ML20195E461
| ML20195E461 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/03/1986 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| JPN-86-25, NUDOCS 8606090088 | |
| Download: ML20195E461 (3) | |
Text
e 123 Man Street White Plains, New York 10601 914 031.6210
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& Authority aune 3, 1986
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Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Daniel R.
Muller, Director BWR Project Directorate No. 2 Division of BWR Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Westinchouse Demonstration Assemblies
Dear Sir:
This letter is to inform the NRC of the Power Authority's intention to include four demonstration assemblies in the Reload 7/
Cycle 8 core of the FitzPatrick plant.
These demonstration assemblies are part of a program to qualify Westinghouse as a fuel supplier for the FitzPatrick plant.
The Authority intends to reference WCAP-10507, the generic QUAD + demonstration report, in the Reload 7 license application.
The design and planned operation of the FitzPatrick plant demonstration assemblies will be bounded by the safety evaluations included in WCAP-10507.
Differences between the QUAD + demonstration assembly design described and evaluated in WCAP-10507 and the FitzPatrick QUAD +
assembly design are outlined in Attachment 1.
The evaluation documented in WCAP-10507 was performed for a BWR/4 plant similar in design and operating parameters to the FitzPattick plant.
The resident fuel censidered in the report is also similar in design and operating characteristics to the FitzPatrick plant resident fuel.
The design approach for the FitzPatrick QUAD + demonstration assemblies is the same as that^used in WCAP-10507.
That is, demonstration assemblies have been designed to match as closely as practical, the four GE7 assemb. lies they are to replace.
They will be placed in low power core locations and will be operated as though they were GE7 assemblies..
This approach valida.tes the evaluation and conclusions reached in WCAP-10507 regarding normal operating, transient, and accident behavior.
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O The NRC has previously reviewed WCAP-10507 as part of the Browns Ferry Unit 2 Cycle 6 licensing application.
In view of this review and the applicability of WCAP-10507 to the FitzPatrick QUAD +
demonctration assemblies, the Authority considers that WCAP-lO507 provides sufficient justification for including the deuonstration assemblies in the next FitzPatrick reload.
Should you or your staff have any questions regarding this matter, please contact Mr.
J.
A.
Gray, Jr. of my staff.
Very truly yours, f
tv~
j 3 hn C.
Brons Senior Vice President
' Nuclear Generation cc:
Office of the Resident Inspector U.S.
Nuclear Regulatory Commission P.
O.
Box 136 Lycoming.
N.Y.
13093 i
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ATTACHMENT 1 TO JPN-86-25 COMPARISON OF QUAD + DEMONSTRATION DESIGNS I.
Major Differences FEATURE WCAP-10507 FITZPATRICK COMMENTS DESIGN DESIGN Bottom Nozzle Lower tie Lower tie plates Neu designs plates supported supported by a eliminate leakage by fingars from plate with square oetween lower tie bottom nozzle, cutouts, flow to plate and channel flow to water-watercross cross provided provided by short by 16 holes pipe Fuel Tube Stress-relieved Recrystallized Liner improves annealed w/o annealed with PCI performance liner liner and market acceptance Helium 3 atmospheres 6 atmospheres Reduces fission Pressure gas release Mini-Bundle Administrative Mechanical Positive means Orientation &
control orientation and to preclude mis-Location location features location and mis-Features orientation II. Minor Differences FEATURE WCAP-10507 FITZPATRICK COMMENTS DESIGN DESIGN Positioning Not removable Removable from Facilitate repair (Channel) from top nozzle top nozzle in case of damage Spring attachment Watercross 0.028 inch 0.0315 inch Provides in-Material creased struc-Thickness tural margin at welds in water-cross Spacer One pair above One pair above Lower pair not Capture
& ona pair each spacer necessary for Rod Tabs below each spacer capture spacer Top Nozzle Without With compliant Relieve differen-Attachment compliant feature tial thermal Nut feature stresses e
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