ML20248F216
| ML20248F216 | |
| Person / Time | |
|---|---|
| Issue date: | 05/29/1998 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9806040156 | |
| Download: ML20248F216 (87) | |
Text
. _ _ _ _ _ _ _
pn atav lt UNITED STATES gy -
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20565-0001
'+
Pty 29,1998 i
MEMORANDUM TO: Thomas H. Essig Acting Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation Egan Y. Wang, Reactor System Engineer f h_
FROM:
Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING
SUMMARY
OF MAY 5,1998 WESTINGHOUSE ELECTRIC CORPORATION REGARDING FUEL ROD INTERNAL PRESSURE AND OTHER FUEL-RELATED ACTIVITIES On May 5,1998, representatives of Westinghouse Electric Corporation met with staff of the Nuclear Regulatory Commission (NRC). Utility representatives were also present. The purpose of this meeting was to update the NRC on Seabrook leaking fuel, rod internal pressure, and fuel rod corrosion issues. Attachment 1 lists the meeting attendees. Attachment 2 is a copy of non-proprietary slides presented by Westinghouse and utility representatives. A portion of the presentation was involved in discussions on proprietary information.
Westinghouse representatives presented a meeting agenda and current fuel related activities within Westinghouse. Some of these activities include multi-functional task teams that are involved in incomplete rod insertion, axial offset anomaly, and rod internal pressure / corrosion issues. In research and development area, Westinghouse is actively involved in hot cell activities (high burnup program), drag testing (incomplete rod insertion issue), and laboratory testing (vibration / crud / corrosion).
An utility representative presented an update of leaking fuel at Seabrook. Preliminary observations indicated that the leaking rods are in high power locations. There is evidence of significant hydriding. The utility representative stated that the poteratialleakage mechanisms are crud-related localized effects and random hydrogen contamination. The utility representative also discussed crud analysis performed. The samples of crud were obtained from peripheral rods from leaking assemblies. The analysis revealed that Ni/Fe ratio is higher than previous sites. The cause of this high Ni/Fe ratio is to be studied. In Phase 3 of the examination, Seabrook plans to increase characterization of the oxide on the non-leaking batch G fuel, take measurements on leaking rod (s), and perform crud distribution evaluation and compare the results with other plants. A draft schedule of various activities at Seabrook I
was also presented.
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As b ckground information of rod intsmal pressura issue, W stinghousa discuss:d cetion items as a result of November 1997 meeting between Westinghouse and NRC staff. These action items include plant-by-plant assessments, review and improve analytical models, and gather additional data to validate fuel performance models. All evaluations were performed with conservative version of PAD (a computer code that analyzes fuel performance). Westinghouse representatives also discussed changes in creep model. The changes to the creep model will not have significant impact on PAD. The expected results from the improved creep model are more consistent with in-reactor experience using mechanistic approach. Westinghouse stated that for some fuel already in reactor cores, it may be possible that the revised PAD model might still predict some gap reopening. If this were to occur, Westinghouse will demonstrate that these assemblies will continue to meet all safety limits as well as 10CFR50.46 oxidation limits, for operating as well as future cycles, using the methodology that has already been presented to the NRC for gap reopening analysis. The staff agrees that this is an appropriate way to l
proceed. Westinghouse is planning to begin implementation of the new PAD model by August, 1998.' The code verification and validation (V&V) will follow Westinghouse Quality Plan.
Westinghouse plans to provide confirmation of successful code V&V to the NRC by July,1998, and requested a NRC letter by August,1998 to allow usage of new PAD model.-
Westinghouse representatives provided a discussion on ZlRLO fuel. Compared to low Tin Zr-4 fuel rod, the ZlRLO fuel rod will reduce corrosion by 50 percent at 60 GWD/MTU, ZlRLO fuel rod and assembly growth is reduced by 50 percent, and the creep performance is better.
l As an update of corrosion issue for low Tin Zr-4, Westinghouse continues to obtain oxide measurement data to validate and upgrade its corrosion models. Currently, four plants have submitted data on oxidation. Four more plants plan to submit additional data. Based on the existing data, Westinghouse has concluded that all crud-free measurements reported satisfy 10 CFR 50.46 oxidation requirements.
l Several action items resulted from this meeting. The NRC staff requested Westinghouse to provide: 1) an update on Seabrook fuel examination; 2) documentation of creep model; 3) creep model verification and validation; 4) schedule for upcoming plants to be examined, and 5) an overall program plan to address rod intemal pressure and fuel corrosion issues.
i j
Subsequent to the May 5th meeting, Westinghouse has provided clarification regarding the overheads presented on the operation of the Spanish plants. The Boron concentrations provided in these overheads for the Spanish plants are for some of the more recent cycles. It should be noted that the Spanish corrosion data that is currently available comes from prior cycles that did not have these high boron concentration levels. Westinghouse has decided that the corrosion data currently available from Spanish plants will be considered as part of the same database as those of the U.S. plants.
Attachments: As stated cc w/att: see next page Document name: 980505MT. SUM
- See previous concurrence OFC PGEB SC:PGEB C:SRXB AC:PGEB kNg NAME EWang:sw*
FAkstulewicz*
TCollins*
DATE 05/22/98 05/18/98 05/26/98 05/A/98 OFFICIAL RECORD COPY
f 1
l Thom:s H. Essig l i
i As background information of rod internal pressure issue, Westinghouse discussed action items as a result of November 1997 meeting between Westinghouse and NRC staff. These action items include plant-by-plant assessments, review and improve analytical models, and gather additional data to validate fuel performance models. All evaluations were perform with conservative version of PA.D (a computer code that analyzes fuel performance). Westinghouse representatives also discussed changes in creep model. The changes to the creep model will not have significant impact on PAD. The expected resul from the improved creep model are more consistent with in-reactor experience using mecha istic approach. Westinghouse stated that for some fuel already in reactor cores, it may be p sible that the revised PAD model might still predict some gap reopening. If this were to occur westinghouse will demonstrate that these assemblies will continue to meet all safety limi as well as 10CFR50.46 oxidation limits, for operating as well as future cycles, using the me odology that has already been presented to the NRC for gap reopening analysis. The staff rees that this is an appropriate way to proceed. Westinghouse is planning to begin imp mentation new PAD model by August,1998.
The code verification and validation (V&V) will f low Westinghouse Quality Plan. Westinghouse plans to provide confirmation of successful co V&V to the NRC by July,1998, and requested a NRC letter by August,1998 to allow usage f new PAD model.
Westinghouse representatives provide a d' cussion on ZlRLO fuel. Compare to low Tin Zr-4 fuel rod, the ZlRLO fuel rod will reduce c rosion by 50 percent at 60 GWD/MTU, ZlRLO fuel rod and assembly growth is reduced by 0 percent, and the creep performance is better.
As an update of corrosion issue for lo Tin Zr-4, Westinghouse continues to obtain oxide measurement data to validate and u grade its corrosion models. Currently, four plants have submitted data on oxidation. Four ore plants plan to submit additional data. Based on the existing data, Westinghouse has neluded that all crud-free measurements reported satisfy 10 CFR 50.46 oxidation require ents.
Several action items resulted om this meeting. The NRC staff requested Westinghouse to provide: 1) an update on Se rook fuel examination; 2) documentation of creep model; 3) creep model verification and valid tion; 4) schedule for upcoming plants to be examined, and 5) an overall program plan to a ress rod internal pressure and fuel corrosion issues.
l Subsequent to the May th meeting, Westinghouse has provided clarification regarding the
{
overheads presented n the operation of the Spanish plants. The Boron concentrations j
provided in these ov rheads for the Spanish plants are for some of the more recent cycles. It j
should be noted th the Spanish corrosion data that is currently available comes from prior cycles that did no ave these high boron concentration levels. Westinghouse has decided that the corrosio data currently available from Spanish plants will be considered as part of the same databas as those of the U.S. plants.
Attachment. As stated J
cc w/att:
.e next page i
j f
Docume t name: 980505MT. SUM
- See evious concurrence M u#
Ofb PGEB /', )
SC:PGEB C:SRXJ /
AC:PGEB EWang:s[
AME FAkstulewicz*
TC TEssig DATE 05/22/98 05/18/98 05/2.6/98 05/ /98 OFFICIAL RECORD COPY
I L
Thomas H. Essig - As background information of the rod internal pressure issue, Westinghouse representatives discussed action items as a result of a November 1997 meeting between Westinghouse and
^ NRC staff. These action items include plant-by-plant assessments, review and improvement of analytical models, and gathering additional data to validate fuel performance modeljiI All evaluations were performed with a conservative version of PAD (a computer code'that analyzes fuel performance). Westinghouse representatives also discussed changes in creep model.
l The changes to the creep model will not have significant impact on PAD.
e expected results i
from the improved creep model are more consistent with in-reactor ex rience. Westinghouse is planning to begin implementation of the new PAD model by Aug
,1998. The code verification and validation (V&V) will follow the Westinghouse Q ity Plan. Westinghouse plans to provide confirmation of successful code.V&V to the C by July,1998, and requested a NRC letter by August,1998, to allow usage of the new P model.
Westinghouse representatives provided a discussion o ZlRLO fuel. Compared to low Tin Zr-4 fuel rod, the ZlRLO fuel rod corrosion is reduce %y 50 percent at 60 GWD/MTU, ZlRLO fuel rod and assembly growth is reduced by 50 pe cent, and the creep performance is better.
As an update of the corrosion issue for low Tin Zr-4, Westinghouse continues to obtain oxide measurement data to validate and upgrade its corrosion models. Currently, four plants have j
submitted data'on oxidation. Four more plants plan to submit additional data. Based on the
{
existing data, Westinghouse has concluded that all crud-free measurements reported satisfy -
10 CFR 50.46 oxidation requirements.
Several action items resulted from this meeting. The NRC staff requested Westinghouse to provide: 1) an update on Seabrook fuel examination; 2) documentation of creep model; 3) creep -
model verification and validation; 4) schedule for upcoming plants to be examined, and 5) an overall program plan to address rod intemal pressure and fuel corrosion issues.
/
/
/
/
Attachments: As stated cc w/att: see nextjage Document /iame: 980505MT. SUM PGEB h h SC:PGEkMul C:SRXB AC:PGEB OFC f8L TCollins TEssig NAME EWang:sw FAkstulewicz DATE 05/18/98 05/[8/98 05/
/98 05/ /98 1
OFFICIAL RECORD COPY
cc:
I Mr. Nicholas Liparulo
. Westinghouse Electric Corporation PO Box 355-Pittsburgh, PA 15230-0355 Mr. Hank Sepp -
Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Andrew Drake WOG Project Manager Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Sumit Ray Westinghouse Electric Corporation PO Box 355 l
Pittsburgh, PA 15230-0355 Adam Moody Edlow International Company 1666 Connecticut Avenue, NW Suite 201 Washington DC 20009 i
l l
l I
NRC/ WESTINGHOUSE OWNERS GROUP MEETING LIST OF ATTENDEES May 05,1998 NAME ORGANIZATION Orr, Frank NRC/NRR/SRXB Desai, Kulin NRC/NRR/SRXB Wang, Egan NRC/NRR/PGEB l
Shoop, Undine NRC/RES/RPSB Wu, Shih-Llang NRC/NRR/SRXB Chatterton, Muffet NRC/NRR/SRXB Collins, Tim NRC/NRR/SRXB l
Harrison, John NRC/NRR Kendrick, Ed NRC/NRR/SRXB Bastin, Jack Westinghouse Wilson, Harley Westinghouse l
Vertes, Chris Westinghouse l
Koontz, Dave Duke Power Bryon, Bob TVA Colburn, David Westinghouse Esposito, Vincent Westinghouse Ray, Sumit Westinghouse Foster, John Westinghouse Leech, Bill Westinghouse Ely, Jay Northeast Utilities Herwing, Bill South Carolina Electric & Gas Larouere, Paula Virginia Power Wise, Doug Com Ed Hunt, Bruce Southern Nuclear Deloach, R. Jeb Seabrook Station ATTACHMENT 1
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DISTRIBUTION: Mtg. Summary of May 5 Meeting with WOG Dated Ny 29, 1998 HARD COPY Central File -
Public l
PGEB r/f C. Hehl, RI J. Johnson, Ril J. Caldwell, Rill T. Gwynn, RIV P. Wen E. Wang C. Craig OGC ACRS E-MAIL F. Miraglia A. Thadani R. Zimmerman B. Sheron T. Martin G. Lainas M. Virgilio E. Jordan D. Matthews R. Wessman F. Akstulewicz J. Roe T. Collins J. Strosnider M. Chatterton E. Kendrick S. L. Wu J. Harrison F. Orr K. Desai U.Shoop
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