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{{#Wiki_filter:- _ _ - _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ . ___ | {{#Wiki_filter:- _ _ - _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ . ___ | ||
,w - -c.-.ee-._*.m-++ .-e | ,w - -c.-.ee-._*.m-++ .-e l . | ||
l . | |||
COUS'JmSTS 90W8T | COUS'JmSTS 90W8T | ||
] agg Stephen H. Howell Vice President oeneral offices: 1945 West Parnell Road, Jackson, MicNgan 49201 | |||
] agg Stephen H. Howell | |||
Vice President oeneral offices: 1945 West Parnell Road, Jackson, MicNgan 49201 | |||
* Area Code 517 788-0453 June 8, 1977 - . , - | * Area Code 517 788-0453 June 8, 1977 - . , - | ||
I 9, | I 9, | ||
a N | a N | ||
~, | ~, | ||
Director of Huelear Reactor Regulation {C) | Director of Huelear Reactor Regulation {C) | ||
Attn: Mr Roger Boyd, Director V Division of Project Ihnagement US Nuclear Regulatory Ccamission Washington, DC 20555 | Attn: Mr Roger Boyd, Director V Division of Project Ihnagement US Nuclear Regulatory Ccamission Washington, DC 20555 kJ ,i ; | ||
kJ ,i ; | |||
D Ng*=r *gD7/A // | D Ng*=r *gD7/A // | ||
MIDLAUD PROJECT q, DOCKET NOS 50-329, 50-330 REACIOR COOLANT SYSTEM 4 iiIGi ENERGY BREAK ANALYSIS CRITERIA FlLE: B3.6 SERIAL: 3773 On }hy 10 via CPC0 Serial 3605 ve transmitted a revised Criteria for Postulating Primary System Pipe Breaks for Midland Plant, Units 1 and 2. Along with that submittal we sent a table ( Attachment 2) showing the postulated pipe breaks that would occur following the revised criteria. | MIDLAUD PROJECT q, DOCKET NOS 50-329, 50-330 REACIOR COOLANT SYSTEM 4 iiIGi ENERGY BREAK ANALYSIS CRITERIA FlLE: B3.6 SERIAL: 3773 On }hy 10 via CPC0 Serial 3605 ve transmitted a revised Criteria for Postulating Primary System Pipe Breaks for Midland Plant, Units 1 and 2. Along with that submittal we sent a table ( Attachment 2) showing the postulated pipe breaks that would occur following the revised criteria. | ||
Since that submittal we have refined the above table so that a separate table is presented for each Midland unit (USS 12 and USS 13) . These new tables , Attach-ment 1 and 2 of this letter supersede and replace Attachment 2 of our previous letter (CPC0 Serial 3605). The revised criteria as previously submitted, has not changed. | Since that submittal we have refined the above table so that a separate table is presented for each Midland unit (USS 12 and USS 13) . These new tables , Attach-ment 1 and 2 of this letter supersede and replace Attachment 2 of our previous letter (CPC0 Serial 3605). The revised criteria as previously submitted, has not changed. | ||
,k- - " | ,k- - " | ||
SIHi/JJZ/jbg | SIHi/JJZ/jbg 80063ggf M V6AW | ||
80063ggf M V6AW | |||
O ATTACHMENT 1 i | |||
REACTOR COOLANT SYSTEM PRIMARY PIPING BREAK LOCATIONS FOR A 177 FA PLANT - | |||
O ATTACHMENT 1 | |||
CONSUMERS POWER COMPANY - NSS-12 (Unit 2) | CONSUMERS POWER COMPANY - NSS-12 (Unit 2) | ||
BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.4 Sm O CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST TWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALUES. | BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.4 Sm O CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST TWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALUES. | ||
MATH PIPING MODEL STRESS (psi) BREAK TYPE RUN JOINT 2.4 Sm(1) Eq 12 Eq 13(4 ) CUF LONGITUDINAL GUILLOTINE NOTES | MATH PIPING MODEL STRESS (psi) BREAK TYPE RUN JOINT 2.4 Sm(1) Eq 12 Eq 13(4 ) CUF LONGITUDINAL GUILLOTINE NOTES 200 46,560 | ||
200 46,560 | |||
) | ) | ||
.010 / HL TERMINAL END HOT (2) 41,760 - - | .010 / HL TERMINAL END HOT (2) 41,760 - - | ||
.630 / HL TERMINAL END LEG 179 44,160 h,150 27,230 .004 , | .630 / HL TERMINAL END LEG 179 44,160 h,150 27,230 .004 , | ||
/ HL INTERMEDIATE BREAK LOOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK A 15 46,560 - - | / HL INTERMEDIATE BREAK LOOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK A 15 46,560 - - | ||
.009 / HL TERMINAL DiD | .009 / HL TERMINAL DiD HOT 128 41,760 - - | ||
HOT 128 41,760 - - | |||
.491 / HL TERMINAL DID LEG 30 44,160 4,000 26,130 .CuY / HL INTERMEDIATE BREAK IDOP 200 46,560 - - | .491 / HL TERMINAL DID LEG 30 44,160 4,000 26,130 .CuY / HL INTERMEDIATE BREAK IDOP 200 46,560 - - | ||
.010 / HL TERMINAL DID B 15 46,560 - - | .010 / HL TERMINAL DID B 15 46,560 - - | ||
Line 75: | Line 49: | ||
/ | / | ||
LOWER 136-h6 40,800 - - | LOWER 136-h6 40,800 - - | ||
.002 / LCL TERMINAL END | .002 / LCL TERMINAL END l COLD 20-19 44,880 13,410 33,120 .012 / LCL INTERMEDIATE BREAK LEG 118-45 h4,880 12,975 50,127 .098 /(3) LCL ELBOU BREAK | ||
l COLD 20-19 44,880 13,410 33,120 .012 / LCL INTERMEDIATE BREAK LEG 118-45 h4,880 12,975 50,127 .098 /(3) LCL ELBOU BREAK | |||
; 3-21 47,280 - - | ; 3-21 47,280 - - | ||
.015 / LCL TERMINAL DiD NOTES: (1) S at m 650 7 for Hot Leg and 600 F for Cold Leg. | .015 / LCL TERMINAL DiD NOTES: (1) S at m 650 7 for Hot Leg and 600 F for Cold Leg. | ||
(2) Location of RCS Decay Heat Nozzle. | (2) Location of RCS Decay Heat Nozzle. | ||
(3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.) | (3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.) | ||
(b) Highest stress value using either X+Y or Y+Z earthquake moments. | (b) Highest stress value using either X+Y or Y+Z earthquake moments. | ||
) | ) | ||
i | i | ||
'1 . ,. | '1 . ,. | ||
T t | T t | ||
} ATTACIIMENT 2 4 | } ATTACIIMENT 2 4 REACTOR COOLANT SYSTEM PRIMARY PIPING BREAK LOCATIONS FOR A 177 FA PLANT , | ||
REACTOR COOLANT SYSTEM PRIMARY PIPING BREAK LOCATIONS FOR A 177 FA PLANT , | |||
CONSUMERS POWER COMPANY - NSS-13 (Unit 1) ; | CONSUMERS POWER COMPANY - NSS-13 (Unit 1) ; | ||
BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.h Sm OR THE CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST 'IWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR , | BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.h Sm OR THE CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST 'IWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR , | ||
CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALU:::S. | CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALU:::S. | ||
} | } | ||
MATH PIPING MODEL STRESS (psi) BREAK TYPE | MATH PIPING MODEL STRESS (psi) BREAK TYPE | ||
~ | ~ | ||
Line 118: | Line 75: | ||
A 15 h6,560 - - | A 15 h6,560 - - | ||
.009 / HL TERMINAL EID !, | .009 / HL TERMINAL EID !, | ||
. HOT 200 46,560 - - | . HOT 200 46,560 - - | ||
.010 / HL TERMINAL END LEG 179 44,160 4,150 27,230 .004 / IIL INTERMEDIATE BREAK IDOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK | .010 / HL TERMINAL END LEG 179 44,160 4,150 27,230 .004 / IIL INTERMEDIATE BREAK IDOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK B 15 h6,560 - - | ||
.009 / HL TERMINAL DID 196-149 44,880 - - | |||
B 15 h6,560 - - | |||
.009 / HL TERMINAL DID | |||
196-149 44,880 - - | |||
.018 / UCL TERMINAL END | .018 / UCL TERMINAL END | ||
. UPPER 191-111 44,880 6,470 29,770 .005 / UCL INTERMEDIATE BREAK COLD 168-37 44,880 26,739 51,774 .042 /(3) UCL ELBOW BREAK LEG 172-47 40,800 - - | . UPPER 191-111 44,880 6,470 29,770 .005 / UCL INTERMEDIATE BREAK COLD 168-37 44,880 26,739 51,774 .042 /(3) UCL ELBOW BREAK LEG 172-47 40,800 - - | ||
Line 134: | Line 86: | ||
(3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.) | (3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.) | ||
(k) Highest stress value using either X+Y or Y+Z earthquake moments, i | (k) Highest stress value using either X+Y or Y+Z earthquake moments, i | ||
e | e | ||
(7 708 | (7 708 | ||
' A " ~ J I M '.3'.S O | ' A " ~ J I M '.3'.S O | ||
~ | ~ | ||
"M """ | "M """ | ||
3DISTRl!1UTION FOn PMIT 50 DOCKET MATERIAL ' | 3DISTRl!1UTION FOn PMIT 50 DOCKET MATERIAL ' | ||
TJ: 'R. BOYD FROM: CONSUMERS POWER CD. OATE Os ooCuuCuT JACKSON, MICHICAN . | |||
TJ: 'R. BOYD FROM: CONSUMERS POWER CD. OATE Os ooCuuCuT | |||
JACKSON, MICHICAN . | |||
6/8/77 | 6/8/77 | ||
. S.D.POWELL DATC aCCCivEo 6/13/77 - | . S.D.POWELL DATC aCCCivEo 6/13/77 - | ||
Line 160: | Line 102: | ||
.- . / 5 / G A> 68 DESCns9 TION ENCLOSUHE , . | .- . / 5 / G A> 68 DESCns9 TION ENCLOSUHE , . | ||
LTR TRANS THE FOLLOWING......... REACTOR, COOLANT SYSTEM' PRIMARY. PIPING BREAK LOC. | LTR TRANS THE FOLLOWING......... REACTOR, COOLANT SYSTEM' PRIMARY. PIPING BREAK LOC. | ||
TION FOR A 177 FA PLANT SURERSEDING AND REPLAC: | TION FOR A 177 FA PLANT SURERSEDING AND REPLAC: | ||
l- | l- | ||
' ING ATTACHMENT 2. OF LTR (CPC0 SERIAL 36d5) . . . . . | ' ING ATTACHMENT 2. OF LTR (CPC0 SERIAL 36d5) . . . . . | ||
l . | l . | ||
(IP) (2P) '' - ' - | (IP) (2P) '' - ' - | ||
'{; ,DONOT REMOn,! | '{; ,DONOT REMOn,! | ||
l . . | l . . | ||
i .. - | i .. - | ||
s , | s , | ||
: . . -. 1 l PLANT NA':I' ? MIDLAND d''l & 2 - - - | |||
: . . -. 1 | |||
l PLANT NA':I' ? MIDLAND d''l & 2 - - - | |||
I | I | ||
* SAB .-- | * SAB .-- | ||
7 3DGNL . | 7 3DGNL . | ||
SAFETY , FOS ACTION /INFORMATION ENvrRO fASSIGNEDAD: Va s _s c #O l ASSIC TO Aa,: | SAFETY , FOS ACTION /INFORMATION ENvrRO fASSIGNEDAD: Va s _s c #O l ASSIC TO Aa,: | ||
i') P.I'ANCll Cl!IEF: Vcp t: A BRARCL.CHIEP - | i') P.I'ANCll Cl!IEF: Vcp t: A BRARCL.CHIEP - | ||
;' PROJECT MANAGER: foU / f (2) PROJECT _ MANAGER? | ;' PROJECT MANAGER: foU / f (2) PROJECT _ MANAGER? | ||
[ LIC. ASST.: __ .S e, ev/Co, T,Ig,, y ST,; | [ LIC. ASST.: __ .S e, ev/Co, T,Ig,, y ST,; | ||
I, ,_ | I, ,_ | ||
_ INTERNAL DISTRi!3UTION WRE'; FTT e 3 SYSTEMS SAFETY pTAg7_Sys7pyg SITE SAygTy_& | _ INTERNAL DISTRi!3UTION WRE'; FTT e 3 SYSTEMS SAFETY pTAg7_Sys7pyg SITE SAygTy_& | ||
Line 208: | Line 126: | ||
__. }{IPC MACCAR"sY ___glithX0_QD ERNST CASE KNIGitT RALLARD ltANAUER SIllWEI' OPERATli!G REACTORS SPAMCTFR | __. }{IPC MACCAR"sY ___glithX0_QD ERNST CASE KNIGitT RALLARD ltANAUER SIllWEI' OPERATli!G REACTORS SPAMCTFR | ||
_._ }MilleI:'SS PAULICKI S.Iy1LQ_ _ | _._ }MilleI:'SS PAULICKI S.Iy1LQ_ _ | ||
RI.TE TFcn-PROJECT MANAGEMENT RI: ACTOR SAFETY OPERATIEG TECTI. CM:511LL | RI.TE TFcn-PROJECT MANAGEMENT RI: ACTOR SAFETY OPERATIEG TECTI. CM:511LL | ||
.REU) ROSS E_ISI' J ilitri STEIT | .REU) ROSS E_ISI' J ilitri STEIT | ||
Line 219: | Line 136: | ||
TIC: REC. VIE til.!tIRSON(ORNI.)_ | TIC: REC. VIE til.!tIRSON(ORNI.)_ | ||
NSIC- 1A PlH! ~ | NSIC- 1A PlH! ~ | ||
.. A'11.ll; CONS!!!.TANTS - | .. A'11.ll; CONS!!!.TANTS - | ||
/ / W O 2- q 4 l ACitS ., CYS_ _!!01.1)lNC ,,,, ,, ,,,/: E!! ? | / / W O 2- q 4 l ACitS ., CYS_ _!!01.1)lNC ,,,, ,, ,,,/: E!! ? | ||
~ | ~ | ||
heit: e nnu tun iv.m , | heit: e nnu tun iv.m , | ||
~}} | ~}} |
Latest revision as of 17:30, 18 February 2020
ML19326D542 | |
Person / Time | |
---|---|
Site: | Midland |
Issue date: | 06/08/1977 |
From: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
To: | Boyd R Office of Nuclear Reactor Regulation |
References | |
3773, NUDOCS 8006180671 | |
Download: ML19326D542 (4) | |
Text
- _ _ - _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ . ___
,w - -c.-.ee-._*.m-++ .-e l .
COUS'JmSTS 90W8T
] agg Stephen H. Howell Vice President oeneral offices: 1945 West Parnell Road, Jackson, MicNgan 49201
- Area Code 517 788-0453 June 8, 1977 - . , -
I 9,
a N
~,
Director of Huelear Reactor Regulation {C)
Attn: Mr Roger Boyd, Director V Division of Project Ihnagement US Nuclear Regulatory Ccamission Washington, DC 20555 kJ ,i ;
D Ng*=r *gD7/A //
MIDLAUD PROJECT q, DOCKET NOS 50-329, 50-330 REACIOR COOLANT SYSTEM 4 iiIGi ENERGY BREAK ANALYSIS CRITERIA FlLE: B3.6 SERIAL: 3773 On }hy 10 via CPC0 Serial 3605 ve transmitted a revised Criteria for Postulating Primary System Pipe Breaks for Midland Plant, Units 1 and 2. Along with that submittal we sent a table ( Attachment 2) showing the postulated pipe breaks that would occur following the revised criteria.
Since that submittal we have refined the above table so that a separate table is presented for each Midland unit (USS 12 and USS 13) . These new tables , Attach-ment 1 and 2 of this letter supersede and replace Attachment 2 of our previous letter (CPC0 Serial 3605). The revised criteria as previously submitted, has not changed.
,k- - "
SIHi/JJZ/jbg 80063ggf M V6AW
O ATTACHMENT 1 i
REACTOR COOLANT SYSTEM PRIMARY PIPING BREAK LOCATIONS FOR A 177 FA PLANT -
CONSUMERS POWER COMPANY - NSS-12 (Unit 2)
BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.4 Sm O CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST TWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALUES.
MATH PIPING MODEL STRESS (psi) BREAK TYPE RUN JOINT 2.4 Sm(1) Eq 12 Eq 13(4 ) CUF LONGITUDINAL GUILLOTINE NOTES 200 46,560
)
.010 / HL TERMINAL END HOT (2) 41,760 - -
.630 / HL TERMINAL END LEG 179 44,160 h,150 27,230 .004 ,
/ HL INTERMEDIATE BREAK LOOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK A 15 46,560 - -
.009 / HL TERMINAL DiD HOT 128 41,760 - -
.491 / HL TERMINAL DID LEG 30 44,160 4,000 26,130 .CuY / HL INTERMEDIATE BREAK IDOP 200 46,560 - -
.010 / HL TERMINAL DID B 15 46,560 - -
.009 / HL TERMINAL END 196-149 44,880 - -
.018 / UCL TERMINAL END UPPER 191-111 44,880 6,470 29,770 .005 / UCL INTERMEDIATE BREAK COLD 168-37 44,880 26,739 51,774 .042 /(3) UCL ELBOW BREAK LEG 172-47 40,800 - -
.001 / UCL TERMINAL eld
/
LOWER 136-h6 40,800 - -
.002 / LCL TERMINAL END l COLD 20-19 44,880 13,410 33,120 .012 / LCL INTERMEDIATE BREAK LEG 118-45 h4,880 12,975 50,127 .098 /(3) LCL ELBOU BREAK
- 3-21 47,280 - -
.015 / LCL TERMINAL DiD NOTES: (1) S at m 650 7 for Hot Leg and 600 F for Cold Leg.
(2) Location of RCS Decay Heat Nozzle.
(3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.)
(b) Highest stress value using either X+Y or Y+Z earthquake moments.
)
i
'1 . ,.
T t
} ATTACIIMENT 2 4 REACTOR COOLANT SYSTEM PRIMARY PIPING BREAK LOCATIONS FOR A 177 FA PLANT ,
CONSUMERS POWER COMPANY - NSS-13 (Unit 1) ;
BREAKS ARE POSTULATED AT PIPING TERMINAL POINTS AND AT INTERMEDIATE POINTS WHERE THE STRESS EXCEEDS 2.h Sm OR THE CUMULATIVE USAGE FACTOR EXCEEDS 0.1. AT LEAST 'IWO INTERMEDIATE BREAK LOCATIONS ARE POSTULATED BASED ON STRESS OR ,
CUF ALLOWABLES BEING EXCEEDED OR ON ACTUAL HIGHEST STRESS OR CUF VALU:::S.
}
MATH PIPING MODEL STRESS (psi) BREAK TYPE
~
RUN JOINT 2.4 Sm(1) Eq 12 Eq 13(4) CUP IDNGITUDINAL GUILIDTINE NOTES -
1 200 h6,560 - -
.010 / HL TERMINAL END .
HOT (2) 41,760 - -
.630 / HL TERMINAL END LEG 128 41,760 - -
.491 / IIL TERMINAL END IDOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK ;
A 15 h6,560 - -
.009 / HL TERMINAL EID !,
. HOT 200 46,560 - -
.010 / HL TERMINAL END LEG 179 44,160 4,150 27,230 .004 / IIL INTERMEDIATE BREAK IDOP 30 44,160 4,000 26,130 .007 / HL INTERMEDIATE BREAK B 15 h6,560 - -
.009 / HL TERMINAL DID 196-149 44,880 - -
.018 / UCL TERMINAL END
. UPPER 191-111 44,880 6,470 29,770 .005 / UCL INTERMEDIATE BREAK COLD 168-37 44,880 26,739 51,774 .042 /(3) UCL ELBOW BREAK LEG 172-47 40,800 - -
.001 / UCL TERMINAL END IDWER 136-46 40,800 - -
.002 / LCL TERMINAL END COLD 20-19 Lh,880 13,h10 33,120 .012 / LCL INTERMEDIATE BREAK LEG 118-45 44,880 12,975 50,127 .098 /(3) LCL ELBOW BREAK 3-21 47,280 - -
.015 / I.CL TERMINAL END N01'ES: (1) S at m 650*F for Hot Leg and 600*F for Cold Leg.
(2) Location of RCS Decay Heat Nozzle.
(3) Split angle in the primary pipe defined by out-of-plane bending criteria. (See para. 2.2.2.)
(k) Highest stress value using either X+Y or Y+Z earthquake moments, i
e
(7 708
' A " ~ J I M '.3'.S O
~
"M """
3DISTRl!1UTION FOn PMIT 50 DOCKET MATERIAL '
TJ: 'R. BOYD FROM: CONSUMERS POWER CD. OATE Os ooCuuCuT JACKSON, MICHICAN .
6/8/77
. S.D.POWELL DATC aCCCivEo 6/13/77 -
I TTCn CNOTOnt2EO PROP .
INPUT FonM . NUMOCn OF COPIES RCCCIVCD
{ n LOIN AL- MNCLASSIFIE D k ,
OCOPY ,
.- . / 5 / G A> 68 DESCns9 TION ENCLOSUHE , .
LTR TRANS THE FOLLOWING......... REACTOR, COOLANT SYSTEM' PRIMARY. PIPING BREAK LOC.
TION FOR A 177 FA PLANT SURERSEDING AND REPLAC:
l-
' ING ATTACHMENT 2. OF LTR (CPC0 SERIAL 36d5) . . . . .
l .
(IP) (2P) - ' -
'{; ,DONOT REMOn,!
l . .
i .. -
s ,
- . . -. 1 l PLANT NA':I' ? MIDLAND dl & 2 - - -
I
- SAB .--
7 3DGNL .
SAFETY , FOS ACTION /INFORMATION ENvrRO fASSIGNEDAD: Va s _s c #O l ASSIC TO Aa,:
i') P.I'ANCll Cl!IEF: Vcp t: A BRARCL.CHIEP -
- ' PROJECT MANAGER
- foU / f (2) PROJECT _ MANAGER?
[ LIC. ASST.: __ .S e, ev/Co, T,Ig,, y ST,;
I, ,_
_ INTERNAL DISTRi!3UTION WRE'; FTT e 3 SYSTEMS SAFETY pTAg7_Sys7pyg SITE SAygTy_&
G. i va . _ HEISEt%N TrDESCO ENVIR9EATXSTS
/ I&E ( L/ SCHROEDER BENAROYA DENTON & MJLLi'E
__. _0ED- LAI?iAS COSSICK & STAFF ENGI! JEERING IPPOL_ITO Et,'V_IP.O TECH _
__. }{IPC MACCAR"sY ___glithX0_QD ERNST CASE KNIGitT RALLARD ltANAUER SIllWEI' OPERATli!G REACTORS SPAMCTFR
_._ }MilleI:'SS PAULICKI S.Iy1LQ_ _
RI.TE TFcn-PROJECT MANAGEMENT RI: ACTOR SAFETY OPERATIEG TECTI. CM:511LL
.REU) ROSS E_ISI' J ilitri STEIT
,_ f. COI. LINS - . NOVAK S!!AO _,j[ULMAN llotISTON ROSZTOCZY 1;AElt -
PETERSON CllECK , lit rLER SITE _A11aLYGIS, t _._ MEl.TZ . CR.1115.S VOLLMC11
!!El.TEMES AT & I _3UMCit SKOVil01.T SALTZMAN i _._
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nu cen L X~ll.lif J AL 01511111161 TION CON illOL NUMill it l [ I.Pliit.: M W a d N $ .NAT M n: ' . _HROOMHAVEN.MAY.UiU_
TIC: REC. VIE til.!tIRSON(ORNI.)_
NSIC- 1A PlH! ~
.. A'11.ll; CONS!!!.TANTS -
/ / W O 2- q 4 l ACitS ., CYS_ _!!01.1)lNC ,,,, ,, ,,,/: E!! ?
~
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