ML20154R824
| ML20154R824 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/26/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-86-052, KMLNRC-86-52, TAC-61086, NUDOCS 8603310203 | |
| Download: ML20154R824 (2) | |
Text
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KA VSAS GAS AND ELECTRIC COMPANY T>E ELECT AC COMPANY March 26 1986 vici me t ser% r hvctra.
F Mr. Harold R. Denton Office of Nuclear Reactor Regulation U. S.-Nuclear Regulatory Commission Washington, D.C.
29555 KMLNRC 86-052 Re.
Docket No. STN 50-482 Subj:
Wolf Creek Generating Station Cycle 2 Reload Using ANC
Dear Mr. Denton:
The refueling shutdown at the end of Wolf Creek Cycle 1 is planned to corrmence in October,1986.
Startup of Cycle 2 is expected to occur in late November or early December, 1986.
This letter is to advise you of Kansas Gas and Electric Company's (KG&E) plans to reference the Westinghouse Advanced Nodal Code (ANC) described belo,w in support of the upcoming Cycle 2 reload design.
The ANC Topical WCAP-10965 was subnitted to the Staff in January 1986 for their review and approval.
KG&E intends to reference this code in the Wolf Creek Cycle 2 reload safety evaluation.
The Topical subnittal is consistent with the Staff's scheduling guidance that reload analyses based on uodels and methods that are not yet approved by the Staff are submitted at least six months prior to the date that a license amendment is required to authorize restart.
To improve the prediction accuracy and to eliminate the need to benchmark nodal calculations against discrete calculations, the ANC methodology will be used in the holf Creek Cycle 2 reload design. 'Ihe ANC includes new nodal methods to predict assembly power, rod power, and reactivities.
The new methodology will confirm that the conclusions given in the currently approved reload methodology (NCAP-9272-P-A) are valid when the A?C is applied to the Cycle 2 core design calculations.
Kansas Gas and Electric Company will perform a technical review of the Westinghouse reload safety evaluation for the Wolf Creek Cycle 2 design including an assessment of the impact of the APC code on the core design and safety evaluation.
It is anticipated that unreviewed safety questions as defined by 10CFR50.59 will not be involved, and therefore, application for
. amendment to the Wolf Creek operating license is not expected. However, 8603310203 860326
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Mr. H. R. Denton KMLNRC 86-052 Page 2 March 26, 1986 i
should the results of our safety' review identify technical specification changes or potential unreviewed safety questions, the Staff will be notified consistent with the requirements of 10CFR50.59, so as to afford adequate i
lead time for Staff review prior to the Wolf Creek Cycle 2 startup.
In sumary, pending NBC approval of the ANC code topical, WCAP-10965, for which an expedited NRC review and approval has been requested (about mid-1986), the Cycle 2 reload design will proceed using the ANC code under the provisions of 10CFR50.59.
If you have questions concerning this matter, please contact me or tir.
O.L.
Maynard of my staff.
Very truly yours,,
Glenn L. Koester Vice President - Nuclear GLK:see I
cc: P0'Connor (2)
JCumins i