ML14317A594
ML14317A594 | |
Person / Time | |
---|---|
Site: | Seabrook ![]() |
Issue date: | 10/21/2014 |
From: | NextEra Energy Seabrook |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML14317A463 | List:
|
References | |
SBK-L-14179 | |
Download: ML14317A594 (33) | |
Text
SEABROOK UPDATED FSAR APPENDIX 3A PIPE BREAK ANALYSIS
SUMMARY
SEABROOK UPDATED FSAR APPENDIX 3A PIPE BREAK ANALYSIS
SUMMARY
Introduction This appendix summarizes the results of the failure mode and effects analyses of breaks in high and moderate energy piping systems.Summary Main Steam and Feedwater Pipe Tunnels and Yard The main steam and feedwater lines are the largest high energy lines located outside Containment, and a rupture in these lines could, therefore, result in more severe environmental conditions locally than any other line outside Containment.
The portions of the main steam and feedwater lines in the containment penetration area between the first pipe whip restraint inside Containment and the first pipe whip restraint outside Containment meet all of the requirements of paragraph B.l.b of MEB 3-1, and are excluded from postulation of circumferential ruptures in this area.In accordance with Branch Technical Position ASB 3-1, paragraph B1.a.(1), longitudinal breaks of the main steam and feedwater lines have beenlated to occur in the penetration areas.A break area of 1.0 square feet has been postulated for this study.Outside the Containment in the annulus between the containment structure and the containment enclosure, the main steam and feedwater lines are enclosed in guard pipes, composed of the containment penetration sleeves, which prevent pressurization of the Enclosure Building.The containment penetrations have been designed to withstand without failure the maximum combination of forces and moments that can be transmitted by the attached piping, so that containment boundary integrity would be assured even without the use of pipe rupture restraints.
The pipe rupture restraints are designed to prevent pipe rupture forces and moments from being applied'to the containment penetrations and the isolation valves and to limit piping stresses to less than the values required by paragraph B.1.b of MEB 3-1, so that pipe ruptures between the inner and outer pipe whip restraints need not be postulated.
In the main steam and feedwater tunnels outside Containment, a maximumature of 325°F and pressure of 4.8 psig can be attained as a result of the postulated
1.0 square
foot rupture.These P-T effects do not result in failures of any essential structure or component for the following reasons: a.Electrical cable in the area is qualified to a temperature-time profile which envelopes the 325°F resulting from a main steam line break.3A-l SEABROOK UPDATED FSAR b.The main stearn and feedwater valve operators are designed to close the valves in the event of loss of instrument air.In addition, the operators are qualified to the 379°F temperature, and the 4.8 psig overpressure would not affect their operation in any way.Direct impingement of stearn from a one square foot rupture of the adjacent line would result in mechanical forces and torsion which would not cause failure of"the valve body or bonnet, or the attached piping.Possible failure of valve operator solenoids, limit or position switches, or instrument, power and control cables would not*inactivate the valve because redundant solenoids, switches and instrument, power, and control cables are located on the"far side of the valve and are protected by the valve body and operator from direct impingement from the postulated break.A failure of one main stearn or feedwater line, would therefore, not result in the loss of function of the other loop.c.The normally closed valves which control the steam flow to the emergency feedwater turbine-driven pump are qualified to IEEE 383, and would be capable of operating under the above postulated accident conditions.
In addition, these valves are designed to fail open in the event of a loss of electrical power and/or instrument air, so that emergency feedwater stearn is available regardless of the results of the accident.One emergency feedwater steam supply line is located in each pipe chase, so that"a single failure in one chase would not affect the steam supply from the other chase.d.A series of seven"blow-out" panels have been incorporated in the design of the upper walls near the roof line of each pipe chase.The panels are designed to blowout at a differential pressure of 0.5 psi to relieve internal pressure following a large high energy line break." e.The seismic Category I structure housing the main stearn andwater pipe chases was analyzed for the temperature and pressure resulting from the 1.0 square foot rupture of the main stearn line.It was concluded that the structure can withstand the 325°F and 4.8 psig conditions, concurrent with SSE, without failure.A flooding study has been performed to establish the maximum water level in the pipe chases.In accordance with BTP ASB 3-1, a one square foottudinal break was postulated in the main feedwater line in the east pipe chase which results in the worst case flood with regard to both flood depth and effect on essential equipment.
The resulting flood reaches a level 2'-5" above the pipe chase floor.The instrument room in the east chase has been provided with watertight door and cable tray seals to preclude damage to the MSIV panels within.No other essential equipment is affected by this flood.3A-2 SEABROOK UPDATED FSAR Outside Containment and north of the main stearn and feedwater pipe chases, pipe whip restraints are located on both the main stearn and the feedwater lines.These whip restraints are designed as boundary restraints to prevent any moments or torsion due to a failure in any part of the nonnuclear portions of these lines from being transmitted to the main stearn or.feedwater isolation valves or to the containment penetrations.
The pipe whip restraints are designed to restrain the maximum forces and moments that can be transmitted by the piping without yielding.Th*load-bearing portions of the piping that pass through these whip restraints consist of heavy-wall forgings with integral lugs to prevent high local stresses and possible pipe wall collapse under pipe rupture loads.Failure of the main steam lines at elevation 40'-2" could result in the impact of the main steam line on the exterior north wall of its respective pipe chase.Impact loading would cause local failure of the wall, generating missiles (spalled concrete)inside the pipe chase, jeopardizing essential main steam and feedwater isolation valves, cable trays and instrumentation.
To provide protection for this essential equipment, pipe whip restraints have been provided to protect the building from damage.The whip restraints are equipped with crush pads and are mounted on a concrete beam to distribute rupture loading into nearby perpendicular walls.Postulated failures in the feedwater lines in this area do not result in unacceptable consequences.
On the east side of the Containment, the nonnuclear portions of the main steam and feedwater lines are run on elevated supports, and no other safety-related equipment is located in the area.On the west side of the Containment, the nonnuclear portions of the main steam and feedwater lines run on elevated supports adjacent to the east wall of the Control Building.It was determined by analysis, that a split in the main steam line which runs nearest to the control building wall could cause jet impingement which might result in failure of the two-foot thick reinfor.ced concrete wall, with formation of missiles inside the Control Building.These missiles could jeopardize the safety-related electrical trays in the southeast corner of the building, as well as the motor generator sets.To avoid this problem, this line is sleeved from the point at which it leaves the pipe whip restraints north to a point beyond which missiles would cause no problem, a distance of about sixteen feet vertically and twenty-two feet horizontally.
Analysis has shown that rupture of the other high energy lines in this area would cause no unacceptable effects.Failure of the main steam or feedwater lines on the west side of thement where they run along the Turbine Building could result in impact of the ruptured lines on the northeast corner of the Control Building, with the possible generation of missiles that could damage safety-related electrical trays in the Control Building.In order to prevent this effect, a pipe whip restraint bumper has been provided to prevent damage to the control building wall.This bumper is equipped with energy absorbing crush pads and beams to distribute pipe rupture loads to nearby perpendicular walls to prevent panel 3A-3 SEABROOK UPDATED FSAR fracture of the control building wall in this area in the event of a rupture of any of these high energy lines.Guillotine ruptures inside the Turbine Building would impose blowdown forces on the manifolds in the south direction which would be resisted by the entire piping system inside the Turbine Building and, thus, no impact on the Emergency Feedwater Pumphouse is postulated.
Containment Enclosure and Penetration Area In the containment enclosure and associated buildings (penetration area), a failure of the chemical and volume control system letdown line, CS-360-9-3" would cause the most severe environmental conditions (see Appendix 31), but all essential equipment in this area is qualified to operate in a more severe environment, and no failures due to temperature, pressure or humidity are anticipated.
A terminal end rupture of lines CS-328-3-2", CS-329-1-2", CS-330-1-2", CS-331-1-2" or CS-335-1-3" could result in a spray of water at 130°F on nearby essential valve operators 2" CS-V-162, 2" CS-V-166, 3" CSV-142, 3" CS-V-143, 8" RH-V-20, CS-V-167, 2" CS-V-158, or 2" CS-V-154 and on rack MM-lR-12.The impingement force of the water would be insufficient to damage the valve operators or the rack.Wetting due to the water spray would not cause failure of the valve operators, but could cause a short-circuit failure of the rack's electrical connections.
Since the rack does not contain any equipment required for safe shutdown of the nuclear reactor, failure of the electrical connections would be acceptable (see Table 3.6(B)-1).
Rupture of the large component cooling water lines would cause flooding of the lower levels, but pressure and flow monitors would alert the operator that a problem existed.The system inventory is limited to the contents of the piping and the head tank, so that flooding to the elevation of the essential equipment in instrument rack MM-lR-13A is not possible, even if no operator action is taken.Rupture of the small high energy lines in the area can cause flooding, but each system is provided with pressure and flow monitoring instrumentation that would alert the operator in the event of a rupture of a line.The operator would have sufficient time to isolate the leaking line in any case.Primary Auxiliary Building and Equipment Vaults In the Primary Auxiliary Building, the worst environmental conditions would occur from a postulated rupture of the 6" auxiliary steam line break in Zone 33C, which could result in an ambient temperature of 249°F and a pressure of 0.20 psig.All electrical equipment in the PAB which is essential for safe plant shutdown is capable of performing its intended function while exposed to this environment.
3A-4 SEABROOK UPDATED FSAR Rupture of the large component cooling, reactor makeup water and containment spray lines could result in flooding of the sumps in the equipment vaults.Pressure and flow indicators in each system would alert the operator that a problem existed, so that action to isolate the ruptured line could be taken.The sump high level indicators would also alert the operator that flooding existed.Uncorrected flooding of one equipment vault might result in loss of function of the equipment in the vault.In this case, the redundant equipment in the other vault would be available for safe plant shutdown.Other Buildings Rupture of the hot water heating lines in the Diesel Generator Building, Emergency Feedwater Pumphouse, Service Water Pumphouse and Control Building, would result in short-term elevations of temperature to a maximum of 127°F for 3 minutes.Relative humidity would approach 100 percent, but no flooding would occur because of the limited hot water inventory in the heating system.3A-5
.-ZONE LOCATION TABLE-ZONE ELEV, OWG.HO.AEJlAftKS 26A 11!lO!51'T5 28*1.HH-'805150 80Sl5l., 80 5 t54 288 180!!151 Jln"i.1"'l 268&291."(-)8'-0" 180SIS?QrlC..,f\7
- vle,'-),-,.."".,"'..., J:If\A.,,,, Mel""I'
'30A 805200 805?04 805205,ec>5206 805201 31 A'."00'BIS3Q4 UNlf I ON LY 815311 805.306 318 z,'*,,*, 8153C4 815311:;2 A
.
ANV;m Hl.'-c:!8O.S2 FInS:'" r""""'0'805Z13 805223 8OS224 80524.\8052515....) tS'-c:t 1 805215 8:>5227.e0522B BOS252'i u....5J...)5'5'-0'805217 805231 805210 IAo 4 5A.)r 35E 86-0.*805704--....33C ,'-0'8ISZI<f UNIT I ONLY 815225 815226 805367.80522 101 330 805216 805229
..
805218 805232 34A 805674-805756 grv:.r.::Ilc.RI'I"c.QQ 348 (-l'!l'-O 805675.a:l5757 80 5'y, A051 Q 5 34C l!i'-O'805676 lV\o::.7f\7 In...*!"O B0571b 80573?AO 4 45*805797 3S8 805678 805708 1057 05795 35C 805679'805700 05<>05112 350 53'-0" 805680 AO", 14 7 368 (..,3"0'80568 lOS 17 In Qn, Clnc.36C 805662 8057 7 IO"7nCll An",..At"I 360 53-0*805683 IM71 ,,,....., Q.05797 37&(-\3'*0'805684 805 pc:;'o 7 ,B05795 37*
'Ilne.'"2, 370 5!l'-O-,805686 le057 r.?0..,..<>1"\,..".., 388\-)'3'*0'8153EI UNITIONY Q.1535Q.......--.-.
38C ZO'-O" I ONLY 8153'4 815366
,'AIC,,,,,",q.
36C 20'*0' UNIT 2 ONLY39A (-l'*0" eOS"'1'UNIT t 0\01 Y A057(;1 4U7't-1""O'92,S",,'UIolI'T t ONL'"\n,,*'c.41B 2.1'-"-
il:rIc,:'71 300(." 8C 5245420 S!I!.o" 805365 e05363.P.055B3
,.--...42C lO'-O'1805360 gf\, lC....Qno::.o::.A
... 1,815,59 430 0'805140 805160"'"'---'4 2B (')(.'-0" 805365 80'\:\6.805363.(80535744D 0'805141 805161:3 rA (-;31;.0-E 5?2e 805731.80574=;0 450 0'805142 3eC 25&43 805673&05688 8057 3G 460 0 605143 805163 42E 86-0 805707 805722 805735 475 H<.'*O" 805243 805239.805.241.805742 trPl'l....."c:.47C 7'-0*805235 ,805239 80524" 605242;BQ"'136 488 Z'-O"805240 805242 48C 7"0'805240,805242.
49BtC 1-'3'-Q" 805689 508 23-0 805691.1t805758 805747805748..
Inl;7.4Q
"'0<;795.B05746 51B 23-0 805692*805759 805747 805748 1i1"'7o::.n In, 10 P,05795 490 53*0 805730 528 ZS'-O" 805305 805306 53A.z." 805101 flO"'7"i-IS:O" 1805097 53C-0'-0" 80510b QI"'I';.I":JC.
l""C.'la 530
'805093 528 2-0'825304 825310 54A-z.<"*O*!805102-54-9-15:0"0'*0'805107 ,54.0 120'-0*805094 52C 64-0 805307 SSA-105103$lno::.1$ln""'7" SSB-s B05099 9iC 80510R An",?h!)50 I'l" 0" 805095 S6A-t/i'805104 AOC;OQI S6B-15'805100 S6e 0'-0*80SLD.9 AOSI?4=; 17,'186509b:;oC I: 80S 202 80C)?04 AOC;;>05 AOC;?l1h AnC;?07 30D 805.203 805204 805205 8o'V(Jf.M'l;>07;7£2.5"0*805115 31"\7Cl.1\
,0:,::.57 80S 14b AOc;I47 F ('C., S80 0'-0' S 1"4 58£25-0"'g0513C;Mile.59.0 5.3'-0*805683 8CS 753 805754 M0575'i 60A 80590"0-590 9&65"9" B05694 e05755 31A 7,0" 825304 UNIT 2 ONLY 805301; 10 590 75-4'805695 e05755 59E 86*0'605756 33C 7'*0" 825214 UN IT 2 ONLY 805367, 825225,B25726 B05221--:3r.-'\H31-0 I (:l{)5760/j<J'.)'51,B0572B-2_eOSlz.o 805130 P.OO;s-nc;,...7C;4+8-2'80512.1 8C5131 805144 l""
J:lt"lo::.':l'o::.-2" 8051'2.1.805/3?RO""'45 An"i148.BOSI4Cl 805 f 68 8051454B 805375 31 C 64-0 80530 33F 8"-0" 805212 805248 3Z, F 8,'-0'"04-IIBto\E.C...
Q.J111.',IQ.
36E..!,"'-o*'04SOZ.PIP,NG. ME.C.lt.SEll""62 1614125 NIT P IPINf" A"....s:,...62&64 624254 NIT L PI PING BY MEUl.5:RVIc.E!l 438 8051414 I"o..c..PUMPS ONLY 448 (.)z.c.'-<l" 805144 R.C..PUMP!!ONL'1 45B 805145 R.C.PUMPS O\llL'I 468 (->''0
805145 R.C_PUM,.s O"'\".'(31C'-4'-0'60413&PIPING BY lo1E(.H.SERVICES 52C 604136 PIPING BY MECH SERVICES'38'4-9 805739 805771 63C 805740 80577380577
..36':'37E 8S;0*180'799 59C 25-0*805886 805887 30E 25-6*805245 NITROGEN c;,38DH 71-0 , 1805722 805735 41 C 1805212 1805248 288&29>\H.5-0 805152 805151 805154 81'-0*1605707 (65C 2.0-0" 805742)*
INOICATU AODITIOtlAL fOR ZONE./" C:OQLING TOWER P""RTIJla....L PLA.N 1;/;;-II II II.II
!:!: II II II II II II II II II II R.H.R.(C.s.,I II (I!: ,I'i II II II II II" II II I,-.GRAOw E.\.Z.O'-O*SECTION-A-A" 3*-_+--1.0"I 1/i SECTION C-CFUEL STORAGEUNIT"122 Composite Piping Zones (Nuclear)Key Plan SEABROOK STATION UPDATED FINAL SAFETY ANALYSIS REPORT 805067 I FIGURE 3A-l I DIAG I I MAIN STE""" STEAM I50ME:TRIC MAIN STEAM ISOME:TRIC COMPRESSED AIR-TUR6., M'SC.VENTS (DR-..,..S VE-NT.5 AS 4 ASC.TO c..8**PA.B.ONLY OEMINERALI'I.EO W__(UMI,.Nell)
WA.'TE R (UMIT 1-40.'2.)TuRBINE BLDG.GEN'L PLM4-EL.'21'-0" I I: II:50'-0" SEcno,.....A-A." I I"1 SECTION" 8-e" SEC-TloN"C-C*SteTlO'"...0-0" I SECTION"E-£"*SECTION"'F-f"" EMERGENCY F"EED PUMP BLDG.
ARRQT.H'TR BAY COMPOSITE EL.21'-0" WEST BAY i E: L.2"-0" I WEST BAY!EL.32'-(,." EAST BAY I E L.32'-<:'" HTR BAY EL.50'-0*'WESTBAY EL.50'-0" EAST BAY ,[L..50'-0" WEST BAY I EL.IS'*0" I EL.75'-0" F'PT ROOM , A,ux..el.OCi$.'ZO.....E KEY Pl"to..""-l SYSiEM DeAWINGS 97"3-F-202329 202328 91(.3-1="-
202303 97(.3-F"-202302 202301 91<O!l-F-l\'Z,300 97'-3-202287 1='-2.02052 1='-202053 F"-202054 F-201055 F-loZOS(.F-202057 F"-202058 F"-202059 F"-2020,"0 F'-2020"5 s-202400 S-202401 s-202402 5-202403 s-5-202405 s-20240(" S-202407 s-202408 S-202409 S-202410 5-202411 s-202412 F-1Cl'ZIIS F-'202'074 MAIN STEAM-5H.1 F-202075 MAIN STEAM-SH.2 F-202011 COfooiDENS-..TE
- '5H.I F-202078 CONDENSAiE-SH.2.1='-2.02079 FEEDW"TER F'-'202080 F-202081 MOIST 5EP REH VENTS 1='-202082 HEATER ORA.INS- F-202083 HEAiER DRAINS-'5H.'2. F'-20208" t:
F'-202087 F"'P'T (MISC STEAM 1='-202093 CONDENSER.
AIR EVACUATION 1='-202094 SEC COMP WATER-!>H.I F'-202095 SEC COMP COOLING WA.TER-SH.'2.F-20Z 104 LUBE OIL
<CONDITIONING F'-'2.02105 COMPRESSED AIR SYS KEY PLAN F"-20210<'COMPRESSED AIR F'-202107 TURBCOMPRESSED AIR HE"DERS F'-20211" HEAT BALANCE F'-,oao...!>\AS.FI"J PIPE
-'PL.AJ.J F" 2020(,,+MSi FI'.I P'f"E F*202blO*..""COMPOSITE WEST CHASE EL, lOZ**O*F*
- ," j1 1 F*202bl2 EAST F'.202G>13*3'.0*
....1'" ,P4l:\1='-20Z088 MISC.EQUIP VEl-JTS\
__
..
tC..3G.4C.C.C.l".&C., Ioc., lie.ZaN!....c...
lC.SC"C.C..1C 1".1",5A-'I,,, 11.1I,!&,4!,'a,e.a.11.
&1.101.111.12&
tC.3G.4C..lOC,IIC.
"....'.10.1e.!.11.IO&.1lI,IC..
IC..lO("IIc.
lC.!'4C,c.e,7e..&C ,oc,ue.lte.
S!.C.6.1B.gB.!>C.C.c.,, lOc.,l\e.(.O,'70.100 110!C, I (0 REFERE.NCE SPECS:
SPEClnCATlON F"OR THE FABRICATION Ot:" SHoP FABRICATED PIPE Q7,,3-oo,,-
SPECIF'ICA'TION J;oR'T..E ASSEMeLY (ERECTION oF" PIPING SP[(':IF"ICATION FOR PIPE SUPPORT E:QUIPMENT 97/.3-00'"-
SPE'=IF"ICAiION FOR NUCLE.AR POWER PLANT SYSTEMS."'1(.3'00(.
SPE<.,,.'C.ArlOIoJHE'-H.EqUIPT REfERENCE DWGS: MAJOIC SYSiEM LOCAI/ONS BUILDING<:OloJoe"",SAiE SYSTEM MAIN$TEAM DRAINS F!I!PWA-r1!1lE:VA.C.U"'i'ION MQISTUr!
5'TEAM SECTION"C-C"
- SOUTH ZONE LOCATIOf\JS ZONE DWG.""" fA£1...'21'-0*
Ie EL..F-10'Z131 Ie F-20'2143--1A!L..'ZI'-O" F-'20'2/70 28 EI...,n'.<o-F-'20'Z13'2 2C E:L..!>O'-o*
F-'202144---3A EL.'2I'*O*
F-'20'ZI'21 3e!1...3'2*""
.3C
---4A r::-'20'2/'Z2 4e EL..32*"
4c F-20'214G:l
---5A EL..'21'-0*F-'20'21'2!
5e EL..32*"*F-'20213S 5C 5D F-'20'2IS-;£1..'21'-0' F-'20'2124!L..32*1O 6C F-20214&
F-']0215(Q iA a.'2J'-o*F-120'Z/'25 78 E.L..32*1O" 7C 7D
!A EL.7l'-O" 1=-'ZOZI2C4>
tle cL..32'-1O ec 6D EL..iS:'O**
F-20'2IS!9A EL..'21'-0" F-'20'21'2'7 EL,3'Z**"*
F-20'2/39 Fo-20'2151 F-'20'215,}
lOA EL.'2t'-O" 1=-'ZC'2I'Z8 loe E.L.3'1*" F-?c'2140 laC E.L.* F-20OZI5'2 10D F-20ZI"'0\lA EL..'2J'-O" 118 EL.3'2*" F-'20'2141 IIC F-'20'2153 liP EL'7S'-O" F-20ZI<Qj F-20'21.30 12e EL 32*" F-'20'ZIA1 I'2C E.L.4Go'-o"
!'2D EL7S'-o" 24 I:L/-\I**o"UZ43Q,"ZONE LOCATIONS M5FU
!OIoJE ELEVATION OWG.Nq 13A EL 3'-0" 13B r-202Z42 13C EL.2"'*"**
F-ZO,,5S I.-A EL.3*-0" F"-'202237 14B EL 1'2.'-0-F'-Z02243 I.-C E.L.2(.'-G."
ISA EL.-2l(,'-O" F-t;,OL1OO 156 EL.20*0 15C EL."2*0'1='-2022414 EL3'-0" F-20zn9 1'8 EL,I'1".O r-202245 I,"C EL.'24*""-to'2.25(o 11A EL.'3'-0" F-z02240 178 EL.IZ-O 17C EL.a,,*-""
18A£:1...-2"-0*
1="-'04100 EL.ZCJ-O" F'-202241 lec EL.-0" F- EL.I"S'-e" OE,l.ER"'TlNG EL.75'-0*M!.7z.....mJ!.'?'-o'----t---0 FI..OOR EL.7!S'-0*ROOF E-L.14\8'-8"opeR-"'TING
-,..--.,;11
!L..
I.0 I MeZZA.I,..j1I.o,j!:
EL.31'-." G<<OUtoJP-+.-..;....__-+-.....+_...............EL.'2I'*O*
PlLOOIt EL..'2t'-O* t-+---'---0
.'-'",",,'.'", I e SEC,IOf\J"A-A" LOOKING W!5T I e SECilON"6-8*LOOKI"IG-TURBINE BUIL.DING PLAN______t----K--'.13 MS f----+I I!i El.iZ*Q EL."4"'"
__EL.ZO**O"__SEABROOK STATION UPDATED Turbine Building Zone Key Plan Piping FINAL SAFETY ANALYSIS REPORT 202117 I FIGURE 3A-2 SYSTEM QRAW'NGS"""UTIQII 0'\..
- (RH.l'a.OF P\PIMe J(,tt (QUIPWN'."0'
- ..,...PUN' LQUIPT.
Tlo,",
AU'&lUAIN'ntt.... O'AMAM'U.II.IAlty)VS"M"..,I O'A6"..M"'UIL'...., STlAIoI,"o.aNa.t.TauY'UH p,t OIAaR_M OlUfl<:ftL A..-snTl"".., S O,AMAM C!IlM.Fl8.0'1., LUBe OIL ,., t WAn""'1 OtA6ll....
....,5.,5T[M.".fI\_N DlAMAM 411l HtAOVt'....et.DCS5'H O'A6'rAM
.,11 I-lhOlll'N;10
.
AEFERHSf SPECS: REa;BE He;DR e@NW;1010601'w..L.....c."(c-£'L':)-4&..l'\..
1"1010t=-'(1.Gill51(.TIOI&S IlU)W<:at"',_IfRANWMINT 10Z"'"
'UWSCil'tAClI W"ML.....
1010'0 OllSI.QDI.81.06.!£TIOWI Aaoltl UteJtAL AltUI\lW'4'"" L"O." AU'ULIAn.c'LI" ltOOM..-..s_..-..*......T%'20.'AU.I\JAtI't ectl.&.-OOM W...IlAL........*"""NT 11101'WATI'" T__ 1,11011 vv_TIA
"'OON*T,o-.S raa..._.....T 97"'-00.-z.,-I
'91"'-00.-z.,-,"..,-0040*z.,'u..c.'!a.oo..
LOIO., ZOlO..ZOlloo lOLIO, lOLIOl lOllO,DIna at..I.NAUIT l,gtlAft,C
---_.-06 COOUN6.Tt.
l)IUlL Gl-.r AI.011.ISOMlTIIIt
.-I)l(SlL...'ull.Oil.OMIT.OCSfL GIJL"'1.Oil'SO..'ac 06 3"IIII,.Na 4" lSO.-TaIt'1**1-'-lit III-------+----------
.,.,s..-,'U15 DW**N*,"",-,-ZOIU)
I...
4'Tf...*,.*'tou.'l.8r-.J.
I Ir;..,J.I
'i'-F-lIUnSToeK.(".........r....J\401ol.t,,,,,\c, I ir.-.J.\-.o.....
10J,,.--_.----i-----------
,,.,3-'-ZO""
I 971.)-'*2013"., P:b3-,.IOU,..1.,*,-%OU5' 10lUO---1 I......
PW6.Nt IONt AUX.
200M ZON e LOCA"'ONS lONe tLIVATION PWC'J.",t...IL.
10e tL.,,'-,,-
11A IL.l-)IGt'-o'
'1.tL.11:-
F-20'Z'lc-.l DIE5E1..
BLDG.ZONE l.OCAiIONS WAiEIl i'fEAiMENi ZONI
'214
...IL, ZONE-ROOM ELEVAilON view eOOM/l/I.;(.'1.__WAiEJt R.OOM-ELEVATION VIEW WAng I I I'I I'r;-I L.-L
_NAOIIIL.....*1QOlI1L.,.....
..GaIJlc."'t r'-l.':
'lOtl&l..
..
II:.NGl.",- 1 1
I I--'"---.-----+'ZONe PLAN CiEN Sl.DG.+-.
1+&"t,T'9'\
"'Lv'(!.£,O PU....!!lt:091fIII'i----
_I.e::::" IT---_I
- I..
___
VIEW GENER"TOR SEABROOK STATION UPDATED Auxiliary Building Zone Key Plan Piping FINAL SAFETY ANALYSIS REPORT 202118 I FIGURE 3A-3 SEABROOK UPDATED FSAR APPENDIX 3B (Deleted in Amendment 58)
SEABROOK UPDATED FSAR APPENDIX 3C PROCEDURE FOR EVALUATING JET IMPINGEMENT LOADS FROM HIGH ENERGY PIPING FAILURES The information contained in this appendix was not revised, but has been extracted from the original FSAR and is provided for historical information.
CONTENTS 1.INTRODUCTION 1 2.REQUIRED INPtIT INFORMATION 3 3.JET IMPINGEMENT FORCES 4 3.-1 BLarocr.m FORCE 4 3.2 FULL JET DIPINGD1ENI' LOAD 5 3.3 JET D1PINGDIENT PRESSURE 6 3.4 JET DrPINGEMENr AREA 7 3.5 JET D1PINGElrE1\"T ENVELOPE 9
4.0 REFERENCES
21 1.INTRODUCTION Amendment 56 November 1985 The scope of this guide is to establish convenient but conservative methods of computing fluid jet impingement loads on structures, components and systems ,due to postulated ruptures in high energy piping (i.e., piping systems where the maximum normal operating temperature exceeds 2000F, or where the maximum normal operating pressure exceeds 275 psig)(REF.4), inside as well as'outside the reactor containment building 1n accordance with REF.5.Only mechanical impingement loads have been considered, thermal shock loads due to high energy fluid jets have not been covered by this guide.The jet impingement loads given in this guide are equivalent static loads, based on the conservative assumption that a target encountering the jet remains elastic.A list of minimum input data required to assess the consequences of jet impingement on essential components is provided.Sfmplified techniques of computing conservative values of jet impingement loads, areas, pressures and envelopes are presented for both circumferential and longitudinal type of pipe failures.For each case, an illustrated example is given.If the stmplicity and, therefore, the inherent conservatism of the jet impingement given in this guide result in unacceptable and/or uneconomical jet impingement protection designs, it is recommended that rigorous.analysis be performed.
Such analysis should include elasto-plastic behavior of the target, non-homogeneous nature of jet, interaction between the jet and its environment, and drag effect due to the shape of the target. 2.REQUIRED INPUT INFORMATION Amendment 56 November 1985 To determine jet impingement loads on essential structures, systems and components or on such structures, systems and components as may adversely affect essential items, the following is prerequisite information: (a)Composite drawings of high energy piping and safety related target structure, systems and components.(b)Locations and types of postulated break points for each high energy piping, and (c)State of high energy piping fluid, fluid pressure and pipe data. 3*JET IMP INGEMENT FORCES 3.1 BLOWDOWN FORCE For steady state flow, neglecting fluid friction in pipe, the force FB (see Fig.1)acting on the discharging pipe segment is given by (REF.1),*****(1)where: K c: thrust fa*ctor (1.26 for flashing and partially flashing fluids and 2.0 for sub-cooled fluids)p=fluid pressure in pipe P to C ambient pressure around the target A-=area of jet opening Area of jet opening for longitudinal breaks and'also'for circumferential breaks on unrestrained pipes (Fig.8)is assumed to be equal to the internal cross sectional area of the pipe.However, if the pipe is axially restrained, then in case of a circumferential break the broken ends of the pipe will separate by circular width B, effecting a fan*jet, and the jet opening area will be given by, A JTDB where: D=inside diameter of pipe B=distance between broken ends of pipe Value of B for a given case depends upon the pipe geometry, pipe material and properties, restraint stiffnesses and fluid characteristics; and can be determined by dynamic or static analysis*of the system including piping and restraints.
3.2 FULL JET D1PINGEMENT LOAD Whenever a discharging jet encounters a target object in its path, the momentum of some fluid particles is chaRged and an impingement force is developed.
Impingement load characteristics depend upon target shape, projected area, and.orientation relative to the jet, as well as jet cross sectional area and flow properties.
However, the simple model shown in Fig.1 is used to estimate jet loads on target(s)encountered in a nuclear power plsnt.The jet discharges from an open pipe with jet opening area A and expands to an area At>>at some distance L.where it is assumed to be homogeneous.
Forward motion of the jet is stopped by the target shown and the net rightward jet impingement force on the target is therefore*****(2)where: Pi=uniform impingement pressure on the target A oo=area of fully expanded jet at the target If momentum and shear interactions between the jet and its environment are assumed to be negligible then, forward momentum conservation for the jet at any location its travel leads to an equality of blowdown force F B and total jet force R.*Equivalent static jet impingement force on the target is J therefore also given by*****(3)3.3 ,lET IMPINGEMENT PRESSURE When a system or component encounters only a part of the jet, it is useful to know the impingement pressure to compute the total jet load on such a target.From equations (2)and (3), the impingement
- pressure, 2K(p-pc.o)A-7-Amendment 56 November 1985*****(4)The jet impingement load on a target with area At which does not encounter full jet (i.e.At<is given by*****(5)3.4 JET nIPINGn1ENT AREA Full jet impingement area be determined if distance L of the target from the jet opening and the shape and size of the jet o opening arc known.A consen'ativc value of 10 (REF.3)can be used for jet expansion half-angle 0.The shape and size of jet opening are governed by the pipe size and the type of postulated pipe failure.CIRcmtFERENTIAL BREAK UNRESTRAINED PIPES: Circumferential breaks are perpendicular to the longitudinal axis of the p.ipe.Total separation of the pipe at the postulated break point is assumed.For unrestrained pipes the break area is therefore equal to internal cross sectional area of the pipe (REF.2).S{D Amendment 56 November 1985 The following equation gives full jet impingement area (Fig.2)2a: O.2SJi (D+2L tan")where: D II: inside diameter of the pipe Ldistance of the target from the jet opening o expansion half-angle of the jet (=10 0)Graph given in Fig.5 can be used to the area Ate for known values of L and D.
PIPES: Full impingement area of the fan jet due to a postulated circumferential break in a restrained pipe (Fig.3)is given by yhere: A,,-II: 2JT (L+O.5D)(B+2L tan0)*****(7)B c distance between the broken ends of the pipe (see sub-section 3.1)Graph given in Fig.6 can be used to determine circular impingement area A oc for known values of L, D and B.
LONGITUDINAL BREAK-9-Amendment S6 November 1985 Longitudinal breaks are parallel to the axis of the pipe and are oriented at any point around the circumference, (REF.2).The jet axis is therefore perpendicular to pipe axis.The break area is assumed equal to internal cross sectional area of*the pipe and the shape of the break is assumed to be rectangular so that the long side of the rectangle is parallel to pipe axis and is equal to twice the inside diameter of the pipe.Full jet impingement area on a normal target plane (Fig.4)1S given by*****(8)where=2L tan ep.Graph given in Fig.7 can be used t6 determine full jet impingement area A oo for known values of Land D.If the jet axis is not normal to the target plane, and makes an angle a to the normal direction, then the full jet impingement area on the target plane is given by: A=(2D(7TD 8, 8*****(9)where2+2L tan rp/cos a 3.5 JET IMPINGEMENT ENVELOPE An area of the target structure larger than the full impingement area A may be affected due to the motion of the unrestrained Amendment S6 November 1985 broken pipe following a circumferential break.Such an area is called jet impingement envelope.It is generally not applicable to longitudinal breaks where pipe displacement is limited.CIRCUMFERENTIAL BREAK In case of a circumferential break due to unrestrained motion of the broken end of the pipe, the jet will traverse a larger area of the target structure.
In Fig.8, first the wall and then the floor will encounter the jet force from point a to point i as the broken pipe swinss from position I to position n.Jet impingement envelope then can be developed by full jet impingement areas at the wall and floor according to initial position, some selected intermediate positions, and the final position of the.broken end of the pipe in mOllon, (i.e.positions 1,2,3,******,n).The locations magnitude of jet impingement loads will vary from points a to i.depending upon the distance between th*e source of the jet and the target structure, and the inclination of the target structure to the jet axis, at any given instant. PAGE 11 OF APPENDIX 3C DELETED IN AMENDMENT 56 Amendment 56 November 1985 p Pressure Vessel-12-Flow FI GURE 1 GENERAL MODEL Impingement Target Discharge.p a:>Jet Area, A CO Target Plane-13-Expansion Half-Angle, 0 Jef L Alnendment 56 November 1985 Full mpingement Area, Am FIGURE 2 FULL IMPINGEME NT AREA-CIRCUMFERENTIAL BREAK UNRESTRAINED PIPE Restraint o Fan Jet L Rest ra i nt FIGURE 3 FULL IMPINGEMENT AREA-CIRCUMFERENTIAL BREAK RESTRAINED PIPE Longitudinal Break"."-, Expansion I Angl e, 0 Jet o ening,A Target Plane FIGURE 4 JET IMPINGEMENT AREA-LONGITUDINAL BREAK FIGURE 5 JET IMPINGEMENT AREA-CIRCUMFERENTIAL BREAK UNRESTRAINED PIPE o o o (1)o CX)o r'-o<D o v o r()o C\J o 't.eo 10.00 20.00 30.00 50.00 6.0.00 70.00 80.00 90.00 100 00!:....L.Q 0 C\0 00/0 CD t'\oI V 0/0 0 CD N V I 0 V 0 0 j..N/0/IN///0 V/V0 0 N/v/0 V V C?/0V V/V II:*I V.......0 l7 1//./-//v/0///v O*£>-v/v/./0 V v v C?/0.//II 7/.//0 V V./.:/v///'c CD V v/7 V"/:/.-"'" c/v;/vc///0-'co/v VV 7/./-0 v v v vvD//I**300:-/./..l/; 1/1 I l/?v/I**I./0/V V v10=.I---':/
- 70C/-NV vvl--'--I40.-L---"---L----::::::--L I*':0.r----,...L---'--...--..'.r.II FIGURE 6 JET IMP)NGEMENT AREA-CIRCUMFERENTIAL BREAK RESTRAINED PIPE FIGURE 7 JET IMPINGEMENT AREA-LONGITUDINAL BREAK o o o (J)o CD o f'-o<.D o 0-""'" l!)...J oo rr>o C\J o *0 I\)'.Aa\," ,'..*LJ*Break Location.,.0'0 , a///1 I//I I//I/I///1 I//I 1(/I I\II 3(, 2'r---==--==.:-_--n"_________0.," 0'ib ().'0 Wall.;O.C***A.C).0;-'*Floor FI GURE 8 JET IMPINGEMENT ENVELOPE-CIRCUMFERENTIAL BREAK UNRESTRAINED PIPE PAGE 20 OF APPENDIX 3C DELETED IN AMENDMENT 56 Amendment 56 November 1985 4.REFERENCES 1.F.J.MOODY,"Prediction of Blowdown Thrust and Jet Forces", ASME Publication No.69-HT-31, May 1969.2.Regulatory Guide 1.46,"Protection Against Pipe'Whip'Inside Containment", Directorate of Regulatory Standards, U.,S.Atomic Energy Commission.
3.ANSI N176,"Design Basis for Protection of Nuclear Power Plants against Effects of Postulated Pipe Failures", ANS-58.2, American Nuclear Society, 1'1ay 1975.