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| number = ML16180A441 | | number = ML16180A441 | ||
| issue date = 02/01/2016 | | issue date = 02/01/2016 | ||
| title = | | title = FSAR Amendment 107, Figures - Chapters 3, 4, and 5, Part 1 of 4 | ||
| author name = | | author name = | ||
| author affiliation = Luminant Generation Co, LLC | | author affiliation = Luminant Generation Co, LLC | ||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
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LUMINANT CPNPP GLEN ROSE, TEXAS | |||
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SYMBOLS & '!OTES Ml-0200 CP-27 Ml-0200 < FINAL PIRINT > | |||
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AMENDMENT 42 SEPTEMBER 12, 1983 COMANCHE PEAK S. E. S. | |||
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYP. EXTERIOR WALL OPENING FOR TORNADO DAMPERS FQff 3.3- | |||
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\'J IJ 14 M\~I L.. e ~tt..(Z.e.t I!: L AMENDMENT 42 SEPTEMBER 12, 1983 COMANCHE PEAK S.E.S. | |||
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYP. ROOF OPENING MISSILE BARRIER FIQ.ff -:i -:t -2 | |||
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FINAL SAFETY ANALYSIS REPORT RML (LA.MPS-f>..S RE:au1i-t:.L SECTION A-A | |||
_ UNIT2 ROLL-AWAY MISSILE SHIELD FIGLIRC .** "3-:S- 2 | |||
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-AMENDMENT 11 JULY 31, 1980 Plfl'E' COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICA.t.' | --i~,..,r t44~o" I CD | ||
PIPE WHIP RESTRAINT-HARD TYPE FIGURE 3. 6B-3 | . 1n.: <<:..11 1410 | ||
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: 2. Branch nozzle breaks | ('J 1.(1 - | ||
HOWEVER. A BREAK WITHIN THIS BOUNDARY RESULTS IN A RELATIVELY SMALL FLOW WHICH CAN NORMALLY BE MADE UP WITH THE CHARGING SYSTEM. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 Loss of Reactor Coolant Accident Boundary Limits FIGURE 3.68-10 | rA (-.I d) 4 © | ||
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('J r-dJI r(l UNIT 2 UNIT I AMENDMENT 24 I. FUEL BLDG. JULY 17, 1981 | |||
: 2. REACTOR BLDG. | |||
: 3. DIESEL BLDG. | |||
: 4. SAFEGUARDS BLDG. COMANCHE PEAK S. E.S. | |||
: 5. AUXILIARY BLDG. FINAL SAFETY ANALYSIS REPORT | |||
: 6. SWITCHGEAR BLDG. UNITS 1 and 2 | |||
: 7. ELECTRICAL 8 CONTROL BLDG. | |||
T~RBINE MISSILE STRIKE | |||
: 8. TURBINE BLOG. ZONE - PLAN VIEW FIGURE 3. 5- 3 | |||
SUPPORTISTRUCTURE BRACKET PIN- COTTER PIN SADDLE SADDLE CLAMP | |||
{TYP. 3 PLACES) | |||
SIDE VIEW CROSS SECTION COMANCHE PEAK S.E.S. | |||
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 11 TYPICAL U-BAR JULY 31, 1980 RESTRAINT FIGURE 3. 6B-l | |||
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..... P AMENDMENT 11 .RESTRAINT-CRUSHABLE JULY 31, 1980 BUMPER TYPE FIGlff 3.68-2 | |||
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FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICA.t.' PIPE WHIP AMENDMENT 11 RESTRAINT-HARD TYPE JULY 31, 1980 FIGURE 3. 6B-3 | |||
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UNITS 1 and 2 AMENDMENT 11 TYPICAL PIPE WHIP JULY 31, 1980 RESTRAINT-IMPACT ABSORB IN FIQff 3. 6B-4 | |||
RESTRAINT SUPPORT STRUCTURE CONTAINMENT BUILDING STRUCTURE PROCESS PIPE RESTRAINT BASE PLATE CONTAINMENT ANCHOR ISOLATION BOLTS VALVE | |||
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Amendment 73 August 5, 1988 COMANCHE PEAK SES | |||
"""- BREAK FINAL SAFETY ANALYSIS REPORT | |||
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EXCLUSION UNITS 1 AND 2 PROCESS FORG THREADED PIPE FLANGE (BQL TEO J AR TYPICAL MOMENT RESTRAINT AND BREAK EXCLUSION AREA BOUNDARY TO STRUCTURE) 051588067 FIGURE 3.68-5 | |||
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'51~~ JULY 31, 1980 FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICAL PIPE WHIP 10'; \ ~ ANALYSIS MATHEMATICAL THRU~T~ | |||
4 MODEL | |||
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COMANCHE PEAK S.E.S. | |||
FR\IAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 PIPING STRESS-STRAIN CHARACTERISTICS FIGURE 3 | |||
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I I-Tl ME SLOWDOWN THRUST-TIME HISTORY COMANCHE PEAK S.E.S. | |||
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 RESTRAINT IMPACT FIGURE 3. 6B-8 | |||
~ DENOTES BREAK LOCATION PLAN VIEW STEAM GENERATOR REACTOR PRESSURE VESSEL ELEVATION NOTE: 1. Postulated main reactor coolant loop break locations 1 through 8 and branch nozzle breaks 9 through 11 are consid ered for containment design, ECCS and enviornmental qualification. These breaks are not postulated for dyn amic effects. | |||
(Sections 3.68.2.1.1 and 3.63.2.1.2) | |||
: 2. Branch nozzle breaks 12 and 13 are considered to account fo r the dynamic effects attribu t ib l e COMANCHE PEAK S.E.S. | |||
to the largest RC L postulated breaks after application of LBB to selected l ines. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 76 MAY l, 1989 Location of Postulated Breaks in Main Reactor Coolant Loop FIGURE 3. 68-9 | |||
i+026-i+91 CASE I OUTGOING LINES WITH MORMALLY CLOSED VALVE | |||
( REACTOR COOLANT PIPING | |||
) r | |||
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~-i..,. BOUNDARY NOTE: PRESSURIZER SAFETY VALVES ARE INCLUDED UNDER THIS CASE. | |||
CASE II OUTGOING LINES WITH NORMALLY OPEN VALVES NOTE: THE REACTOR COOLANT PUMP NO. I SEAL IS ASSUMED TO BE EQUIVALENT TO FIRST FAIL CLOSED OR VALVE FAIL-AS-IS VALVES I 1kRY RESTRAINT CASE m INCOMING LINES NORMALLY WITH FLOW NO. I NO. 2 _J_ | |||
BOUNDARY TEST CONNECT I OH CASE II INCOMING LINES NORMALLY WITHOUT FLOW | |||
_l BOUNDARY TEST CONNECTION (MEANS OF VERIFYING THAT CHECK VALVE IS CLOSED) | |||
CASE Y ALL INSTRUMENTATION TUBING AHO INSTRUMENTS CONNECTED DIRECTLY TO THE REACTOR COOLANT SYSTEM IS CONSIDERED AS A BOUNDARY. HOWEVER. A BREAK WITHIN THIS BOUNDARY RESULTS IN A RELATIVELY SMALL FLOW WHICH CAN NORMALLY BE MADE UP WITH THE CHARGING SYSTEM. | |||
COMANCHE PEAK S.E.S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 Loss of Reactor Coolant Accident Boundary Limits FIGURE 3.68-10 | |||
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N FINAL SAFETY ANALYSIS REPORT UNIT 1 AUlCIUARY F. W. SYSlEM: LOOP J OUTSIDE CONTAINMENT SIRESS NOOE BREAK POINT ANO RESTRAINT LOCATION FlGURE 3.68-29 PROB. 1-12E | |||
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....,. J. FlGURE 3.68-30 PROB. 1-108 | |||
1. | |||
Amendment 91 April 15, 1994 COMANCHE PEAK S E FINAL SAFETY ANALYSIS UNI AUXILIARY F.W. SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT ANO RESTRAINT ION FIGURE 3.68-31~*1 PROB. 1-12A | |||
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COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 1 Amendment 96 AUXILIARY F.W.SYSTEM August 2, 1999 OUTSIDE CONTAINMENT STRESS NOOE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-31-2 PROB 1-128 vp()()()?-fn rlnn | |||
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FINAL SAFETY ANALYSIS REPORT 0 SltO'S NOO£ POINT UNIT 1 AUXILIARY r.w. SYSiEM c:::::> ~Jfm OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RES1RAINT LOCATION AGURE 3.68-32 PROB. 1-128 | |||
PR.0&\.~M 1*10 | |||
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AMENDMENT 41 JULY 11, 1983 LEGEND COMANCHE PEAK S.E.S. | |||
CONT. fROll FNAL SAFETY ANALYSIS REPORT FIG.NO.J.6&-31 CI::) CIRCUWfEIW:NTIAL BREAK UNITS 1 and 2 0 STRESS NOOE POINT AUX. F.W. SYSTEM STRESS NODE, BREAK POINT .AtlD FIGURE 3.6B-33 | |||
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LEGEND 0 S1ll£SS NOOE PONT 151""1;:1!,;'), C) aRClllRl'IEK1IA Allll/al LONCll'l'UIMNAl BAEM | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 S1M. GEN. SLOWDOWN SYS. LOOP 2 INSIDE CONTAINMENT SlRESS NOOE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCATION MAY 1, 1989 AGIJRE 3.68-39-2 PR06. 1-768 | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 o:sY 59Xrfi'Y STEAM GENERATOR BLOWDOWN SYSlEM OUiSIDE CONTAINMENT AMENDMENT 76 STRESS NOOE BREAK POINT AND ftESlRAINT LOCATION MAY 1, 1989 FIGURE 3.66-42 PROB. 1-79E | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 AMENDMENT 78 JANUARY 15, 1990 | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 S1EAM GEN. SLOWDOWN S'l'S1al AUX. BUILDING AMENDMENT 76 STRESS NOOE BREAK POINT AND ~AINT LOOAllON MAY 1, 1989 FlGURE 3.89-t5 PROS. 1-1<48 | |||
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NOTE: FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 | |||
: 1. NO BREAK POINTS ARE POSTULATED IN MODERATE ENERGY PIPE. STEAM GEN. BLOWIJOWN SYS | |||
* STRESS NODE BREAK POINT & | |||
RESTRAINT LOCATIONS FIGURE :L 68-46 | |||
~N AUXILIARY BUILDING. | |||
26 1981 COMANCHE PEAK S.E.S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 S'l'mft;EN; lltOWDOWN SYS : | |||
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T Lllll<<llDW.lllftDIC I AMENDMENT 80 I NOVEMBER 30, 1990 I | |||
I COMANCHE PEAK S. E. S. | |||
I FINAL SAFETY ANALYSIS REPORT I UNIT 1 I SAFE1Y INJECTION SYSTEM l INSIDE CONTAINMENT S1RESS NOOE BREAK POINT ANO RES'IRAINT LOCA110N AGURE 3.89-48-1 PROB. 1-138 | |||
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AMENDMENT 80 I NOVEMBER 30, 1990 I -<ti" I COMANCHE PEAK S. E. S. | |||
t FINAL SAFETY ANALYSIS REPORT I UNIT 1 I SAFETY INJECTION SYSTEM I INSIDE CONTAINMENT SlRESS NOD£ BREAK POINT J. AND RES1RAINT LOCA110N FIGURE 3.88-48-2 PROB. 1-13A | |||
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FINAL SAFETY ANALYSJS REPORT UNIT 1 SAF£TY INJEC'TION S'1STEM OUlSIDE CONTAINMENT STRESS NOOE BREAK POINT AMENDMENT 76 AND RESlRAINT LOCA110N MAY 1, 1989 FlGURE 3.68--56 PROB. 1-51A | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 SAffTY INJECTION S't'SlEM INSIDE CONTAINMENT S1RESS NOOE BREAK POINT AMENDMENT 76 AND REl>IRAINT LOCAllON MAY 1, 1989 FIGURE 3.68-57-2 PROB. 1-146 | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 AMENDMENT 78 JANUARY 15, 1990 FIGURE 3.68-59-1 PROB. 1-135A | |||
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FINAL SAFETY ANALYSIS REPORT 0 STRESSNCDEl'a!IT UNIT 1 | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 AUXILIARY STEAM SYSTEM AUX. BUILDING STRESS NOOE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCATION MAY 1, 1989 flGURE 3.68-61-2 PROB. 1-147E | |||
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FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYSTEM OUTSIDE CONTAINMENT SlRESS NODE BREAK POINT AND RESlRAINT LOCATION FIGURE J.6B-82-1 PROB. 1-46A | |||
x~ | |||
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: j. ~~"t-lJ llUl.f'ER RES1IWNT AMENDMENT 76 MAY 1, 1989 | |||
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LEGEND 0 S'IR£SSNODEPOINT C) QRllUllF'ER£JfllA AND/OR UH:ll'llJlllNAlllll£N( | |||
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~ BUMPfR ll£l!'lRAM | |||
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~ll' FINAL SAFETY ANAL YSJS REPORT I .... ~~~"< | |||
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UNIT I' ... ,'Y eves S'iS1EM OUTSIDE CONTAINMENT AMENDMENT 76 S1RESS NODE BREAK POINT AND RES1RAINT LOCATION MAY 1, 1989 f1GURE 3,6!iH32-3 PRO!'!. 1-N068 | |||
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..y LEGEND 0 SlftEllNllDEPOINT C) ~-/'111 UlNGl'1UDINAl. lllQK COMANCHE PEAK S. E. S. | |||
FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYS1£M AUX. BUILDING STRESS NOOE BREAK POINT AMENDMENT 76 AND RES'IRAINT LOCA110N MAY 1, 1989 FlGURE 3.68-83 PROB. 1-51A | |||
xv ,,,,.. | |||
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--~ | |||
.......... Amendment 78 | |||
.......... "Y ~Nil/a' January 15, 1990 c:::> IJlNCl'MlllN..1111£N( | |||
690 lJ COMANCHE PEAK s. E. s. I FINAL SAFETY ANALYSIS REPORT UNIT 1 | |||
' FlGURE eves SYS1EM AUX. BUll..OING STRESS NOOE BREAK POINT AND RESTRAINT LOCATION 3..llB-64 PROB. 1-51B | |||
xv | |||
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~ANO/OR C) Wllll1\IDlllALBREAK lJ II-MR RESlRAlllT BUllP£l! RE!!'l!IAINT HNm RES'IRNNT COMANCHE PEAK S. E. S. | |||
FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYSTEM AUX. BUil.DiNG AMENDMENT 76 STRESS NODE BREAK POINT AND RESTRAINT LOCATION MAY 1, 1989 3.66-85 PROB. 1-51C | |||
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~ lJl<<lflUmw.- | |||
Lr ll-BAR RllSl'RAINT BUllPfl!RES'lltAINT | |||
,@ HARD RES!lWNT COMANCHE PEAK S. E. S. | |||
FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYSTEM AUX. BUILDING AMENDMENT 76 f:'::l.IE ON~,,,,, | |||
STRESS NOOE BREAK POINT AND RESlRAlNT LOCATION MAY 1, 1989 FlGURE 3.68-88 PROB. 1-510 | |||
x~ | |||
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riZ LEGEND 0 CIRCilll'!RENTW AHll/fJft C) l..CINGl1UDINAlllR£AK | |||
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~Er8 AMENDMENT 76 COMANCHE PEAK S. E. S. | |||
FINAL SAFETY ANALYSIS REPORT UNIT 1 eves S'l'S"TEM AUX. BUILDING STRESS NODE BREAK POINT | |||
~G- AND RESTRAINT LOCATION MAY 1, 1989 AGURE 3.68-87-1 PROB. 1-52X | |||
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LEGEND 0 | |||
c::> CIRMIF1'.llEN1INID/IJI IJlHGl'llJDINALl!AEAK | |||
~~ | |||
v.3,~ | |||
COMANCHE PEAK S. E. S. | |||
FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSTEM SAFEGUAROS BUILDING SIRESS NOOE BREAK POINT AMENDMENT 76 AND RES1RAINT LOCATION MAY 1, 1989 AGURE 3.68-87-2 PROB. 1-52Z | |||
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FINAL SAFETY ANALYSIS REPORT UNIT eves SYS'TEM SAFEGUARDS BUILDING S1RESS NOOE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCATION MAY 1, 1989 FIGURE 3.68-88-1 PROB. 1-52Y | |||
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FINAL SAFETY ANALYSIS REPORT UNIT eves SYSlEM SAFEGUARDS BUILDING STRESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCATION MAY 1, 1989 flGURE 3.68-88-2 PROB. 1-52Z | |||
. | N()Tfi.$: | ||
: 1. Break locations 4*RC*l-o18*2C,OIR* I l to 13 per Table i~~- ~c- I* oto*t~o11t-1 i | |||
N 3.6B-2. | |||
Foe cotJT. *et: fll<O- !>-~e.-~o | |||
: 2. Based on GDC-4, leak-before-break (Section 5.4.14) | |||
~ IO-Cf.:+02t- 2&0U::t *I the loop whip Rrll.C'Tt>flt COOV\NT , I P'U""'"'" .I' POii c.oN'T. S.L.. | |||
FWii. 'S. '-& - 5Z restraints and non-Tax- RC"'C',..C-01 , "17f"I ) crushab le insulati are not required . | |||
btr.\1l . | |||
.<\' | |||
... ~. ~-C:.9*7~ | |||
Slt"-M | |||
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r.-.. ~ l.- | |||
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. "'c;.e.c:;,., | |||
" | ~EEfl'IG.;;.. '\ | ||
'L 007-s="Ollll! C'Cl"'T* 61.f. | |||
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(!)*SEE MOrE ~ | |||
l _ _ _ _ _ __ | |||
UNITS I .-id 2 REACTOR COOlAHT LOOP I l AMENDMENT 76 STRESS MODE ' BREAIC POINT uo pEsTp*tMT 1oc1T1cw5 MAY 1, 1989 'l'lJllW: 3.68-89 !LOOP I l l | |||
. | |||
.. | |||
.. | |||
- | |||
I | |||
I | |||
NOTE<;,: | |||
: 1. Break locations 1 to 13 per Table 3.6B-2. | |||
~ | |||
: 2. Based on GDC-4, leak-before-break (Section 5.4.14) the loop whip restraints are not required. | |||
N | |||
~E,...CTOR ----4 COOLA.'-lT PUM~ " - - - - ll!'C-2''501R-I T&lC..- F(CP'C P'C-Ot 'Z't~l D. Plfl'I! (1:\ctt LECO) | |||
R'C- 2'501 ~- l e.t 1.0.... U"'E ( C'l!'O!l>*ovt:") | |||
I | |||
~~ 'Z-ec-t-O'l!>:*a ""'G- ~-~*-Go* | |||
J..., | |||
'Ollt.-I RllA..C'TOR S:Ollt co ""I', T**-ec.-cev LE:-GEUD CD* 5EE NOTE COMANCHE PE AIC S E S fllW. SAFETY NIW..YSIS AEf'QU UNITS 1-.ct 2 AMENDMENT 76 REACTOR COOi.ANT LOOP I l MAY 1, 1989 STRESS NODE ' BREAJI: POINT a,n BESTp*tNT *tr*TtQNS ftarl l.6B-90 (LOOP 12t | |||
~: | |||
: 1. Break locations 1 to 13 per Table 3.6B-2. | |||
~ | |||
: 2. Based on GDC-4, leak-before-break (Section 5.4.14) the loop whip restraints are not required. | |||
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--7 1~1- RC-1*0~7- t!)OtR-1 r:o" COt..tf1'KIC F1c, ?>-C.&*SI FICO,. ~-~&-4., | |||
RE"-Ctowe. COOt.a..'-IT PuMfl' Ta'll..- lite PC l"'C'*O... | |||
sa DllTAIL .... i:.ico. 1.Go l't -e., | |||
llltC-'l~OUt*I '27-!> U>. 1"'11"'1!:' | |||
( C:.01...0 La C,) | |||
~E....:.-,.olll T&l<.- lite: .. c:: c '1 lH*\""I) COMANCHE PE AK S E S FtW. SNETY ANN.YSIS ~POOT CD | |||
* SEE NOTE t AMENDMENT 76 UNITS 1 and 2 | |||
-------1 REACTOR COOLANT LOOP IJ MAY 1, 1989 STRESS NOOE ' B~EA~ POINT AND Rf.'STRAINT IOCATl()NS F~ l.68 | |||
* 91 (LOOP tJ | |||
' | |||
* | |||
... , | |||
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"'°"' | |||
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- | COIJT. St:E. F 14 !.. '-&* '-& FOR! co....T !>E.l MOTli!i.* | ||
F*<i ~ c..e-51 Break locations | |||
!!> | |||
* RC-1-0lli>-ZS01"-1 ~ | |||
FO~ co...aT. &E-E 1=14. ?>.G.&- l!!:> 1 to 13 per Table 3.6B-2. | |||
N 10.Rc- 1-o'le-*zt;ou~-1 -- | |||
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' / | |||
leak-before-break (Section 5.4.14) the loo whip restraints I I SliE OllTM.. .... | |||
are not required | |||
~ | |||
* | |||
.... | |||
l | |||
: 1 | |||
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y s::o" co,...T &&. e. | |||
~OA CONT 'SU F"i S:-1~. ~ "8* .. | |||
*04 I _........-Z*trC-l*O"lf*2'5011il-1 y s::o" co,...T &&. e. | '!.'" 1!1- '-4 ll'.CUi,t..10 CD - S&I: NOT~ 1 COMANCHE PE AK S E S Ftw.. SAFETY ANALYSIS REPOOT UNITS 1 and 2 AMENDMENT 76 llf:l\CTOR COOLANT LOOP I 4 MAY 1, 1989 STRESS NOOE &. 81'.EAJ< POINT ANO RESTRAINT !QC&TIONS flilft l.f>B-'12 11.00P 141 | ||
!QC&TIONS flilft l.f>B-'12 11.00P 141 CPSES/FSAR Figure 3.66-93-1 This figure has been deleted. Amendment 87 December 18, 1992 CPSES/FSAR Figure 3.68-93-2 This figure has been deleted. Amendment 87 December 18, 1992 CPSES/FSAR Figure 3.68-94 This figure has been deleted. Amendment 87 December 18, 1992 CPSES/FSAR Figure 3.68-95 This figure has been deleted. Amendment 87 December 18, 1992 REG | CPSES/FSAR Figure 3.66-93-1 This figure has been deleted. | ||
__ ..____._-+---"-_ | Amendment 87 December 18, 1992 | ||
Le La Amendment 71 May 27 1 1988 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 LONGITUDINAL PIPE BREAK JET CONE FIGURE 3.68-968 Le L | |||
CPSES/FSAR Figure 3.68-93-2 This figure has been deleted. | |||
Amendment 87 December 18, 1992 | |||
I I '" "" L. I I J. ---L. --L -"j ' 4l' .L. _1 -I r"' | CPSES/FSAR Figure 3.68-94 This figure has been deleted. | ||
l I I I I ..... I 1.0 + (fl/De) | Amendment 87 December 18, 1992 | ||
CPSES/FSAR Figure 3.68-95 This figure has been deleted. | |||
Amendment 87 December 18, 1992 | |||
PLANE AT END OF JET CORE ASYMPTOTIC PLA,NE REGION 3 REG I0 N 2 ---o-t--t-i REGION 1 1o* | |||
Da JET CORE BREAK PLANE Le__....,......_, | |||
La ----i---~ | |||
L Amendment 71 May 27, 1988 COMANCHE PEAK S. S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPARATION JET CONE FIGURE 3.68-96A | |||
n z | |||
0 0 | |||
w 0::: | |||
PLANE AT END ASYMPTOTIC PLANE OF JET CORE | |||
/BREAK PLANE | |||
-+---~--"'------~ __..____._-+---"-_ | |||
REGION 2 REGION Le La Amendment 71 May 27 1 1988 COMANCHE PEAK S.E.S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 LONGITUDINAL PIPE BREAK JET CONE FIGURE 3.68-968 | |||
Le Dj L | |||
Amendment 71 May 27, 1988 COMANCHE PEAK S.E.S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 JET CORE REGION GEOMETRY FOR A CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPERATION FIGURE 3.6B-96C | |||
I* | |||
.... 80 ----L----~---L--L-.l-.l-L~-1 I I I I I 1u 11. | |||
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1oo*r Veuel Subcoo~1n1 1 | |||
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-*.i I I | |||
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Po*IOOO paia Po*JOO pd~ | |||
I I I | |||
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*"" I I ' " "" L. I I 20 J. - - - L. - - L - "j ' 4l' .L. _1 - I r"' ....._~ l I I 1'~1 I I ~ ..... | |||
I 1 10 1.0 + (fl/De) | |||
COMANCHE PEAK S.E.S. | |||
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 EFFECT OF IRREVERSIBLE LOSSES ON JET SUBCOOLING AMENDMENT 76 MAY 1, 1989 FIGURE 3,6B-96n}} |
Latest revision as of 20:19, 24 February 2020
ML16180A441 | |
Person / Time | |
---|---|
Site: | Comanche Peak |
Issue date: | 02/01/2016 |
From: | Luminant Generation Co |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML16042A346 | List: |
References | |
txx-16006, CP-20160003 | |
Download: ML16180A441 (136) | |
Text
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- 3. DIESEL BLDG.
- 4. SAFEGUARDS BLDG. COMANCHE PEAK S. E.S.
- 5. AUXILIARY BLDG. FINAL SAFETY ANALYSIS REPORT
- 6. SWITCHGEAR BLDG. UNITS 1 and 2
- 7. ELECTRICAL 8 CONTROL BLDG.
T~RBINE MISSILE STRIKE
- 8. TURBINE BLOG. ZONE - PLAN VIEW FIGURE 3. 5- 3
SUPPORTISTRUCTURE BRACKET PIN- COTTER PIN SADDLE SADDLE CLAMP {TYP. 3 PLACES) SIDE VIEW CROSS SECTION COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 11 TYPICAL U-BAR JULY 31, 1980 RESTRAINT FIGURE 3. 6B-l
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EXCLUSION UNITS 1 AND 2 PROCESS FORG THREADED PIPE FLANGE (BQL TEO J AR TYPICAL MOMENT RESTRAINT AND BREAK EXCLUSION AREA BOUNDARY TO STRUCTURE) 051588067 FIGURE 3.68-5
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I DISPLACEMENT RESTRAINT STIFFNESS F EFFECTIVE IMPACT MASS LL. I-I.fl a:: I I-Tl ME SLOWDOWN THRUST-TIME HISTORY COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 RESTRAINT IMPACT FIGURE 3. 6B-8
~ DENOTES BREAK LOCATION PLAN VIEW STEAM GENERATOR REACTOR PRESSURE VESSEL ELEVATION NOTE: 1. Postulated main reactor coolant loop break locations 1 through 8 and branch nozzle breaks 9 through 11 are consid ered for containment design, ECCS and enviornmental qualification. These breaks are not postulated for dyn amic effects.
(Sections 3.68.2.1.1 and 3.63.2.1.2)
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to the largest RC L postulated breaks after application of LBB to selected l ines. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 76 MAY l, 1989 Location of Postulated Breaks in Main Reactor Coolant Loop FIGURE 3. 68-9
i+026-i+91 CASE I OUTGOING LINES WITH MORMALLY CLOSED VALVE ( REACTOR COOLANT PIPING
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'~l . . . l" LEGEND FINAL SAFETY ANAL YSlS REPORT UNIT 1 0 STRESS NODE POINT eves SYSiEM INSIDE CONTAINMENT C1RCUMFERamAI.. ANt>/aR C) L.OtlGl'IUDIHAI. BflEAK S1RESS NOOE BREAK POINT AND RESTRAINT LOCATION flGURE 3.BB-74 PROB. 1-430/C .ti: 1-<4-30
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CPSES/FSAR Figure 3.66-93-1 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-93-2 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-94 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-95 This figure has been deleted. Amendment 87 December 18, 1992
PLANE AT END OF JET CORE ASYMPTOTIC PLA,NE REGION 3 REG I0 N 2 ---o-t--t-i REGION 1 1o* Da JET CORE BREAK PLANE Le__....,......_, La ----i---~ L Amendment 71 May 27, 1988 COMANCHE PEAK S. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPARATION JET CONE FIGURE 3.68-96A
n z 0 0 w 0::: PLANE AT END ASYMPTOTIC PLANE OF JET CORE
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REGION 2 REGION Le La Amendment 71 May 27 1 1988 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 LONGITUDINAL PIPE BREAK JET CONE FIGURE 3.68-968
Le Dj L Amendment 71 May 27, 1988 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 JET CORE REGION GEOMETRY FOR A CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPERATION FIGURE 3.6B-96C
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