ML20244D931
| ML20244D931 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/12/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244D935 | List: |
| References | |
| NUDOCS 8906200070 | |
| Download: ML20244D931 (19) | |
Text
{{#Wiki_filter:. - - - ./ 'o.,, UNITED STATES j. n. NUCLEAR REGULATORY COMMISSION -U E WASHINGTON, D. C. 20555 \\ * * * * *./j t.. j CAROLINA POWER & LIGHT COMPANY, et al. DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT-T0 FACILITY OPERATING LICENSE t Amendment No.132 License No. DPR-71 1. The Nuclear Regulatory Comission (the Commission) has found that: A. The application for amendment filed by Carolina Power & Light Company (thelicensee),datedSeptember 27, 1988, complies with the standards and requirements of.the Atomic Energy Act of 1954, as amended (the j Act)t and the Commission's rules and regulations set forth in 10 CFR Chapter It B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; j C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the i comon defense and security or to the health and safety of the i public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements j have been satisfied. 2. Accordingly, the license is ame%ed by changes to the Technical I I Specifications, as indicated in the attachment to this license amendment; and p.r agraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows: l 8906200070 890612 T PDR ADDCK 05000324< P puu 1 i
n h y. i S. 2 '. l 1 (2)--Technical-Specifications j The Technical Specifications-contained in ~ Appendices A and B,.as revised through Amendment No.132,' are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility l in accordance with the Technical Specifications. l 3. This license amendment is effective'as of the date of its issuance and shall be implemented within 60 days of issuance.- l FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By: Elinor G. Adensam Director I Project Directorate 11-1 Division of Reactor Projects I/II i Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i Date of Issuance: June 12,1989 j I l 1 1 l I &n O B" :OGCgg: 0:PD21:DRPR. lOFC-lLA:F 11 PR:PM: 1:DRPR: I.....:. ngham : yj: EAdensam ' NAME : P NLe: d
- JCu
,.....:............:............:...........:.g..........h.Qr.'........:............:........... -DATE :4/ n/89
- 4/b/89
- 4/0/89
- 4//7/89
- // /89 yl
[ ^ l OFFICIAL RECORD COPY J l 1 1
s -ATTACHMENT TO LICENSE AMENDMENT NO. 132 FACILITY OPERATING LICENSE N0. DPR-71 DOCKET NO. 50-325 'Repisce the following pages of the Appendix A Technical. Specifications with the enclosed pages. The revised areas are indicated by marginal lines. Remove Pages Insert Pages 3/4 3-12 3/4 3-12 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-22 3/4 3-22 3/4 3 3/4 3-23' 3/4'3-27 3/4 3-27 I 1 L L l _____-___________A
C 0 0 0 0 1 2 2 1 1 1 8 A 2 2 2 2 2 2 2 2 2 2 2 5 .L EA LNN BOO AI I 3 3 3 3 3 3 ) 3 3 CTT I AI e ( LRD 2 2 2 2 2 2 2 2 2 PEN PPO AOC 1 1 1 1 1 1 1 1 1 1 1 ) c ( ) Sb L( REM ENE e BNT n MAS i ) ) UKY l d d NCS / ( ( 2 2 2 2 2 2 2 2 2 4 1 MEP ULI MBR AT N I O NR I I ER T MPE A OP TN E M U SY R PB 8 T U ) S OD a N RE( 7 7 I CTL 1 AA N ERN 6 6 2 O VEG ) I LPI h 3 T AOS 2 3 1 2 1 1 1 1 1 1 ( A V 3 UT E C L A BA N T O I TALO S h I l g e i N v H O e h I L g l w T i h e o a A r H g nh L eh n L e i w ng rg o O t H o ui Ai i S a1 2 3 L TH H t I W e h m g a l l l r e g e-u n-i T l e e e u nn i n u i d N ev v v s i o e H ie c d e a E se e e s Li r L r a l r R sL L L e t u u V iu tS l e r ma s mt ut k V P ai s w aa r B a c l A w w w ed e o er e r a T ro o o l t a r l t e s ee t N oL L L l SR P F S p n np S O t e m e im N C c w n ne d b e n O a y i iT n rT i I Y e. r a. a o u a T R R1 2 3 D M1 2 3 M C T M C A N M U I F R P a b c d e f g P I R T 1 i. 5iEM9 EU. ts YC g o g-o 5. i P 1 } j {.[
^ TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours and in COLD SHUTDOWN within the following 30 hours. ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours or be in at least HOT SHUTDOWN within 6 hours and in COLD SE3TDOWN within the next 30 hours. ACTION 22 - Be in at least STARTUP within 2 hours. ACTION 23 - Establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hour. ACTION 24 - Isolate the reactor water cleanup system. l ACTION 25 - Close the affected system isolation valves and declare the affected system inoperable. ACTION 26 - Verify power availability L4 the bus at least once per 12 hours. ACTION 27 - Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits. ACTION 28 - Close the affected isolation valves within 14 days or be in HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the following 24 hours. NOTES When handling irradiated fuel in the secondary containment. (a) See Specification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve group. (b) A channel may be placed in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. (c) With only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken. (d) A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE. (e) With reactor steam pressure > 500 psig. (f) Closes only RWCU outlet isolation valve. (g) Alarm only. (h) Isolates containment purge and vent valves. l l BRUNSWICK - UNIT 1 3/4 3-17 Amendment No. $@,772. { 132 l
I ) ) e f c s a a w a e ( ( o d v h s s p e c e e t g n h h l a H i c c l r n n ud g s E L 5 g u s o h i i f n i f e BE 2 2 5 i xo p F c F AU 6 1 s r n WL 1 1 2 p g 5 0 0 i 0 OA
- 5. k 2
4 0 0 LV + + + 2 3 c 8 1 2 7 2 ) L a b A l> 5 < b 3 $ $ 3 < ( S T N I O w m P o u ) T l u E a ) ) f c ( a a r a S s ( ( e d v e s s w e ) N d O T h e e o t g N c h h p a H e I u T n c c r I O i n n l d g s n A P i i l n i f e i T T t N 5 g uu s o h n E E 2 5 i f o p F c F S 2 1 s r n o M C U 6 1 2 p xg 5 0 0 i 0 k P 1 k 2 4 0 0 ( R I + + + 2 3 c 8 1 2 7 2 ) T R 2 S a b N T 3 3 3 3 < b 3 3 < ( 2 I 3 NO 3 I T E A L U B T A C T A hg N i O H I T AL e O r h S u g t i I a H r e p h l m p g N e e m i O v T e H I e h T T L g l w A i h e o a L r H g n L e n O e i w n r o S t H o u A i I a L T t W1 2 3 e h m g a T r e g e u n i N l l l l u nn i n u i d E ee e e s i o e H i c d a ( s v v v s Li r L a l R R s e e e e t u V i l l eL L L r ma s m u k A V P ai s w a r B c T w w w ed e o e e a N ro o o l t a r l t s e t O oL L L l SR P F S n n S N C t e e i O c w n n d b n I Y a y i i n r i T R e. r a. a o u a C A R1 2 3 D M1 2 3 M C T M N M U I F R P a b c d e f g P I R T 1 s NkEiM ' Ny - ' Y ;* . " t Dn O* l
) D a o ( t se L h A c U n g N E i i A L~ BE s H AU 5 p N WL 2 0 O OA 6 4 IT LV 1 1 L A A L UC LAC E S S T O N D I O E P T T I ) E S a S F ( ) N s F d O T e O N h e I u T c e I n A O n g h t P i i i T T s t N n E 5 p n E i S o M C U 2 0 d P 6 4 ( R e I 1 1 T R n 2 S i N T a 2 I tn 3 N o O c 3 I T .y E A O g L U R o B T El A C Z o T A d Lo N Eh O V t I E e T L m AL h E 'e O g Ch i S Nt H E I R r N E e O F p I e E T l r R s A e u t L v s on O e s ti I ' L e o S r rp r P et M e f e E t e es T a m r S W o p Y D si S l l r n e a et C s a v/ N s1 e ee I e t l r L Vl S a O e rl O rv r ea C oe o t N t L t ah O N c c ws W aw a i I T O eo e l l C D RL R eb N T s a U U st F H es S a b VE P I )) R ab T 5 (( 3EE;;n' Ey - U e. Y M ID R g* ~
e. -) k-( a-a i t .i I TABLE 3.3.2-3 4 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIF FUNCTION RESPONSE TIME (Seconds)(*) 1. PRIhARY CONTAINMENT ISOLATION -a. Reactor Vessel Water Level - 1. Low, Level 1 2. Low, Level 2 (13 (d) ~ 1.0 3. Low,, Level 3 51.0(d) b. Dryvell Pressure - High $13 c. Main Steam Line 1. Radiation - High(b) <1.0(d) 2. Pressure:- Low <13 3. Flow - High 30.5(d) d. Main Steam Line Tunnel Temperature - High _13 e.- Condenser Vacuum - Low $13. f. Turbine Building Area Temperature - High NA g. ' Main Stack D idiation - High(D} $ 1.0(d) l 2. SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b) <g3 a. b.. Drywell Pressure - High <13 Reactor' Vessel Water Level - Low, Level 2 11.0(d) c. -- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a. A Flow - High _13 b. Area Temperature - High $13 c. Area Ventilation Temperature AT - High <13 d. SLCS Initiation NA e. Reactor Vessel Water Level - Low, Level 2 <1.0(d) BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.0,722.132
LWQ A E NNR 33 OI 33 33 33 3 I E 3 TSC 22 22 22 22 2 ANN ROA l 2 EI L 1 1 1 1 PTL 1 1 1 1 1 g 1 i1 OI I 1 ' DE NV OR CUS STN N EM O LI ) ) ) ) ) ) ) E R ET b b b h d b b NA ( ( ( I ( ( ( I U NR RM RM RM RM R RM RM R AB Q E HI CL R A E C C NALL I L E LA V EN R U N O. T N 7 S 1 S A1 E a A A A A A HCT Ni NM NM NM W NM NM M N 2 CN I O U 3 F I T 4 AT E N L E 1 ) ) ) ) ) ) ) B M L - a a a a a A U EK ( ( ( ( I ( T R NC A A A A A A A TS NE ND ND ND ND D ND ND N AH N HC I C N O 6 I TAUTCA N O le I T N v A O e h L I L g l w O T i h e o A r H g nh L S L e i w ng I Ot r: r: r H or: r: ui S a1 ec 2 ec 3 ec Lec ec TH I W ti ti ti e ti hti m l t g l t g l t g r e t g gt g e-u Tl eio eio eio u: nn i o ii o n u: N evmL vmL vmL s r: i o emL H mL i e cr: d E ses es es s ec Li rs s Lr aec sL np L np L np eti t unp - np u Vti te e ai ai ai rt g ma s ai ai mt l l V,rr ,rr ,rr Pi o ai s rr wrr aa rio B A wTT wTT wTT mL ed eTT oTT er emL T ro o o l s t a r l t e s s N oL L L l np SR P F S p nnp n Ot eai m eai N C c wrr n ne d r r O a yTT i iT nT I Y e. r a. a o T RR1 2 3 D M1 2 3 M C C A N M U I F R. P a b c d e P I R T 1 giEAM : @C t* Y w ga R i i. i l j
[se.m: UNITED STATES -+ ~ ) g, NUCLEAR REGULATORY COMMISSION ,L .b j _ ASHINGTON, D C. 20S55 W \\...../ I CAROLINA POWER & LIGHT COMPANY, et al. DOCKET N0. 50-324 BRUNSulCK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. DPR-62 1 1. The Nuclear Regulatory Commission (the Comission) has found that: A. The application for amendment filed by Carolina Power & Light Company (the licensee), dated September 27, 1988, complies with the standards and requirements of the Atomic Energy tict of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is atended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read-as follows: ._.-__.______a_s____.___.
s _7---_ eg >4 c I ', ' ' O e 4 (2) Technichl Specifications o The. Technical. Specifications contained'in Appendices A and B, as revised through Amendment No.162, are hereby incorporated in the ' license. Carolina Power & Light Company shall operate the facility - in.accordance.with the Technical Specificati.ons. -{
- 3.
This license amendment is-effective as of the datt of its issuance and. shall be implemented within 60 days of issuance. ~ FOR THE NUCLEAR REGULATORY COMMISSION a t Original Signed By: l l Elinor G. Adensam, Director Project Directorate II-I Division of Reactor Projects I/II-l ^ Office of Nuclear ~ Reactor. Regulation. j
Attachment:
i Changes to the Technical Specifications Date fof_ Issuance: Jun'e 12,1989 L. ~ I J I J %n nn UFc qLA:P]
- U PR:PM:PD21:DRPR:
F
- DSC
- D:PD21:DRPR :.
) J -NAME : 'PA p' NLe:bd ingham :
- EAdensam/g
- 04k/89
. :04,//f/89 f//89 DATE:04/h/89;
- 04 9
L( [0FFICIALRECORDCOPY gg- - - - _ = - _. - -
I j _. y, u. 4 .+: + ,1 s -l h, . ATTACHNENT' TO LICENSE AMENDMENT NO.162 .'j .x. -FACILITY OPER. WING LICENSE NO. DPR-62 L DOCKET NO. 50-324 Replace the following.pages of the Appendix A Technical Specifications with. the. enclosed pages. The revised areas are indicated by'margina.1' lines. p hemovePages' ' Insert Pages 3/4 3-12^ 3/4 3-12 3/4 3 3/4 3-17 3/4 3-18 3/4 3-18 P 3/4 3-22 3/4'3-22 3/4 3-23 3/4 3-23 3/4 3-27: 3/4 3-27 ~3/4 3 3/4 3 : k i \\ t L{ w ---J
ITC 0 0 '0 u 1 2 2 1 1 1 1 A 2 2 2 l 2 2 2 2 2 2 2 2 L EA LNN B OO AI I 3 3 3 3 3 CTT 3 ) 3 3 I AI LRD 2 2 2 2 2 3 2 2 2 2 I PEN PPO AOC 1 1 1 1 1 1 1 2 1 1 1 1 ) - c S( L) reb EN( BNM en MAE i ) UHT l d NCS / ( Y 2 2 2 2 2 2 2 2 2 2 4 1 MES UL N MBP I AI O NRR I ET I TA MP ) T OR d N E P e E u M n U i R S t T PY n S UB 8 o N O ) c I RD a ( N GE( 7 7 TL O 1 EAA I 2 T VRN 6 6 A LEC API ) 3 U h T VOS 2 3 1 2 1 1 1 1 1 1 1 ( 3 C A EL N B O A I T TA L O S I h l g e i N v H O e h a, I L g l w T i h e o s A r il g nh L eh n L e i w ng rg o O t H o ui Ai i S a1 2 3 L TH H t I W e h h m g a l l l r e g g e-u n-i T l e e e u nn i i n u i d N ev v v s i o e H H i e c d e a E se e e s Li r L r a l r R ( sL L L e t u u V i u W e r ma s mt ut k I V, P ai s w w aa r B a c A w w w ed e o o er e r a T ro o o l t a r l l t e s ee t N oL I L l SR P F F S p n np S O t e m e i N C c w n ne d b e n m O a y i i T n rT i I Y e. r a. a o u a T R R1 2 3 D M1 2 3 4 M C T M C A N M U I F R P a b c d e f g P I R T 1 $EyEM 8 EeH u y t'& 'f C gug, E r {* .f .Il l l!
N TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours and in COLD SHUTD0kN within the following 30 hours. ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours or be in at least HOT SHUTDOWN within 6 hours and in COLD SHUTDOWN within the next 30 hours. ACTION 22 - Be in at least STARTUP within 2 hours. ACTION 23 - Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within one hour. ACTION 24 - Isolate the reactor water cleanup system. ACTION 25 - Close the affected system isolation valves and declare the affected system inoperable. ACTION 26 - Verify power availability to the bus at least once per 12 hours. ACTION 27 - Deactivate the shutdown cooling supply and reacto vessel head spray isolat't, valves in the closed position until the reactor steam dome pressure is within the specified limits, ACTION 28 - Close the affected isolation valves within 14 days or be in HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the following 24 hours. NOTES When handling irradiated fuel i'n the secondary containment. (a) See Specification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve group. (b) A channel may be placed in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. (c) With only one chant.el per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function I to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken. L (d) A channel is OPERABLE if 2 ef 4 instruments in the channel are OPERABLE. l (e) With reactor steam pressure > 500 psig. (f) Closes only RWCU outlet isolation valve. (g) Alarm only. (h) Isolates containment purge and vent valves. l l l f ( BRUNSWICK - UNIT 2 3/4 3-17 Amendment No.ES,f$,7/, y}1, 195, 162
e ( ( o d v h s s, p e d c e e t e g n h h I a t H i c c l r a n n ud g r s EL~ 5 i i f n i f e i xo p o F c F g u s o f h BE 2 2 5 AU 6 1 s ~ r n WL 1 1 2 p OA 5 g 5 0 Z 0 i 0 k 2 4 0 0 0 LV + + + 2 3 c 8 1 4 2 7 2 ) L - a b A <b 3 $ < $ 3 < ( ~ ST N I O w m ) P o w u T a l o u E ( ) ) f l c s a a r f a S e ( ( e d v N h s s w e d T c e e o t e g O N n h h p a t H I I i c c r a TA O n n l d g r s T PT 5 ~ g uu s o f h i i l n i f e 2 N E E 2 2 5 i f o p o F c F S 6 1 s r n 2 M U 1 1 2 p xg 5 0 0 i 0 P 3 R k 2 4 0 0 0 T + + + 2 3 c 8 1 4 2 7 2 ) I R 3 S a b N T 3 3 3 < <b 3 5 $ < 3 < ( E I L B N A O T I TAU T C A hg N i O H IT A L e O r h S u g I t i a H r e p h l m p g N e e m i O v T e H I e h T T L g l w A i e o a L r H h n L e n O e g n r o S t i w u A i I a H o T t W1 2 3 e L m g a T r e-h h e u n i N ll l l u n g g n u i d E ee e e s in i i i c d a M s v v v s Lo H H L a l R B s e e e e i r V i I eL L L r mt u m u k A V P aa s a r B c T ei s w w e e a N rw w w l td e o o t s e t O oo o o l S a r l l S n n S N C t L L L e R P F F e i O c w n n d b n I Y a y i i n r i T R e. r a. a o u a C A R1 2 3 D M1 2 3 4 M C T M N M U I F R P a b c d f g P ~ I d 7 T 1 ~ jE{ - $yn R* T3 -= ; yE hR 5 m N -e ~ b m4
~- Ii ,I ~ 4 ~ l 1 J n ) ) M a CD ( s O e ( hc L n g A .E U i i L - s N AU 5 p A BE M WL 2 0 OA 6 4 NO LV 1 1 L T I A 3 AL UCLAC
- +
E S S T O N D I O E P T T I ) E S a S F ( ) N s FO d O T e N h e I e u T c I n A O n g ht P i i i T T s t N n E 5 p n E i S o M C U 2 0 d P 6 4 ( R e I T 1 1 R n 2 S i N T a 2 I tn 3 N o O c 3 I T y E A O g L U R o B T E l A C Z o T A d 1 L o N E h l O V t e I E e T v L m A e L L h E e O g C h S w i I t o H D I L R r N E e O F p I e E T l r R s A e u t L v s o n O e s t i S L e o I r r p r P e t M e f e E t e e s T a m r S W o p Y D s i S l l r e m e t G s a v / N s e e m I e t l r L V S a O r l O r r e a C o o t N t t a h O N c c w s I W a a i T O e e l l C D R R e b N T s a U U s t F H e s S a b V E P I ) ) R a b T 5 ( ( 4* gEg;;M e Ey" wE Y% EIE E - E *... s lll l! t
s + L;; TABLE 3.3.2-3 ISOLATIONSESTEMINSTRUMENTATIONRESPONSETIME TRIP FUNCTION' RESPONSE TIME (Seconds)(*)
- 1.. PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level - 1. Low, Level 1 <13 2.. Low, Level 2 21.0(d)
- 3.. Low, Level'3.
31.0(d) b. Drywe11' Pressure - High $13 c. Main Steam Line l'.- Radiation - Higb(b) <1.0(d) 2.. Pressure - Low 213 (d). 3. Flow - High 70,5(d) 4.- Flow - High 30.5 d. Main Steam Line Tunnel Temperature - High $13 e. ' Condenser Vacuum - Low $13 f. Turbine Building Area Temperature - High NA g. Main Stack Radiation - High(b) $ 1.0(d). 2. SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(D) <13 a. b. Drywell Pressure - High' <13 c. Reactor Vessel Water Level - Low, Level 2 $1.0(d) 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a. A Flow - High. <13 b. Area Temperature - High <13 c. Ares Ventilation Temperature a T - High $13 d. SLCS Initiation NA e. Reactor Vessel Water Level - Low, Level 2 $1.0(d) BRUNSWICK - UNIT 2 3/4 3-23 Amendment No. 9/,7J),162
NNR OI 33 3 3 33 33 3 3) I : E TSC ANN 22 2 2 22 22 2 3 2 ROA EI L PTL 1 1 1 1 1 1 1 1 1 g 1 3 1 2 1 OI I DE NV OR CU S STN N E - O M LI ) ) ) ) ) ) E ET b b b d b b R NA ( ( ( ( ( ( I U NR RM RM RM RM R RM RM M R' AB Q E HI CL R ' A C E C N A LL I L E LA V EN R NOT U NI S 1 S ATE A A A A A A 2 N HCT NM NM NM NM W NM NM M M CN - O U 3 I F T 4 AT E N L E ~ ) ) B M L a a g ) ) ) a a a A U EK ( ( T R ( ( ( NC A - A A A A A A T NE ND ND ND ND D ND ND D N S AH N HC I C 'N O I TA UTCA N l O e I T N v A O e h I L g L l O T i h e Ar H g nh L S L e i w: I ng Ot r: r: r: H or: r: ui S a1 ec 2 ec 3 ec L ec ec TH I W ti ti ti e ti hti h l t g l t g l t g r e - t g gt g g e'- Tl eio eio eio u: nn i o ii o i n N evmL vmL vmL s r: i o emL H mL H ie E ses es es s ec Li rs s L r a MsL np I np L np eti t unp - np - u l B e ,ai ai ai rt g ma s ai ai mt I V rr ,rr ,r r Pi o ai s rr wrr w aa r A wTT wTT wTT mL ed eTT oTT o er e T ro o o l s t a r l l t e s N oL L L l np SR P F F S p n Ot N C c - eai m wrr n ne d O a yTT i iT I Y e. r a. . a T RR1 2 3 D M1 2 3 4 M C A N M U I F R. P a b c d P I R T 1 gE*5nM i gU, R* 5;n" g,8Eo
- j
A E NNR OI ~ I E 5, 33 33 3 3 3 3 33 TSC ANN 3, 22 y2 2 2 2 2 y 2 ROA EI L 2, PTL 1 1 1 g 1 1 1 1 1 g 1 OI I DE NV OR CU S STN E N M O LI ) ) E ET b b ) R NA b ( ( I A ( U NR R RM RM R R R N RM Q AB E HI CL R A E C CNALL I E L LA V EN RU NOT NI S 1 S ATE A A A 2 N HCT M NM NM M M M R NM CN O U 3 F I T 4 AT E N L E B M ) ) L ) U a a A t W C A A A A A A a T f EK ( ( ( T NE D ND ND D M N N ND S AH N HC I C NO ITA N U O T I C T h A A g L i N O H O N l S l O e I e I I t v v TA T s h e M h p e L A u g L E g m L O L a i T i e Oh H r S H T r S S n e Y e I I Eh t S A t g a a T gi e W P e n W N nH r U r o n Ei u: l 2 : N u i o l 2 : 6 d - s r: e rs A h t t i e r: Bl l s ec sl ec E g a a t sl ec l i n ati s eti L i r l a s eti A uo rt g evt g C H e i i evt g TBi Pi o V ei o p t t Veio N t mL L mL R m n i L mL Ora l s r s E e e n r s C oi l np o, np T w T V I o, np t d eai t wai A o t wai N Y ca wr r cor r W l a a S corr O R aR yTT aLTT F e e C aLTT I A e r e R r r L e T DR D R O A A A S R C N T N O C U C A F E. E S a b c R a b c d e P I R T 2 3 I f f gig Et @ti~ t* yg E$ E@ " @ i e i P ll{}}