ML18249A143
| ML18249A143 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 08/13/2018 |
| From: | Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18249A165 | List:
|
| References | |
| RA-18-0131 | |
| Download: ML18249A143 (37) | |
Text
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
26 Chapter:
6 Page:
1 of 4 LIST OF FIGURES FIGURE NUMBER TITLE 6-1 DELETED IN REVISION 21 6-2 DELETED IN REVISION 21 6-3 DELETED IN REVISION 21 6-4 DELETED IN REVISION 21 6-5 DELETED IN REVISION 21 6-6 DELETED IN REVISION 21 6-7 DELETED IN REVISION 21 6-8 DELETED IN REVISION 21 6-9 DELETED IN REVISION 21 6-10 VARIATION OF PEAK DRYWELL PRESSURE WITH DRYWELL FREE VOLUME 6-11 CONTAINMENT PRESSURE RESPONSE TO DESIGN BASIS ACCIDENT LOCA AT 120 PERCENT UPRATE 6-12 CONTAINMENT TEMPERATURE RESPONSE TO DESIGN BASIS ACCIDENT LOCA AT 120 PERCENT UPRATE 6-13 DELETED IN REVISION 24 6-14 ORIGINAL CALCULATED DRYWELL CONDITIONS FOLLOWING LOSS OF COOLANT ACCIDENT (SCALED UP 25 PERCENT TO ESTABLISH DESIGN CONDITIONS) 6-15 LOSS OF COOLANT ACCIDENT PRIMARY CONTAINMENT PRESSURE RESPONSE (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT) 6-16 PRIMARY CONTAINMENT TEMPERATURE RESPONSE TO LOSS OF COOLANT ACCIDENT (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT)
( ~ DUKE ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
26 Chapter:
6 Page:
2 of 4 LIST OF FIGURES FIGURE NUMBER TITLE 6-17 DRYWELL PRESSURE RESPONSE TO STEAM LINE BREAKS AT 120 PERCENT UPRATE 6-18 DRYWELL TEMPERATURE RESPONSE TO STEAM LINE BREAKS AT 120 PERCENT UPRATE 6-19 PRESSURE AND TEMPERATURE TRANSIENTS FOR SMALL STEAM LINE BREAKS (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT) 6-20 PRESSURE AND TEMPERATURE TRANSIENTS FOR SMALL STEAM LINE BREAKS (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT) 6-21 PRIMARY CONTAINMENT CAPABILITY INDEX FOR METAL-WATER REACTION 6-22 DELETED IN REVISION 21 6-23 DELETED IN REVISION 21 6-24 SUPPRESSION CHAMBER MAXIMUM NEGATIVE DIFFERENTIAL PRESSURE 6-25 MAXIMUM NEGATIVE DIFFERENTIAL PRESSURE VERSUS A/K 6-26 PRESSURE-TEMPERATURE RESPONSE FOLLOWING LOSS OF DRYWELL COOLING 6-27 DELETED IN REVISION 17F 6-28 RECIRCULATION LINE AT SACRIFICIAL SHIELD 6-29 SHORT-TERM DESIGN BASIS ACCIDENT LOCA CONTAINMENT PRESSURE RESPONSE AT 120 PERCENT UPRATE 6-30 SHORT-TERM DESIGN BASIS ACCIDENT LOCA CONTAINMENT TEMPERATURE RESPONSE AT 120 PERCENT UPRATE 6-31 POOL TEMPERATURE RESPONSE VERSUS RESIDUAL HEAT REMOVAL COOLING INITIATION
( ~ DUKE ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
26 Chapter:
6 Page:
3 of 4 LIST OF FIGURES FIGURE NUMBER TITLE 6-32 SCHEMATIC DIAGRAM - HIGH PRESSURE COOLANT INJECTION AND REACTOR CORE ISOLATION COOLING SYSTEMS 6-33 DELETED IN REVISION 21 6-34 DELETED IN REVISION 21 6-35 DELETED IN REVISION 21 6-36 DELETED IN REVISION 21 6-37 SUPPRESSION CHAMBER UNCONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 6-38 DRYWELL UNCONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 6-39 CONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 6-40 MAXIMUM NITROGEN REQUIRED FOR DILUTION, SAFETY GUIDE NO. 7 ASSUMPTIONS, 0.5 PERCENT PER DAY CONTAINMENT LEAKAGE 6-41 DELETED BY REVISION 18A 6-42 DELETED BY REVISION 18A 6-43 DELETED BY REVISION 18A 6-44 CONTAINMENT PRESSURE RESPONSE TO CONTAINMENT ATMOSPHERE DILUTION OPERATION 6-45 PROCESS DIAGRAM - HIGH PRESSURE COOLANT INJECTION 6-46 DELETED IN REVISION 21
( ~ DUKE ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
26 Chapter:
6 Page:
4 of 4 LIST OF FIGURES FIGURE NUMBER TITLE 6-47 CHARACTERISTIC CURVE - HIGH PRESSURE COOLANT INJECTION PUMPS (MAIN AND BOOSTER) 6-48 CORE SPRAY SYSTEM PROCESS DIAGRAM 6-49 CHARACTERISTIC CURVE - CORE SPRAY PUMP 6-50 AVAILABLE NET POSITIVE SUCTION HEAD - REACTOR CORE ISOLATION COOLING AND HIGH PRESSURE COOLANT INJECTION PUMPS 6-51 RESIDUAL HEAT REMOVAL HEAD AND RESISTANCE CURVES 6-52 SCHEMATIC DIAGRAM - CONTROL ROOM VENTILATION SYSTEM - AIR FLOW DIAGRAM FOR HIGH RADIATION ISOLATION 6-53 SCHEMATIC DIAGRAM - CONTROL ROOM VENTILATION SYSTEM - AIR FLOW DIAGRAM FOR CHLORINE ISOLATION 6-54 STANDBY GAS TREATMENT SYSTEM
( ~ DUKE ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
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1 of 1 VARIATION OF PEAK DRYWELL PRESSURE WITH DRYWELL FREE VOLUME I.I D.OJ A~ a. e>r1111.o. \\L Ar~a..
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 CONTAINMENT PRESSURE RESPONSE TO DESIGN BASIS ACCIDENT LOCA AT 120 PERCENT UPRATE 0
10 20 30 40 50 100 1000 10000 100000 1000000 Time (seconds)
Drywell Pressure Wetwell Pressure Pessure (psia) fa DUKE
~ ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-12 Page:
1 of 1 CONTAINMENT TEMPERATURE RESPONSE TO DESIGN BASIS ACCIDENT LOCA AT 120 PERCENT UPRATE 0
50 100 150 200 250 300 100 1000 10000 100000 1000000 Time (seconds)
Suppression Pool Temperature Drywell Temperature Temperature (°F) fa DUKE
~ ENERGY
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-14 Page:
1 of 1 ORIGINAL CALCULATED DRYWELL CONDITIONS FOLLOWING LOSS OF COOLANT ACCIDENT (SCALED UP 25 PERCENT TO ESTABLISH DESIGN CONDITIONS)
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1 of 1 LOSS OF COOLANT ACCIDENT PRIMARY CONTAINMENT PRESSURE RESPONSE (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT)
( ~ DUKE ENERGY
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 PRIMARY CONTAINMENT TEMPERATURE RESPONSE TO LOSS OF COOLANT ACCIDENT (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT)
( ~ DUKE ENERGY 300 ______________________________ __
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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6-17 Page:
1 of 1 DRYWELL PRESSURE RESPONSE TO STEAM LINE BREAKS AT 120 PERCENT UPRATE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-18 Page:
1 of 1 DRYWELL TEMPERATURE RESPONSE TO STEAM LINE BREAKS AT 120 PERCENT UPRATE 0
50 100 150 200 250 300 350 Temperature (°F) 1 10 100 1,000 10,000 100,000 1,000,000 10000000 Time (seconds) 0.75 sq ft SLB 0.30 sq ft SLB 0.10 sq ft SLB 0.01 sq ft SLB I '-.~ ~~~~Gv, ll ~~~~~~~
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1 of 1 PRESSURE AND TEMPERATURE TRANSIENTS FOR SMALL STEAM LINE BREAKS (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT)
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1 of 1 PRESSURE AND TEMPERATURE TRANSIENTS FOR SMALL STEAM LINE BREAKS (FOR ORIGINAL RATED THERMAL POWER, 2436 MWT)
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1 of 1 MAXIMUM NEGATIVE DIFFERENTIAL PRESSURE VERSUS A/K
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1 of 1 PRESSURE-TEMPERATURE RESPONSE FOLLOWING LOSS OF DRYWELL COOLING
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 SHORT-TERM DESIGN BASIS ACCIDENT LOCA CONTAINMENT PRESSURE RESPONSE AT 120 PERCENT UPRATE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-30 Page:
1 of 1 SHORT-TERM DESIGN BASIS ACCIDENT LOCA CONTAINMENT TEMPERATURE RESPONSE AT 120 PERCENT UPRATE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-31 Page:
1 of 1 POOL TEMPERATURE RESPONSE VERSUS RESIDUAL HEAT REMOVAL COOLING INITIATION (BASED ON ORIGINAL DESIGN)
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 SCHEMATIC DIAGRAM - HIGH PRESSURE COOLANT INJECTION AND REACTOR CORE ISOLATION COOLING SYSTEMS fa DUKE
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1 of 1 SUPPRESSION CHAMBER UNCONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 DRYWELL UNCONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 CONTROLLED HYDROGEN AND OXYGEN CONCENTRATION FOLLOWING A LOSS OF COOLANT ACCIDENT, NO CONTAINMENT LEAKAGE 0
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UPDATED FSAR CHAPTER TITLE CHAPTER 6 FIGURES Revision:
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1 of 1 MAXIMUM NITROGEN REQUIRED FOR DILUTION, SAFETY GUIDE NO. 7 ASSUMPTIONS, 0.5 PERCENT PER DAY CONTAINMENT LEAKAGE 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 CONTAINMENT RESPONSE TO CONTAINMENT ATMOSPHERE DILUTION OPERATION 0
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UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
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1 of 1 PROCESS DIAGRAM - HIGH PRESSURE COOLANT INJECTION
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- TOI t TO 11 10 To.21 MIHlMUMNrSH AVA,V,at..f: IS tJ fT'MTH SUr'l"ff(S~ON root. SUCTIOH A.NO A Tt:.Mr't:IV,T\\1111( Of' 170., AS rt:111 C:AlC tSU-*-t:* 1-01-f' MI-Hl""'1MNrSHAVA,U.k( IS,. fTWHH COHO(NSATt S'l"OMC( SVC'TIOH AM'O A Tt:.M,r(,V.T\\1111;( o, 100 *FAS r(II.CAlC M-U-0011 30J fTAT 4100 llrMAS rtl\\ V(/'tOO~ TUT OATA IHfr'-UH IS _rr ATMIH s.rtto. 2.100 ArM., AS" Vl(MOOA TUT OATA 1H,,..,...
,1.111 Ff AT
,u rT AT\\.OW MAS ftA Gt: OATA S~((T l2AIJ61AN IM.J(CTIOH Ufjt: N!,(~SIJII( 011.0l"IS U l"SIAT *2150CMAS Pfll (SI\\ H-00ll!-*l1 MAXIMUM O(SICH l'llUSUl*t:. QlltOf" 1$ 1' NC O(SIGH l'I.AlfC( 1:S TO U rsv. AS'°' Cf OATA S:Ht:IT 1%.,UUAN HMMAlOAOf" LS,, TO 20 f'SCAS,CA l,CT\\IAll'V.HTOAfA 111.QMOrr-o,..z MAXIMUM NIUflM< AV~ D *t N1A SUfflCSOfT,MUIMI! TO 11.(1'\\MH TO rvMr SUCTIOH OUfLMG Ol't'.M T'IOH
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-47 Page:
1 of 1 CHARACTERISTIC CURVE - HIGH PRESSURE COOLANT INJECTION PUMPS (MAIN AND BOOSTER)
( ~ DUKE ENERGY ltooo 5ooo i
-4000
'l..
~
~000 l
0
~
~
(\\, :r Q
woo 1000 0
&,~
~
"° 1
- r AO f 2
1000 1000
~000
-4000
~PE°li:0 I~ 12,PM,
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-48 Page:
1 of 1 CORE SPRAY SYSTEM PROCESS DIAGRAM
( ~ DUKE
~ ENERGY A
A CORE SPRAY LOOP 'A'
{'l>IEIE NO':'£ ~\\
PUMP COOIA Specific Valve Orientation is Detailed on "Value Positions" Table 10 FOOi.A LOU..T ION I
z 9
4 b
1 FLDw-&PM 1-v'.. *n-:.
<°5 0
0 rn m
.m m
Pl,H,S.
- P~IA T(MP
- 0 f
'>f"£ >10l£ OP. rt.
LCX,t."rlON rLQw *C.PM 1Pt!E&,* P61A Ti.MP* *r SU NOT£
.ti.P
- FT L.OU,."Tt<JN fl.ON *GPM PRE~-~IA TEMP* T SU: NOH ID.ti.P-n.
L.OC>-TION KON*GPM
[) Pl!E~!o* P!>I._
"TEMP * °F
!>EE NOTE 6P
- FT 14.7
'10 I
N/A I
M/A 1%
I N/A 19.Q l'l(o
~*
ry'A 90 It.VA.v,.
-t.!o,- -*~-
2 9
4 7
1,7 700 14.7
>'I.Ai}
Al.A&
-570- -28.2- -?,96-z
?,
- b 500 500 0
1'9G
-740-I 2
4
'!i, b,
- ns 4'25 l~l.<
l'l<o 5
-6!>!1- -*~- -1911-ID lj) a g
10 1 11 11 725 0 - r-o 0 ry'A oyA 90 lyA L.
m a
9 IO II It 0
0 ~700,...... 7(X N/A N/A ll.lB -
iWII m
6
~
IC II It 0
soo 0 -
0 1%
(iJ e
9 IO II It 0 -
0
~Tt5 4TZl
,q.. 1,..
NOTES *. -VALUES AR£ TO BE FILLED IN BASED ON ARR.AHGEMEHT DRAi,,' [NG.
FOR ALL EKl'TY DATA 8~ (PRESS. TEMP & ELEV.) AND SUBMITTED TO APED FOR REVIEW.
IF CORE SPRAY LOSSES ARE NOf SYHETRICALLY AI\\RAllCED, VALITT:S FOR BOTH LOOPS SHALL BE SUBMITTED.
- 2.
TH! BY*PASS FLOW IS APPROIIIIATED AND \\/ILL BE SPECIFIED BY THE PUMP VENDOR,
- 3.
ONLY ONE CORE SPRAY LOOP IS SHCJl,IS, THE SECOND LOOP IS IDENTICAL.
I,.
IN CONDITION 11 THE NET POSITIVE SUCTION HEAD (NPSH )
AVAILABLE AT THE PUMP INLET (LOCATION 2) HUST BE 32 FT.
5,
IN COIIDITION IV THE NET POSITIVE SUCTION HEAD (NPSH)
AVAILABLE AT THE PUMP INLET (LOCATION 2) HUST BE 13.4 FT ALSO, UNDER THE SAKE TEHP!RATUR! AND PRESSURE CONDITIONS THE NPSH AVAILABLE WITH A FLOW OF 670() GPH HUST BE 19.4
- n. THESE T\\IO NPSH UQUIIU!IIF.NTS ASSIIIE THAT ADEQUATE SUCTION Puss. IS AVAILABLE UNDER ALL CONDITIONS OF FLO\\/
FR~ TBE SUPPJJ!SSION POOL.
6.
100 Gl'lt IS LNCLUDED IN THE FLIJII RATE GIVEN FOR MODE IV to ALLOW FOl LUICAGE LN TBE REACTOR INTERNALS.
- 7.
THE P IETVEEN LOCATIONS 11 AND 17 WILL BE DETERMINED I~ PU-OP!IIATIOIIAL TEST.
THE P \\/ILL BE All.JUSTED TO HEET TH! PLOW UQUIREKENTS OF CONDITION IV.
Rl!!Fl!R!NCE DOCIIKENTS :
- l.
CORI! SPRAY PUD - * - * - - -
- 2.
CORI! SPRAY DESIGN SPEC. * * -
J.
PIPING & INSTRUMENT SYMBOLS -
(OUT,ow I
II m
1V W.IIE l-0.
fOOI J<a roo, Kil!
0 t
0 C.
t 0
0 0
0
(.
0 t
0 C.
0 0
0 *IU.L. OPEN c.-~Cl.05£O
- p. ~Tl"L OPEN l'OQ1 11QI~
0 p
0 C.
0 C.
0 C
III HPL !TEii NO.
E21-IOIO
£21-4010 197R56 7
~
C 0
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-49 Page:
1 of 1 CHARACTERISTIC CURVE - CORE SPRAY PUMP
-r A.
~
'2
( ~ DUKE ENERGY t-Iii l&J
- IL IL 0
0 Ill Cl 0
'2
- )
X r,i-lP (i -SP. C.12. 1.0
"!)
4
'5 1'1-10U5AI-.JCI!, or d.ALL0fv6 PIE.12 MrAJLJTC.
'lo 10~1 0
"° ea
-ro
~ r.o t
"2 ~o Ii.I
~
k-Ao Ul
~
'1000
'2o
' 000ll 10 0
0
~
7
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-50 Page:
1 of 1 AVAILABLE NET POSITIVE SUCTION HEAD - REACTOR CORE ISOLATION COOLING AND HIGH PRESSURE COOLANT INJECTION PUMPS
( ~ DUKE ENERGY lle"1' :
~
I-IPC I
~
12 C. IC I?
IOD 1'2.~
'200
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-51 Page:
1 of 1 RESIDUAL HEAT REMOVAL HEAD AND RESISTANCE CURVES 2 RHR PUMP CURVE 2.-.0 -'r--l.__
22.0
--;--!_!_ ---~
kEPP..Ol>UCTION Of SITE CUR'JES 200
.-.......*~
}
I~
)
.Q -
vi \\~C) 0-
~
I 0
I
~ H:,O UJ
- i: t \\~()
Cl
~
~ \\'Z.O 4-
"":'\\.
/
5'<~'T1!.M 1'.!!!.~\\5T~~~-e.
'X N()"'M""'- \\..PC.\\ r\\..~W V \\
I
/
\\
I/
I'\\ 1/
,J
~/
)(
/
... v \\
~
\\00
/,
/.
./'
/.
80
/
~
/i
_.,,1/
&'<STEM 9..~~\\ST/11\\NC.E \\N\\"n-\\ 9 t.9..0~'=.N '-.i.C.\\l\\.C. \\.OOP
~
2.0 0
- z.
4 10 I?
\\4
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-52 Page:
1 of 1 SCHEMATIC DIAGRAM - CONTROL ROOM VENTILATION SYSTEM - AIR FLOW DIAGRAM FOR HIGH RADIATION ISOLATION
( ~ DUKE
~ ENERGY
~
0 ao
!ii I NOTE:------------- CHARCOAL---------------------,
EMERGENCY FLOW PATH I
- 1. ONLY ONE FILTER TRAIN IN OPERATION DURING EMERGENCY.
- 2. BATTERY ROOM FANS OPERATE DURING AN EMERGENCY.
CHLORINE DETECTORS FILTER
~
1¢ I
f 1¢ RAO DETECTORS
~
0 U>
a,
!?!
!Uil l!l INI.EAKAGE = 5 CFM DURING EMERGENCY NORMAL FRESH AIR
"--1------l I
I 2,iJ/if/if CFM
~ONLY(1)1N
/
OPERATION 2,iJ/if/if CFM
~, MECH. EQUIP. ROOM BOUNDARY TOTAL INFIL -
264/if CFM TOTAL VOLUME 46,851!1 CUBIC FEET I
I (10/if/if CFM)
NORMAL TOILET EXHAUST Ir~
I OA DURING ISO.
C>O
---ti- °1-'b'f~~~JriJ:lfM ~--------1"-..+------t INI.EAKAGE -
14 CFM DURING ISOLATION rMECH. EQUIP.
& I ROOM VENT
---fi &,_I _ __,*-:-OO=LE sP§EADI~ RM.= H & ~"--f-----+-
....,.I I & I
- I~~
ROO~ 1A
= H & 1---+,i---,.-
1
--:""'I I g I
- I~~
ROO~ 1B =H & 1---+,~
I
_ _..., I & I
- I ~TTE~ ~
2A =H g 1---+,~
I
--.w1 I & I
- I~~
ROO~ 2B =H g 1---+,~
I
--~ & I
- ~LE sP§EADI~G RM.= H & ~"--f-----+-
I
--f1 & H"--1 MECH. EQUIP. RM. VENTILATION I
I I
RETURN
- FROM CONTROL ROOM J (37,878 CFM)
FILTER
-~8~~~C~'---------
.._ _____ _._.,.~ To coNTROL ROOM UNIT 11 jr---.__coNTROL ROOM SUPPLY AIR (2/if,iJ/if/6 CFM)
UNIT 1 & 2 TOTAL INFIL -
2774
~OT~8,~Mfl-J 1
TOTAL FLOW -
4/if,iJ/if/6 CFM I
,._ _____....i,_,..1 ___ TO CONTROL ROOM UNIT #2 I
i -- SUPPLY AIR (2/if,iJ/6/6 CFM~ - +
3998 CFM NOTE-1: REQUIRED TO BE 2/if/6/if CFM +/- 1/6,C FROM COMBINED TOILET EXHAUST AND FILTERED MAKE-UP AIR.
898 CFM DURING ISOLATION
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-53 Page:
1 of 1 SCHEMATIC DIAGRAM - CONTROL ROOM VENTILATION SYSTEM - AIR FLOW DIAGRAM FOR CHLORINE ISOLATION NOTES
- 1. The chlorine protection/isolation system has intentionally been rendered non-functional by powering off the detectors for this system, and the chlorine tank car has been permanently removed from the site while the chlorine protection mode has been rendered non-functional. See Section 6.4.4.2 for additional information.
( ~ DUKE ENERGY 1----------------------------------------
SYSTEM OPERATING I NOTE:
1-;:-;-ERG. FILTER TRAINS 00 NOT 1
OPERATE DURING CHLORINE I
ISOLATION.
1 2* BA:~~ ~~tk~ SJ!iPti'tJ'G I
CHLORINE ISOLATION.
1 3.
INFILTRATON AND INLEAKAGE NUMBERS CALCULATED IN REFERENCE 6.4.ll-4 ARE PROVIDED FOR INFORMATION.
l>S DISCUSSED IN SECTION 6.4.2.3 HID TABLE 6.4.4-2, 2B88 CFM OF OUTSIDE AIR Wl>S l>SSUMED TO ENTER THE CONTROL ROOM DURING THE CHLORINE TNIK CAR RUPTURE EVENT.
5 CFM INLEAKAGE NORMAL FRESH AIR CHARCOAL DURING CHLORINE ISOLATION.
EMERGENCY FILT. 'B'
~I MECH. EQUIP. ROOM BOUNDARY TOTAL INFIL
- 2648 CFM I
TOTAL VOWME 46,880 CUBIC FEET NORMAL TOILET r
EXHAUST ISOLATED DURING CHLORINE DETECT.
.,.-----1,1------------
1,1----IN-LEAKAG--E---,4-CFM--
DURING ISOLATION
~-----j~----,,1--------------
'--l---,,f-----1 g,__ ___ _
I I
I I
I I I
EMERGENCY RECIRC FROM
---+--
TOILET EXHAUST DUCT EXHAUST RECIRC. ~
ISOLATION DAMPER I
-t1 g,_, ---,-~~LE SP~EADI~G RM.=H g f-----j,~
I
-H g I I I~~
ROO~ 1A =H g !----f,+--
1
-H g I J I ~TTE~ R~ 1B =H g !----f,+--
1
-Hg I
- .~TTE~ROO~ 2A =Hg !----I,+--
I
-H g I I I ~TTE~ ROO~ 2B =H g !----f,+--
1
~
g I
-~
SP~EADI~G RM.=H g f-----j,~
I
~
g H........ I MECH. EQUIP. RM. VENTILATION Jo I
I I
RETURN FROM CONTROL ROOM J (DU~~if?s5~0N)
~
>------~-.. 1--TO CONTROL ROOM UNIT 11 l'--coNTROL ROOM 1
SUPPLY AIR (2B.ll88 CFM}
1
¥~-lli. \\~Flt I
I
~Rgo=RM.
= 1258 CFM I
I TOTAL VOLUME
>-------+-..... -* TO CONTROL ROOM UNIT #2 1
m 298,658 CUBIC FEET.
i _ - SUPPLY AIR (2S.ll"" CFM~ _---.
- r:tt ~
- 3)
UPDATED FSAR ENGINEERED SAFETY FEATURES CHAPTER 6 FIGURES Revision:
24 Figure:
6-54 Page:
1 of 1 STANDBY GAS TREATMENT SYSTEM
( ~ DUKE ENERGY RTC-REl'-'IOTE RE.~DlhlC. TEMP, SE.N~R RHI - RELATIVE HUMIOl"TY INOIC.,i..To~
dPI - Dll='F"ERENTl,,_L. PRES.:;URE ~UA.~E Tl -
TEMPEQATURE INDICATOR TC - THER.MOC.OUPLE l*O:;,._TER. C.ONT.
WOO-W,._"'l"E.R SP~Y OVE.R.HEA..T Dlt.Tc.C.TOR HOOL..- HEATER OVERH!:AT CET. (LOW)
RODH-HkA.TEROVERl-nu1,T OET. (1-11~1-0 EOO-E.MERC:iE.NC..Y OVERHE:-.T DETEC.TOR MOV-MO"TOR OPE.RATED VALVE F"E.I - FLDW ELEMENT 11-lOJC.ATOR Z:L.- Pos1*noN Sw'ITC.H TO OTHEI<:
STA,1-JDB'< C.AS TREATME.._.T Ul,JIT FROM SECONDA.RY Cm.IT,-.INMENT (0
0 I 0
/
O,RBOtJ l='ILiER CARBON l=ILTE.R.
HEPA 1"°11....'TER PRE-FILTER CAL.IBRl'-.,ED FLOW a..£MENT
~, ------
v HEATE.R MOISTU~E ELEMENi