ML19270H370

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Submits Evaluation of 771220 GLP-5588, Safety Analysis -- Use of H-451 Graphite in Ft St Vrain Fuel Elements. Responses to NRC Questions Provide Reasonable Assurance That Fuel Substitution Is Viable
ML19270H370
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 05/21/1979
From: Gammill W
Office of Nuclear Reactor Regulation
To: Fisher C
GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
References
NUDOCS 7906270270
Download: ML19270H370 (2)


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i Mr. Colin Fisher, Director Division of Licensing General Atomic Company i

P. O. Box 81608 San Diego, California 92138 i

Dear Mr. Fisher':

SUBJE 8: ' EVALUATION OF TOPICAL REPORT GLP-5588 i

Please find enclosed our evaluation of General Atomic Company's Topical Report " Safety Analysis Report -- Use of H-451 Graphite in Fort St.

Vrain Fuel Elements," GLP-5583 December 20, 1977. We conclude that the information provided in this topical report and responses to staff questions provides reasonable assurance that the substitution of H-451 for H-327 graphite elements in the Fort St. Vrain reactor will (a) result in negligible changes t

in the nuclear and thermal behavior of the core and (b) will not result iri reduced safety margirs or reliability compared to the reference H-327 core.

l We conclude further that this report may serve as an acceptable reference i

and the initial basis for allowing the substitution of near-isotropic H-451 graphite fuel and reflector elements for the current reference needle-coke j

H-327 graphite elements in the Fort St. Vrain reactor. Final acceptance of H-451 is contingent on the items identified in the last paragraph of this letter.

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Because this review pertains to the Fort St. Vrain reactor both the Public Service Company of Colorado and the public document room in Greeley, Colorado were provided with copies of all correspondence dealing i

with the review. Final decision to use H-451 graphite in Fort St. Vrain i

must be based on our review of an application from Public Service of Colorado describing the exact composition of any reload fuel utilizing H-451.

I Because data acquisition on H-451 properties and thermal irradiation performance I

is ongoing, we will require, as part of any future application for insertion of reload H-451 elements, that timely and acceptable reports on any test results involving H-451 graphite be provided or referenced. Specifically, we require that reports on the results of (a) the ongoing irradiation creep program and (b) post-irradiation examinations and surveillance on the eight H-451 elements that are being inserted in Fort St. Vrain as part of reload 2271

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Mr. Colin Fisher

-2 MAY 211975 Segment 7 be provided.

In addition, should changes be made in the precursor j

materials or methods of fabrication of the H-451 graphite blocks produced by the H-451 graphite manufacturer, we will require evidence to support the i

i perfcrmance predictions for the graphite elements produced from the altered materials or process parameters.

9 Sincerely.

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I 3besda P. Spes William P. Gamill Assistant Director for Standardization and Advanced Reactors j

Division of Project Management i

Enclosure:

As stated cc: Mr. J. K. Fuller, Vice President DIST:

Engineering and Planning Docket File 50-267 Public Service Company of Colorado NRC PDR /

Vendor File P. O. Box 361 ARB R/F JKnight Platteville, Colorado 80651 WGammill PTan TSpeis DFieno Bryant O'Donnell, Esquire PWilliams WBrooks Kelly, Stansfield & 0'Donnell GKuzmycz 990 Public Service Company Building RIreland Denver, Colorado 80201 RSchamberger i

RBoyd James B. Graham HGearin Manager, Licensing and Regulation RMattson East Coast Office MTokar General Atonic Company RMeyer i

2021 K Street, H.W.

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Washington, D. C.

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