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Notification of 931001 Meeting W/Util in West Lafayette,In to Discuss GE Testing Program for Sbwr Design & NRC Confirmatory Test Program Activities
	ML20057B610
Person / Time
Site:	05200004
Issue date:	09/17/1993
From:	Malloy M; Office of Nuclear Reactor Regulation
To:	Borchardt R; Office of Nuclear Reactor Regulation
References
	NUDOCS 9309220333
	Download: ML20057B610 (8)
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g'o,, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 5 ;p WASHINGTON, D. C. 20555 o# September 17, 1993 ;

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i Docket No.52-004 4

3 MEMORANDUM FOR: R. W. Borchardt, Director ,

Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal ,

Office of Nuclear Reactor Regulation FROM: Melinda Malloy, Project Manager _

Standardization Project Directorate i Associate Directorate for Advanced Reactors and License Renewal ,

Office of Nuclear Reactor Regulation '

SUBJECT:

NOTICE OF MEETING WITH GE NUCLEAR ENERGY (GE) TO DISCUSS THE- ;

GE TESTING PROGRAM AND NUCLEAR REGULATORY COMMISSION CONFIR- !

MATORY TESTING PROGRAM FOR THE SIMPLIFIED BOILING WATER i REACTOR (SBWR) !

October I, 1993 - (8 a.m. - 5:10 p.m.)-

> DATE &-TIME:

LOCATION: Purdue University School of Nuclear Engineering Nuclear Engineering Building (Grant Street)

West Lafayette, Indiana 47907 PURPOSE: To discuss GE's testing program for the SBWR design and the NRC's confirmatory test program activities. See enclosed agenda.

NQTE: Proprietary features on the GE SBWR design are expected to be discussed during the meeting. These portions of the meeting will be closed to the public.

NBC FRE CENTER COPT 9309220333 930917 'M

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l September 17, 1993 ,

PARTICIPANTS:* NRC GE Purdue i.

M. Malloy P. Billig M. Ishii )

R. Hasselberg K. Vierow V. Ransome, et al. ;

J. Han J. Fitch, et al.

R. Elliott, et al.

Origin!Swer pw. ;

Melinda Malloy, Project Manager i Standardization Project Directorate '

Associate Directorate for Advanced Reactors i and License Renewal !

Office of Nuclear Reactor Regulation :

l Enclosure-Agenda .

cc w/ enclosure:

See next page j

Meetings between NRC technical staff and applicants or licensees are open I for interested members of the public, petitioners, intervenors', or other i parties to attend as observers pursuant to "Open Meeting Statement of NRC ;

Staff Policy," 43 Federal Reaister 28058, 6/28/78. However, portions of l this meeting may be closed to protect GE Nuclear Energy proprietary t information. Members of the public who wish to attend should contact me at '

(301) 504-1178. {

DIS'RIBUTION:

Docket File PDST R/F- TMurley/FMiraglia, 12G18 - l DCrutchfield PDR WRussell, 12G18

, WTravers RBorchardt JNWilson i l AThadani/MVirgilio, 8E2 MMalloy SNinh PShea DMcPherson, 8E2 RCaruso, 8E2 RBarrett, 8H7 JKudrick, 8H7 RElliott, 8H7 CHoxie, 8H7 JMonninger, 8H7 MSnodderly, 8H7 RJones, 8E23 TCollins, 8E23 Alevin, 8E23 JWiggins, 7026 GBagchi, 7H15 DTerao, 7H15 SNHou, 7H15 AAli Syed, 7H15 Slee, 7H15 BSheron/TKing, NLS007 LShotkin, NLN353 JHan, NLN353 TLee, NLN353 YSchen, NLN353 FEltawila, NLN344 CTinkler, NLN344 ANotafrancesco, NLN344 J0'Brien, NLS217 ETana, 12G18 P0' Dell, 12E4 GDick, 12G18 JMoore, 15B18 MFinkelstein,15B18 ATGody, Jr., 17G21 ACRS (11) RHasselberg- g 0FC: LA:PDST:ADAR 'P: T:ADAR P4 DST:ADAR NAME: PShea g 09//g/93'g alloy:sg S1 SC:PDST:h[}

JNWilson DATE: 09/ /6/93 09 ,,/93 09/g1/93 J

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General Electric Company Docket No.-52-004 I cc: Mr. Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy 175 Curtner Avenue San Jose, California 95125 i

Mr. Laurence S. Gifford 1 GE Nuclear Energy I 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 l l Director, Criteria & Standards Division l Office of Radiation Programs i

U.S. Environmental Protection Agency 401 M Street, S.W.

Washington, D.C. 20460 Mr. Sterling Franks l U.S. Department of Energy

NE-42 Washington, D.C. 20585 :

Mr. Jeffrey C. Baechler I GE Nuclear Energy :

175 Curtner Avenue, MC-782 :

San Jose, California 95125 i Mr. Frank A. Ross I Program Manager, ALWR :

Office of LWR Safety & Technology '

U.S. Department of Energy i NE-42 19901 Germantown Road Germantown, Maryland 20874 !

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MEETING ON GE TESTING PROGRAM & NRC CONFIRMATORY TESTING PROGRAM FOR THE SIMPLIFIED BOILING WATER REACTOR (SBWR)

October 1,1993 Proposed Agenda Purdue Universitv. West Lafavette. Indiana >

(Meet in Student Union Lobby at 7:55 a.m. and walk to the meeting room a block away) l 8:00 - 8:10 a.m. Introduction 8:10 - 9:00 a.m. Overview of SBWR design (GE) 7 9:00 - 9:50 a.m. Answers to Purdue's questions (attached) (GE) 9:50 - 10:00 a.m. Overview of GE's SBWR testing programs (GE) 10:00 - 10:10 a.m. BREAK 10:10 - 11:10 a.m. GIST facility design, instrumentation, and test results (GE) 11:10 - 12:10 p.m. GIRAFFE facility design, instrumentation, ace vst results (GE) 12:10 - 1:10 p.m. LUNCH 1:10 - 1:50 p.m. PANDA facility design, instrumentation, and test matrix (GE) 1:50 - 2:00 p.m. Overview of NRC confirmatory testing program (NRC) 2:00 - 3:30 p.m. Purdue test facility scaling, design, instrumentation, and test matrix (Purdue) 3:30 - 3:40 p.m. BREAK 3:40 - 4:10 p.m. Comments on Purdue Facility (GE and NRC) 4:10 - 4:30 p.m. Action items and conclusions (NRC) 4:30 - 5:10 p.m. Tour of Purdue test facility site 5:10 p.m. ADJOURN Enclosure

i PURDUE UNIVERSITY )

SCHOOL OF NUCLE AR ENGINEERING N llk September 15,1993 '

8 A Draft of i Required Informations From GE About Prototype SBWR System

1. Fced Water Line

a. During a feedwater line break the flow will be choked / restricted by the area of the !'

sparger. Therefore we need detailed design of the sparger.

b. Isometric drawing of the Feedwater supply line is needed to know the elevation difference etc. in ca.te of break. .

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c. . What action is taken with feedwater supply line during a LOCA? Which valves are !

closed ( There is one manual valve, three check valves and one motor operated - ;

valve on each line. Which of these are closed during LOCA)? See attached Table ;

3.1 in SBWR Response to Loss of Feed Water. At Level 2, what actions are taken? ;

2. Provide detailed information on the loss coeffecients for all the lines. In particular give the l !

minor loss coeffecients of all the valves in the following lines: l

a. Main Steam line l b. IC Supply line (from vessel toIC) '

c. 1C condensate drain and vent line ,

d. PCC supply, drain and vent line

e. GDCS drain line

f. Equalization line j g. CRD line (into vessel bottom)

h. RWC/SDC system linc

! i. Drywell & wetw ell spray lines (flow rates also needed)

j. Feed Water line

3. Provide the following information for the ICCS and PCCS :

a. What is the design of the headers and the separators? (drawings are needed). In l particular please provide the loss coeffecients for these.

b. IC pool water level depletion as a function of time (up to 3 days). Can we reduce the volume?

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c. Provide the elevation of the PCCS condensate return line.

d. Do we have IC tube rupture detection system? What is the automatic detection system? Line break (retum) need not be consider.

e. Detailed design of the ICS and PCCS modules.

4. RPV:

a. What is the insulation material? (its physical thennal properties and thickness are needed)

b. What is the loss coefficient across the steam separators?

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c. Explain the pressure drop data across the lower plenum and the core plate. K values l of the core inlet flow restrictors (orifice K values)is needed.

5. How am the upper drywell and the lower drywell connected? Detail of drywell design including neutron shield outside the vessel are needed. (drawings, flow area, loss coefficcts).

6. Need isometric drawings for pipings of the following auxiliary systems :

a. Reactor water cleanup system / Shut Down System

b. Control Rod Drive System

c. Fuel and Auxiliary Pool Cooling Systems

d. Feed Water Lines

7. Can GE provide us with their code calculations of blowdov7n phase? We are interested in the thermal hydraulic parameters at about 150 sec. After MSL break, information on vessel liquid level (time dpendent level due to swelling), quality, void fraction, and exact ;

decay heat power levels will be useful.

8. During the initial transients following LOCA or blowdown, say at and after 150 psi, what are the status of the following lines?

a. Is RWC/SD System operating? What valves are open?

b. In CRD system what valves are open? Arc pumps active?

c. Is FAPCS active? What valves are open? Are pumps active?

d. Is FWL pump is tripped? How does it work during and after this stage of transient?

What valves are open?

c. How the vacuum breakers operate during transient? What is the AP to open them?

9. What is the setpoint to open vacuum breakers? What logic am used to open three valves?

10. Operating procedures and actuation logic for low pressure coolant injection of FAPCS and s CRD and RWCU/SDC.

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11. Fault tree analysis for SBWR needed to develope test matrix. Detection of ICS tube j ruptme? Any automatic function to handle ICS tube nipture. ;

. Question and Requests on GIST Facility

1. How were heaters fitted to the vessel? How heater surface temperatures were j measured? l

2. Provide the loss coeffecients in all the lines of GIST facility.

3. Need detailed test results and conditions for five GIST tests used for TRAC G l

! calculations in order to run similar experiments as required by NRC. Need design . l of the break simulation using pipe and valve on various lines of GIST facility.

4. How the pressure sense line were connected to the vessel and pressure transducers?

5. What flow meters were used to measure a) water, b) steam and c) two-phase flow in pipe? And what flow meters were used for downcomer liquid flow rate? ,

ML20057B610

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