ML20086P343

Rev 1 to Vol 5,to Plant-Unique Analysis Rept,Safety Relief Valve Piping Analysis

ML20086P343
Person / Time
Site:	Fermi
Issue date:	11/30/1983
From:	Edwards N, Steinert L NUTECH ENGINEERS, INC.
To:
Shared Package
ML20086P296	List: ML20086P293 ML20086P313 ML20086P316 ML20086P328 ML20086P336 ML20086P343
References
DET-20-015-5, DET-20-015-5-R01, DET-20-15-5, DET-20-15-5-R1, NUDOCS 8402270109
Download: ML20086P343 (6)

Text

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l DET-20-015-5 l Revision 1 O. November 1983 ,

1 l

ENRICO FERMI ATOMIC POWER PLANT UNIT 2 PLANT UNIQUE ANALYSIS REPORT VOLUME 5 SAFETY RELIEF VALVE PIPING ANALYSIS Prepared for:

Detroit Edison Company Prepared by:

NUTECH Engineers, Inc.

s Approved by: Issued by:

Dr. N. W. Edwards, P.E. L. D. Steinert President Project Manager NUTECH Engineers, Inc.

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8402270109 840221 DR ADOCK 05000341 PDR

REVISION CONTROL SHEET TITLE: Enrico Fermi Atomic REPORT NUMBER: DET-20-015-5 Power Plan.t, Unit 2 Revision 1

/' Plant Unique Analysis Report

'x j Volume 5

. BM kin / Engineering Manager Ingials

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'H. T. Ho/ p(ciali's ' ~ ~

HTF Initials b

L. R. Hussar /Eng(neer Initials A.

L-.- c/d AImandoust/ Specialist A.r.

Initials Esy Zd4a R. Jaffari/ Consultant II d

Initials Yt,3 V. Kumat/ Project Engineer Initials

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R. A Lehnert/Enginedring Manager

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J. D. Lowe/ Engineering Analyst Initials P. R.

<t - w Para / Specialist

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Initials a m- . i, )

S. P. Quinn/ Senior Technician Initials T P.R. Ei, MI Shah / Consultant I

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P. R. Initiials fLJfi 17 tu W. E. Smith /Asiifociate ' Engineer Initials C. Y JOs-x9 8rc<3 C. T. Wong/ Pro $ect Engineer Initials G

. Won / Engineering Analyst I bials a L.

b D. Steinert/ Project Manager as Initials 5-"

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REVISION CONTROL SHEET f] (Continuation)

TITLE: ENRICO FERMI ATOMIC POWER REPORT NUMBER: DET-20-015-5 PLANT, UNIT 2 Revision 1 PLANT UNIQUE ANALYSIS REPORT ,

VOLUME 5 ACCURACY CRITERIA PRE- ACCURACY CRITERIA T REV PRE- REV PARED CHECK CHECK PARED CHECK CHECK PAGE (S) PAGE (S) 5-3.1 0 gA(,,, V( yk 5-3.60 0 through 5-3.2 5-3.62 JDL CM N 3 5-3.63 HTH Lfg VK 5-3.64 5-3.5 throuch dDL /,,g//- VK N3 $1 MhL VK 5-3.68 5-3.12 through

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5-2.2.3 Combination of Dynamic Loads v

The methods used in the analyses for combining dynamic loads are based on NUREG-0484, Revision 1,

" Methodology for Combining Dynamic Responses" (Reference 7). As described in NUREG-0484, when the time-phase relationship between the responses caused by two or more sources of dynamic loading is undefined l or random, the peak responses from the individual loads are combined by absolute sum (except for combined SSE and LOCA loads). The peak responses l

which result from SSE and LOCA loads are combined l

using the square root of the sum of the squares (SRSS) technique. Additional information on NRC acceptance

[T of the SRSS method for combining dynamic responses in Mark I piping systems is provided in Reference 9.

pg DET-20-015-5 Revision 1 5-2.61 NJ) nutggb

5-2.3 Analysis Acceptance Criteria The acceptance criteria defined in NUREG-0661 on which the Fermi 2 SRV piping analysis is based are discussed in Section 1-3.2. In general, the acceptance criteria follow the rules contained in ASME Code,Section III, l

l Division 1 up to and including the 1977 Summer Addenda for Class 2 piping and piping supports (Reference 6).

The corresponding Service Level limits, allowable stresses and fatigue requirements are also consistent with the requirements of the ASME Code and NUREG-0661.

The acceptance criteria used in the analysis of the SRV piping are summarized in the following paragraphs.

l The SRV piping is analyzed in accordance with the requirements for Class 2 piping systems contained in Subsection NC of the Code. Table 5-2.3-1 lists the applicable ASME Code equations and stress limits for each of the governing piping load combinations.

The SRV piping supports are analyzed in accordance with cequirements for Class 2 piping supports as pro-vided in Subsection NF of the Code. The applicable stress limits for support structures are based on the Service Level assignments listed for the governing DET-20-015-5 Revision 0 5-2.62 nutggh 1

t

LIST OF REFERENCES fx 5-4.0 V " Mark I Containment Long-Term Program," Safety 1.

Evaluation Report, USNRC, NUREG-0661, July 1980.

2. " Mark I Containment Program Load Definition Report," General Electric Company, NEDO-21888, Revision 2, December 1981.

3. " Mark I Containment Program Plant Unique Load Definition," Enrico Fermi Atomic Power Plant, Unit 2, General Electric Company, NEDO-24568, Revision 1, June 1981.

4. Enrico Fermi Atomic Power Plant, Unit 2, Final Safe.ty Analysis Report, Detroit Edison Company, Section 3.9, Amendment 3, June 1976.

5. " Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Applications Guide," Task Number 3.1.1, Mark I Owners Group, General Electric Company, NEDO-24583, Revision 1, October 1979.

6. ASME Boiler and Pressure Vessel Code, Section

- III, Division 1, 1977 Edition with Addenda up to I and including Summer 1977.

LJ 7. " Methodology for Combining Dynamic Responses,"

USNRC, NUREG-0484, Revision 1, May 1980.

l 8. " Combining Modal Responses and Spatial Components in Seismic Response Analysis," USNRC, Regulatory Guide 1.92, Revision 1, February 1976.

9. Letter from Domenic B. Vassallo (NRC) to H. C.

Pfefferlen (GE), " Acceptability of SRSS Method for Combining Dynamic Responses in Mark I Piping Systems," dated March 10, 1983.

DET-20-015-5

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v Revision 1 5-4.1 nutggh

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