ML20059F216

Submits Daily Highlight Re Meeting W/Util on 940120-21 at Monroeville,Pa to Discuss Seismic Analysis & Structural Design Criteria Used for AP600 Design

ML20059F216
Person / Time
Site:	05200003
Issue date:	01/10/1994
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Murley T NRC
References
NUDOCS 9401130200
Download: ML20059F216 (7)

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.7  % UNITED STATES E[172

[ NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555-0001

%,,,,,# January 10, 1994 Docket No.52-003 9

MEMORANDUM FOR: T. Murley G. Lainas R. Zimmerman F. Miraglia J. Roe B. Boger W. Russell J. Zwolinski C. Thomas J. Callan E. Adensam F. Congel D. Crutchfield B. Grimes E. Butcher W. Travers J. Wiggins W. Bateman, ED0 F. Gillespie B. D. Liaw M. Slosson S. Varga A. Thadani Operations Center J. Calvo M. Virgilio C. Rosei THRU: R. W. Borchardt, Director Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation FROM: Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

SUBJECT:

DAILY HIGHLIGHT - NOTICE OF MEETING WITH WESTINGHOUSE TO DISCUSS THE DESIGN OF THE AP600 DATE AND TIME: January 20 and 21, 1994 8:30 a.m. - 4:30 p.m.

LOCATION: Westingtnwr Energy Center Westinghou a Electric Corporation Monrocil'ile, Pennsylvania PURPOSE: To discuss the seismic analysis and structu' al design criteria used for the AP600 design.

3 2 O O.:f 7 94o1:302o0 9aoito PDR NBC RE CEdIE0 biEEY ADOCK 05200003 P PDR

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January 10, 1994 PARTICIPANTS *: ME Westinahouse G. Bagchi R. Orr S. Lee D. Lindgren T. Cheng et al.

D. Terao H. Graves T. Kenyon et al.

(Original signed by)

Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

Agenda cc w/ enclosure:

See next page

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to the "Open Meetings and Statement of NRC-Staff Policy," 43 Federal Reoister 20858, June 28,1978. However, portions of this meeting may be closed to protect Westinghouse proprietary information.

Members of the public who wish to attend should contact me at (301) 504-1120.

DISTRIBUTION:

4; Docket = File' PDST R/F RBorchardt RArchitzel PDR PShea TKenyon FHasselberg KShembarger AChaffee, EAB JMoore, 15B18 EJordan, MNBB3701 WDean, 17G21 OPA NRR Mailroom ACRS (11) (w/o encl)

GZech, RPEB GBagchi, 7H15 Slee, 7H15 TCheng, 7H15 DTerao, 7H15 HGraves, NLS217A 7

0FC LA:PDST:ADAR PMWbSk:dDAk SC:PDST:ADAR NAME PShea 44/9 TK'ehohikz RArchit5el DATE 01/9/94 Ol/)DY94 01//0 /94 0FFICIAL RECORD COPY: ECSBMTG.TJK

Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo Mr. Victor G. Snell, Director Nuclear Safety and Regulatory Analysis Safety and Licensing Nuclear and Advanced Technology Division AECL Technologies Westinghouse Electric Corporation 9210 Corporate Boulevard P.O. Box 355 Suite 410 Pittsburgh, Pennsylvania 15230 Rockville, Maryland 20850 Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C. 20585 l l

Mr. S. M. Modro EG&G Idaho Inc. .

Post Office Box 1625 '

Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Room 8002 Washington, D.C. 20503 Mr. Frank A. Ross i U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 u

9 Seismic Analysis and Structural Design Criteria Meeting Agenda - January 20 and 21, 1993 SSAR Chapter 3.3 - Wind and Tornado Loadings 3.3.1 Wind Loadings

1. Importance Factor for Non-Safety-Related Structures (EPRI URD Passive Section 4.5.2, Chapter 1) 3.3.2 Tornado Loadings SSAR Chapter 3.5 - Missile Protection 3.5.1.4 Missiles Generated by Hntural Phenomena 3.5.2 Structures, Systems and Components to be Protected from Externally Generated Missiles 3.5.3 Barrier Design Procedures SSAR Chapter 3.7 - Seismic Design

1. Seismic Input

2. Seismic System Analysis of Nuclear Island Structures

a. Response Spectrum Analysis

b. Time-History Analysis

c. Soil-Structure Interaction

d. Development of Floor Response Spectra

3. Interaction of Non-Category I structures with Seismic Category I Structures

4. Seismic Subsystem Analysis

a. Seismic Analysis of Hiscellaneous Structures, Including Equipment and Piping Modules SSAR Chapter 3.8 - Design of Category I Structures 3.8.2 Steel Containment

1. Seal Material at Transition Region

a. Composition

b. Obtaining Method

c. Uncertainties

d. Accessibility for Periodic Inspection

e. Behavior under Severe Accident Enclosure

I i

f. Degradation for 60-Year Design Life

g. Measurements for Moisture Collection

2. Pre-Operational SIT

a. Measurements at Critical Locations for SCV

3. Potential Sources of a Missile or High-Pressure inside/outside SCV from High-Energy Line Break

4. Air Baffle

a. Design and Effects on SCV and SB

b. Flexible Seal

c. Connection to SB Roof

5. Basis for (1.0,0.4,0.4) Method for Seismic Loads

6. Ultimate Capacity Calculation

a. Level C

b. SI Criterion vs. von Mises Criterion

c. Strain Calculations

7. ASME Codes for Buckling (EPRI URD Passive, Sec. 6.6.2.1, Chap. 5)

a. NE-3222 for External Pressure

b. N-284 for Internal Pressure

8. Penetrations Requirements

9. Basis for Corrosion Allowance

10. Most Stressed Portion of SCV

a. Membrane, Bending

b. Buckling

11. Sandia Strain Criteria

a. Far from Discontinuities

b. At or Near Discontinuities 3.8.3 Concrete and Steel Internal Structures of Steel Containment

1. Effects of Concrete Cracking for C-I Structures 3A Structural Modules

1. Integrity of Joints

a. Strength and Ductility

2. Seismic Damping Values

3. Stiffness Degradation

4. QA and QC Requirements for Transportation and Installation of Modules

5. Verification Testing after Installing Modules

6. Codes for i

a. Steel-only

b. Concrete-only

c. Steel-and-Concrete Composite

7. Analysis Methods and Design Criteria for Severe Accident Impulse Loads ,

3.8.4 Other Category I Structures

1. Embedded Portion of Exterior Walls of NI

a. Design

b. Static Soil Pressure

c. Soil Pressure Induced by Earthquake

d. Local Failure during SSE

2. Safety-Related-Structure Roof

a. Drainage

b. Ponding Possibility

3. Settlement of Adjacent Buildings

a. Integrity of Underground Piping or Tunnel

4. Stability Evaluation for Safety-Related-Structure  ;

a. Foundation Rebound

b. Settlement

c. Differential Settlement

d. Bearing Capacity-

5. Seismic Load Calculation Method

a. SRSS or (1.0, 0.4, 0.4)

b. Reduced Live Load for Global Seismic loads Computation .;

6. Global Pressure / Temperature Effects for Subcompartments

7. Use of Epoxy Coated Reinforcing Steel

'i I

8. Design Criteria for C-II

9. Critical Locations 3.8.5 Foundations

1. Basis for Exclusion of C-II

2. Foundation Hat Construction Procedures

3. FS against Slinging and Overturning of NI due to Tornado and Wind 1

1