ML20211F297
| ML20211F297 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 08/17/1999 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20138C028 | List: |
| References | |
| TAC-MA2359, TAC-MA2361, TAC-MA2411, TAC-MA2412, NUDOCS 9908300297 | |
| Download: ML20211F297 (9) | |
Text
m, f7 Duke Energy Corporation a
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526 South Church Street
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P.O. Box 1006 (EC0711)
Charlotte, NC 28201-1036 ht. S. Tutkman UM)382*22M DM Executive Vice 1%ident O M)38243f0 W Nuclear Generation August 17, 1999 U.S. Nuclear Regulatory Commission Washington, D.C.
20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station - Units 1 &2 l
Docket Nos. 50-369 and 50-370 Catawba Nuclear Station - Units 1 &2 Docket Nos. 50-413 and 50-414 Update of Fuel Design Section of Topical Report DPC-NE-2009 (TAC MA2359, MA2361, MA2411, MA2412) l l
REFERENCE:
1.
WCAP-12610-P-A, VANTAGE + Fuel Assembly Reference Core Report, April 1995.,
Attached are three updated pages for DPC-NE-2009, submitted July 22, 1998.
These pages modify the Fuel Design and Thermal-Hydraulic Analysis sections of DPC-NE-2009 to i
reflect the use of the standard length Westinghouse fuel assembly design at McGuire and Catawba.
Duke Power has
-decided, at the recommendation of Westinghouse, to use the
. standard length fuel design versus a reduced length assembly.
This change was pursued to mitigate the recent (spring of 1999) problems identified with broken holddown screws on some Westinghouse fuel designs.
The change reverts to a previously approved fuel assembly design for overall dimensions shown in Reference 1.
1 Therefore, this does not constitute a design change and no
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10CFR50.59 evaluation is required.
The net fuel assembly h)()\\
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holddown forces are the same for both assembly lengths.
Consequently, the robustness of the fuel design with respect to Incomplete Rod Insertion is identical.
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U.
S. Nuclear Regulatory Commission j
' ATTENTION: Document Control Desk
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August 17, 1999
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Page 2 l
The attached pages of DPC-NE-2009 were revised to reflect l
this change.
The discussion of a shorter fuel assembly as a design feature was removed from Page 2-2.
Additionally, the RFA length dimension on Table 2-1 (Page 2-4) and Table 5-1 (Page 5-6) was updated to the correct value.
l The attached Page 2-4 of Topical Report DPC-NE-2009 contains information that Duke considers PROPRIETARY. In accordance with 10CFR 2.790, Duke requests that this information be withheld from public disclosure.
A non-proprietary version 1
of.this page is included in the attachment.
An affidavit l
which attests to the proprietary nature of the affected information is also included with this letter.
Any questions regarding these updates should be directed to J.
S. Warren at (704) 382-4986.
Very truly yours,
~jl. b,
(>L M.
S.
Tuckman MST/JSW Attachment l
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1
, b.-S. Nuclear: Regulatory Commission ATTENTION: Document Control: Desk August 17, 1999 Page 3
-1 xc w/ Proprietary
Attachment:
-F. Rinaldi, NRC Project Manager.-(;MNS)-
}
U.-S.' Nuclear Regulatory Commission I
Mail Stop O-8 H12'
' Washington, DC 20555-0001 P. S.. Tam, NRC Project Manager (CNS) l LU.fS.. Nuclear Regulatory Commission Mail.Stop_O-8 H12 Washington, DC 20555-0001' xc w/o Proprietary
Attachment:
L. A.
Reyes,' Regional Administrator I
U.S.. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth.St., SWW, Suite 23T85 Atlanta, GA 30303 i
'S.
M. Shaeffer, NRC Senior Resident' Inspector (MNS)
L D.
J. Roberts, NRC Senior Resident Inspector (CNS) t 2
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~
S. NuclearIRegulatory Commisslon
' ATTENTION: Document? Control Desk August 17, 1999 l
Page 4 l
AFFIDAVIT I am Executive Vice President of Duke Energy 1.
. Corporation; and as~such have the responsibility for j
L reviewing information sought to be withheld from public disclosure in connection with nuclear power plant licensing; and am authorized on the part of said Corporation.(Duke) to apply for this withholding.
2.
I am making this affidavit in conformance with the L
provisions of 10CFR 2.790 of.the regulations of the Nuclear Regulatory Commission (NRC)~ and in conjunction with Duke's application for withholding, which accompanies this affidavit.
3.
I have knowledge of the' criteria used by Duke in designating information as proprietary or confidential.
4.
Pursuant to the provisions of paragraph (b) (4) of 10CFR'2.790, the following is furnished for consideration by the NRC'in determining whether the information sought to be withheld from public l
disclosure should be withheld.
(i)
The information sought to be withheld from
.public disclosure 10 owned by Duke and has been held'in confidence by Duke and its consultants.
k-M.
S.
Tuckman (Continued) l l
V.:
v.
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0.
S. Nuclear Regulatory Commission
[
' ATTkNTION:! Document Control Desk August 17, 1999 Page 5 l:
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(ii).The.information is of.a type that wouldL customarily be held in confidence by Duke. The
,information consists:of analysis methodology details,. analysis results, supporting-data, and l
aspects of development programs relative to a method of analysis that provides a competitive advantage to Duke.
(iii)The information was transmitted to the NRC in
' confidence and under the provisions of 10CFR 2.790, it'is to be received in confidence by the i
NRC.
(iv) The information. sought to be protected is not available in public to the best of our knowledge and belief.
(v)
The proprietary information sought to be withheld in this submittal is that.which is marked in'the proprietary. version of the Duke Topical Report designated DPC-NE-2009P, Duke Power Company Westinghouse Fuel Transition Report, and omitted
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.from the non-proprietary version. This topical report was submitted to the NRC by Duke letter
]
dated July 22, 1998 and revised by Duke letter
-dated August 17, 1999. This information enables Duke to:
(a)
Respond to Generic Letter 83-11, Licensee Qualification for Performing Safety Analyses I
in Support of Licensing Actions.
M. S. Tuckman (Continued)
RF.
l I
U. S. ' Nuclear-Regulatory Commission ATTENTION: Document Control Desk August 17, 1999 Page 6
- (b)-
Perform core design, fuel rod design, and thermal-hydraulic analyses for the 3
Westinghouse Robust Fuel Assembly design.
(c)
Simulate UFSAR Chapter 15 transients and accidents for McGuire and Catawba Nuclear Stations.
(d)
Perform safety evaluations per 10CFR50.59.
i (e)
Support Facility Operating
' Licenses / Technical Specifications amendments j
for McGuire and Catawba Nuclear Stations.
i l
(vi); The proprietary information sought to be withheld from public disclosure has substantial commercial
]
value to Duke, l
(a)'
It allows Duke to reduce vendor and
)
- consultant expenses associated with supporting the operation and licensing of i
~
nuclear power plants.
(b)
Duke intends to sell the information to nuclear utilities, vendors, and consultants for the purpose of supporting the operation
~and-licensing of nuclear power plants.
(c)
The subject information could only be duplicated by competitors at similar expense to that incurred by Duke.
h. S.
UL M. S. Tuckman (Continued) l 1
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U.
S. Nuclear Regulatory Commission ATTENTION: Document Control Desk August 17, 1999 Page 7 l
t 5.
Public disclosure of this information is likely to cause harm to Duke because it would allow competitors
)
in the nuclear industry to benefit from the results of a significant development program without requiring commensurate expense or allowing Duke to recoup a portion of its expenditures or benefit from the sale of the information.
l
,b.'
M. S. Tuckman (Continued)
Vs:
.b.
S. Nuclear Regulatory. Commission
' ATTE'NTION: Document' Control Desk August 17,:1999.
Page 8 i
M.
S.
Tuckman, being dulyLsworn, states that he is the person-who subscribed his name to the foregoing statement, and that'all the matters and facts set.forth within are
.true and correct to the best of his-knowledge.
I
,S-M.
S. Tuckman,; Executive.Vice President Subscribed and sworn to before me this 2.3 8 day of i
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1998
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' Notary Pdblic 1
My Commission Expires:
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JA# 22; 2ool SEAL
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- The RFA design used at McGuire and Catawba will include the following additional features to
' help mitigate debris failures:
L
- Pre-oxide coating on the bottom of the fuel rods and Protective bottom grid with longer fuel rod end-plugs.
l l
The RFA design used at McGuire and Catawba will include the following feature to help mitigate Incomplete Rod Insertion (IRI):
' fuel rods positioned on the bottom nozzle i
The three features listed above will be evaluated using the 10CFR50.59 process.
One new feature that will be added to the McGuire and Catawba RFA design is a Quick Release Top Nozzle (QRTN). This top nozzle design is similar to the Reconstitutable Top Nozzle (RTN)
' design, but has been modified for easier removal. This design change will be licensed by Westinghouse using the Fuel Criteria Evaluation Process (Reference 2-2) and notification will be made to the NRC.
l The Westinghouse RFA is designed to be mechanically and hydraulically compatible with the
. FCF Mark-BW fuel (Reference 2-4) that is currently used at McGuire and Catawba. The basic design parameters of the RFA are compared to those of the Mark-BW fuel assembly in Table 2-1.
. The IFM grids are non-structural members whose primary function is to promote mid-span flow
- mixing. Therefore, the design bases for the IFM grids are to avoid cladding wear and interactive damage with grids of the neighboring fuel assemblies during fuel handling. Westinghouse fuel with IFM grids has been flow tested both adjacent to another assembly with IFM grids and adjacent to an assembly without IFM grids. There was no indication of adverse fretting wear of the fuel rods by the standard structural or IFM grids (Reference 2-5). No adverse fretting wear is 2-2
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