Temperature - High NA R 1, 2, 3 - .l V 9, RCIC Equipe.ent koom Ambient Temperr.ture - High NA 1,.2, 3 l / g 10. RCIC Equipment Room i g A' Temperature - High NA i / 1, 2, 3 l c. 11. RCIC Steam Line Tunriel Temperature - High / R Time Delmy Relay NA /1 E ~1, 2, ~ 3 ' zo 12. Dryvell Pressure - High Transmitter: NA(a)- g(b) y, y, ) ~ pg ' Trip" Logic: D M H-1, 2, 3 / y 4
L ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & S0-324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REQUEST i OR LICENSE AMENDMENT STEAM LEAK DETECTION INSTRUMENTATION NUMAC UPGRADE
- ECHNICALSffCirl:AT!ON PAGES - UNIT 2 s
L I l 6 l u--
- m. A u A _
.m_ M
n-TABLE 3.3.2-1 (Continued) Ey ISOLATION ACTUATION INSTRUMENTATION 5 M VALVE CROUPS MINIMUM-NUMBER A?PLICABLE 8 OPERATED BY OPERABLE CHANNELS O?ERATIONAL E TRIP FUNCTION SIGNAL (a)' PER TRIP SYSTEM (b)(c) CONDITTON ACTION U w 2. SECONDARY CONTAINMENT ISOLATION a. Reactor Building Exhaust (1) 1 1, 2, 3, 5, 23 -l Radiation - High and
- 6 1
1, 2, 3 20 l= b. Drywell Pressure - High (1) 2 1, 2, 3 ' 2' 3 2, 6 2 1, 2, 3 20-c. Reactor Vessel hter Level - (1) 2 1,2,3 23-' w Low, Level 2 3 2 1,2,3 -24 5 u 3. REACTOR.lATER CLEANUP SYSTEM ISOLATION d a. a Flow :-High 3 1 1, 2, 3 24-b. Area.Tamperature.High 3 2 1,2,3 24 c. Area Ventilation a Temperature --High 3-2 1,2,3 24 l-IfI' NA 1, 2,. 3
- 24 d.
SLCS Initistion' 3 e. Reactor Vessel Water Level - Low, Level:2 3 2 1,2,3 .24 . t l .f. A Flow - High - Time Delay NA. I 1,'2,;3- '24 ]- ,' (- (h '. y '} 9. Pqwy Outside_ Rwcv pCoon _ 3 I- ^ C 4+ -w,y 7' A% r i _st .m..
q - ;, ~. ~ g '- TABLE 3.3.2-2 (Continued) ~ 'E ISOLATION ACTUATION INSTRUMENTATION.SE~ POINTS E M ALLOWAELE ' TRIP FUNCTION ~ PIP SETPOINT VAI.bE N. 5 2. SECONDARY CONTAINMENT ISOLATION u a. Reactor Building Exhaust Radiation - High $ 11 mr/hr 3 11'er/hr b. Drywell Pressure - High $ 2 psig $ 2 psig c + 112 Inches (a)' ..'2 inches (a) c. Reactor Vessel Vater Level - Los, Level 2 ^ >+ s 3.' REACTOR WATER CLEAhUP SYSTEM ISOLATION m [ ~t. ~/3 ' g L a.- 4 Flow - High gal / min -f gal / min b. Area Temperature - High 1 150*F 1 150*F w h c. Area Ventilation A Temperature - High $ 50*F $ $0*F l d. $LCS Initiatic, NA. NA e. Reactor Vessel Water Lesel - Low, Level 2 > + 112 inches (a) > + 112 inches (a) s f. 4 Flos -'High - Time Delay R.ay ' ~<!45 s onds -< 45 onds 3-a li 30
- 'JiW fCS f w~-
1 ,A ,/ f;,[a9 0*hsidG A WCE) bood
- p o
{f A % s A c.-how ~ c. ~ i =
e>4h 2 TABLE 3.3.? 3 ~ 1 SOLATION SYSTEH 7N5TRURENTAT10N RESPONSE T!HE RESPONSE TIHE (Seconds)I^II"I TRIP FUNCTION - 1 RIMARY CONTAINHEt4T ISOLATION 5 1. a. Reactor Vessel Water f.evel - 1. L( -, i.e ve l 1 $13 -E 13{(d) < l. I) 2. Low, Level J b. urywell Pressure - High '313 c. Main St - sm Lire 1. RC.ation - 'igb(b) 3, ). sa i 2. Pressure - Low $13 Id) 3. Flow - liigh -<0.5 '733(f) - l-(d) 4. Flow - lii gh <0.)f)' l- ~ }3t d. Hain Steam Line.Tunn.1 Temperature - High 313 e. Londenser Vacuum - Low $13 f. Turbine Buisding' Area Temperature - High HA Id) Main Stack Radiation - Higt,(b) 1.0 g. Reactor Building Exhaust Radiat ion - High(b) l NA h. 2. SECONDARY CONTAINHENT ISOLATION a. Reactor Building Exhaust Radiation - High(b) 33 5. Drywell Pressure - High $13 c. Reactor-Vessel Water Level - Low, Level.2 313 - l 3. kEACTOR WATER CLEANUP SYSTEM ISOLATION [JA a. A Flow - liigh l b. Area Temperature - liipb c. Area Vent ilat ion a Temperature - liigh l d. SLCS Initiction NA e. Reactor Vessel Water Level -- Low, Level 2 313 l f. A Flow - liigh - Time Delay NA l G r;<in o.>1au ucai.w w v W y D BRlJNSWICK - UNIT 2 3/4 3-23 Arneadment No. 179
.-,,,,,..c,LT AB_l,E 3.,. 3. 2 - 3 ( Co n t i n ue d )' ISOLATION SYSTEM INSTRUMENTATION REfPONSE TIME-RESPONSE T1 HE ( Secc..d_s)(a )(e)l TRI_P FUNCTION 4. CORE STANDBY COOLING SYSTEMS I SO LATI ON liigh Pressure Coolant Inject ion System Isolatinn a. $13(C) l 1. IIPCI St eam Line Flow - lii 6h 2. IIPCI Steam Line Flow - liigh Time Delay Relay NA l 3. 110C1 St eam Supply Pressure - Low $13 p M8 4. IIPCI Stcam Line Tunne1 Temperature - HJ gh 5. flus Power Honitor NA 6. HPCI Turbine Exhaust Diaphragm Pressure - High NA '. IiPCI Steem 1.ine Ambient Temperature - High NA 8. IlPCI Steam Line Area a Temr-.ature - liigh NA l 9. IIPCI Equi pment Area Tempe ra t u re - liigh NA l 10. Drywell Pressure - High NA l b. Reactor Core Isolation :ooling System isolation 1. RCIC St eam i ~ ne Flow - High $13(c) Flow - High Time Delay Relay NA l 2. RCIC Steam t...e 3. RCIC Steam Supply Pressure - Low NA 4. RCIC Steam Line Tunnel Temperature - High NA l 5. Bus Power Honitor NA 6. RCIC Turbine Exhaust Diaphram Pressure - High NA 7. RCIC Steam Line Ambient Temperature - High NA 8. RCIC Steam Line At ea a Temperature - liigh NA l 9. RCIC Equipment Room Ambient Temperature - High NA l 10. RCIC Equipment Room a Temperature - liigh NA l 11. RCIC Steam Line Tunnel Temperature - liigh NA ~ine Del ay Rel ay 12. L well Pressure - High NA BRUNSWICK - UNIT 2 3/4 3~24 Amendment No. 179
TABLE 4.3.2-1 (Continued)
- n E
MOLATION ACTUATION INSTRUMENTATION OURVEILLANCE REQJIREMEN'3 E CFERATIONAL c) CHANNEL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN VdICH CHECK TEST CALIBRATION StjRVEILLANCE REQUIRED E TRIP FUNCTION ~ .-s 2. SECONDARY CONTAINMENT ISOLATION u Reactor Building Exhaust 1,2,3,5, and (f} l l a. D M R Radiation - High b. Dryvell Pressure - High NA(a) NA R(b) 1, 2, 3 Transmitter: D M M
- 1. 2, 3 Trip Logic
- l Reactor Vessel Water Level -
c. Low, Level 2 R(b) 1, 2, 3 NA(a) NA w 3 Transmitter: D M M 1,2,3 Trip Logic: 1 w L> 3. REACTOR WATER CLEANUP SYSTEM ISOLAfION NA R 1, 2, 3 A Flow - ?iigh a. NA R 1, 2, 3 l b. Area Tempens.nre - High R 1, 2, 't '
- j Area Ventilation a Temperature - High NA c.
d. SLCS Initiation NA R NA 1, 2, 3 Reactor 5'essel Water Level - 2 e. Low, Level 2 I R(b) 1, 2, 3 WA ") NA E. Transmitter: D M M 1, 2 3 { Trip Logic: f. A Flow - High - Time Delay NA R 1,2,3 l g O ds.d ~ A"'W A** ? -_ ~ pg sh R s, 2, 3 9 P.r;9 u ( gu Twpakt A9L
m 2 E TABLE 4.3.2"1 (Continued) E U ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E* CHANNEL OPERATIONAL CFAFNEL FUNCTIONAL CHANNEL CONDITIONS IN WhICH E TRIP FUNCTILa CNECX T1ST CALIBRATION SURVEILLANCE REQUIRED 9m u 4. CORE STANDBY COOLING SYSTF.MS ISOLATION a. High Pressure Coolant Injection System Isolation 1. HPCI Steam Line Flow - High I ID) NA ") NA R 3, 2, 3 Transmitter: Trip Logic: D M M 1, 2, 3 2. HPCI Steam Line Flow - High l Time Delay Relay NA R R 2, 2, 3 w 3: 3. HPCI Steam Supply Pressure - Low NA M R 1, 2, 3 w A 4. HPCI Steam Line Tunnel jjQ Temperature - High NA h. Q 1, 2, 3 5. Bus Power Monitor NA 11 NA 1,2,3 6. HPCI Turbine Exhaust Diaphragm Pressure - High NA M Q 1,2,3 7. HPOI Steam Line Ambient I5fk 3*aperature - High NA P R 1, 2, } 8. 9 ".1 Steam Line Area A~e "erature - High NA )( R 1, 2, 3 l 5 9. HPCI Equipment Area S Temperature - High NA 1, 2,. 3 l z 10. Dryvell Pressure - High Transmitter: NA(a) NA R ID) 1, 2, 3 g Trip Logic: D M M I, 2, 3 e
~.,. o- ~' TABLE 4.3.2-1 (Con:inued) E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS mc N CHANNEL OPERATIONnL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTIOg CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E G 4 CORE STANDBY COOLING SYSTEMS ISOLATION (Continued) u b. Reactor Core Isolation Cooling System Isolation 1. RCIC Stean Line Flow - High Transmitter: NA(a) NA R(D) 1,2,3 Trip Logic: D M M 1,2,3 2. RCIC Steam Line' Flow - High l-Time Delay Relay NA R R
- 1. 2, 3 3.
RCIC Steam Supply Pressure - Low NA M Q 1, 2, 3 ti 4. RCIC Steam Line Tunnel 4{g Temperature - High NA M R 1, 2, 3 ] 5. But Power Monitor NA R NA 1, 2, 3 o 6. RCIC Turbine Exhaust Diaphragm Pressure - High NA M R 1,2,3 7. R"IC Steam Line Ambient Temperature - High NA M R 1, 2, 3 l c 8. RCIC Steam Line Area i a Temperature - Hig! NA JM R 1, 2, 3 l h 9. RCIC Equipment Room Ambient l Temperature - High NA M Q R 1, 2, 3 l B g 10. RCIC Equipment Room' g-4 Temperature - High NA M Q l 1, 2, 3. I i o E 11. RCIC Steam Line Tunnel Tempera-( ture - H.gh Time Delay Relay NA M .R 1,2,3 12. Drywell Pressure - High O Transmitter: NA(a) - NA R(b) 1 2, 3 e Trip Logic: D. M M 1, 2, ' 3}}