ML19282B926
| ML19282B926 | |
| Person / Time | |
|---|---|
| Site: | Atlantic Nuclear Power Plant  |
| Issue date: | 02/28/1979 |
| From: | Birkel R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903190036 | |
| Download: ML19282B926 (12) | |
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.I WASHINGTON, D. C. 20555 p4/j 00CXET N0. STN 50-437 APPLICANT: 0FFSHORE POWER SYSTEMS FACILITY:
FLOATING NUCLEAR PLANTS 1-8
SUBJECT:
SUMMARY
OF MEETING HELD ON FEBRUARY 23, 1979 At the request of the applicant a technical meeting was held with the applicant on February 23, 1979, subsequent to a senior management meeting with H. R. Denton held on the same d'y.
Attendance at the technical meeting is shown in Enclosure No.1.
The aoplicant opened the meeting by presenting an organization chart (Enclosure No. 2) reflecting recent changes in the Offshore Power Systems organization.
Thereupon the applicant presented a milestone chart (Enclcsure No. 3) outlining a proposed schedule for providing design in-formation pursuant to Fr.S-III Condition 4 and site requirement 1.B (page xv, NUREG-0502) and completion of the review of the application. A pro-cess flow chart (Enclosure No. 4) graphically illustrates the proposed schedule. The staff indicated that the schedule was ambitious and required the cooperation of all parties.
The following criteria for core melt mitigation (Condition 4) were pro-posed by the applicant:
1.
Delay (holdup) time shall be two days (minimum).
2.
Radiation level below containment boundary shall be no greater than 15 mr/hr. (present criteria).
3.
Gas generation shall be acceptable and not greater than a four foot slab of Basaltic concrete.
A design proposed to implement the above consisted of four feet of mag-nesium oxide and two feet of concrete (for neutron attenuation).
The question of qualification of the base mat material was raised and the applicant indicated that no testing would be performed prior to issuance of an ML.
On the matter o criteria of acceptability for site design features (l.B estuarine and riverine) the applicant indicated the folicwing:
7 9 0 319 0 03G g
- 1.
FNP site shall be rade equivalent to a typical LBP at an estuarine or riverine site.
2.
One approach is a design goal for source mitigation for site features be a population dose "of the order of 104 Man-Rem" (FES-III, Table 3.4-2).
3.
Acceptability criteria could be included in plant-site inter-face table in Chapter 2 of the PDR, but quantification is an open matter.
NOTE: Site applicant would provide site features.
During the discussion, the staff provided the applicant with information regarding Sandia molten core experiments using magnesium oxide (Enclosure No. 5).
The applicant stated that they did not plan to address any other FES, Part III matters.
The applicant was reminded that it would be expected that the effect of the base mat design change on the accident conse-quences as discussed in NUREG-0440, " Liquid Pathway Generic Study,"
would be addressed.
The staff indicated that we would consider the above matters and that fur-ther discussion may be necessary.
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Ralph A. Birkel Light Water Reactors Branch No. 2 Division of Project Management
Enclosures:
1.
Attendance List 2.
Organization Chart - FNP 3.
Milestone Chart 4.
Flow Chart 5.
Aerospace Evaluation of Slag Line Attack Issue Raised by Sandia ces w/ enclosures:
See next page
Mr. A. R. Collier President Of fshore Power Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 cc: Vincent W. Campbell, Esq.
Vice President a General Counsel Offshore Power Systems P. O. lox 8000 8000 Arlingtan Expressway Jacksonville, Florida 32211 Thomas M. Daugherty, Esq.
Offshore Power Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 22211 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. O. Box 757 34 Washingtr-Street Toms River, New Jersey C8753 Anthony Z. Roi sman, Esq.
Natural Resources Defense Council 917 15th Street, N. W.
Washingtcn, D. C.
20005 Cr. Glenn L. Paulson Assistant Commissioner State of New Jersey Departnent of Environmental Protection Labor and Industry Building John Fitch Plaza Trenten, New Jersey 08625 Keith A. Cnsdorff, Esq.
Miri am N. Span, Esq.
Assistant Ceputy Public Advccates
$20 East State Street
?ast Cffice Box 141 Trenten, New Jersey CS625
Mr. A. P. Zechel la cc: Mark L. Fi'st, Esq.
New Jersey State Deputy Attorney General State House Annex Trenton, New Jersey 08625 Carl Valore, Jr., Esq.
Valore, McAllister, DeBrier, Aron & Westmoreland Mainland Professional Plata 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 Rumson Avenue Margate, New Jersey 08402 Mr. John Williamson 211 Forest Drive Linwood, New Jersey 08221 Mr. Kenneth B. Walton Brigantine Tutoring 309 Twenty-first Avenue, South Brigantine, New Jersey 08203 Harold P. Green, Esq.
Fried, Frank, Harris, Shriver and Kamcelman Suite 1000, The Watergate 500 600 New Hampshire Avenue, N. W.
Washington, D. C.
20037 Nuclear Coordinator Office of Merchant Marine Safety Cormandant (G:dT-4)
U. S. Coast Guard Washington, D. C.
20590
Mr. A. P. Zechella cc:
Mr. Mitchell Attalla 4028 Ponce DeLeon Avenue Jacksonville, Florida 32217 Mr. Reg Crowder Jacksonville Journal P. O. box 1949 Jacksonville, Florida 32201 Sheldon J. Wolfe, 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. & M. 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. Salzman, 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.
20555
EtlCLOSURE NO. 1 ATTEilDAtlCE LIST MEETIflG WITH OFFSHORE POWER SYSTEMS FEBRUARY 23, 1979 0FFSHORE POWER SYSTEMS A. R. Collier P. 8. Haga D. Walker J. Nutant NRC - STAFF T. Speis A. Marchese R. Birkel
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re a 9 197; ENCLOSURE 5 AEROSPACE EVALUATION OF SLAG LINE ATTACK ISSUE RAISED BY aANDIA SANDIA MOLTEN CORE EXPERIMENTS: MeO During this experiment, molten steel at 1700 C was heated in an MgO crucible. Slag formed on top of the steel and was observed to attack the MgO. The phenomenon has been described a s " slag line attack" by Sandia.
An erosion rate was observed of 1 in. in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. This was ascribed to a low melting eutectic between iron oxide and MgO at 1591 C.
A phase diagram for the iron oxide-MgO system is shown in Fig. 1.
It wa s suggested that this erosion rate coul.d lead to the failure of a MgO sacrificial layer if one is employed to protect concrete from molten core debris.
We believe that the erosion observed in this' test represents the total erosion that should be expected at this temperature rather than an erosion rate. When molten steel comes in contact with oxygen in either air or a 23:0~
atm sphere, a layer of iron oxide slag will form and ficat on top 2
2 of the molten iron. This iron oxide will dissolve MgO from the sidewalls until the iron oxide-MgO mixture has the composition shown by the pha se diagram at the temperature of the slag. At 1700 C, the saturated mixture will contain 10% MgO and, at 2000 C, it will contain 265 MgO. When the saturation con-centration is reached, dissolution of MgO by iron oxide will cease. The total amount of MgG that dissolves will be relatively small because the slag layer will be thin and because of the relatively small cuantity of MgO in solution at satura-tien. As the tempe rature of the mixture is increa sed, the e:: tent of e ro sion will also inc rease, as given by the phase diagram. Since the sla g laye r vill shield the molten iren metal underneath from further attack by oxy;en, ne additional iron oxide will form and, consecuently, no further erc sion cf the M;O sidewall
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,.7 will occur. As iron oxide and iron have very limited miscibility and the oxide floats on top of the metal, it ' vill remain in place as a p: otect.cc layer unless the steel is vigorously agitated, as by boiling (boilin; point : 2750 C). Ir on w ill not attack MgO directly unless it is above the melting point of 3.igO (2750 C) because molten iron and higO are immiscible.
It should be noted that the extent of sidewall erosion will increase with the amount of slag which, in turn, increases with cavity diameter. One approach to this problem would be to leave loose MgO bricks on top of the NigO structure.
In the event of an accident, these bricks would float to the top of the molten pool and saturate the slag layer.
A representative of Harbison and Walker R efractories, ma nu fa c tu r e r s of Harklase NigO, indicated that slag line attack did not represent a problem at either 1700 C or 2000 C.
He based this conclusion on their past experience with steel manufacturing ope rations.
For these reasons, the crosion observed during the test at Sandia was probably the total erosion that can be expected at this temperature rather than an crosion rate. Erosion will occur, but it will be limited by the small amount of slag present and the saturation composition of the mixture on its phase dia-gram at each temperature. However, it should be noted that irnpurities in the higO may substantially alter the expected behavior. SiO and A10 6.pu M es 3
2 3 in NigO, if present in substantial cuantities, can lead to the formation of com-plex three or four component mixtures with Icw melting points.
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