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To Evaluation of Effects of Postulated Pipe Failures Outside Containment for McGuire Nuclear Station
	ML20039D708
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/21/1981
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20039C073	List: ML20039C072; ML20039D708;
References
	MDS-PDG-77-1, MDS-PDG-77-1-R05, MDS-PDG-77-1-R5, NUDOCS 8201060038
	Download: ML20039D708 (50)
	v • d • e

EVALUATION OF THE EFFECTS OF POSTULATED PIPE FAILURES OUTSIDE CONTAINMENT FOR MCGUIRE NUCLEAR STATION Revision 5 December 21, 1981 Remove and insert pages in accordance with the following tabulations:

Recove These Pages:

Insert These Pages:

Cover Sheet Cover Sheet List of Figures List of Figures Figure 3.10 (3 of 4)

Figure 3.10 (3 of 4)

Figure 3.10 (4 of 4)

Figure 3.11 (5 of 8)

Figure 3.11 (7 of 8)

Figure 3.12 (1 of 6) thru (6 of 6)

Figure 3.12 (1 of 12) thru (12 of 12)

Figure 3.15 (5 of 9)

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Figure 3.16 (1 of 3) thru (3 of 3)

Figure 3.16 (1 of 13) thru (13 of 13)

Figure 3.17 (1 of 5) thru 5 of 5)

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Table 6-1 (1 of 19) thru (19 of 19)

Table 6-2 (1 of 6)

Table 6-2 Sheet (1 of 6) Deleted Table 6-2 (2 of 6)

Table 6-2 (2 of 6)

Table C-1 Table C-1 Table C-3 Table C-3 8201060038 811221 PDR ADOCK 05000 K

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Revision 3 11-05-80 i

Revision 4 1-26-31 Revision 5 12-21-81

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LIST OF FIGURES Figure Sunber Title 2-1 McGuire Nuclear Station, Key Plan 2-2 Compartment Locations, Elevations 695 and 736 2-3 Compartment Locations, Elevation 716 2-4 Compartment Locations, Elevation 733 2-5 Compartment Locations, Elevatica 750 2-6 Compartment Locations, Elevation 767 3-1 Flow Diagrammatic, Steam Generator Blowdown System - BB 3-2 Flow Diagrammatic, Auxiliary Feedwater System - CA 3-3 Flow Diagrammatic, Feedwater System - CF 3-4 Flow Diagrammatic, Safety injection Sptem - Nr 3-5 Flow Diagrammatic, Boron Thermal Regeneration System - NR 3-6 Flow Diagrammatic, Chemical & Volume Control System - NV

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3-7 Flow Diagrammatic, Main Steam Supply to Auxiliary Equipment - SA 3-8 Flow Diagrannatic, Main Steam System - SM 3-10 Piping Layout, Steam Generator Blowdown System 3-11 Piping Layout, Auxiliary Feedwater System (See Figure 3-12 also) 3-12 Piping Layout, Feedwater System 3-13 Piping Layout, Safety injection System (Upper Head Portion) 3-14 Piping Layout, Boron Thermal Regeneration System 3-15 Piping Layout, Chemical & Volume Control System 3-16 Piping Layout, Main Steem System and Main Steam to Auxiliary Equipment 5

3-17 Piping layout, Main Steam Vent to Atmosphere 4-1 Logic Symbols 4-2 Main Turbi,e Trip Logic Diagram 4-3 Start / Trip Logic Diagram for Main and Auxiliary Feedwater Pumps 4-4 Reactor Trip Logic Diagram 4-5 Reactor Coolant Pump Start / Trip and Main Steam isolation Valve Logic Diagram

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m.tv. PCS'ILT.NED PEEAKS IN THE SV SYSTE4 FIGURE 3.17 l SHErr 5 CF 5 REV. 5 N 4= -Wu.h*67 ~ * - = ---U-y -w--Mg.y++p-e-e+w--w-g v y+-+--e i.,isywe-e w y* m-g-4-e., .ymy-ywwr-o,--e.~--e--W--4w-*------ww--,eeww~-- - - - * - ' ' - -Ntr*.--
V each postulated break to assure that essential structures and components are not damaged. Only circumferential breaks are postulated since the stress at all locations is less than 0.3 (1.2Sh+S). It should be noted that the A main steam and feedwater penetrations are free floating and do not constitute an anchor. Figure 6-1 shows the main steam system isometric drawings. Typical guard pipe to f process pipe internal restraints are shown in Figure 6-2. Energy absorber and rigid pipe rupture restraints are shown in Figures 6-3 and Figure 6-4. Feedwater break locations are chosen at those locations shown 5 on Figure 3.12 based on high stress points and consequences (See FSAR Table 3.6.5-1)i only circumferential breaks are ) postulated since the stresses are less than 0.8 (1.2Sh*3} A at all locations. Pipe rupture restraints are provided for all postulated feedwater breaks to assure that essential components and structJres are not damaged. 6.1.2 Steam Generator B1cwden Svstem The high energy portion of the blowdown system consists of one blowdown line per steam generator entering the Auxiliary Building in the Elevation 716/733 penetration room and exiting to the Turbine Building (see figures 3.1 and 3.10). Only circumferential breaks are postulated since the piping is of seamless construction 3 and the stresses are less than 0.8 (1.2Sh + S ) at all locations *. A 5 d 3 In Section AB 716-07 only one intermediate break location is shown for 2 of the four lines because of the low stress levels. 6-2 Revision 5 ~ ~~~ ~ ~ ' ~ ~ ~ ~ ~ ~ p =*-Ntr7-tw
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%{ 5 6.1.3 Auxiliary Feedwater System The high energy portion of this systen consists of the Motor Driven Auxiliary Feedwater Pump 1A and 18 discharges 3 frcm the pumps at Elevation 716 (room 716-10 on Figure 2-3) to the main feedwater lines in the doghouse (rooms 750-23 3l and -26, Figure 2-5). The flow diagransnatic is shown in Figure 3.2 and the piping layout is shown on Figure 3.11 and 3.12. The Turbine Driven Pump is considered moderate energy since it will only be used for emergency or testing conditions. ' The stress levels in the system are less than 0.8. (1.2S # h A O and seamless piping is used. As a result, only circumferential (j ' - breaks are postulated. 3 A review of the potential consequences resulting from Dice whio and Jet impingement indicates pipe whlo restraint and jet im-pingement barriers are required for postulated. breaks cal-51 and CA1-70A to protect essential electric equipment. 6.1.4 Safety iniection Svstem (Upper Head) The high energy portion of the Safety injection System consists of the Upper Head injection Accumulator Tanks and cennecting piping. The flow diagrannatic is gl. yen in Figure 3.4. sheet 2 and the piping layout is shown on Figure 3.13 The stresses at h * $ ) and seamless piping all locations are less than 0.f+ (1.2S A ( Is used; therefore, only circumferential terminal end breaks are v postulated. Revision 5 g ~ _ -.... ~..
O ( in the letdown line, breaks are postulated to occur at the I terminal ends and at the only two locations where stress levels 3 in excess of 0.4 (1.2Sh* A occur. Only circumferential breaks are postulated since h + S ) at all the stress levels are less than 0.8 (1.2S A locations. The pipe whip and jet Impingement evaluation shows that damage to electrical cables, containment spray piping and/or nuclear service water piping is possible due to 5 break Hvi-07.. A pipe whip restraint will be pro-vided to preclude this dimage. 6.1.7 Main Stean Sucolv to Auxillarv Equipment - SA The high energy portion of the SA System consists of the piping from main steam headers B and C to the normally closed pisten operated valves. Figure 3.7 shows the flow diagrams for the system wi. 1e Figure 3.16 shows the piping configuration. Circumferential pipe breaks are postulated at the terminal ends and at the highest stressed intermediate locations in the seamless 3 piping. All other stresses in the high energy portion are less than C.4 (1.2S ^$). The p'rpe whip and jet evaluatio* indicate h A that no unacceptable damage would occur fer the:e breaks. 6.2 Compartment Pressurization Effects The only breaks outside centainment that result in significant differential pressures are the main steam and feedwater systems which are located in the doghouse areas. Inside the Auxiliary Bulld-Ing, the venting through HVAC ducts, hallways and doors prevent excessive pressure differentials from occuring. I 6.2.1 Main Steam and Feedwater y 1 Main steam and feedwater breaks in the 4cgh ase were reviewed i for pressurization effects using the TMD Code (see Section Revision 5 64 ~~ '~^ ^^i- - --r 1 -.-' - - ~
Sgs (vD TABLE 6-1 5 llIGil ENERGY PIPE BREAK LOCATION Sheet 1 of 19 Break Stress Ratio to Number System Description Fig. No. Location Allowable (1) l B81-01 Steam Gen. 4" BB Blowdown "lA" T.E. 0 3.10 AB-716-07 Terminal End Break l Blowdown M-300 Sheet l Recycle Sys. 3 of 4 3 BB1-02 Steam Gen. 4" BB Blowdown "lB" T.E. 0 3.10 AB-733-06 Terminal End Break Blowdown M-301 Sheet Recycle Sys. 3 of 4 BB1-03 Steam tien. 4" BB Blowdown "lC" T.E. 0 3.10 AB-733-06 Terminal End Break Blowdown M-303 Sheet Recycle Sys. 3 of 4 881-04 Steam Gen. 4" BB Blowdown "lD" T.E. 0 3.10 AB-716-07 Terminal End Break Blowdown 11-304 Sheet Recycle Sys. 3 of 4 881-36B Steam Gen. 2" Intennediate break 0 3.10 AB-733 OG 0.56 Blowdown inlet of 2nd tee downstream Sheet Recycle Sys. of valve IBB3B 3 of 4 I BB1-278 Steam Gen. 2" Intennediate break 01st 3.10 AB-733-06 0.65 Blowdown standard elbow downstream Sheet Recycle Sys. of M-301 3 of 4 l 5 BB1-28 Steam Gen. 2" Intennediate break 0 3.10 AB-733-13 0.64 Blowdown inlet of 1st tee downstream Sheet Recycle Sys. of valve 18832 4 of 4 l 881-35 Steam Gen. 2" Intermediate break 0 3.10 AB-733-13 0.66 Blowdown inlet of lst tee downstream ' Sheet Recycle Sys, of valve 18B29 4 of 4 (1) Ratio = Stress, S/(0.8 (1.2Sh + S )); intermediate breaks only A Revision 5 0 4.
y O O O TABLE 6-1 HIGH ENERGY PIPE. BREAK LOCATION Sheet 2 of 19 i' BREAK STRESS RATIO TO NO. SYSTEM DESCRIPTION FIG. NO. LOCATION ALLOWABLE (1) b B81-445 Steam Gen. 2" Intermediate break at 3.10 AB-733-06 .847 blowdown inlet of first tee downstream Sheet recycle sys, of valve IBB1B 3 of 4 t' i B81-100 Steam Gen. 2" intermediate break at 3.10 AB-733.06 .605 blowdown inlet of 4" x 2" reducer Sheet 21 recycle sys. downstream from IBB3B 3 of 4. I B81-104 Steam Gen. 2" Intermediate break at inlet 3.10 AB-733-05 .699 blowdown of first standard elbow Sheet recycle sys. downstream from H304 3 of 4 BB1-301A Steam Gen. 2" intermediate break at 3.10 AB-733-06 927 i blowdown inlet of 4 " x 2" reducer Sheet j' recycle sys. downstream from valve 1BB4B 3 of 4 .i 881-998 Steam Gen. 2" terminal end break at 3.10 AD-733-13 Terminal End blowdown blowdown HX nozzle Sheet Break recycle sys. 4 of 4 1 i l i a l' Revision 5 Entire Page Revised \\
I 3 TA 6-1 tilGil ENERGY PIPE BREAK LOCATION BREAK STRESS RATIO TO NO. SYSTEM DESCRIPTION FIG. NO. LOCATION ALLOWABLE (1) cal-43A Auxiliary Inlet of elbow downstream of valve 3.11A AB-750-23 .853 Feedwater ICF135A f cal-43B Auxiliary Outlet of. elbow downstream of valve 3.11A AB-750-23 .901 i Feedwater ICF135A 5 l C A l-51 Auxiilary At 4" x 2" half coupling downstream 3.11 AB-750-23 .886 Feedwater of valve ICF136A Sheet 5 of 8 cal-50 Auxiliary At 6" takeoff from 18" CF line 3.11 AB-750-23 Terminal End Break Feedwater between valves ICF119 and ICF28 -Sheet 5 of 8 l cal-87 Auxiliary Terminal end at 6" takeoff from 3.11 AB-750 23 Terminal End Break Feedwater 16" x 16" x 6" tee between the Sheet 4 ' valves ICF30 and ICF120 5 of 8 3 cal-96 Auxiliary Terminal end at 6" takeoff from 3 11 AB-750-23 Terminal End Break Feedwater 18" x-18" x 6" tee downstream of Sheet I vhlve.1CF135A 5 of 8
n cal-62 Auxiliary Terminal end at 6" takeoff from 3.11 AB-750-23 Terminal End Break E
Feedwater 18" x 18" x 6" tee downstream of Sheet I valve ICF136A 5 of 8 o (1) Ratio = Stress, S/[0.8(1.2 Sh + SA)); intermediate breaks only. (2) Stress is less than 0.4(1.2 Sh + SA). 1.
T. 6-1 5 Sheet 4 of 1.9 HIGH ENERGY PIPE BREAK LOCATION BREAK SIRESS RATIO T0 i NO. SYSTEM DESCRIPTION FIG. NO. LOCATION ALLOWABLE (1) CA1-113 Auxiliary Terminal end at motor driven FDW pump 3.11 AB-716-10 Terminal End Break Feedwater IA discharge Sheet 6 of 8 cal-126 Auxiliary Terminal end at motor driven FDW pump 3.11 AB-716-10 Terminal End Break 7 Feedwater 18 discharge Sheet 6 of 8 CA1-70A Auxiliary Intermediate break at inlet of elbow 3.11 AB-750-26 0 966 Feedwater downstream of valve ICF158 Sheet 8 of 8 CA1-70B Auxiliary Intermediate break at outlet of elbow 3.11 AB-750-26 0.990 Feedwater downstream of valve ICF158 Sheet 8 of 8 CA1-110 Auxiliary Terminal end at 6" takeoff from 18" 3.11 AB-750-26 Terminal End Break Feedwater CF line upstream of valve ICF160 Sheet 3 4 of 8 CA1-120 Auxiliary Terminal end at 6" takeoff from 3.11 AB-750-26 Terminal End Break Feedwater 16" x 16" x 6" tee downstream of Shee* valve ICF134A 4 of 8 CA1-109 Auxiliary Terminal end at 6" takeoff from 3.11 AB-750-26 Terminal End Break Feedwater 18" CF line upstream of valve ICF163 Sheet i 4 of 8 CA1-150 Auxiliary Terminal end at 6" takeoff from 3.11 AB-750-26 Terminal End Break Feedwater 16" x 16" x 6" tee downstream of Sheet valve ICF137A 4 of 8 5 CA1-28B Auxiliary At outlet of first elbow downstream 3.11 AB-750-23 766 Feedwater of valve ICF136A Sheet 5 of 8
o (1) Ratio e Stress, S/ 0.8(1.2 Sh + SA)

intermediate breaks only.
{ (2) Stress is less than 0.4(1.2 Sh + SA). m \\ t,
\\. "'( / Sheet 5 ofl9 TABLE 6-1 tilGH EllERGY PIPE BREAK LOCATIOf(S yRE R BREAK tJUMBER SYSTEM DESCRIPTl0tl FIGURE t10. LOCATI0tl f CF1-01 Feedwater @0utlet of first cibow Fig. 3.12 AB-750-2 3 .447 before penet. H-262 Sht. I of'12 ) CFI-02 reedwater @ inlet of first elbow Fig. 3.12 AB-750-23 <0.408 before penet. M-262 Sht. I of 12 CF1-03 icedwater @0utlet of first elbow Fig. 3.12 AB-750-23 0.467 before pene. M-308 Sht. I of 12 7eedwater @ inlet of first elbow Fig. 3.12 AB-750-23 0.529 l CF1-04 before penet. H-308 Sht. I of 12 eedwater 60utletof first elbow Fig. 3.12 AB-750-26 <0.408 i r CFI-05 I before penet. M-153 Sht. I of 12 i CFI-06 Feedwater @lniet of first elbow F i c,. 3.12 AB-750-26 <0.408 before penet. M-153 Sht. I of 12 CF1-07 feedwater @0utlet of first cibow Fig. 3.12 AB-750-26 0.451 before penet. M-440 Sht. 1 of 12 ) CF1-08 Feedwater @ Inlet of first elbow Fio. 3.12 AB-750 26 <0.408 before penet. H-440 Sht. I of 12 3 l l (1) Rat io = St ress, S/ I.0.8 (1.2Sh + S )); intermediate breaks only A (2) Stresses at all locations in the piping run are less than 0.4 (1.25 + 5 ). Revision 5 Entire Page Revised \\
im p] m Sheet 6 of 19 5 TABLE 6-1 j lilGli EtlERGY PIPE BREAK LOCATI0flS i BREAK flVMBER SYSTEM DESCRIPTI0tt FIGURE fl0. LOCATI0fl STRESS RATIO TO ALLOWABLE (1) 3 CF1-09 Feedwa ter 18" CF to steam See Turbine TB-739 Terminal End generator lA 0 Building Break j feedwater header CF1-10 Feedwater 18" CF to steam See Turbine TB-739 Terminal End l generator 18 0 Building Break feedwater header 4 l CF1-ll Feedwater 18" CF to steam See Turbine TB-739 Tenninal End j generator 100 Building Break i feedwater header CF1-12 Feedwater 18" CF to steam See Turbine TB-739 Terminal End generator ID 0 Building Break feedwater header 5 CF1-13 Feedwater Breaks located 0 all. 3.12 AB-750-23 fio Rigorous thru fittings in 2" and 4" Sheets AB-750-26 Stress Analysis CF1-54 CF lines upstream 7-12 Perfonned from valves ICF 154 1CF 156, ICF 158, ICF 152 in the Doghouses. l l (1) Ratio = Stress, S/(0.8 (1.2Sh
b )); internediate breaks only A
(2) Stresses at all locations in the piping run are less than 0.4 (1.2Sh+S) A 1 Revision S \\
5 Sheet 7 of 19 l TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS TR R 0 BREAK NUMBER SYSTEM DESCRIPTION FIGURE tiO. LOCATION g. ) Nil-01 Safety injection 12" NI-T.E. Brk. @ upper 3.13 AB-750-01 Terminal End head injection nitrogen Break accumulator (2)' Nil-02 Safety injection 12" N I-T.E. B r k. @ Pene t. 3.13 AB-750-01 Terminal End M-334 Break (2) i, Nil-03 Safety injection 12" ti l-T. E. B r k. 9 Pene t. 3.13 AB-750-01 Terminal End M-349 Break (2) Nil-04 Safety injection 12" NI-From Vill nitrogen 3.13 AB-750-05 Terminal End accumulator to water Break (2) accumulator, T.E. Brk. O upper head inj. water accur 1 Nil-05 safety injection 12" Ni-To Valve INI244B. 3.13 AB-750-05 Terminal End T.E. Brk. @ upper Head inj Break (2) 3 water accumulator. Nil-06 Safety injection 12" NI-To Valve INI242B. 3.13 AB-750-05 Term inal End ) T.E. Br k. @ upper head inj Break (2) water accumulator. Nil-07 Safety injection li"NI-To Viv. INI326. T.E. 3.13 AB-750-05 Terminal End brk G water accumulator. Break (2) (1) Rat h = St ress, S/ (0.8 (1.25 + S )); intermediate breaks only. A (2) r.es at all locations in the piping run are less than 0.4 (l.2Sh*S)* A Revisions \\ l.
i ;i
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O1) T( E OL d d I B n n TA E) E) 9 AV 2 2 l ( l ( RO 1 L a a nk nk f SL ime me n a 5 o SA a i E 8 R r r r r o T eB eB i t S T T s e i e v h e S R NO I 5 5 T 0 0 A C 0 0 O 5 5 L 7 7 B B A A A h S O N 2 3 3 1 E y ( 1 1 R l U 3 3 n 4 G I o 0 F s k n S a a N j e h O n r t I u b T i m s A .d u e s C 0 a 4 c t e O c a l 2 e 1 L 3H 3A i d e K 1 1 1 N r r N r e r - A I e m a eo I 6E pt t r R N epa ea e n EB O vUl vW t u L I n r u l l BE T m v@ TI I a@u a i AP P v gn .c P R ok c ok ) i C T rA Tr ) p Y S B B A i G E l r I S p R D i \\ .e N t e E E. t E. h N a E 2TW 2T h t S H n 2 G i I n n 1 H o o ( sn i i 8 o t t c c i e e 0 t M j j ( a n c E n i / o T i S S l Y y y S t t l e e s l f f s a a a e S S r t t a S R s E = e B s ~ M i e o s U 2 3 1 1 t r N a t K R S l l A i i E N N R '2 B 1 5 3 3 ~ ~ l 1 .lI;I!. i ll;
a... ! o O c0 0 4 5 Sheet 9 of 19 f TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS BfE (1) BREAK NUMBFR SYSTEM DESCRIPTION FIGURE NO. LOCATION L a Nil-16 Safety injection 1)" HI To valve IN1280. 3.13 AB-750-01 Terninal End T.E. Brk. @ taitrogen Break (2) Accumulator. i l Nil-17 Safety injection 2" NI To valve int 2558. 3.1-3 AB-750-05 Termiru l End T.E. Brk. # 12" Hi Line Break (2) Hil-18 Safety injection li" To valve IN1279. T.E. 3.13 AB-750-05 Terminal'End l brk. @ Water Accumulator. Break (2) l i ) W (1) Rat io - St ress, S/ (0.8 (1.2Sh* A)); interraediate breaks only. (2) Stresses at all locations in the piping run are less than 0.4 (1.2Sh* A* Pevision 5 \\
Jl; e i 5 Sheet 10 of 19 TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS S ATIO TO BREAK NUMBER SYSTEM DESERIPTION FIGURE NO. LOCATION Alt 0WABLE (l) i NRI-01 Boron Thermal 4" NR to letdown reheat 3.14 A6-750-16 Te nninal End ) Regeneration Sys. H.X.-T.E. Brk. @ Inlet of Break (2) Letdown Reheat H.X. NRI-02 Boron Thermal 4" NR To letdown reheat 3.14 AB-750-16 Terminal End Regeneration Sys. H.X.-T.E. Brk. @ Outlet Break (2) of letdown reheat H X. l l 1 t
nterme ate breaks only.
(1) Rat io = St ress, S/ (0.8 (1.2Sh A (2) Stresses at all locations in the piping run are less than 0.4 (1.2Sh+SA* Revision 5
QO dO c) i I TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS Sheet 11 of 19 STR I BREAK NUMBER SYSTEM DESCRIPTION FIGUR$ NO. LOCATION AL 0 PL (1) NVI-01 Chemical and 3"NV -Letdown H.X. T.E. @ Fig. 3.15 AB-750-17 Terminal End ^ i Volune Control inlet of Letdown H X. Sht. 9 of 9 Break NVI-02 Chemical and 3" NV-F rom Letdown H.X., Fig. 3.15 AB-750-17 Terminal End Volume Control Outlet of Letdown H.X. Sht. 9 of 9 Break NVI-03 Chemical and 3" NV-To Regenerative H.X. Fig. 3.15 AB-716-06 Termina l End Volume Control T.E. B rk. @ Penet. M-329 Sht. 2 of 9 Break 4-i' l 5 i : NVI-07 Chemical and 3" NV to Letdown H.X. T.E Fig. 3.15 AB-750-01 Terminal End Volume Control Brk. ? M-347 Sht. 6 of 7 Break NVI-08 Chemical and T.E. Brk. @ Outlet of seal-Fig. 3.15 AB-733-il J Terminal End i Volume Control water inj. Filter IB Sheet 4 of 9 Break (2) h + S )); intermediate bre6ks only. (1) Ratio = Stress, S/ (0.8 (1.2S A (2) Stresses at all locations in the piping run are less than 0.4 (1.2Sh* A* 1 e s I Revision 5
~. ~-- - i i 5 Sheet 12 of 19 TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS a 1 i d BREAK UUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION LL E (1) NVI-09 Chemical and T.E. Brk. @ Inlet of seal-Fig. 3.15 AB-733-10 Terminal End Volume Control water inj. Filter "lA." Sht. 4 of 9 Break (2) NV'-10 Chemical and T.E. Brk. @ Outlet of seat Fig. 3.15 AB-733-10 Terminal End Volume Control water inj. Filter "lA." Sht. 4 of 9 Break (2) l HVI-il Chemical and T.E. Brk. @ inlet of Seal-Fig. 3,15 AB-733-Il Terminal End l Volume Control water inj. Filter "lB." Sht. 4 of 9 Break (2) -I' 5 NVl-13 Chemical and T.E. Brk. 0 Penetration Fig. 3.15 AB-733-7 Terminal End Volume Control M-339 4" dia. Sht. 5 of 9 Break (2) i i NVI-14 Chemical and T.E. Brk. O Penetration Fig. 3.15 AB-733-7 Terminal End Volume Control M-344 4" dia. Sht. 5 of 9 Break (2) 2 NVl-15 Chemical and T.E. Brk. O Penetration Fig. 3.15 AB-733-7 Terminal End i Volume Control M-343 4".dia. Sht. 2 of 9 Break (2) i NVI-16 Chemical and T.E. Brk. 9 Penetration Fig. 3.15 AB-733-7 Terminal End f Volume Control M-350 4"~dia.. Sht. 2 of 9 Break (2) HV1-17 Chemical and 2" Intermediate break at Fig. 3.15 AB-733-7 .632 l 3 Volume Control Inlet of 2nd elbow up-Sht. 5 of 9 5 stream of Penetration M-344 NV1-18 Chemical-and At 3" Tee Downstream of Fig. 3.15 AB-750-17 0.599 Volume Control Valve NV-121 Sht. 9 of 9 h + S )); intermediate breaks only. (1) Ratio = Stress, S/ (0.8 (1.2S A (2) Stresses at all 1ocations in the piping run are less than 0.4 (1.2Sh
S )*
A . Revision 5
5 Sheet 13 of 19 . TABLE 6-1 HIGH ENERGY PIPE DREAK 1.0 CAT 10NS S BREAK NUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION L LO'. AB sal-01 Main Steam Supply 6" SA To CA Turbine T.E brk fig. 3,16 AB-750-23 Terminal End 3SM Line IB Sht. 3 ofl3 Break 3 to Aux. Equip. sal-02 Main Steam Supply 6" SA To CA Turbine T.E. Fig. 3.16 AB-750-23 Terminal End to Aux. Equip. Brk. 3 Stt Line IC Sht. 3, ofl3 Break i 5 t I I l l (1) Rat io = S t ress, S/ (0.8 (1.2Sh
S )); intermediate breaks only.
A (2) Stresses at all lo' cat i ons in the piping run are less than 0.4 (1.2Sh*S} A Revision 5 {
1 4U TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS 1 i $E BREAK NUMBER SYSTEM OESCRIPTION FIGURE NO. LOCATION AL 0 B, (I) SMI-01 Main Steam inter. Brk. @ inlet ist(SM' Fig. 3.16 AB-750-23 0.284 elbow downstream of M-261 Sht. I ofl3 SMI-02 Ma i n d r ean inter. Brk. @ outlet ist Fig. 3.16 AB-750-23 0.378 (SM) elbow downstream of Sht. I ofl3 4 M-261 l SMI-03 Main Steam Inter. Brk. @ inlet 1st (Sil) F ig.116 AB-750-23 0.507 elbav downstream of M-393 Sht. I ofl3 j i SMI-04 Main Steam Inter. Brk. @ Outlet 1st Fig. 3.16 AB-750-23 0.531 (SM) elbow downst ream of Sht. I ofl3 M-393 i SMI-05 Main Steam Inter. Brk. @ inlet of is t Fig. 3.16 AB-750-26 0.282 (SM) elbow downst ream of Sht. I ofl3 M-154 SMI-06 Main Steam inter. Brk. G Outht ist Fig. 3.16 AB-750-26 0.374 (St) elbow downstream of Sheet I ofl3 M-154 SMI-07 Main Steam Inter. Brk. @ inlet of ist Fig. 3.16 AB-750-26 0.5 (SM) elbow downstream Sht. 1 ofl3 J M-441. (1) Rat io = St ress, S/ (0.8 (1.2Sh S )); intermediate breaks only. A (2) Stresses at all locations in the piping run are less tha.n 0.4 (1.2Sh*SA Revision 5 Entire Page Revised \\.. e ,w
r 1 5 Sheet l5 of 19 TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS i 1 ) BREAK NUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION TO At 04 Bt (1) SMI-08 Main Steam Inter. Brk. @ Outlet of Fig. 3.16 AB-750-26 0.522 5 ist (SM) elbow downst ream Sht. I ofl3 i of M-441. l j SMI-09 Main Steam 34" (SM) lA @ High Pressur e Turbine Bldg. TB-786 Terminal End j Turbine T.E. @ Inlet 6f Break L i H.P. Turbine SMI-10 Main steam 34" (SM) IB @ High Pressur e Turbine Bldg. '9-786 Terminal End Turbine T.E. Brk. @ Inlet Break of H.P. Turbine y I, ~ SMI-il Main Steam 34" (SM) IC @ High Pressur Turbine Bldg. TB-786 Terminal End Turbine. T.E. Brk. @ inlet Break g 1 of H. P. Turbine i SMI-12 Main Stecm 34" (SM) ID @ H.P. Turbine Turbine Bldg. TB-786 Terminal End i T.E. Brk. @ Inlet of H.P. Break l* Turbine. ') p I (1) Rat io = S t ress, S/ (0.8 (1.2Sh
S )); intermediate breaks only A
(2) Stresses at all locations in the piping run are less than 0.4 (1.2Sh*S)* A t i l l Revision 5 l \\.
f~') [y p ,I O L] l Sheet 16 of 19 TABLE 6-1 tilGH ENERGY PIPE BREAK LOCATIONS blRLb5 KAllU ~ BREAK NUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION TO ALLOWABLE (1) SM1-07A Main Steam 5" Terminal End @ Fig. 3.16 AB-750-26 Terminal End halve ISH7AB Sht. 9 of 13 Break SMI-07B Main Steam 2" Terminal End @ Fig. 3.16 AB-750-23 Terminal End Valve 1SMSAB Sht. 6 of 13 Break SMI-07C Main Steam 2" Terminal End @ Fig. 3.16 AB-750-23 Terminal End Valve 1SM3AB Sht. 5 of 13 Break SMI-07D Main Steam 2" Terminal End @ Fig. 3.16 AB-750-26 Terminal End Valve ISM 1AB Sht. 8 of 13 Break SM1-28A Main S: .a 2" Terminal End @ Fig. 3.16 AB-750-26 Terminal End Valve ISM 7AB Sht. 9 of 13 Break SM1-28B Main S.eam 2" Terminal End @ Fig. 3 16 AB-750-23 Terminal End Valve ISMSAB Sht. 6 of 13 Break SMI-28C Main Steam 2" Terminal End @ Fig. 3.16 AB-750-23 Terminal End Valve ISH3AB Sht. 5 of 13 Break SMI-28D Main Steam 2" Terminal End @ Fig. 3.16 AB-750-26 Terminal End Valve ISM 1AB Sht. 8 of 13 Break SMI-13A Main Steam 2" Intermediate Break Fig. 3.16 AB-750-26 .824 @ Valve ISM 19 Sht. 9 of 13 SMI-ISA Main Steam 2" Intermediate Break @ Fig. 3.16 AB-750-26 706 2" x 3" Reducer Down Sht. 9 of 13 stream from Valve i ISM 12AB Revision 5 New Page
O O O Sheet 17 of 19 f TABLE 6-1 HIGH ENERGY PIPE BREAK LOCATIONS I STRESS RATIO BREAK NUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION TO ALLOWABLE (1) SMI-31B Main Steam 2" Intermediate Break Fig. 3.16 AB-750-23 942 Downstream from Valve Sht. 6 Of 13 ISMSAB SM1-310 Main Steam 2" intermediate Break Fig. 3.16 AB-750 942 Downstream from Valve Sht. 5 of 13 ISM 3AB SM1-31D Main Steam 2" Intermediate Break Fig. 3 16 AB-750-26 .942 Downstream from Valve Sht. 8 of 13 ISM 1AB SM1-13 Main Steam Breaks Located @ all Fig. 3.16 AB-750-23 No Rigorous Thru Fittings in High Energy Sht. 10 of 13 AB-750-26 Stress Analysis SMI-86 Portions of Steam Performed Drain Piping SV1-1A Main Steam Vent 6" Terminal End Break @ Fig. 3.17 AB-750-26 Terminal End 34" SH Line 1A Sht. 2 of 5 Break SV1-1B Main Steam Vent 6" Terminal End Break @ Fig. 3.17 AB-750-23 Terminal End 34" SM Line IB Sht. 3.of 5 Break SVI-1C Main Steam Vent 6" Terminal End Break @ Fig. 3.17 AB-750-23 Terminal End 34" SM Line 1C Shts. 1, 4 Break SVI-ID Main Steam Vent 6" Terminal End Break @. Fig. 3.17 AB-750-26 Terminal End 34" SM Line ID Sht. 5 of 5 Break Revision 5 New Page \\..
O O O f Sheet - 18 of 19 ^ i TABLE 6-1 i HIGH ENERGY PIPE BREAK LOCATIONS } l STRESS RATIO f.- BREAK NUMBER SYSTEM DESCRIPTION FIGURE NO. LOCATION TO ALLOWABLE (1) SV1-10A Main Steam Vent 6" Intermediate Break @ Fig. 3.17 AB-750-26 .633 Inlet of First Elbow Sht. 2 of 5 ,i ! Downstream'from Valve ). ISV27 i SV1 11 B Main Steam Vent 6" Intermediate Break @ Fig. 3.17 AB-750-23 .633 0 Inlet of First Elbow Sht. 3 of 5 Downstream from Valve ISV28 l' SVI-10D Main Steam Vent 6" Intermediate Break @ Fig. 3.17 AB-750-26 .633 jl Inlet of First Elbow Sht. 5 of 5 i i Downstream from Valve )l 1sv25 SVI-11A Main Steam Vent 6" Intermediate Break @ Fig. 3.17 AB-750-26 .660 Outlet of First Elbow Sht. 2 of 5 Downstream from Valve ISV27 SV1-11B Main Steam Vent 6" Intermediate Break @ Fig. 3.17 AB-750-23 .660 Outlet of First Elbow Sht. 3 of 5 i Downstream from Valve ISV28. SV1-11D Main Steam Vent 6" Intermediate Break @ Fig. 3,17 AB-750-26 .660 Outlet of First Elbow Sht. 5 of 5 ' Downstream fran Valve ISV25 Revision 5 New Page \\. y - - ~
O O O Sheet 19 of 19 TABLE 6 HIGH ENERGY PIPE BREAK LOCATIONS STRESS RATIO BREAK NUMBER SYSTEM OESCRIPTION FIGURE N3. LOCATION TO ALLOWABLE (1) SVI-22C Main Steam Vent 6" Intermediate Break @ Fig. 3 17 AB-750-23 .684 Inlet of First Elbow Shts. 1, 4 Upstream from Valve ISV7 SVI-17C Main Steam Vent 6" Intermediate Break @ Fig. 3 17 AB-750-23 .630 Inlet of Third Elbow Shts I, 4 Upstream from Valve ISV7 e Revision 5 { New Page
..- - =.- _- - -__-..._..-.-.--- i i I 4 i i i t 1 i I f i l i r i 4 i t 1 i t i i i I I l i I J i t i 4 TABLE 6-2 Sheet 1 of 6 i i 1 Deleted 6 i I i I 1 i l i l I } !e i l I f r r s*
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l i I a i 1 I I 4 i 1 4 I I Y 4 I I Revision 5 ~ h i i ~ - - - - - -,,,...... -,, - - - - - -, - -, -,. - -. - - ~ - - - - -, - - -. - - - - - - - - -
\\ TABLE 6-2 Sheet 2 of 6 RESULTS OF DAMAGE EVALUAT10ft Uf4 ACCEPTABLE PIPE WillP/ JET IMPillGEMEflT EFFECTS BREAK fiUMBER TYPE BREAK EFFECT ON REQUIRED COMP 0f4EtlTS RESOLUT10tl cal-51 Circumferential Pipe whip and Jet impingement on Add whip restraint (forward flow) essential electrical cable to and Jet barrier, valve ICA508. 3 cal-70A Circumferential det impingement on essential Add whip restraint (forward flow) electrical cables to valves ICA38B and jet barrier. and ICAl:28. cal-70B Circumtarontial Pipe whip and jet impingement Add whip restraint 5 (forward flow, damage to hand wheel and cables to and jet barrier. I reverse flow) Valves ICA38B and ICA420 Revision 5 9 e
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6 2 B 8 6 B 7 4 B 8 0 taa 8 9 8 9 0 1 3 1 2 3 2 3 l 3 3 4 4 R w l l l o a a a a sl n 0 0 n 0 0 n 0 0 n 0 0 sl i i i i eA m m m m r r r r r o e e e e MT T T T T 9 3 0 9 3 0 9 3 0 9 3 0 n 0 1 6 0 1 6 0 1 6 0 1 6 o 8 8 7 8 8 . 7 8 8 7 8 8 7 i t l l l 1 l l l l l 1 l 1 a E E E E E E E E E E E E c o B B B B B B B B' B B B B L R R R R R R R R R R R R er. 1 1 1 1 1 1 1 1 1 1 1 uo t gN C C C C C C C C C C C C n i e F s m nn d d d d oi n n n n i a o m o m o m o m t t c a c a c a c a an e e e e e e e e co e s t e s t e s t e s t oC l S l S l S l S L z f z f z f z f 'D e z oA f z oB f z oC f z o f kd o I o o I o o I o o I o 1 ai N t N t N t N t es er m er m er m er m C r n A l o a B l o a C l o a D l o a BI I tt e I t t e I t t e I t t e E ua r ua r ua r ua r L ee r or t r or t r or t r or t B pn o e s o e s o e s o e s A ii t t n n t t n n t t n n t t n n T PL a ae w a ae w a ae w a ae w r G o r G o r G o r G o ym e r d e r d e r d e r d ga n em n em n em n em re e sa w e sa w e sa w e sa w et G i e o G i e o G i e o G i e o nS Rt b Rt b Rt b Rt b E m S l m S l m S l m S l n a m e a m e a m e a m e hi e af e af e af e af ga t eo d t eo d t eo d t eo d i M S t r S t r S t r S t r I S m i S m i S m i S m i l r t a h t a h t a h t a h \\ o a ne t a ne t a ne t a ne t F n ir i r ir i r o d at fA d at fB d at fC d at fD i n Ms oI n Ms oI n Ms oI n Ms oI t E n E n E n E n p f w t r f w t r f w t r f w t r i l oo eo l oo eo l oo eo l oo eo r a d l t a d l t a d l t a d l t c n p t a n p t a n p t a n p t a ow ur i ow ur i ow ur i ow ur s i e m t o oe m t o oe m t o oe m t o oe r' D r b n b . n r b n r b n e tl t e e tl t e e tl t e e tl t e T Ae AG T Ae AG T A e AG T A e AG m m m m m m m m m m m m a a a a a a a a a a a a m e e e e e e e e e e e e e t t t t t t t t t t t t t S S S S S S S S S S S S sy n n n n n n n n n n n n S i i i i i i i i i i i i a a a a a a a a a a a a M M M M M M M M M M M M I R R R R R R R R R R R R r I 2 3 4 5 6 7 8 9 0 1 2 n k e 0 0 0 0 0 0 0 0 0 1 1 1 ab em 1 I I I I I I I I I I I ru M M M M M M M M M M M' M BN S S S' S S S S S S S S S ggm$# " ggs* E$ mEE$ r if i f )
. - ~. ~ b b C v ts i l' TAllLE C-3 l liigh Energy I'igie Break Locations j For Auxiliary Feedwater Lines Inside Containment i Break Figure Stress Ratio j k Numl>c r System Description No. Location To Allowal>le(l) i l j cal-0IR Aux. Feedwater Terminal End at Steam Generator IA Nozzle C-6-3.1 Hit Terminal End Break I 3 cal-02R Aux. Feedwater Terminal End at Steam Generator til Nozzle C-6-3.1 RB Terminal End Break cal-03R Aux. Feedwater Terminal End a' Steam Generator IC Nozzle C-6-3.2 Rit Terminal End Ilicak cal-04R Aux. Feedwater Terminal End at Steam Cencrator in Nozzle C-6-3.2 Ril Terminal End fireak j. cal-05R Aux. Feedwater Interw:diate lireak at the inlet of C-6-3.1 RB 0.628 l elbow C08 S j cal-06R Aux. Feedw: iter Intermediate lireak at the outlet of C-6-3.1 Ril 0.625 i clbow C08 i i l i i I ( ! i i i - 1 1 un oa k u f i 4 i i \\.. --}}

ML20039D708

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