ML19256B454

Responds to IE Bulletin 79-07.None of Methods Specified Are Used in Listed Computer Program for Seismic Analysis of safety-related Piping.Review of Modal Results in Pinping Analysis Establishes Specified Spectral Methods Not Used

ML19256B454
Person / Time
Site:	Midland
Issue date:	05/24/1979
From:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7907110215
Download: ML19256B454 (2)

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CODSilmBiS POW 6r Stephen H. Howell (QQ y* ** Senwr L'sce Pressdent General of fices- 1945 West Pernall Roacf, Jackson, Machigan 49201 e ($17) 788-0453 May 24,1979 Hove 156-79 Mr James G Keppler, Regional Director Nuclear Regulatory Co==ission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND PROJECT D0ci:ET NO 50-329, 50-330 IE BULLETIN 79-07 FILE: 0505 12 SERIAL: 705h We have reviewed IE Bulletin 79-07 on the subject of "Seis=ic Stress Analysis of Safety-Related Piping" against the Midland Plant Unit 1 and 2 design and have the following response which is keyed to the items within the IE Bulletin.

The Balance-of-Plant Syste: provided by Bechtel -

The co=puter codes that have been used by the San Francisco Power Division of the Bechtel Power Corporation in the seismic stress analyses of safety-related piping are:

s a)

E 632 - Seismic Analysis of Piping Systems, Bechtel Power Corporation (b) E 101 - LEAP - Linear Elastic Analysis of Pipe, Bechtel Power Corporation (c) PISOL - ED3 Nuclear Inc (d) NUPIPE - Nuclear Services Corporation

( e) SAPIPE - PMB Systems Engineering Inc (f) TRIPE - PM3 Systems Engineering Inc Of these, only E 632 and E 101 have been used for seismic analyses of piping for the Midland Plants.

1. None of the methods specified were used in the listed computer progra=s for the seismic analysis of safety-related piping.

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%2 91979 7 9 0711047/f-

Serial 7054 2

2. Not applicable.

3 The computer programs listed have been verified as follows:

(a) ME 632 - Has been verified using PISOL, PIPESD, and TRIPE.

(b) ME 101 - Has been verified using ME 632, TRIPE, and SUPERPIPE.

(c) PISOL - Has been verified using N0PITE, PIPESD, ADLPIPE, and ME 101.

(d) NUPIPE - Has been verified using ADLPIPE. (In the veritication, the algebraic su=mation option in ADLPIPE vas not used.)

(e) SAPIPE - Has been verified using PISOL.

(f) TRIPE - Has been verified using PISOL and ME 632.

k. Not applicable.

The HcS Scope of Supply provided by the Babcock & Wilcox Company -

1. A review of modal results in the piping analyses clearly establishesModal that the spectral methods mentioned in IE Bulletin 79-07 vere not used.

reactions were determined, then the square root of the sum of the squares (SRSS) were Stresses of thecalculated modal contributions were using the SRSS determined method fortwo to conbine thehorizontal entire structure.

In other words ,

earthquake responses with the vertical earthquake response.

the seismic resultant was obtained from the SRSS of three earthquake directions.

2. Not appliceble.

3 The analyses of all piping within B&W's Scope were performed using ST3DG/ LUM 3 These computer codes were verified using sa=ple problems (References 1 & 2). The cor aination of modal reactions by SRSS contained in the users manuals.

was verified by hand calculation, and the conbination of directional earthquake response was done by hand calculations,

k. Not applicable.

Beferences A S Kadakia, P G Tuttle: " Users Manual, ST3DS Piping Flexibility Analysis 1.

Program as Modified for B&W Application", NPGD-TM-126, Babcock & Wilcox, PO Box 1260, Lynchburg, Virginia 24505, May 1971.

" Users Manual, Piping Flexibility Analysis Program

2. P G Tuttle A S Kadakia:

LUFE as Modified for B&W Application", NPOD-TM-127, Babcock & Wilcox, PO Box 1260, Lynchburg, Virginia 24505, January 1971.

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SHH/jbg CC: n'. rector, NRC Office of Inspection and Enforcement 0 "

Director, Nuclear Reactor Regulation