ML20062A980

Summary of 780929 Meeting W/Ga Co Re Use of H-451 Graphite in Reactor.Ga Co Questions Resolved.Validation of Computer Codes Used in Analysis of Stress or Chemical Reactions Not Required

ML20062A980
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/10/1978
From:	Williams P Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7810190014
Download: ML20062A980 (4)

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MEETING

SUMMARY

DISTRIBUTION Vendor File (General Atomic) IE (3)

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G. Lainas R. Denise V. Benaroya J. Stolz T. Ippolito K. Kniel V. Moore

0. Parr R. Vollmer S. Varga ti. Ernst T. Speis W. Gammill C. Heltemes G. Knighton R. Houston B. Youngblood L. Crocker W. Regan R. Mattson D. Bunch H. Denton J. Collins D. Muller W. Kreger R. Clark R. Ballard Project Manager - P. M. Williams J. Stepp Attorney, ELD L. Hulman L. Rubenstein F. Rosa

' R. Bosnak W. Haass R. Schamberger G. Wessman, GAC H. Cobb J. K. Fuller, PSCo C. P. Tan B. O'Donnell, PSCo F. B. Litton J. B. Graham, GAC M. W. Dickerson, IE:IV R. E. Ireland G. Kuzmycz M. Tokar

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• g'* i OCT 101978 TOPICAL REPORT TITLE: Safety Analysis Report, Use of H-451 Graphite in Fort St. Vrain VENDOR: General Atomic Company (GAC)

SUBJECT:

REPORT OF ftEETING ON H-451 GRAPHITE

SUMMARY

On September 29, 1978, we met in Bethesda with representatives of the General Atomic Company on the subject of H-451 graphite, a graphite type that GAC proposes for fuel element manufacture in place of the. current s type, H-327 and would use in the Fort St. Vrain reactor. The GAC representatives desired clarification and discussion of the " Request for

'idditional Infonnation" transmitted to them on September 19, 1978. A list of attendees is attached.

Satisfactory resolution of GAC's questions was apparent. Validation of the computer codes used in the stress analysis or in the analysis of chemical reactions might require a long-term commitment but would not be a required portion of the H-451 review. We advised GAC that we would confirm this position with management.

DETAILS:

1. General Atomic stated it had believed that our review would consist mainly of comparing the physical properties of H-451 with H-327, and had not anticipated many of the questions raised by the staff. We ,

responded that since H-451 would become the basis for the standard fuel of the Fort St. Vrain reactor we desired that a reference type document be developed.

2. We discussed the issue of graphite reproducibility in its manufacture (Q231.1) in the context of the past d'fficulty in developing a RDT Standard in this area. It was noted chat the coefficient of thermal expansion of the coke used in manufacturing the grtphite was a useful method to characterize graphite reproducibility, but that information -

on fabrication process parameters was also required to provide adequate assurance.

78/O NY

i Mtg. on H-451 Graphite 10 M 3 " Worst case" stresses in the graphite fuel blocks were stated to occur under shutdown conditions.

4. We stated that simplified methods could be used to meet the intent of Q231.6. Relative rather than absolute information is the objective of this question. Off-nonnal conditions would include cases of both anticipated operational occurrences and accidents. Bounding case illustrations, however, should be considered rather than a full spectrum of off-normal conditions.

5. General Atomic s'tated that the responses to Q231.7 and Q231.11 could involve lengthly programs of computer code validation. We stated that it was not our intent to include such validation reviews in the H-451 review, but knowledge of the validation status of the codes used is desired. A long-term commitment for code validation might be required, however. We noted that research programs in graphite oxidation are underway and that we were in the process of contracting with LASL for independent stress analysis of the reactor fuel elements.

Such programs might form a means of eventually validating the codes used in support of H-451.

6. General Atomic stated it desired completion of our review before the end of December 1978 and planned to expedite its responses to our questions in order to achieve this end. ,

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Peter M. Williams

'to Advanced Reactors Branch i Division of Project Management Enclos~ure:

List of Attendees a

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ATTENDEES MEETING WITH GENERAL ATOMIC COMPANY SEPTEMBER 29, 1978

, REV_IEW 0F H-451 GRAPHITE NRC General Atomic P. M. Williams G. Wessman R. E. Ireland D. Lessig

'i. Tokar W. Simon G. Kuzmycz J. Graham D. Albertstein L. Sevier l

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