ML20196C249
| ML20196C249 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/30/1988 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8812070234 | |
| Download: ML20196C249 (23) | |
Text
_ _ _ _ _ _ _ _ _ _ _ - _
November 30, 1988 5
~
Docket No. '50-344 LICENSEE:
PORTLAND GENERAL ELECTRIC COMPANY (PGE)
FACILITY:
TROJAN NUCLEAR POWER PLANT
SUBJECT:
SUMMARY
OF MEETING WITH PGE TO DISCUSS PROJECTED USE OF BABC0CKANDWILCOX(B&W)FUELINTROJAN The NRC staff met with representatives of PGE and B&W on November 10, 1988 to discuss the use of B&W manufactured fuel in the Trojan reactor.
Selected handcuts for the meeting are in Attachment 1.
Attendees at the meeting are given in Attachment 2.
r The pre:;entation by PGE and B&W includes a general comparison between the currently-used Westinghouse (W) fuel and the B&W fuel to be used in a future core reload. The new fuel will be substantially the same as B&W fuel now under review for use in McGuire and Catawoa. Small differences were also identified.
As regards the analysis and safety evaluation for using the new fuel, there are no significant plant changes in the reanalysis; transient and accident responses are expected to be the same as for oreviously-used W fuel. Applicable generic topical reports on ECCS and plant transients are addressed in Safety Analysis Model BAW-10169. For plant-specific ECCS evaluation (LOCA) analysis, the large-break in the limiting location will be considered. Since this is a first use of a new fuel in this reactor, the licensee was urged to consider breaks other than the limiting condition large break in its analysis.
The licensee was encouraged to be forward-looking in its needs for staff review for both design changu and license amendrents appropriate for using the new fuel. The staff agreed that the licensee proposal and schedule for implementing the changes appear to be realistic, provided the licensee continues to work l
with the staff and presents complete, adequate, and timely submittals, i
i original signed by i
l Roby B. Bevan, Project Manager l
Project Directorate V I
Division of Reactor Projects - III, IV, Y and Special Projects l
Attachments:
DISTRIBUTION As stated Docket tue OGC MJohnson
- RC & LPDRs EJordan Licensee PD5 Reading PGrimes j
GKnighton NRC Participants RBevan ACRS(10)
DRSP/
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/ P RDBevin:dr GWKnighton 114,0/88 11/3./88 8812070234 001130 il PDR ADOCK 05000344
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UN!TED STATES NUCLEAR REGULATORY COMMISSION o
D r-wAsstNG TON,0. C. 20665 November 30, 1988 Docket No. 50-344 LICENSEE:
PORTLANDGENERALELECTRICCOMPANY(PGE)
FACILITY:
TROJAN NUCLEAR POWER PLANT
SUBJECT:
SUMMARY
OF MEETING WITH PGE TO DISCUSS PROJECTED USE OF BABC0CKANDWILCOX(B&W)FUELINTROJAN l
The NRC staff met with representatives of PGE and S&W on November 10, 1988 to discuss the use of B&W manufactured fuel in the Trojan reactor. Selected handcuts for the me2 ting are in Attachment 1.
Attendees at the meeting cre given in Attachment 2.
The presentation by PGE and B&W includes a general comparison between the currently-used Westinghouse.(W) fuel and the B&W fuel to be used in a future core reload. The new fuel will be substantially the same as B&W fuel now under review for use in McGuire and Catawba.
Small differences were also icentified.
As regards the analysis and safety evaluatics for using the new fuel, there are no significant plant changes in the reanaly;is; transient and accident responses are expected to be the same as for previously-used W fuel. Applicable generic topical reports on ECCS and plant transients are addressed in Safety Analysis Model BAW-10169. For plant-specific ECCS evaluation (LOCA) analysis, the large-break in the limiting location will be considered. Since this is a first use of a new fuel in this reactor, the licensee was urged to consider breaks other than the limiting condition large break in its analysis.
The licensee was encouraged to be forward-looking in its needs for staff review for both design changes and license amendments appropriate for using the new fuel. The staff agreed that the licensee proposal and schedule for implementing the changes appear to be realistic, provided the licensee continues to work with the staff and presents complete, adequate, and timely submittals.
Tf V
Roby B. Bevan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Attachments:
As stated 1
ATTA6HP1ENT l l
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i PGE-NRC-B&W MEETING TL DISCUSS CONVERSION TO B&W FUEL AT THE TROJAN NUCLEAR PLANT l
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INTRODUCTION i
I ATTENDEES l
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MEETING OBJECTIVES MEETING AGENDA I
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MEETING AGENDA 4 -
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INTRODUCTION
............. SCOTT BAUER l
r BACKGROUND.
. JIM TAYLOR r
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FUEL COMPARISON
. CHRIS RUSCH t
A h.
i CURRENT STATUS, B&W LICENSING ON MCGUIRE/ CATAWBA.
. FRANK MCPHATTER s
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REQUIRED ANALYSIS
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AND LICENSING.
. GUS ALBERTHAL i
i SCHEDULE.
. CHRIS RUSCH 4
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SUMMARY
.. SCOTT BAUER j
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B&W MARK-BW FUEL ASSEMBLY VERSUS WESTINGHOUSE STANDARD 17 X 17 FUEL ASSEMBLY GENERAL COMPARISON COMP 0NENT COMPARIS0N t
ns
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GENERAL COMPARISON OUTLINE DIMENSIONS OF THE FUEL ASSEMBLY l
FUEL ROD 0.D.
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i THIMBLE TUBES i
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ACTIVE FUEL LENGTH I
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AXIAL BLANKETS l
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4 NEUTRONICS 4
i FUEL ROD BURNUP - 60,000 MWD /MTU l
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COMPONENT COMPARISON REMOVABLE TOP N0ZZLE -
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COMPONENT COMPARIS0N STRUCTURAL GRIDS -
TWO INCONEL GRIDS LOCA1ED ON TOP AND BOTTOM OF FUEL
- ZIRCALOY GRIDS
. GRIDS ARE OF THE FLOATING DESIGN
- FERRULE RESTRICTS MOVEMENT
- ROD BOW PERFORMANCE
- PRESSURE DROPS I
- FLOW TESTS WITHIN 1 PERCENT INCREASE J
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M so nsroe sTirrENiNG oiunte STREAM LINED CORNER Babcock & Wilcox v
ZlRCALOY INTERMEDIATE v
SPACER GRID
Fuel Assembly Pressure Drop Testing Verification of TROJAN fresh fuel and Mark-BW prototype hydraulic compatibility Test Location : BWFC Commercial Nuclear Fuel Plant Facility : Transportable Flow Test Rig Test : Mark-BW prototype and 4 PGE FAs Results : Measured pressure drop difference is within 1%.
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j' COMP 0NENT COMPARISON i
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FUEL RODS -
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l CLADDING THICKNESS (0.024 MARK-BW i
VERSUS 0.0225 NOW) t
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TOP AND BOTTOM PLENUMS
- FUEL COLUMN GROWTH
- FUEL COLUMN ALIGNMENT FUEL ON THE BOTTOM N0ZZLE l
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- TURBULENCE AND FRETTING FAILURES
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I ANALYSIS AND SAFETY EVALUATION l
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PERSPECTIVE -
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B&W FUEL IS VERY SIMlLAR TO EXISTING FUEL I
I NO SIGNIFICANT CHANGES TO PLANT ACCOMPANY THE REANALYSIS TRANSIENT AND ACCIDENT RESPONSE EXPECTED TO BE SAME AS BEFORE l
i CONCENTRATE ON THE EVENTS THAT ARE LIMITING i
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9 ANALYSIS AND SAFETY EVALUATION REVIEW PROCESS -
GENERIC TOPICAL REPORTS
- PLANT-SPECIFIC TOPICAL REPORTS
- TECHNICAL SPECIIICATION CHANGES
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- OTHER REPORTS l
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GENERIC TOPICAL REPORTS ECCS AND PLANT TRANSIENTS
- SYSTEMS MODEL BAW-10169 THERMAL HYDRAULICS CODE CRITICAL HEAT FLUX CORRELATION PHYSICS METHODS EJECTED ROD ACCIDENT METHODS FUEL ASSEMBLY DESIGN FUEL MECHANICAL LOADS
QEfoRTS
, PLANT-SPECIFIC 40riCAL5 ECCS EVALUATION (LOSS-OF-COOLANT ACCIDENTS)
LARGE BREAK, LIMITING LOCATION BC'JNDING ANALYSIS SAFETY EVALUATION OF TRANSIENTS LIMITING EVENTS:
ROD WITHDRAWAL FOUR PUMP COASTDOWN LOCKED ROT 0F, TURBINE TRIP STEAM LINE BREAK THERMAL-HYDRAULIC EVALUATION DEPARTURE FROM NUCLEATE BOILING RATIO STATISTICAL CORE DESIGN (SCD) METHODS 9
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i TECHNICAL SPECIFICATIONS -
LIMITS CONSISTENT WITH SAFETY ANALYSIS PROVIDED
- BASED ON PREVIOUS TOPICAL REPORT METHODS /
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RESULTS
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OTHER REPORTS CURRENT TROJAN TECHNICAL SPECIFICATIONS REQUIRE RADIAL PEAKING FACTOR REPORT 60 DAYS PRIOR TO CRITICAt.ITY ABOVE MAY CHANGE DEPENDING ON GENERIC LETTER 88-16 PROPOSAL PLANT STARTUP REPORT PROVIDED AFTER BEGINNING OF CYCLE i
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TROJAN ANALYSIS ASSUMPTIONS _
CURRENT LCA 161 B&W
- ANALYSIS, (UNDER REVIEW)
(PRELIMINARY)
CORE POWER 3411 MW 3411 3558' DhB TRANSIENTS CORE POWER 3577 MW 102% OF 102% OF ECCS ANALYSIS 3558 3558 F
2.32 2.5 2.5 g
F6H 1.55 1.62 1.62 LOOP FLOW 92,925 92,925 88,500 DNB TRANSIENTS RCS FLOW 88.500 88,500 88,500 OTHER EVENTS STEAM GENERATOR 6%
11.5%
11.5%
TUBE PLUGGING DNB CORRELATION WRB-1 WRB-1 BWCMV
- POWER UPRATE NOT PART OF SUBMITTAL, BUT B&W ANALYSIS WILL SUPPORT INCREASED POWER LEVEL M
e
SUMMARY
SAFETY ANALYSIS IS TO SUPPORT USE OF A SIMILAR FUEL DESIGN SIGNIFICANT EVENTS TO BE REANALYZED ANALYSIS IS EXPECTED TO BE CONFIRMATORY
T o pic al R e p o r t S u b mit t al a n d N R C R e vie w S chedul'e '
88 87 88 89 90 91 t
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Saf ety Analysis A:
Y BEACH j
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Fuel Mechanical Design A
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LOC A Evaluation Model A
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- Cycle M Y
'CritWestty Trojan LOC A i
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Y Trojan Saf ety Analysta 4
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Final Report Submitted Y
NRC Saf ety Evaluation Report Date
SCHEDULE FOR LICENSING B&W FUEL FOR THE TROJAN NUCLEAR PLANT l
SCHEDULED LICENSING ACTIVITY DATE(S) 1 B&W PERFORM FLOW TESTS AND MEASUREMENTS ON 11/88 WESTINGHOUSE FUEL ASSEMBLIES NRC APPROVE GENERIC METHODS TOPICALS FIRST HALF l
1989 NRC APPROVE CRITICAL HEAT FLUX CORRELATION FIRST HALF TOPICAL 1989 l
PGE NOTIFIES B&W OF INTENT TO PERFORM ALL OR A 9/89 PORTION OF THE RELOAD FUEL MANAGEMENT SERVICES I
PGE SUBMITS PLANT-SPECIFIC TOPICALS TO NRC 1/90
[
1 1
1 PGE SETS FINAL SCHEDULED DELIVERY DATE FOR 1991 3/90 i
RELOAD FUEL
[
f B&W DELIVERS FOUR LEAD ASSEMBLIES AND 50.59 3/90 EVALUATION TO JUSTIFY USE IN CYCLE 13 l
PGE SETS THE ENRICHMENT FOR 1991 RELOAD 5/90 NRC APPROVE PLANT-SPECIFIC TOPICALS 7/90 j
PGE SUBMITS TECHNICAL SPECIFICATION CHANGES TO 7/90 NRC
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SCHEDULED LICENSING ACTivlTY DATE(S)
NRC APPROVES TECHNICAL SPECIFICATIONS 32/90 1991 RELOAD FUEL SCHEDULED DELIVERY DATE 3/91 PGE SUBMITS PEAKING FACTOR LIMIT REPORT To NRC 4/91 (SUBJECT TO GENERIC LETTER 88-16 RESOLUTION)
CYCLE 14 CRITICALITY 6/91 PGE PROVIDES CYCLE 14 STARTUP REPORT TO NRC 8/91 m
6
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Y 46 4
S
SUMMARY
CAN THE SCHEDULE BE SUPPORTED?
e ATTACHMENT 2 NEETING WITH PGE AND NRC USE OF B&W FUEL IN TROJAN November 10, 1988 t
ATTENDEES Roby Bevan NRC/NRR, Training PM Gus Alberthal PGE/ Nuclear Safety Frank McPhatter B&W Roger Powers B&WFC Chris Rusch PGE/ Project Manger, Nuclear Fuel Robert Jones NRC/NRR/ Reactor Systems i
J. H. Taylor B&W I
Scott Bauer PGE/ Manager Nuclear Reg.
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--.,___ ___ _ _