ML19326D542

Forwards Table Re Postulated Pipe Break Locations, Superseding Table Sent 770510 W/Revised High Energy Break Analysis Criteria

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

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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 - . , -

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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  ;

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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.

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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

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.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

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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.

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} 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

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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

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3DISTRl!1UTION FOn PMIT 50 DOCKET MATERIAL '

TJ: 'R. BOYD FROM: CONSUMERS POWER CD. OATE Os ooCuuCuT JACKSON, MICHICAN .

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INPUT FonM . NUMOCn OF COPIES RCCCIVCD

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LTR TRANS THE FOLLOWING......... REACTOR, COOLANT SYSTEM' PRIMARY. PIPING BREAK LOC.

TION FOR A 177 FA PLANT SURERSEDING AND REPLAC:

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