ML19208A899

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Discusses ACRS Review of Core Ladle Design.Lists Addl Info Required to Complete Review.Attendance List of 790815 Meeting & Drawings Encl
ML19208A899
Person / Time
Site: Atlantic Nuclear Power Plant PSEG icon.png
Issue date: 07/25/1979
From: Fraley R
Advisory Committee on Reactor Safeguards
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19208A898 List:
References
NUDOCS 7909180228
Download: ML19208A899 (25)
v • d • e


Text

,

ENCLOSURE 1 f'g.., u, y,.

UNI T k D ST ATES NUCLEAR REGULATORY COMMISSION j y.

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS

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g, July 25, 1979 Harold R. Denton Director, Of fice of Nucledt Regulatory Regulations ACRS REVIEd CF THE FLCATI?G NUCLEAR PIR4T CORE IADLE DESIGN SUM ECT:

27, 1979 ACES Subcoemittee Meeting or the Floating Nuclear At the June Plant, members of your staff requested that the ACTS neet at an early date to discuss the proposed R4P Core Ladle Design and to write a letter to Mr. Gossick cocmenting on that preliminary design prior to the NRC Staff's issuance of its safety evaluation. The Acting ACRS Subcommittee Chairman inferred your staff and representatives of Offshore Power Systems that the suggestion to hold an early ACRS meeting would be considered at the July 1979 AC3S meeting.

The proposal to hold an early ACRS review of the conceptual design of the RIP core ladle was discussed at the.Tuly 1979 AC?S meeting.

It was decided that additional infor.ation, as indicated.below, is necessary be-fore the Cocmittee can proceed with its review of the R4P.

Itens Related to the Impact that the Cere Ladle Will Have on Other a.

Contair. rent Structures Calculate the fraction of decay heat radiated frxa the pool 1.

for the proposed design.

Calculate the effects of heat radiation in Itan 1 on the rate of:

2.

(a) disintegration and collapse of exposed concrete disintegration and collapse or melting of concrete behind (b) the 6 inch magnesite brick wall (c) collapse of steel from the reactor cavity.

3.

Discuss the consequences of Itsa 2 with respect to:

(a) loss of integrity of superstructures (b) loss of hearth capacity

~%b.T. ')G 7909180 DO.

wo

ACAS Review of FNP Core Ladle Design July 25, 1979 (c) impact resistance of the hearth and its supports (d) integrity of structural steel members.

Discuss the stability of the 6 inch magnesite brick wall above the 4.

hearth level with respect to:

(a) loss of brick by spallirq (b) differential motion with respect to the hearth, concrete walls, and anchors loss of concrete behind the wall by spalling, disintegration, (c) and melting at calculated temperatures, or at temperatures indicated in Fig IV-6 of OPS Topical Report No. 36A59 (d) slagging reaction between the brick walls and melted concrete.

Discuss the fluxing of magnesite brick by siliceous material falling 5.

into the hearth.

6.

Discuss the properties and merits of basalt as a concrete aggregate.

Discuss the passibility of the heat flux being higher on the 7.

sides of the molten mass than on the bottom (FR3 conclusion for concrete melt) with melting going horizontally faster than vertically.

b.

Items Related to Three Mile Island Accident Discuss the possibility of the Upper Head Injection System re-1.

leasing nitrogen into the primary system and impeding the ability to establish or maintain natural circulation.

Discuss the acceptability of the single failure criterion.

2.

Discuss the timed sequence of events upon the loss of all AC power 3.

before core damage will result.

4.

Discuss the reliability of the auxiliary feedwater system.

Discuss how H., buildup in the ice condenser containment is dealt 5.

with following a TMI event and following a core melt.

Discuss how the FNP compensates for the difficulty, due to the re-6.

r:ute location and the lack of space available, in improvising new systems and techniques in case of an accident.

Discuss how one faces lack of flexibility for design changes due 7.

to the compactness and lack of available space on the ENP.

Ii>b1?I2

ACRS Review of Core Ladle Design July 25, 1979 Items Concerning the Effects of Changing Base Mat Materials c.

Discuss the effects of changiryg the base mat from concrete to 1.

ragnesium oxide.on the probability of a rajor air release during a core melt accident. Discuss the comparisons of probabilities and dose levels for air releases associated with concrete and ragnesium oxide during a core melt accident.

Discuss the consideration given to the use of a vented contaircent.

2.

Discuss the consideration given to the use of sea water for venting and/or cooling a molten core.

Discuss the change in position for allowing the WP to be placed 3.

on riverine and estuarine sites. Has the proposed installation af the core ladle changed the NRC Staff's position on this matter, if so, why? What actions and in what time period, are considered practical to isolate the core for a riverine or estuarine site?

Discuss the NPC Staff's position that the WP Core Ladle is con-4.

sidered an envirorcental issue and not a safety issue.

d.

Additional Information Recuested From the NRC Staff Provide available information on the Sandia 100 plant liquid path-1.

way study.

Provide available inforination on the WASH-1400 type study of the 2.

ice condenser type plant, along with a comparison for non-ice condenser type plants.

Eclic' sing receipt of Offshore Power System's response to the items listed above and a written evaluation by the NRC Staff, another ACRS Subcommittee meeting will be held. Please advise us of the date by which you believe the above information will be availaale so we can schedule related ACRS activities.

R. F. Fraley Executive Director cc:

D.

Fuller, DSE E. Case, NRC D. Vassallo, DPM F. Schroeder, DSS Os:rb'E:iij)

ENCLOSURE 2

~~

ATTENDANCE LIST MEETING WITH OFFSHORE POWER SYSTEMS AUGUST 15, 1979

_0FFSHORE POWER SYSTEMS P. B. Haga R. A. Bruce D. H. Walker C. Dotson N. Seaborne R. A. Touchton H. J. Stumpf

_BROOKHAVEN NATIONAL LABORATORIES R. D. Gasser W. T. Pratt WESTINGHOUSE J. C. Connor f4RC - STAFF R. L. Baer*

A. R. Marchese S. A. Varga*

F. Rinaldi J. Read C. Haupt*

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SELECT.lON AND USE OF REFRACTORIES 223 i

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jt The horizontal e.xpansion joints through a Type or Espan. ion Joints: Individual prefer.

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wall whic' has a thickness of two or more brick ences generally govern the choice of the kind

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,y may be staggered. In thin walls, expansion of expansion joints. The types illastrated in joints extending throuch from the inner to the Ficures 12 to 16 are in common use and are ji 9 j

outer face cannot always be avs,Hed. For such regarded as satisfactory.

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cases, leakaze of gas can be reduced to a mini.

Expansion joints in basic brick walls of all.

Q j mum by packing the outside ends of open joints header construction on the hot face are some.

M j wah a compressible inorganic packing material times made as shown in Figure 12.

p3 or hy covering them temporarily with a loose For walls with header and stretcher bond /

4 4 courae of brick, expansion allowance may be made as shown in..

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q-type, the vertical expansion joints may be gered joints.hown in Figure 13 may be used K{

staggered as desired. However, if the brick are when the brick are laid either dry or with a

( l la;u with an air setting mortar, the expansion heat setting bonding mortar. Expansion joints

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joints will not function properly unless those at corners may be made as shown in Figures 14 1

%j in successive courses are in vertical alignment. and 15. When the brick are laid with an air.

Ilrick which are required to move with respect setting bonding mortar, vertical alignment of i

to each other, as the material expands and con.

the expansion joints in successive courses is j.,

tracts on heating and cooling shouhl not be good practice. In the construction of a bridge s

bonded together with an air. setting mortar.

wall, expansion spaces shoubi always be pro.

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Fig.13. Saggered Sponaan losnt in Tall 13H' Thick.

Ileader Gmuruawn ons lia Face.

Alternate fleeier and Sretcher Cmuructions.

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I, i l SELECTION AND USE OF REFRACTORIES M5 r

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EXP ANSION JOINTS t

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TABLE 1 CilEMICAL COMPOSITI0il 0F ACCREGATE GRAfilTE GRAfilTE IGflE005 BASALT (GEORGIA)

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CO2

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FLOOR SPACE STUDY FriP VERSUS SEQUOYA I.

Il0 CLEAR AUXILIARY AREAS Scauova l

Ft:P 1.

Total Floor Space 2.03 x 105 ft.2 2.83 x 105 ft,2 2.

Volume 4.87 x 106 ft,3 5.32 x 106 ft,3 3.

Space Available 25,7C0 ft.2 67,700 ft.2 II. COltTROL GUILDI!;G Scouoya FhP 1.

Total Floor Space 2.50 x 104 ft.2 1.49 x 104 ft.2 2.

Volume

.95 x 106 ft,3

.23 x 100 ft.2 3.

Space Available ti/A ti/A III.

IURBI?tE BUILDiriG Sequoya l

FilP 1.

Total Floor Space 1.70 x 105 ft,2 2.08 x 105 ft,2 2.

Volume

5. 5 < 106 ft,3 8.81 x 106 ft,3 3.

Space Available 54,700 ft.2 46,000 ft.2 a J u..$.:

..

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