ML19337B661

Application for Amend of License DPR-34,changing Tech Specs Table 6.1-1 Re in-core Residence Times of Fuel Test Elements

ML19337B661
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/03/1980
From:	Lee O PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19337B660	List: ML19337B659 ML19337B661 ML19337B663
References
NUDOCS 8010080467
Download: ML19337B661 (7)

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BEFORE TIIE UNITED STATES NUCLEAR REGULATORY CO?CilSSION In the Matter of the Facility Operating License)

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of ) Docket No. 50-267

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PUBLIC SERVICE COMPANY OF COLORADO )

Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 0F Tile PUBLIC SERVICE COMPANY OF COLORADO FOR Tile FORT ST. VRAIN NUCLEAR GENERATING STATION This application for Amendnent to Appendix A of Facility Operating License, License No. DPR-34, is submitted for NRC review and approval.

Respectfully subnitted, PUBLIC SERVICE COMPANY OF COLORADO

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By O. R. Lee, Vice President KELLY, STANSFIELD & 0'DONNELL Bryant O'Donnell Robert E. Thonpson Public Service Company Building Denver, Colorado 80202 Attorneys for Applicant 8010080 syg 7

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STATE OF COLORADO )

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CITY Alm COUNTY OF DENVER)

O. R. Lee, being first duly sworn, deposes and says; That he is Vice President of Production of Public Service Company of Colorado, the Licensee herein; that he has read the foregoing Application for Amendment to Appendix A of Facility Operating License and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

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O. R. Lee Subsc. lbed and sworn to before me this ?j' day of h C to ,

Witness my hand anu official seal.

My Camaixion bpires Oct. 7,1M

?!y commission expires: .

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Notary Public I

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ATTACHMENT 1 References t

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P-80203 Attachment 1 Page 1 of 1

1. PSC letter P-78004, C. K. tiillen to R. P. Denise, dated January 9,1978

2. NRC letter G-78047, R. P. Denise to J. K. Fuller, dated May 10, 1978

3. PSC letter P-78102, J. K. Fuller to W. P. Gammill, dated June 20, 1978

4. PSC letter P-78165, J. K. Fuller to W. P. Gammill, dated October 9,1978

5. PSC letter P-79025, J. K. Fuller to W. P. Gammill, dated January 25, 1979

6. PSC letter P-79031, J. K. Fuller to W. P. Gammill, dated January 26, 1979

7. NRC letter G-79070, T. P. Speis to C. K. Millen, dated April 20, 1979 i

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ATTACHMEtn 2 Background Information

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P-80203 Attachment 2 Page 1 of 2 Eight fuel test elements were installed in the Fort St. Vrain core during the first refueling. In Reference 1, PSC submitted the safety analysis report for the proposed fuel test elements (General Atomic Document GLP-5494 Amend-ment 1, June 30, 1977) to the NRC. Attached to that letter was a Technical Specification change request, which would incorporate information concerning the fuel test elements into Section 6.1 of the Fort St. Vrain Technical Speci-fications, permitting installation of the eight fuel test elements into the reactor core at first refueling. In Reference 2, the NRC stated "the safety analysis report provides an acceptable basis for demonstrating the capability of the reload test elements to perform in a predictable manner under norms' conditions and postulated off-normal events. The report does not, however, contain any description of the planned interim and post-irradiation examin-ation (PIE) of the test fuel." The NRC refused to permit installation of the fuel test elements until an acceptable fuel surveillance program was sub-mitted by PSC and approved. In Reference 3, PSC submitted a fuel surveil-lance program which included the required post-irradiation analysis. This program represente Amendment 2 to the " Safety Analysis Report for Fort St.

Vrain Reload 3 Iest Fuel Elements FTE-1 through FTE-8" (Reference 1) .

In Reference 4, PSC informed the NRC of the Fort St. Vrain Nuclear Facility Safety Committee's (NFSC) decision to extend the operating time of the Cycle 1 core from 150 to 200 equivalent full power days (EFPD). This de-cision was based on General Atomic Company's lengthy safety review of the ef fects of this extension, in which it was determined that no unreviewed safety question existed, nor were any changes to the Technical Specifications necessary. Likewise, in Reference 5, PSC informed the NRC of the NFSC's de-cision to extend the operating time of the Cycle 2 core from 150 to 200 EFPD, based on another safety review conducted by General Atomic Company encom-passing the entire Cycle 2 core. See " Safety Analysis Report for Reload 1 Extended Operations," GLP-5646 of June 16, 1978, Attachment 4.

In Reference 6, PSC submitted Amendment 3 of the Fuel Test Element Safety Analysis Report to the NRC. Amendment 3 extended the evaluation of the fuel  !

test element core residence time from 150 to 200 EFPD in the Cycle 2 core.

This amendment increased tne fuel test element residence time by approxi-mately 0.2 equivalent full power years as noted in revised Table 2-1 of this safety analysis report. Table 2-1, in Amendment 1 of the safety analysis report (GLP-5494, June 30,1977) had been submitted to the NRC in Reference 1, in support of the fuel test element data to be entered in the Fort St. Vrain Technical Specifications as Table 6.1-1. In Reference 7, the NRC incorporated the data from the original version of Table 2-1 (the Amendment 1 version),

into the Fort St. Vrain Technical Specifications. Reference 7 approved in-sertion of the eight fuel test elements into the operating core, approving the Technical Specification change originally proposed by PSC in Ret.cence 1.

This became Amendment No. 20 to the Fort St. Vrain Facility Operating License.

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P-80203 Attachment 2 Page 2 of 2 Attached to Amendment 20 of Reference 7 was the Safety Evaluation Report by the Office of Nuclear Reactor Regulation supporting Amendment 20 to Facility Operating License No. DPR-34. The NRC states on page 4 of this safety evalu-ation " Amendment 3 to GLP-5494 was submitted on January 26, 1979, extending Cycle 2 core operation from 150 to 200 effective full power days. This cycle would include the eight test fuel elements. Our review of GLP-5494 reported here does not include review of Amendment 3 or constitute approval for ex-tension of Cycle 2 operation."

Amendment 3 to the " Safety Analysis Report for Fort St. Vrain Reload 1 Test Elements FTE-1 through FTE-8" (GLP-5494) documents the safety analysio con-ducted on the proposed extension of the FTE core residence time by 0.2 equiva-lent full power year.

The units of residence time have been changed in the revised Table 6.1-1 from years to equivalent full power years so as to reflect the original in-tent and prevent any misinterpretations. The fuel test element safety analysis supports these residence times in equivalent full power years, having con-sidered maximum potential irradiation, time at elevated temperatures, and the resulting fuel kernel migration distances.

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