ML20087N242
| ML20087N242 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/26/1984 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8404030259 | |
| Download: ML20087N242 (2) | |
Text
J Malling Address 4
~
Airma Power Company
_g 600 North 18th Strr.ct Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.
Senior Vice President riintnege suiioino AlabamaPower the southem electnc system March 26,1984 Docket No. 50-348 Director, Nuclear Reactor Regulation
- U..S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 1 Revised Cycle-6 Reload Design Gentlemen:
Farley Unit 1 is currently.in its fifth refueling outage with startup scheduled for mid-April. The fifth cycle of operation was 3
terminated at a cycle burnup of 11,100 MWD /MTU. By letter dated February' 10, 1984, F. L. Clayton, Jr. to S. A. Varga, Alabama Power Company advised you of its initial. plans for Cycle-6. This letter is to advise you of Alabana Power Company's review of the Farley Unit 1
' revised Cycle-6 core reload design and plans regarding its implemen-tation.. This revision was necessary to accommodate a minor loading pattern change associated with replacement of two leaking fuel
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assemblies.
The Farley Unit I revised Cycle-6 core reload was designed to perform within the currently approved nominal parameters and Technical Specifications with related bases and setpoints. A total of 2 Region-4,
- 38 Region-6, 50 Region-7, and 77 fresh Region-8 assemblies' will be inserted during this refueling outage. The mechanical, nuclear and
.thenaal-hydraulic design lof the Region-8 fuel cssemblies is identical to the design of the previous region except for top and bottom end plug
- design modifications, increased fuel tubing length, and increased plenum
' spring length. Each of these changes is related to the reconstitutable-fuel _ bundle development,- is generic in nature to the 17X17 fuel assembly, and is not reload-dependent.
W.
Alabama Power Company has performed a detailed review of the
. estinghouse Reload-Safety Evaluation Report (RSER) for Farley Unit 1 Cycle-6, including all postulated incidents in the FSAR and the
-Westinghouse fuel densification report, WCAP-3219, " Fuel Densification Experimental Results and Model for Reactor Operation." The RSER
, }gp included a review of the core characteristics to determine those 8404030259 840326 PDR ADOCK 05000348 i
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Mr. ' S.. A. ' Varga March 26, 1984 U. S. _ Nuclear Regulatory Commission Page 2
.parame ers affecting the postulated accident analyses reported in the t
Farley FSAR. Alabama _ Power Company concluded that revised Cycle-6 design parameters are conservative with respect to those assumed in the
. previous analyses; therefore, no accident was reanalyzed based on Cycle-6 parameters..This verification is consistent with the Westinghouse reload safety evaluation methodology as outlined in the March 1978 topical report entitled, " Westinghouse Reload Safety Evaluation Methodology," (WCAP-9272).
- The reload safety-evaluation demonstrated that Technical
- Specification changes are not required for operation of Farley Unit 1
- during Cycle-6. Alabama Power Company's Plant Operations Review
. Committee and Nuclear Operations Review Board have concluded that no unreviewed safety questions defined by 10CFR50.59 are involved with this reload. Therefore, based on thi.c review, an application for an amendment to. the Farley _ Unit 1 operating license is not required.
Verification of the reload core design will be performed per the standard str.rtup physics tests normally performed for Westinghouse PWR reload cycles.
These tests will include, but not be limited to, measurements of:
[(1)L Control rod drop time;
_ 2)' ! Critical. boron concentration;
(
'(3) Control rod bank worth;-
(4)' Moderator temperature coefficient; (5) Startup-power distribution using the 'incore flux mapping system.
Results of. these tests and a core. loading map will be submitted
. approximately ninety (90) days after startup of Cycle-6.
Yours very truly,
/
F. L. - Cl ayton, J r.
FLCJ r/MDR:lsh'-D5 cci Mr. R. A'.LThomas Mr. :J. P. O' Reilly-
'Mr.~ E. A.' Reeves.
Mr. W. H. Bradford
.Dr.-I. L. Myers I
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