ML20237K046

Summary of 870624 Meeting W/Eqe,Inc to Discuss Lll Seismic Design Audit of Plant.Viewgraphs Encl

ML20237K046
Person / Time
Site:	Hatch
Issue date:	08/18/1987
From:	Tan C Office of Nuclear Reactor Regulation
To:	Crocker L Office of Nuclear Reactor Regulation
References
NUDOCS 8708270029
Download: ML20237K046 (71)

Text

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[ Distribution *w/o enclosure Central FileMLReiter

• Local /NRC PDR CPTan

• ESGB Rdg File

• GBagchi

• MEMORANDUM FOR:

L. Crocker, Project Manager Project Directorate II-3 Division of Reactor Projects I/II FROM:

C. P. Tan, Civil Engineer Structural and Geosciences Branch Division of Engineering and Systems Technology

SUMMARY

OF MEETINGS WITH DR. JAMES JOHNSON OF EQE CONSULTANT TO LLNL A meeting with Dr. James Johnson of EQE consultant to LLNL was held in Room P1114-8 on June 24, 1987 to discuss the status of the LLNL technical assistance project on Hatch Units 1 and 2 seismic design audit. Dr. Johnson described the status of-the project and presented the findings to date in his independent review of Hatch 1 and 2 seismic analysis and design.

The meeting was attended by myself, L. Reiter, Chief of the Geosciences Section and G.

Bagchi, Acting Chief of ESGB. A copy of the viewgraphs used in the presentation is enclosed.

4. f. Y C. P. Tan, Civil Engineer Qs2Joh29s p

- [

Structural and Geosciences Branch n0 Division of Engineering and Systems Technology

Enclosure:

As stated cc:

J. Richardson w/o enclosure B. Youngblood w/o enclosure CONTACT:

C. P. Tan, X29444 l

Y hb ESGB: DEST 4['T ESGB: EST ESGB: DEST CPTan:jch LR 1-r GBagchi 8//(/87 8/ g 87 8/tV/87

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REVIEW OF SEISMIC ANALYSIS AND DESIGN OF HATCH UNITS 1 AND 2:

STATUS REPORT Presented to US NRC Nuclear Reactor Regulation Presented by James J. Johnson June 24,1987

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L THIS PRESENTATION WILL DISCUSS THE FOLLOWING k

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• BACKGROUND

• REVIEW OF HATCH DESIGN 1-e HATCH STRUCTURES e SEISMIC ANALYSIS PROCEDURES e UNITS 1 AND 2

• ORIGINAL AND REANALYSIS

• HATCH SITE CHARACTERISTICS

• INDEPENDENT SEISMIC ANALYSES e REACTOR BUILDING

• CONTROL BUILDING l-e RESULTS AND CONCLUSIONS e NEXT STEPS

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I THE HATCH REVIEW ENCOMPASSES SEVERAL ISSUES f

e UNITS 1 AND 2 SEISMIC DESIGN CRITERIA e IN - STRUCTURE SPECTRA PEAK BROADENING

{

(

15% VS 10%)

e UTILITY REANALYSIS e UPGRADE MODELS e REMOVE EXCESS CONSERVATISM

• GENERATE FLOOR RESPONSE SPECTRA e COMPARE WITH ORIGINAL DESIGN SPECTRA e EVALUATION e DVRC DAMP!NG FOR PIPING e UNIT 1 DESIGN GROUND RESPONSE SPECTRA

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g INFORMATION FOR THIS EVALUATION WAS PROVIDED AS FOLLOWS:

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• INITIAL REQUEST SEPTEMBER 11,1986

• SOIL PROFILE, FOUNDATION DATA

• DAMPING -- PROCEDURES, VALUES

• FLOOR RESPONSE SPECTRA COMPkRISON

• DYNAMIC MODEL -- DG BLDG

• SEISMIC ANALYSIS METHODS COMPARISON

• NOVEMBER 13,1986

• FOLLOW - UP REQUEST DECEMBER 15,1986

• SOIL PROFILE

• DYNAMIC MODELS -- RB UNIT 1, CONTROL

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BLDG, INTAKE STRUCTURE

• ARTIFICIAL ACCELERATION TIME HISTORIES -- UNITS 1 AND 2

• MARCH 4,1987 i

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• SUBSTANTIAL CONSERVATISM EXISTS IN DESIGN RESPONSE DUE.TO SSI/ STRUCTURE ANALYSIS PROCEDURES EVEN IGNORING EMBEDMENT

• IN GENERAL, BOTH SOIL PROFILES SHOW CONSERVATISM. HOWE"ER, LOW FREQUENCY RESPONSE FOR THE SOFT PROFILE SHOWS SOME EXCEEDANCES.

l CASE 2 EMBEDDED FND/ UNIT 1 GROUND MOTION eVERY SUBSTANTIAL CONSERVATISM EXISTS IN DESIGN RESPONSE WHEN EMBEDMENT EFFECTS ARE INCLUDED FOR THE SOFT PROFILE: COMPARABLE RESPONSES FOR THE STIFF PROFILE l

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• DESIGN RESPONSES ENVELOPE EXCEPT FOR SLIGHT EXCEEDANCES AT LOW FREQUENCIES

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p' NEXT STEPS

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e SUPPLEMENT EXISTING COMPARISONS WITH UNIT 2 DESIGN RESULTS l

e COMPLETE SIMILAR ANALYSES FOR THE DIESEL GENERATOR BUILDING AND THE INTAKE

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STRUCTURE

• NRC TO PROVIDE SITE SPECIFIC GROUND MOTION DEFINITION FOR UNIT 1 EVALUATION l

e PERFORM EVALUATION OF REACTOR BUILDING, CONTROL BUILDING, DIESEL GENERATOR BUILDING, AND INTAKE STRUCTURE FOR NRC SPECIFIED SITE SPECIFIC SPECTRA e DOCUMENT RESULTS AND CONCLUSIONS i

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