ML20210H388
| ML20210H388 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/08/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9708130462 | |
| Download: ML20210H388 (23) | |
Text
',
August 8, 1997 LICENSEE:
Wisconsin Electric Power Company FACILITY:
Point Beach Nuclear Plant. Units 1 and 2
SUBJECT:
SUMMARY
OF AUGUST 5, 1997 MEETING ON PROPOSED NEW FUEL FOR USE IN 18-MONTH CYCLES
-On August 5. 1997. NRR staff members met in Rockville Maryland, with representatives of Wisconsin Electric Power Company (WEPC0) and Westinghouse to discuss plans to submit two Technical Specification (TS) change requests that will address 422V+ fuel and the proposed schedule for review.
A list of meeting attendees is included as Enclosure 1. and a copy of the licensee's presentation-is included as Enclosure 2.
Original signed by Linda L. Gundrum Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50 266 and 50-301
Enclosures:
1.
List of Meeting Participants 2.
Licensee Presentation' cc w/encls:
See next page DISTRIBUTION: See attached page DOCUMENT NAME:
G:\\WPDOCS\\PTBEACH\\PTBFUEL.MTG To receive a copy of this document, itKlicate in the tex: T
- Copy without ottachment/ enclosure T
- Copy with attactrent/ enclosure T = No 0FFICE PM:PD31 E
LA:PD31
]E D:PD31 y/ h/
NAME LGundrum:.Md CJamerson W JHannon[/ I DATE 9/P
/97 9/0 /97
/; / f /97 0FPICIAL RECORD COPY 9708130462 970008 PDR ADOCK 05000266 P
PDR g
August 8, 1997 LICENSEE:
Wisconsin Electric Power Company FACILITY:
Point Beach Nuclear Plant. Units 1 and 2
SUBJECT:
SUMMARY
OF AUGUST 5. 1997, MEETING ON PROPOSED NEW FUEL FOR USE IN 18 MONTH CYCLES On August 5, 1997. NRR staff members met in Rockville, Maryland, with representatives of Wisconsin Electric Power Company (WEPC0) and Westinghouse to discuss plans to submit two Technical Specification (TS) change requests that will address 422V+ fuel and the proposed schedule for review. A list of meeting attendees is included as Enclosurefl. and a copy of the licensee's presentation is included as Enclosure 2.
l l
Original signed by Linda L. Gundrum. Project Manager Project Directorate 111 1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50 266 and 50-301
Enclosures:
1.
List of Meeting Participants 2.
Licensee Presentation cc w/encls:
See next page
//
b)
DISTRIBUTION:
See attached page DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTBFUEL.MTG to.cei... c,y or this e-t. indic.t. in the tu r - c m, e t w.tt.c w ti n ios,, r. c=,
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30046-0001
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August 8,1997 LICENSEE:
Wisconsin Electric Power Company FACILITY:
Point Beach Nuclear Plant. Units 1 and 2 SU3 JECT:
SUMMARY
OF AUGUST 5, 1997. MEETING ON PROPOSED NEW FUEL FOR USE IN 18-MONTH CYCLES On August 5, 1997. NRR staff members met in Rockville. Maryland, with representatives of Wisconsin Electric Power Company (WEPC0) and Westinghouse l
to discuss plans to submit two Technical Specification (TS) change requests that will address 422V+ fuel and the proposed schedule for review. A list of meeting attendees is included as Erclosure 1. and a ccpy of the licensee's presentation is included as Enclosure 2.
hdk mahnw Linda L. Gundrum. Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nudlear Reacter Regulation Docket Nos. 50-266 and 50-301
Enclosures:
1.
List of Meeting Participants 2.
Licensee Presentation cc w/encls:
See next page i
.g
O ~
Distribution for Meeting Summary of 8/5/97 dated Auaust 8, 1997 Distribution w/ encl:
Docket File l
PUBLIC i
PD3 1 r/f OGC ACRS E-Mcil S. Collins (SJCl) l F, Miraglia (FJM)
R. Zimmerman (RPZ)
J. Roe (JWR) l E. Adensam (EGA1)
J. Hannon (JNH)
L. Gundrum (LLG) l C. Jamerson (CAJ1)
D. Ross (e-mail to SLM3)
G. Tracy (GMT)
G. Grant (GEG).
J. Lyons (JEl.)
L. Phillips (LEP1)
E. Kendrick'(EDK)
S. Wu (SL,W2)
M.-Chatterton (MSCl)
A. Attard (ACA)
F. Orr (FR0)
Di e
Wisconsin Electric Power Company Point Beach Nuclear Plant Unit Nos.1 and 2
- cc:
4 Mr. Richard R. Grigg Chief Nuclear Omcor Wisconsin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee, WI 53201 Emest L. Blake, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mr. Scott A. Patulski Vice President i
Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road-Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region til -
U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office -
U.S. Nuclear Regulatory Commission 6612 Nuclear Road -
Two' Rivers, Wisconsin 54241 Ms.' Sarah Jenkins -
Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 March 1997
NRC MEETING WITH WISCONSIN-ELECTRIC POWER COMPANY AND WESTINGHOUSE NEW FUEL-PROPOSED FOR 18 MONTH OPERATING CYCLES AUGUST 5, 1997 NAmt Affiliation i
James Lyons NRR Larry Phillips NRR Edward Kendrick NRR Shih-Liang Wu NRR t
Muffet Chatterton NRR-Tony Attard NRR Frank Orr NRR Linda Gundrum NRR Michael Bauman WEPC0 John-Hughes WEPC0 Curtis Castell WEPCO-Sumit Ray-Westinghouse:
William Slagle Westinghouse Gerald Sieranzki Westinghouse Mark Lloyd -
-Robert Creighton-Westinghouse I
" h e
0 MEETING HANDOUTS l
t t
l ENCLOSURE 2 6
' " ' ~ '
~
I 14x14, 0.422" OD VANTAGE (422V!) FLEL DESIGX l
Application for Point Beach L nits 1 & 2 l
NRC / WEPCO / WESTINGHOUSE Meeting Rockville, MD August 5,1997.
m W
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LJMMM Agenda i
+ Introduction Michael Baumann (WEPCO).
+ Design Description William Slagle (W)
+ Mechanical Design Testing Mark Lloyd (W)
+ WRB-1 Applicability Mark Lloyd (W)
+ Thermal Margins William Slagle (W)
+ Summary and Conclusions William Slagle (W)
+
Summary / Discussion All 2
4 Introduction 1
of the 14x14 422V Fuel for
~
Point Beach Units 1 & 2
~
Michael Baumann Wisconsin Electric Power Company August 5,1997 3
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e Planned Changes for Fall,1998 Reload l
1 l
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+ 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 1
4
FuelUpgrade Licensing Approach
+ Fuel changes licensed through Fuel Criteria Evaluation Process (FCEP)
+ Technical Specification change licensing through separate submital Fn increase to 1.77 from current 1.70 a
ZIRLO Set-Point changes
+ Change Licensing Basis to incorporate new Westinghouse UPI.
BELOCA methodology 5
l__
i Purpose t
+- Prehent FCEP basis of fuel changes to NRC Provide fuel mechanical design summary Discuss fuel testing and results Justify use of WRB.-1 Correlation
. Reviewthermalmargins
+ Establish schedule to support Fall 1998 Reload I
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Reasons for Fuel Upgrade l
1 I
+ Increase Safety Margin
+ Reduce number of feed assemblies
~
+ Utilize existing improved assembly components
+ Support extended fuel cycles
+ Improve economics 7
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~
L Schedule WEPCO/ Westinghouse presents FCEP Fuel Changes to NRC. 08/97
+
+ WEPCO submits TSCR for Fuel Upgrade................................
10/97
+ WEPCO submits 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 r
+ Westinghouse begins conversion for 422V+ Assemblies......... 07/98
+ WEPCO reloads Point Beach with 422V+ Assemblies............ 09/98 8
.l Agenda
+ Introduction Michael Baumann (WEPCO)
+ Design Description William Slagle (W)
+ Mechanical Design Testing Mark Lloyd (W)
+ WRB-1 Applicability Mark Lloyd (W)
+ ThermalMargins William Slagle (W)
+
Summary and. Conclusions William Slagle (W)
+
Summary / Discussion All
~
9
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Design Description of the 14x14 422V t Fuel for Point Beach Units 1 & 2 h
i William Slagle Commercial Nuclear Fuel Divisi6n
~
Westinghouse Electric Corporation August 5,1997
^
10
~
Overview
+ Introduction
+
14x14 422V+ Design Features
+
14x14 OFA and 422V+ Fuel Assemblies
+ Comparison to 14x14 OFA
+ Fuel Criteria Evaluation Process (FCEP) 11 O
~
Introduction
~
As part of an overall licensing. submittal for the fuel upgrade features and revised safety analyses, this presentation focuses on the upgrade fuel features and specifically the licensing aspects of those fuel changes. The principal fuel changes are ZIRLO
,0.422" OD fuel rod; and a new grid.
The ZIRLO incorporation is a standard change in the industry.
The larger diameter-fuel rod is a standard in the industry.
The new grid is the focus of this presentation.
The new grid design changes have been made under the guidelines of the Fuel Criteria Evaluation Process (FCEP).
i The 14x14 422V+ design 1 incorporates and adapts inany of the. current l
Westinghouse advanced fuel features, but parameters and dimensions are designed to be identical or compatible with current Point Beach fuel (14x14 OFA).-
12
14x14 422V Design Features ~
)
i
+
14x14 422V+ design has the following key features:
14x14 standard ZIRLO fuel rod (0.422 in. OD 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 4
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f 4
o 14x14 OFA and 422V+ Fuel Assemblies 6.645 31.00
-57.I9 83.38 - -109.57--I35.76 I53.4-
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Comparison to 14x14 OFA The principal design differences between the 14x14 4-22V+ 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-grid.s
+ 0.200 in.. lower t.op 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 design uses a solid pellet.
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e Fuel Criteria Evaluation Process (FCEP).
t The FCEP approach has been approved by the NRC.
The only requirements that have been specified by the NxC 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 process.
. This presentation and the associated slides that will be sent to the NRC for ~
tlie re~ cord, serve as the ~ vehicle 6f notification for firdt time application.
16
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