ML19274G033
| ML19274G033 | |
| Person / Time | |
|---|---|
| Site: | Atlantic Nuclear Power Plant, Braidwood  |
| Issue date: | 08/02/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908270497 | |
| Download: ML19274G033 (26) | |
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DOCKET NO. STN 50-437 APPLICANT: 0FFSHORE POWER SYSTEMS FACILITY:
FLOATING NUCLEAR PLANTS 1-8
SUBJECT:
SUMMARY
OF MEETING HELD ON JULY 24, 1979 A meeting was held with the applicant on July 24, 1979 to discuss the state-of-technology applicable to the staff evaluation of the FNP core ladle to detennine the need for research in support of the core ladle design. Attendance at the meeting is shown in Enclosure 1.
The agenda of the meeting is presented in.
The Sandia Laboratory summarized its review of the core ladle design as described in OPS Topical Report No. 36A59, "FNP Core Ladle Design and Safety Evaluation."
The viewgraphs used in the presentation are presented in Enclosure 3.
Subsequent to a discussion of the Sandia connents, the applicant stated that they had developed (see Enclosure 4) a testing program which would confirm the adequacy of i.he core ladle design.
It was agreed that tia research program would address the major uncertainties of the core ladle design and would be satisfactory if acceptably complete. The results of the program must be available to the staff to support a final design approval which the applicant would request approximately six inonths prior to the start of platen assembly at the manufacturing site (Blount Island).
The applicant stated that the information presented at the meeting was to be incorporated by an amendment to the topical report.
L e
Ralph A. Birkel Light Water Reactors Branch No. 2 Division of Project Management
Enclosures:
1.
Attendance List 2.
Meeting Agenda 3.
Sandia Viewgraphs 4.
OPS Testing Program For Confinning Adequacy of Ladle Design ces w/ enclosures:
See next page 7908270993
,/
Mr. A. R. Collier President 40G 0 2 9 Offshore Powr Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 cc: Vincent W. Campbell, Esq.
Vice President & General Counsel Of fshore Powr Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 Thomas M. Daugherty, Esq.
Offshore Power Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 Barton Z. Cowan, Esq.
Eckert, Seamans, Cherin & Mellott 600 Grant Street, 42nd Floor Pittsburgh, Pennsylvania 15219 Franklin H. Berry, Jr., Esq.
County Counsel County of Ocean P. 0. Box 757 34 Washington Street Toms River, New Jersey 08753 Anthony Z. Roi sman, Esq.
Natural Resources Defense Council 917 15th Street, N. W.
Washington,D. C.
20005 Dr. Glenn L. Paulson Assistant Connissioner State of New Jersey Department of Environmental Protection Labor and Industry Building John Fitch Plaza Trenton, New Jersey 08625 Keith A. Onsdorff, Esq.
Mi ri am N. Span, Esq.
Assistant Deputy Public Advocates
'520 East State Street Post Office Box 14l Trenton, New Jersey 08625
Mr. A. R. Collier AUG 0 2199 cc:
Mark L. Fi rst, Esq.
New Jersey State Deputy Attorney General State House Annex Trenton, New Jersey 08625 Carl Valore, Jr., Esq.
Valore, Mc Allister, DeBrier, Aron & Westmoreland Mainland Professional Plaza 535 Tilton Road P. O. Box 152 Northfield, New Jersey 08225 Mr. Harold P. Abrams 9100 Amherst Avenue Margate, New Jersey 08402 Dr. Willard W. Rosenberg 8 North Runson Avenue Margate, New Jersey 08402 Mr. John Williamson 211 Forest Drive Linwood, New Jersey 08221 Harold P. Green, Esq.
Fried, Frank, Harris, Shriver and Kampelman Suite 1000, The Watergate 600 600 New Hampshire Avenue, N. W.
Washington, D. C.
20037 Nuclear Coordinator Office of Merchant Marine Safety Connandant (GMMT-4)
U. S. Coast Guard Washington, D. C.
20590 Mr. Mitchell Attalla 4028 Ponce DeLeon Avenue Jacksonville, Florida 322 17 Mr. Reg Crowder Jacksonville Journal P. O. Box 1949 Jacksonville, Florida 32201 o'
.i Mr. A. R. Collier AUG 01109 cc: Sheldon J. Wol fe, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. David R. Schink Department of Oceanography Texas A. & N. University College Station, Texas 77840 Mr. Lester Kornblith, Jr.
Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Richard S. Sal aman, Esq., Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington,D. C.
20555 Mr. Michael C. Farrar Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
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M B o 2 1979 ENCLOSURE 1 ATTENDANCE LIST MEETING WITH OFFSHORE POWER SYSTEMS JULY 24, 1979 0FFSHORE POWER SYSTEMS D. Walker P. Haga C. Dotson R. Bruce NRC - STAFF R. Birkel T. C. Houghton*
T. Walker M. Silberberg A. Marchese R. Sherry ACRS - STAFF G. Qaittschreiber SANDIA LABORATORY R. Coats D. Powers D. Varela AEROSPACE CORPORATION D. Swanson
- Part Time
ENCLOSURE 2 pgg g2 ERI AGENDA i
MEETING WITH OFFSHORE POWER SYSTEMS FNP CORE LADLE DESIGN JULY 24, 1979 1.
Summary of Sandia comments on Topical Report No. 36A59.
2.
OPS evaluation of Sandia comments.
3.
Discussion of state-of-technology for Ladle Design.
4.
Summary of technical uncertainties for core ladle design and associated design impacts.
5.
Discussion of research needs to resolve technical uncertainties.
6.
Status review and future plans for NRC/RES programs of interest.
7.
OPS plans for research support, including fallback positions.
8.
Summary of possible research support for resolution of technical uncertainties.
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TEMPERA TURE BRICK POROSZTY OZFFUSZVZTY MEL T COMPOSZTZON
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AUG 0 21979 CRAC4 D E N E R A-
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AUG 0 21979 PHENOMENOLOGICAL QUESTION-00 THE THERMO-NYDRAUL ZCS OF THE MEL T LEAD TO LOCAL PENETRATZON OF THE MgO 7
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D Aus o 21st PHENOMENOLOGICAL QUESTION-ZS A STABLE, INSULATING CRUST FORMED OVER THE MEL T 7
AUG 0 2 WPS C[VV{\\~
NORZZONTAL EROSZON ZS THE LZFE-TZME LZMZTING PROCESS FOR THE CORE RETENTION DEVICE
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ENCLOSURE 4 AUG o?.MG9 TESTING PROGRAM FOR CONFIRMING ADEQUACY OF LADLE DESIGN PURPOSE The purposes of ile testing program for confirming the adequacy of the ladle design are:
- 1) Obtain otherwise unavailable data required to confirm that the core ladle will meet its functional design requirements.
- 2) Obtain otherwise unavailable data required to confirm that the core ladle does not compromise existing safety.
GENERAL The refractory ladle is being incorporated in the Floating Nuclear Plant design to assist in reducing environmental consequences of a postulated core-melt accident.
Because the ladle is not required by the NRC for public health and safety, the approach of providing a high degree of confidence for highly conser-vative design assumptions is not being taken.
Thus for confirmation of ladle design adequacy, an approach will be taken of justifying that the functional requirements can be met. This approach is consistent with the approach required by NRC for evaluating consequences and risk.
SC_K0ULE It is Offshore Power Systems' intent to initiate a testing program af ter an FNP customer is identified. Offshore Power Systems has responsibility for providing the information needed to qualify the ladle to fulfill its environmental protection function.
However, if NRC or DOE sponsored testing programs provide
AUG 02 1R9 the needed information or if such programs appear highly likely to provide such information, these existing or completed programs will be relied upon by Offshore Power Systems.
As indicated in the attached tables, it is estimated that the testing program can be completed in 18 months. Offshore Power Systems estimates that it would take about six months to initiate the testing program. At the conclusion of the testing program, the pertinent data would be summarized, evaluated and the evaluations submitted to NRC for their review.
Six months is estimated as the time needed for the NRC review and evaluation process.
The estimated 2-1/2 years from initiation of the testing program to completion of NRC review coincides with the period between customer identification and the need to begin manufacture of major elements of the FNP hull projected by Offshore Power Sy.'. ems.
Cost Total estimated cost of the testing program is about $700,000.
AUG 0 2 M79 LADLE QUALIFICATION INFORMATION NEEDS AND TESTING PROGRAMS 1.
Physical and Chemical Interaction Between Melt Debris and Mg0 Bed IflFORMATION TYPE OF ESTIMATED COMMENTS OR NEEDED TEST TESTIflG PERIOD ESTIMATED COST a.
Eutectic formation for the 15 to 20 small scale 18 months 250,000 Mg0, U0, Zr0, Fe0 compound furnace tests 2
2 systems b.
Effect of Mg0 impurities on 5 to 10 small scale 6 months 50,000 rate of penetration by melt furnace tests debris c.
Potential enhanced attack by 2 medium scale tests 6 months 50,000 erosion at temperatures below eutectic temperatures I
d.
Potential for slag line attack 1 medium scale test assuming 3 months 25,000 data from (la) are employed e.
Potential for rapid attack at 2 - 4 small scale, high 15 months 125,000 high temperatures due to chemi-temperature tests.
cal interaction between melt debris and Mg0 2.
Physical Behavior of Mg0 Bed Industrial experience a.
Brick floatup upon contact None sufficient to establisr with high density melt there is not a problem Industrial experience b.
Thermal shock with bed flone sufficient with additic spalling of resistant top layer of brick
AUG 02 373 INFORMATION TYPE OF ESTIMATED COMMENTS OR NEEDED
_ TEST TESTING PERIOD FSTIMATED COST c.
Mechanical shock causing None Industrial experience shows degradation of bed this is not a problem d.
Extensive melt penetration 3 small scale 9 months 50,000 of cracks between brick tests leading to breakup of bed 3.
Thermal Interaction Between Bed, Melt and Surroundings a.
Energy loss due to radiant None T.reated by bounding upward heating calculations which assume all energy is directed inte bed b.
Energy split between the 2 medium scale high 18 months 150,000 downward and lateral temperature tests directions 4.
Safety Related Concerns a.
Radiation shielding properties None Adequate cross section of M90 bed data can be derived from existing literature b.
Gas generation capability None Bounding gas generation from top layer of chem-ically bonded brick can be tolerated c.
Possible effects of bed on None Possible effects cat be nearby containment pressure adequately treated boundary under accident analytically based on condi tions available information
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