ML20038C773

Forwards Ga Co Nondestructive Exam at 51 Fuel & Reflector Elements from Fort St Vrain Core Segment, & Post-Irradiation Exam & Evaluation of Fort St Vrain Fuel Element 1-0743

ML20038C773
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/16/1981
From:	Lee O PUBLIC SERVICE CO. OF COLORADO
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML20038C774	List: A16000, Nondestructive Exam of 51 Fuel & Reflector Elements from Fort St Vrain Core Segment 1 A16258, Post Irradiation Exam & Evaluation of Fort St Vrain Fuel Element 1-0743 ML20038C773
References
FSV-78A, P-81254, TAC-57625, NUDOCS 8112140117
Download: ML20038C773 (2)

Text

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PUBLIC SERVICE COMPANY OF COLORADO P.

O. 8OX 84 O OENVER.

COLORADO 80201 O(hU L7fj/

November 16, 1981 scan n. tre Fort St. Vrain

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Unit No.1 O

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P-81254 6

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F3V-HA Z4 Mr. Thomas M. Novak

\\4 h.,

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-h Assistant Director for Operating Reactors

\\off Division of Licensing Qf pT\\

U.S. Nuclear Regulatory Commission

~w Washington, DC 20555

Subject:

FSV Segment 1 Fuel Surveillance

Dear Mr. Novak:

Our letters of June 20, 1978 and June 23, 1978 (P-78103 and P-78103A, respectively) described the Fort St.

Vrain Surveillance Program.

This program is funded through General Atomic Company by the Department of Energy (D0E).

For FSV Core Segment 1, the program scope included nondestructive examination at the reactor site of five pre-characterized fuel elements and a destructive post irradiation examination (PIE) in San Diego of one of those five fuel elements.

Data evaluation and documentation of the results of the Segment I surveillance examination have been completed.

Accordingly, PSC is enclosing for your review 40 copies of each of the following reports:

" Nondestructive Examination of 51 Fuel and Reflector Elements from Fort St. Vrain Core Segment 1," GA-A16000, December 1980.

(

"Postirradiation Examination and Evaluation of Fort St. Vrain i

Fuel Element 1-0743," GA-A16258, May 1981.

Despite the publica tion dates of these reports, they have only very recently received patent clearance and been made available by General Atomic for general distribution.

The PIE resul ts described in these reports indicate that the performance of the fuel during Cycle 1 was excellent.

Irradiation

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induced di;aensional change of the fuel elements was minimal.

No in-service coated fuel particle failure was observed, a result which is consis tent wi th the very loa and cons tant circulating activity observed in the primary circuit during Cycle 1.

P

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P-81254 Page 2 November 16, 1981 i

The commitments made in letters P-78103 and P-78103A have ~ been met and, in fact, have been exceeded by the. scope of work described in the enclosed documents.

because the FSV Fuel Surveillance Program I

is funded by DOE-in support of the generic HTGR technology program, the reports were prepared by General Atomic for the. purpose of satisfying DOE reporting requirements.

Much of each report is-devoted to comparison of measured performance parameters (e.g.,

l coated particle failure, irradiation-induced fuel rod and graphite block dimensional change, etc.) wi th corresponding parameters calculated using large HTGR core design computer programs. _ In keeping wi th the intent of the DOE program, the reports contain the-results of examinations which are beyond the scope of

PSC's commitments to the NRC.

l In GA-A16000, the report on nondestructive examination, the results of examinations which meet PSC's comitments are described in Section 5.1 (metrology) and in Section 7.0 (visual examination).

Please note that in Table 1-1 of GA-A16000, the first five elements listed are the pre-characterized surveillance elements.

Examination i

of the remaining 46 elements was beyond-the scope of PSC's commitments.

In GA-A16258, the report-on destructive examination, the following sections contain the results of examinations which meet PSC's commitments:

Section 3.2 (gamma scanning); Sections 3.3, 3.4 and 3.5 (temperature, burnup, fluence monitor analyses); Section 4.3.2 (fuel rod me tr01 ogy); Section 4.1.2 (graphite metrology);

Section 4.3.5 (metallography); and Section 4.3.4 (TRIGA activation and fission gas release).

i Because most of the large HTGR core design methods referenced in the reports have not been reviewed by the NRC staff and accepted for use in PSC analyses, those portions of the reports which describe l

comparisons between measured parameters and parame ters calculated with non-FSV design me thods are provided for information only.

Results of examinations beyond the scope of PSC's commi tments are also provided for infomation only.

In view of year-to-year uncertainties in the level of DOE funding for HTGR programs.

PSC cannot assu re that the scope of reporting contained in the enclosed j

documents will be repeated in future surveillance reports.

PSC will, i

of course, endeavor to complete the scope of work described _in P-78103 and P-78103A as DOE funding levcis allow.

Very truly yours, i

f i

0. R. Lee, Vice President Electric Production ORL/JS:pa Encle:ures i

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