ML20045B975
| ML20045B975 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 06/16/1993 |
| From: | Wambach T Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| NUDOCS 9306210341 | |
| Download: ML20045B975 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 g
June 16, 1993 Docket No.52-002 MEMORANDUM FOR:
T. Murley G. Lainas R. Zimmerman F. Miraglia J. Roe B. Boger W. Russell J. Zwolinski R. Gallo J. Partlow E. Adensam F. Congel D. Crutchfield B. Grimes E. Butcher W. Travers J. Richardson W. Bateman, EDO A. Gody B. D. Liaw A. Vietti-Cook S. Varga A. Thadani Operations Center J. Calvo M. Virgilio C. Rossi THRU:
A R. W. Borchardt, Acting Director
,1 Standardization Project Directorate IAssociateDirectorateforAdvancedReactors and License Renewal Office of Nuclear Reactor Regulation FROM:
Thomas V. Wambach, Project Manager, Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
DAILY HIGHLIGHT - FORTHCOMING MEETING WITH ABB-COMBUSTION ENGINEERING (ABB-CE) FOR SYSTEM 80+ (PIPING, STRUCTURAL, MECHANICAL, AND MATERIALS OPEN ISSUES)
DATES & TIMES:
June 21, 1993 (10 a.m. - 5 p.m.)
June 22-25, 1993 (8:30 a.m. - 5 p.m.)
LOCATION:
ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500 PURPOSE:
Discussion of remaining open issues from the CE System 80+
draft safety evaluation report (DSER) in the structural, piping, mechanical, and materials areas. A proposed agenda is enclosed.
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PARTICIPANTS *:
HR.Q NRC CONSULTANTS ABB-CE M. Franovich G. DeGrassi S. Ritterbusch S. Magruder P. Bezler L. Gerdes G. Bagchi J. Braverman et al.
D. Terao P. Chen J. Huang S. Ali D. Smith S. Lee i
H. Ashar R. Li S. Hou (Original signed by) i Thomas V. Wambach, Project Manager Standardization Project Directorate Associate _ Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation r
Enclosure:
Meeting Agenda cc w/ enclosure:
See next page
- Meetings between the 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 "Open Meeting Statement of NRC Staff Policy," 43 Federal Reaister 28058, 6/28/78. Members of the public who wish to attend should contact me at (301) 504-1103.
DISTRIBUTION:
Docket File PDST R/F SBajwa,12G18 TEssig PDR JNWil son TVWambach RBorchardt TBoyce MXFranovich PShea _
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EJordan, MNBB 3701 GGrant, EDO -
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GBagchi, 7H15 NRR Mailroom; 12G18
' P0' Dell, PTSB JMoore, 15B18 RPerch, 8Dl-DTerao, 7H15 JHuang, 7E23 SAli, 7H15 MPratt, 7E4' DSmith, 704 Slee, 7H15 HAshar, 7H15 RLi,'7E23 Shou, 7H15 SC:PDST:fDAR 0FC:
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CM0621.TVW
ABB-Combustion Engineering, Inc.
Docket No.52-002 cc:
Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Mr. C. B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stan Ritterbusch Nuclear Licensing ABB-Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 Mr. Sterling Franks U. S. Department of Energy NE-42 Washington, D.C.
20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Washington, D.C.
20503 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 Washington, D.C.
20006 Joseph R. Egan, Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, D.C.
20037-1128 Mr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500
System 80+ DSER Issuas/Rssoluticn Mesting (Mechanical. Structural, Materials, Chemical, and Cdntainment Performance)
June 21-25, 1993 ABB/CE offices (Windsor, Connecticut)
Monday, June 21 10:00 Introductory remarks (ABB/CE and NRC) 10:30 - 12:00-Structural DSER Issues 12:00 Lunch 1:00 - 5:00 Structural DSER Issues (continued)
Tuesday, June 22 8:00 - 12:00' Structural DSER Issues (if necessary)
Materials / Chemical DSER Issues 12:00 Lunch 1:00 - 5:00 Containment Performance Issues (related to structural integrity under severe accidents)
Wednesday, June 23 8:00 - 12:00 Piping DSER/DSDG Issues Mechanical Issues (e.g., IST, seismic EQ, safety classification, RV internals) 12:00 Lunch 1:00 - 5:00 Piping DSER/DSDG Issues (continued)
Mechanical Issues (continued)
Thursday, June 24 8:00 - 12:00 Piping DSER/DSDG Issues (continued)
Mechanical Issues (if necessary) k 12:00 Lunch g
1:00 - 5:00 Piping OSER/DSDG Issues (continued) 2 Friday, June 25 8:00 - 12:00 Piping DSER/DSDG Issues (continued) 12:00 Lunch 1:00 - 5:00 Piping DSER/DSDG Issues (if necessary)
NRC Meeting with ABB/CE on RESOLt1 TION OF SYSTEM 80+ PIPING DESIGN ISSUES June 23-25, 1993 At Offices of ABB/CE, Windsor, CT AGENDA I.
Discussion on DSER open issues Specific edition of ASME Code List of ASME Code Cases a
Design specifications Experimental stress analysis,
Inelastic analysis methods Small-bore piping method Non-seismic / seismic interaction a
Buried piping ASME Section III, Appendix N Computer _ codes Dynamic piping model Seismic input Design transients Thermal oscillations (Bulletin 88-03)
Combination of Seismic Inertia and SAM Modal composite damping Enviromental effects on fatigue Safety relief valve design, installation and testing Welded attachments Intersystem LOCA Pipe support jurisdiction boundaries Pipe support' loads and load combinations Pipe support baseplate and anchor bolt design Use of energy absorbers and limit stops Pipe support stiffness and deflection limits design of supplementary steel pipe support gaps and clearances II.
Discussion on April-93 audit open issues Single earthquake design Dynamic analysis methods Fluid transient analysis a
Thermal stratification and striping Equivalent static method Definition of ZPA Spectral peak broadening NSSS response spectrum Response spectrum options Response spectrum amplification
Nodal point spacing Cut-off frequency effects Branch decnupling criteria Seismic /non-seismic interface Functional capability criteria Pipe support design to N690 a
Expansion anchors Tubesteel design criteria Snubbers and seismic supports Tubing design III. Discussion on May-93 audit open issues A.
Questions on sample analyses --
Pressurizer surge line
=
Shutdown cooling system Feedwater economizer line -
B.
Information for Benchmark Program --
== - --
Feedwater line waterhammer sample analysis using direct
=
integration time history mmethod C.
Issues on high-energy line breaks --
Loads on main steam valve house wall Document the purpose of calculation
- Justify the torsional reaction moment Calculate flooding and compartment pressurization
- Evaluate wall capacity to withstand the loads
- Revise SSAR and DSDG to include: (1) pipe whip restraint design criteria, and (2) methods of containment penetration analysis Pipe whip effects on division wall --
- Provide document on CVCS charging pump discharge line n break Revise SSAR and DSDG to include design criteria and analysis methods Break locations in Feedwater Economizer line --
l Provide finalized analysis and verify Code version D.
Issues on leak-before-break --
t l
Type 347SS fabrication problems l
Thermal aging in cast stainless steels Justification for neglecting torsional moments l
Consideration of nondimensional representations Justification for linearity assumption l
.