ML20198D242
| ML20198D242 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/09/1997 |
| From: | Sepp H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Collins S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20070L082 | List: |
| References | |
| CAW-97-1166, NUDOCS 9801080166 | |
| Download: ML20198D242 (52) | |
Text
_ _ _ _ _
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Westinghouse Energy Systems b 355 Electric Corporation
" * '" " * * '523"3" September 9,1997 CAW-971166 4
Document Control Desk US Nuclear Regulatory Commission Washington, DC 20555 Attention:
Samuel J. Collins, Director Of6ce of Nuclear Reactor Regulation APPLICATION FOR WITill10LDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
Slide Presentation "14x14,0.422" OD VANTAGE + (422V+) Fuel Design, Application for Point Beach Units 1 & 2,"
(Praprietary), August 5,1997.
Dear Mr. Collins:
The proprietary information for which withholding is being requested in the above referenced letter is further identified in Af6 davit CAW 97 Il66 signed by the owner of the proprietary information, Westinghouse Electric Corporatien. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specincity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Cormnission's regulations.
Accordingly, this letter authorized the utilization of the accompanying Affidavit by Wisconsin Electric Power
- Company, Correspondence with respect to the proprietary aspec'
'the application for withholding or the Westinghouse affidavit should reference this letter, CAW 971166, ano should be addressed to the undersigned.
Very truly yours,
/
Ilenry
.S p,.
ger Regulatory and Licensing Engineering Enclosures cc:
Kevin Bohrer / NRC (12115)
^
9001000166 971216 PDR ADOCK 05000266 P
PDR L__
J
Proprietary Information Notice Transmitted herewith are proprietary and non proprietary versions of documents furnished to the NRC.
In order to conform to the requirernents of 10 CFR 2.790 of the Conunission's regulations conceming the protection of proprietary information 50 submitted to the NRC, the information which is proprietary in the proprietan versions is contained within brackets, and w here the proprietary information has been deleted in the non proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justi6 cation for claiming the informatioi, so designated as proprietary is indicated in both versions by means of lower case letters (a) through (0 hxated as a superscript iminediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information % estinghouse customarily holds in confidence identined in Sections (4)(ii)(a) through (4)(11)(O of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).
A
l l
Copyright Notice The documents transmitted herewith ca 'h bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies for the information contained in these reports which are necessary for its internal use in connection with generic and plant specine reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, m 'ification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection not withstanding. With respect to the non proprietary versions of these reports, the NRC is permitted to make the number of copies beyond these necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proptietary.
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CAW.971166
,(,
3 AFFIDAVIT COMMONWEALTil OF PENNSYLVANIA:
ss
. COUNTY OF ALLEGHENY:-
Before rne, the undersigned authority, personally appeared Henry A. Sepp, who, being by me duly sworn according to law. deposes and says that he is authorized to execute this Affidavit on behalf of Westinghou.*e Electric Corporation (" Westinghouse") and that the averments of fact set forth in this
' Affidavit are true and correct to the best of his knowledge, information, and belief:
i hu0 14/
Henry A. Sepp, Man / N l
ager Regulatory and Licensing Engineering Sworn to and subscribed before this /s d dr.y of 1997.
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%*Schwab, Notary PubNo Som. A49 Cwty W Commason Eacww er E 2000
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CAW.971166 2
(1)
I am Manager, Regulatory and Licensing Engineering, in the Nuclear Services Div.sion, of the Westinghouse Electric Corporation and as such, I have t'ren specifically delega:ed the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Units.
(2)
I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in conjunction with the Westingne.se application for withholding accompanying this Affidavit.
(3)
I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Units in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4)
Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i)
The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii)
The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed te the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilites a system to determine when and whether to hold certain types of infottnation in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a)
The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
CAW.97 l!66 3
(b)
It consists of supporting data, including te9 data, relative to a process (or component, structure, tool, tnethod, etc.), the application of w hich data. secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c)
Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the desigr. marafacture, shipment, installation, assuran:.e of quaiity, or lictusing a similar product.
(d)
It reveals cost or prhe information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers, (e)
It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f)
It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the fol!cwing:
(a)
TL: use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors, it is. therefore, withheld from disclosure to protect the Westinghouse competitive position, b)
It is informatien which is marketable in many ways. The extent to which such information is available 'o competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c)
Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expendaure of resources at our expense.
(d)
Each component of proprietary information pertinent to a particular competitive advantsge is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage, l
j CAWC1 ll66
> (c)
Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f)
The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competirke advantage.
Y (iii)
The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv)
The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our howledge and belief.
(v)
The proprietary information sought to be withheld in this submittal is that which is provided in the document, NPL 97 0538, "14x14,0.422" OD VANTAGE + (422V+)
Fuel Design, Application for Point Beach Units 1 & 2," which i a copy of the slide presentation presented to.the NRR/SRXB staff of the Fuel Criteria Evaluation Process application for the new fuel design proposed for the Point Beach Units I and 2, submitted to the Commission, bemg transmitted by Wisconsin Electric Power Company in Docket Nos. 50 266 and 50-301 and Applicatlan for Wi:hholding Proprietary Information from Public Disclosure, Henry A. Sepp, %,(, Manager Regulatory and Licensing Engirrering to the attention of Samuel J. Collins, Director, Office of Nuclear Regulatory Regulation.
The proprie'.ary information was provided by Westinghouse Electric Corporation.
This information is part of that which will enable Westinghouse to:
(a)
Support plant specific analyses as they relate to operational issues (b)
Assist customers to obtain license changes for improved operational flexibility
CAW.971166 5-Further this information has substantial commercial value as follows:
(a)
Westinghouse plans to sell the plant analyses to other customers to improve plant operational flexibility (b)
Westinghouse can use this information to further enhance their licensing.
position with their competitors.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar licensing programs for commercial power reactors without
- commensurate expenses. Also, public disclosure of the information would enable others to use the.nformation to meet NRC licensing requirements without purchasing the right to use the information.
The development of the technology described in part t > :Se information is the result of applying the results of many years of experience in an imensive Westinghouse effort and the expenditure of a considerabie sum of money, in order for competitors of Westinghouse to duplicate this inf(,rmation, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended for dew !oping the improved fuel design.
Further the deponent sayeth not.
14x14,0.422" OD VANTAGE (422V+) FUEL DESIGN Application for Point Beach Units 1 & 2 NRC / WEPCO / WESTINGHOUSE Meeting Rockville, MD August 5,1997 Westinghouse Non-Proprietary Class 3 L
i i
Agenda
+
Introduction Michael Baumann (WEPCO)
+
Design Description William Slagle (W)
+ Mechanical Design Testing Mark Lloyd (W) t
+ WRB-1 Applicability Mark Lloyd (W)
+ Thermal Margins William Slagle (W)
+
Summary and Conclusions William Slagle (W)
I
+
Summary / Discussion All t
I
9 Introduction of the 14x14 422V! Fuel for Point Beach Units 1 & 2 Michael Baumann Wisconsin Electric Power Company-August 5,1997 3
i
u
-1 Planned Changes for Fall,1998 Reload Fuel. Upgrade to 0.422" rod OD VANTAGE + Design
+.
+
Increase in RCS Pressure to 2250 psia
+ Maintain thermal power at 1518.5 MWt
+ Move to 18 month fuel cycles l
4 L-
.O l
Fuel Lpgrade Licensing Approach
+
Fuel changes licensed through Fuel Criteria Evaluation Process (FCEP)
+ Technical Specification change licensing through separate submital F
increase to 1.77 from current 1.70 an ZIRLO Set-Point changes
+ Change Licensing Basis to incorporate new Westinghouse UPI BELOCA methodology 5
l L
Purpose
~
+
Present FCEP basis of fuel changes to NRC Provide fuel mechanical design summary Discuss fuel testing and results Justify use of WRB-1 Correlation Review thermal margins
+
Establish schedule to support Fall 1998 Reload t
6 i
~
)
Reasons for Fuel Upgrade
+
Increase Safety Margin l
+
Reduce number of feed assemblies
+
Utilize existing improved assembly components
+
Support extended fuel cycles
+
Improve economics l
7
Schedule
+
WEPCO/ Westinghouse presents FCEP Fuel Changes to NRC. 08/97
+
WEPCO submiR; TSCR for Fuel Upgrade................................
10/97
+ WEPCO subr.;iits Point Beach Specific BELOCA...................
10/97
+ WEPCO submits Plan for Control Room Habitability.............
02/98
+
Westinghouse gains NRC Approval for UPI BELOCA............. 04/98
+
Westinghouse begins manufacture of 422V+ Fuel Rods.......... 04/98
+ NRC approves TSCR for Fuel Upgrade.................................... 05/98
+
Westinghouse begins conversion for 422V+ Assemblies......... 07/98
+ WEPCO reloads Point Beach with 422V+ Assemblies............ 09/98 I
H
. -l Agenda
)
+ Introduction Michael Baumann (WEPCO)
+
Design Description William Slagle (W)
+
Mechanical Design Testing Mark Lloyd (W) l
+ WRB-1 Applicability Mark Lloyd (W)
+ Thermal Margins William Slagle (W)
+
Summary and Conclusions William Slagle (W) l
+
Summary / Discussion All 9
Design Description
~
of the 14x14 422Vl Fuel for Point Beach Units 1 & 2 William Slagle Commercial Nuclear Fuel Division Westinghouse Electric Corporation August 5,1997 f
10
i-.
Overview
+ Introduction
+
14x14 422V+ Design Features o
14x14 OFA and 422V+ Fuel Assemblies
+ Comparison to 14x14 OFA
+
Fuel Criteria. valuation Process (FCEP)-
.1 5
II
L Introduction l
L
' As part of'an overall licensing' submittal for the fuel upgrade features an'd 1
revised safety analyses, this presentation focuses on the upgrade fuel features and specifically the licensing aspects of those fuel changes. The i
principal fuel changes are ZIRLO
,0.422" OD fuel rod, and a new grid.
The ZIRLO
. incorporation is a standard change in the industry.
l l
The larger diameter fuel rod is a standard in the' industry.
The new grid is the focus of this presentation.
j The new grid design changes have been made under the guidelmes of the Fuel Criteria Evaluation Process (FCEP).
i The 14x14 422V+ design incorporates and adapts many of the current-j Westinghouse advanced fuel features, but parameters and= dimensions are designed to be identical or compatible with current Point Beach fuel (14x14 OFA).
i
^
12 4
i
.N_
i y
e 14x14 422V+ Design Features
+
14x14 422V+ de. sign has the following key features:
14x14 standard ZIRLO fuel rod (0.422 in. ODl clad) with zirconium oxide coated lower section 14x14 OFA ZIRLO instrumentation (0.422 in. OD) and guide.
thimble tubes (0.526 in. OD)
Mid-enriched annular blanket pellets Five ZIRLO OFA-type mixing-vane mid-grids with minor enhancements in the mixing vane pattern 13
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Comparison tO 14x14 OFA The principal design differences between the 14xi4 422V+ and the 14x14 OFA designs are:
+ 0.422 in. OD fuel rod versus 0.400 in. OD for 14x14 OFA:
14x14 Standard design uses a 0.422 in. OD rod 15x15 Standard and OFA designs use a 0.422 in. OD rod
+ Thin strap ZIRLO OFA-type mid-grids versus thick strap Zircaloy-4 OFA mid-grids
+ 0.200 in. lower top nozzle adapter plate and top grid elevation-
+ Both designs use mid-enriched blanket pellets. The 422V+ design uses an annular pellet which is a VANTAGE + product. The OFA l
design uses a solid pellet.
15 l
Fuel Criteria Evaluation Process (FCEP)
The FCEP approach has been approved by the NRC.
The only l
requirements that have been specified by the NRC to Westinghouse are:
Inform the NRC of each first time application of the FCEP process for each design change, and Maintain auditable records for each application of the FCEP i
process.
This presentation and the associated slides that will be sent to the NRC for the record, serve as the vehicle of notification for first time application.
u,
Mechanical Design Testing.
of the 14x14 422V ! Fuel for Point Beach Units 1 & 2 i
Mark Lloyd Commercial Nuclear Fuel Division Westinghouse Electric Corporation August 5,1997 1
17
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+
+
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'N Design Testing i
+
Fuel Assembly Tests Fuel Assembly Pressure Drop Fuel Assembly Flow-Induced Vibration
+
Component Tests Grid Mechanical Tests I
19 4
Design Testing Pressure Drop:
t
+ Core pressure drop results indicate that the 14x14 422V+ design is
[
]=>c the 14x14 OFA design.
l t
+ The pressure drop differences noted are well.within the Westinghouse experience base (e.g.,17x17 with IFM's).
+ Transition core crossflows due to pressure drop differences have:been.
analyzed and are acceptable.
20-
Design Testing i
P Fuel AssemblyVibration:
+ No evidence of self-induced vibration was present when the assembly was subjected to the axial flow.
+
No resonant peaks were observed.
+
Results of test were acceptable.
w Design Testing Grid Mechanical Design confirmatory tests:
+
Mechanical design tests included:
Mid-grid impact strength and stiffness
]
Grid assembly spring force and stiffness
+ All. grid mechanical design criteria have been met for the 14x14 422V+ design.
t 22 w
e
Summary / Conclusions 14x14 422V+ fuel assembly design is similar to the 14x14 OFA
+
design, with the exception of the new grids to accommodate the 0.422 in. OD fuel rods.
All mechanical design criteria have been met for the 14x14 422V+
+
j fuel design.
t l
l 23
WRB-1 Applicability for Point Beach L nits 1 & 2 14x14 422V ! Fuel 1
l Mark Lloyd Commercial Nuclear Fuel Division Westinghouse Electric Corporation August 5,1997 24
~
.;j E
^
Overview i--%
+ Introduction and Glossary of Terms
+ WRB-1 Correlation 1
+ Relevant WRB-1 DNB Test Series
+
FCEP Criteria
+
FCEP Geometric Comparisons
+
Summary i
25 l
\\
Glossary of Fuel Assembly Terminology (from a DNB Perspective) i
+
I4x14 OFA (14x14 Optimized Fuel Assembly):
0.400 in. OD fuel rods, zircaloy mid-grids 26 in. grid spacing in DNB-limiting region
+
14x14 422V+ (14x14 0.422" OD VANTAGE + Fuel Assembly):
Same as OFA in grid location, grid strap height ZIRLO straps to accommodate 0.422 in. OD fuel rods
Glossary of Fuel Assembly Terminology (from a DNB Perspective)
+ Inconel Grid:
Inconel mixing-vane mid-grid design Makes up large portion of WRB-1 DNB database over a wide range of grid spacings I
'l t
27
WRB-1 Correlation: Overview
+ WRB-1 database contains over 1100 DNB points.
+. Correlation 95/95 DNBR limit is 1.17.
+
Is applicable to most fuel designs.
+ Well proven within its applicable range.
T L
WRB-1 Correlation: Robust fOr Scaled Designs
+ Original database:
0.374 OD Inconel,0.422 OD Inconel 970 points
+ Scaled 0.374 OD Inconel to 0.360 OD OFA:
DNB tesi of 17x17 OFA confirmed WRB-1 limit DNBR of 1.17 17x17 OFA geometry & test data added to database
+ Scaled 0.422 OD Inconel to 0.400 OD OFA and 0.422 OD OFA:
DNB Test of 14x14 OFA confirmed WRB-1 limit DNBR of 1.17 14x14 OFA geometry & test data added to utabase
+ Scaled 0.374 OD Inconel to 0.374 OD V5H Subsequent test confirmed WRB-1 limit DNBR of 1.17 n
WRB-1 Correlation: Applicability to 14x14 422V i
+ Plant analysis conditions (G, x, p) well bounded by WRB-1 tested database range.
i
+
14x14 422V+ geometry bounded by/ consistent w;th WRB-1 tested geometric comparisons.
30
i Relevant WRB-1 DNB Test Series Rod OD Pitch Lheat GSP Heat Flux Profile Config (in.)
(in.)
(ft.)
(in.)
0.422 0.555 8
26 sin 4x4 TYP 0.422 0.555 14 26 sin 4x4 TYP 0.422 0.555 14 26 sin 4x4 TYP 0.422 0.555 14 26 uniform 4x4 TYP 31
^^'
Fuel Criteria Evaluation Process (FCEP)
Westinghouse FCEP Section 6.0 specifies the guidelines relevant to licensing a new grid design.
"An existing DNB correlation will be valid and will meet... the design basis without reservation provided the new fuel assembly geometry is similar to or bracketed by the test data and correlation parameters" (of the licensed database for the DNB correlation ofinterest).
i As specified in the TER of FCEP.
"An existing NRC approved DNB correlation is considered to be valid by l
Westinghouse for application to a new design when the new fuel assembly geometry is similar to or bracketed by the fuel assembly geometric parameters and correlation parameters of the critical heat flux (CHF) test data used to develop the approved DNB correlation."
I 32 e
e-
FCEP Criteria The relevant geometric parameters are:
+ Rod Size (Diameter),
+ Rod Pitch,
+
Heated Length, i
+ Grid Spacing,
+ Grid / Vane Orientation,
+ Ratio of Vane Area to Gridded Cell Flow Area,
+ Ratio of Gridded to Ungridded Cell Flow Area, and
+ Azimuthal Extension of the Vanes Around the Rod Circumference.
t 33 i
FCEP Geometric Comparisons Inconel i4x14 14x14 l'est Grid OFil 422V+
Rod OD (in.)
0.422 0.400 0.422 Red Pitch (in.)
0.555 0.556 0.556 Heated Length (ft.)
8 - 14 14 12 Grid Spacing (in.)
13 - 32 26 26 Grid / Vane Orientation grids grids grids aligned aligned aligned Ratio of Vane Area to Gridded Cell 0.121 0.120 0.120 Flow Area Ratio of Gridded to Ungridded Cell 0.81 0.70 0.77 Flow Area Azimuthal Extension of the Vanes 48.5 54.0 57.4 around the Rod Circumference (deg.)
ll, u
l r..
Summary t
i
+
14x14 422V+ geometric parameters are directly comparable to the 0.422 in OD test sections in the the WRB-1 database.
l
+
14x14 422V+ design is consistent with the 14x14 OFA design with the exception of the larger rod OD.
+ WRB-1 has historically proven to be a robust correlation within its applicable range.
i l
+
WRB-1 correlation limit of 1.17 remains applicable to 14x14 422V+.
j 35 4
i w
d 14x14,0.422" OD V I Fuel Assembly Thermal Margins William H. Slagte Commercial Nuclear Fuel Division Westinghouse Electric Corporation August 5,1997 u,
a
Overview
+
Introduction and Basis
+ Limits for DNB Analysis
+ DNBR Margin Summary 37
introduction & Basis Existing thermal-hydraulic analysis of the 14x14 OFA fuel is based on
+
the WRB-1 DNB correlation, Revised Thermal Design Procedures L
(RTDP), and the Improved THINC-IV Modeling.
l The DNB analysis of the core containing both 14x14 OFA and the l
+
422V+ fuel assemblies has been shown to be valid with the WRB-1 DNB correlation, RTDP, and the Improved THINC-IV Modeling.
l The W-3 correlation and Standard Thermal Design Procedures (STDP)
+
are still used when conditions are outside the range of the WRB-1 correlation and RTDP.
+ All analyses have been performed to cover the fuel upgrade, increased peaking factors and future uprating.
38
Limits for DNB Analyses
+ As presented previously, the 95/95 Correlation Limit of 1.17 for I
WRB-1 applies.
+ Using the. proposed uncertainties and combining them statistically l
yields a plant specific Design Limit DNBR of 1.24/1.23 (Typ/Thm) for l
l both the 14x14 OFA and the 14x14 422V+ fuel.
+ For use in the DNB safety analyses, the Design Limit-DNBR is conservatively increased to provide DNB margin to offset the effect of Rod Bow, Transition Core and any other DNB penalties that may i
occur, and to provide flexibility in design and operation of the Point Beach Units.
4 t
~
3 DNBR Margin Summary
+ Effect of fuel assembly geometry changes:
Reference is 14x14 OFA
[
]=,c DNBR margin for the 422V+ design
+ Overall Margin Summary *:
OFA 422V+
Transition Core Penalty
[
]=> c Net available margin
[
] =, c
- Based on 1518.5 MWt; 2250 psia; MMF 184,200 gpm; Fw = 1.70 (OFA),1.77 (422V+)
40
I 4
4 Summary and Conclusions ofthe 1
14x14,422V! Fuel Assembly f
i William H. Slagle l
Commercial Nuclear Fuel Division Westinghouse Electric Corporation August 5,1997 i
i 4!
4
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6 C
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Ec CO
+
i l
[
Summary and Conclusions In October 1995, Westinghouse informed the NRC ofits intentions to use the FCEP process in the development of the 14x14 422V+ design. This presentation is the formal notification of that process.
+ The 14x14 422V+ fuel assembly design has met all design criteria as specified in FCEP, WCAP-12488-A.
I
+ The WRB-1 DNB correlation has been shown to be applicable to the 14x14 422V+ design with a 95/95 correlation limit of 1.17.
+ Sufficient thermal margins exist to cover both fuel designs through transition core cycles.
43
l L
Summary and Conc ~ usions i
1-l A separate, detailed plant specific analysis submittal along with the associated Best Estimate LOCA analysis submittal for Point Beach will be issue to the NRC shortly. This plant specific application is based on the 14x14 422V+ design.
44
_