ML19296D820

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Forwards Preliminary Subj Agenda for 800227-28 Loft Review Group Meeting in Salt Lake City,Ut.Eg&G Describing L3-6 Nuclear Experiment Plans Encl
ML19296D820
Person / Time
Issue date: 02/14/1980
From: Mcpherson G
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Agee L, Banerjee S, Barber R
ELECTRIC POWER RESEARCH INSTITUTE, ENERGY, DEPT. OF, MCMASTER UNIV., HAMILTON, ON
Shared Package
ML19296D821 List:
References
PROJECT-344A NUDOCS 8003130286
Download: ML19296D820 (16)
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Text

{{#Wiki_filter:e-g#>A RfC d UNITED STATES y* NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 \\ } ppg Ph lwe 5 g g pq s9Ll

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February 14,19 0^) kl j,' d cuac Those on Attached List Gentlemen:

Subject:

LOFT Review Group Meeting The preliminary subject agenda for the LOFT review group meeting on February 27 and 28 has been finalized and is attached. The meeting location is at the Tri-Arc Travel Lodge (telephone: 801-521-7373) in Salt Lake City, Utah. The following materials are enclosed for your review and discus-sion during the meeting. 1. LOFT Expe 1 ental Program Document (LEPD). 2. Operational Transient (L6) Test Series EOS. 3. Letter describing the L3-6 nuclear experiment plans. You will note that there are four items on the agenda which invite review group participant comment. All members, advisors, and consultants are cordially invited to attend. Sincerely, f G. D. McPherson, Chief LOFT Research Branch Division of Reactor Safety Research

Enclosures:

As stated 60031 no 28f

(P-Addressees - Letter Dated February 15, 1980 L. Agee, EPRI S. Banerjee, McMaster Univ. R. W. Barber, DSE, DOE-HQ R. G. Bearden, EG&G Idaho W. Binner, IfR, AUSTRIA J. Block, CREARE K. J. Brinkman, ECN, NETHERLANDS G. F. Brockett, ITI

1. Catton, ACRS P. Y. Chen, NRR, NRC C. B. Davis, EG&G Idaho D. Eisenhut, NRR, NRC S. Fabic, RES, NRC T. Fernandez, YAEC R. Fraley, ACRS (3 cys)

P. Griffith, MIT S. Hanauer, NRR, NRC Y. Y. Hse, RES, NRC W. V. Johnston, RES, NRC W. Kato, BNL N. C. Kaufman, EG&G Idaho S. Kellman, W S. T. Kelppe7 EG&G Idaho N. N. Kondic, RES, NRC R. T. Lahey, RPI R. R. Landry, RES, NRC N. Lauben, NRR, NRC P. Leach, EG&G Idaho m. D. Lummerzheim, FRG G. Markoczy, SFIfFR, Switzerland F. Mayinger, LulfV, GERMANY M. Meerbaum, B&W G. Menzel, CE C. Moser, EI T. E. Murley, RES, NRC S. A. Naff, EG&G Idaho H. Nakamura, JAERI, JAPAN P. E. Norian, NRR, NRC P. North, EG&G Idaho T. M. Novak, NRR, NRC F. Odar, NRR, NRC A. Olsen, RISO, DENMARK K. Parczewski, NRR, NRC D. Ross, NRR, NRC Z. R. Rosztoczy, NRR, NRC S. Z. Rouhani, EG&G Idaho P. J. Schally, EG&G Idaho N. H. Shah, B&W B. Sheron, NRR, NRC M. Shiba, JAERI, JAPAN J. E. Solecki, DOE-ID T. M. Su, NRR, NRC

,s-Addressees - Letter Dated February 15, 1980 T. Sudoh, EG&G Idaho J. Voglewede NRR, NRC G. H. Weimann, EG&G Idaho J. D. White, ORNL K. R. Wichman, NRR, NRC L. Winters, EG&G Idaho L. J. Ybarrondo, EG&G Idaho Public Document Room (2 cys)

LOFT REVIEW GROUP MEETING AGENDA Salt Lake City, Utah - Tri-Arc Travel Lodge February 27th and 28th, 1980 Wednesday - 2/27/80 8:00 Introduction G. D. McPherson Experimental Results 8:15 LOCE L3-1 D. L. Batt 8:35 LOCE L3-2 D. L. Batt 9:00 L3-1/L3-2 Comparisons D. L. Batt E.ceriment Predictions 7 9:20 LOCE L3-1 K. G. Condie 9:40 LOCE L3-2 K. G. Condie 10:00 BREAK 10:20 L3-1/L3-2 Comparisons; Break Flow K. G. Condie and Core Bypass Sensitivities 11:00 Core Bypass in Commercial PWRs Vendors ~ 12:00 LUNCH Code Experience in Small Break Analysis 1:00 L3-1 Pre-and Post-Experiment c lcu-K. G. Condie a lations - Model Preparation 1:30 L3-2 Pre-and Post-Experirnent Calcu-K. G. Condie lations - Learning Curve 2:00 Adequacy of Codes, Best Code, Areas for K. G. Condie Improvement, New Algorithm Needs 2:30 BRE1K 2:50 Vendor and Research Group Small Break Review Group Participants Calculation Experience 5:00 ADJ0 URN

LOFT REVIEW GROUP MEETING AGENDA (Contii.ued) Thursday - 2/28/80 LOFT Schedule and Experiment Definition 8:00 Experiment Sequence S. A. Naff 8:20 Operational Transients (L6 Series) P. A. Harris 9:00 L6 Interests Review Group Participants 10:20 BREAK 10:40 LOCEs L3-3 and L3-4 Plans J. R. White 11:10 Pumps On/0ff (L3-5/L3-6) Plans J. D. Burtt 11:40 L3-5/6 Interests Review Group Participants 12:30 LUNCH LOFT-Semiscale-PWR Relationships for Small Breaks 1:30 LOFT-Semiscale Counterpart Experiment Corres-J. P. Adams pondence 2:00 PWR Design Instrun,entation and Operation L. D. Goodrich Implications 2:30 LOFT Man / Machine Program

0. R. Meyer 3:00 BREAK LOFT Experimental Measurements 3:20 Break Flow Measurement Calibration J. S. Martinell 3:40 Small Break Instrumentation - Experience and D. J. Hanson Plans 4:30 Additional Topics G. D. McPherson 5:30 ADJOURN

66E6 Idaho, Inc. g

p. o. Box 1625 Idaho Falls, Idaho 83401 February 15, 1980 Mr. R. E. Tiller, Director Reactor Operations & Programs Division Idaho Operations Office - DOE Idaho Falls, ID 83401 REVISION TO L3-6 INFORMATION PACKAGE - Kau-34-80 Ref:

N. C. Kaufman ltr to R. E. Tiller, Kau-29-80, L3-6 I' .;.ation Package, February 5, 1980

Dear Mr. Tiller:

The Loss-of-Fluid Test (LOFT) Loss-of-Coolant Experiments (LOCEs) L3-5 and L3-6, referenced in the above letter, have been changed from nonnuclear tests to nuclear tests. The purpose of this letter is to transmit this change to those organizations participating in the standard problem. Attached is a revised summary of the L3-6 initial conditions and plant con-figuration description and should replace the referenced summary. The summary is identical to that described in the reference, with the following excep-tions: 1. Power level will be established at 50 MW prior to the test; scram will occur on low pressure trip (2058 psia). 2. Accumulator and low pressure injection system will not be valved out; accumulator will inject at 600 psig, LPIS will initiate at 308 psia; however, flow will not start until pressure is less than 232 psia. An Experiment Operating Specification (EOS) for LOFT LOCE L3-5 and L3-6 will be transmitted as soon as possible. Very truly yours, /[ , /\\ u N. C. Kaufman Director, LOFT JDB:tc

Attachment:

As stated

Mr. R. E. Tiller February 15, 1980 Ka u-34-80 Page 2 cc: L. Agee D. Alf, NRC S. N. Aksan, Switzerland T. M. Anderson Jean-Claude Amrouni, France R. W. Barber, DSE, DOE-HQ (2) G. Brockett J. Bolstad R. Brodsky, DOE, Washington D.C. M. Buckner H. S. Chung A. R. Edwards, United Kingdom H. Holmstrom, Finland T. Knight A. Levine E. Johnson, France I. H. Karwat, F. R. Germany G. D. McPherson, RSR, NRC (2) G. F. Owsley R. Perssan, Sweden K. T. Routledge, United Kingdom I. G. Santarossa, Italy S. Shannon J. H. Taylor B. Teitiman N. Tellier, France T. Tobioka, Japan W. J. Turner, Australia W. Winkler, West Germany R. W. Kiehn, EG&G Idaho w/o enc.

SUtdARY OF L3-6 TEST CONDITIONS L3-6 Initial Conditions Core Power 50 fG t 1 6 PCS Flow Rate 3.8x10 .05 lbm/hr PCS Pressure (hot leg) 2168 15 psia ~ PCS Temperature: T 542.8 t 7 F cold Thot (Ref) 573.8 t 7 F PZR Level 44.5 t 7 inches PCP Injection Flow 1 t.E gpm Control Rod Pos'n 54 1.5 inches HPIS a. Flow Rate See attached Figure 1 b. Initiation Setpoint 1908 t 27 psia c. Liquid Temp. 85 t 5 F d. Injection Point Downcomer LPIS a. Flow Rate See Figure 2 b. Initiation Setpoint 308 t 27 psia c. Liquid Temp 85 t 5 F d. Injection Point Downcomer Accumulator a. Initiation Setpoint 612125 psia b. Liquid Temp 90 t 10 F c. Injection Point Downcomer 3 d. Volume to be injected 76.2 ft e. N Volume 42.8 ft 2 BST (Initial conditions only - pressure and temp. will not be controlled during the test) a. Liquid Level 50 t 2 inches b. Temp and Pressure See attached Figure 3 c. Recirc Rate 300 gpm

L3-6InitialConditions(Contin Broken loop Hot and Cold Leg (nea Steam Generator Liquid Levelr GOBVs) a. Aux feedwater (at 8 gpm) b. Aux feedwater temp 90 F System Configuration Immediately P i Test L3-6 is a nuclear testr or to Rupture The prime specified power and flow for 40 hours coolant - The broken loop will be installed and minimum pric configured f The following equipment will be t rupture: urned off or isolz 1. Pressurizer heaters 2. Broken loup recirculation 3. Broken loop hot leg heaters 4 Purification system The break will be in the intact l to the blowdown suppression tank (Boop The t piping configuration. ST). See attachec piece attached to the intact loopAll p choke plane remains at the break orifico of the break. ce. This inclut The valve downstream of seconds. a will The test will be terminated when t The accumulator will be isolated e LPIS flow has beer system. when it empties, prior S* Me

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_.j EGsG idano,inc. r.o.eo,,e2s idaho Falls, Idaho 83401 January 15, 1980 Mr. R. E. Tiller, Director Reactor Operations & Programs Division Idaho Operations Office - DOE Ioaho Falls, ID 83401 LOFT EXPERIMENTAL PROGRAM DOCUMENT (LEPD) - Kau-35-80

Dear Mr. Tiller:

Enclosed is a copy of the Loss-of-Fluid Test (LOFT) Experimental Program Document (LEPD) for your approval. Your approval is re-quested by March 1,1980. The LEPD, upon your approval, will become a controlled access, numbered document. Updates to the LEPD will be sent out on a section-by-section basis. In this way, all parties concerned will have a document that reflects LOFT's current plans and schedule. In addition, it is our intention to make the LEPD the primary approval document for the Department of Energy (DOE). The descrip-tion of planned experiments will be sent as they are finalized for your approval. Table 1 of the LEPD lists the status of the experi-ments at this time. The Experiment Operating Specification would become an internal document sent to you for your information. LOFT's standard practices are being altered to incorporate these changes in the document opproval procedures. Verytrulyyours[ // A.' / N. Kau Director,' LOFT / JDB:tc

Enclosure:

As stated cc: R. W. Barber, DSE, DOE-HQ (2) G. D. McPherson, RSR, NRC (2) R. W. Kiehn, EG&G Idaho (w/o enc.)}}

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