ML20211K213
| ML20211K213 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/31/1999 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NEL-99-0308, NUDOCS 9909070132 | |
| Download: ML20211K213 (4) | |
Text
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Dave Morey Southern Nucl:ar Vice President Opera'.ing C:mpmy,Inc.
Farley Project Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 a
SOUTHERN August 31, 1999 COMPANY Energy oServeYourWorld" Docket Number: 50-364 -
NEL-99-0308 50-348 U. S. Nuclear Regulatory Commission A*ITN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Comments on NRC Reactor Vessel Interrity Database. Version 2 (RVID2)
Ladies and Gentlemen:
k In your letter of July 2,1999 on closcout of Generic Letter 92-01 TAC Nos. MA0543 and i
MA0544, the NRC staff advised Southern Nuclear Operating Company (SNC) of the l
release of Version 2 of your Reactor Vessel Integrity Database (RVID2) and l
recommended that we review the information in this database. We have conducted a review of RVID2 with respect to Farley units 1 and 2 and conclude that the latest data submitted for the Farley units has not been incorporated into RVID2.
I Enclosed is a listing of conunents on RVID2 based on our review.
Please advise if you have any questions or need additional information.
Respectfully submitted, f hbru' Dave Morey DWD/maf: RVID2 review. doc
Attachment:
"SNC Conunents on NRC Reactor Vessel Integrity Database Version 2 (RVID2) for Joseph M. Farley Nuclear Plant" l
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9909070132 990831 PDR ADOCK O j8.
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U. S. Nuclear Regulatory Commission cc:
Southern Nuclear Ooeratinn Companv Mr. L. M. Stinson, General Manager - Farley U. S. Nuclear Regulatory Commission. Washinnton. D. C.
Mr. L. M. Padovan, Licensing Project Manager - Farley U. S. Nuclear Regulatory Commission. Renion II Mr. L. A. Reyes, Regional Administrator Mr. T. P. Johnson, Senior Resident hispector - Farley 1
1
Attachment -
Joseph M. Farley Nuclear Plant SNC Comments on NRC Reactor Vessel Integrity Database Version 2 (RVID2)
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A.
General Comments RVID2 does not incorporate the latest data submitted for the Farley units.
1.
For Farley 1, RVID2 does not include data from Westinghouse reports WCAP-14687 and i
WCAP-14689, submitted by SNC letter dated October 27,1997.
2.
For Farley 2, RVID2 does not include data from Westinghouse report WCAP-15171, submitted by SNC letter dated March 19,1999.
B.
Comments on the PTS Summary Repost 1.
For the Farley 1 intermediate shell axial weld (heat 33A277), the correct value for RTm from WCAP-14689 is 117'F (versus 119.2*F in RVID2).
2.
For Farley 2 intermediate shell plate B7212-1 (heat C7466-1), the correct value for RTm from WCAP-14689 is 20l*F (versus 204.9"F in RVID2).
3.
For Farley 2 intermediate shell axial weld 19-923B (heat BOLA), the values of 0.010% P.
and 0.016% S reported by SNC letter dated July 1,1992 should be used (versus 0.000% for both elements in RVID2) 4.
For Farley 2 circumferential weld Il-923 (heat $P5622), the value of 0.008% S reported by SNC letter dated July 1,1992 should be used (versus 0.018% S in RVID2).
~
C.
Comments on the Surveillance Data Summary Report 1.
As discussed under General Comments, the latest surveillance data have not been input into RVID2 for the Farley units. Consequently, this data and corresponding calculated values have not been verified.
. 2.
For Farley 1, the chemical analysis values in RVID2 for surveillance plate B6919-1 appear
' to be a mixture of the results from separate analyses performed by Combustion Engineering and Westinghouse. The results of both analyses, from WCAP-8810, are given below. One set of values should be chosen for use in RVID2.
Plate B6919-1 analysis by:
. % Cu
% Ni
%S
%P CE 0.14 0.55 0.015 :
0.015
)
Westinghouse 0.10 0.56 0.013 0.015 l of 2 e
I Attachment 3.
For Farley 2, the following chemical analysis results obtained from capsule Z analysis in WCAP-15171 should be used in place of the values now in RVID2.
Material
% Cu
% Ni
%S
%P Plate Unirradiated 0.20 0.60 0.016 0.018 B7212-1 Capsule W 0.186 0.59 0.016 0.008 Best Estimate 0.193 0.60 0.016 0.013 Unirradiated 0.03 0.90 0.014 0.004 Weld Metal Capsule W 0.026 0.88 0.013 0.006 Best Estimate 0.028 0.89 0.014 0.005 4.
The definition of Upper Shelf Energy (USE) given in ASTM E185-82 was strictly applied in a re-analysis of all Farley 2 surveillance data reported in WCAP-15171. As a result, the measured USE values changed slightly from the RVID2 values for the two cases below.
Measured USE values (fl-lb)
Material Original Data Revised Data (in RVID2)
Plate heat #C7466-1, longitudinal, capsule X 94.0 96 Weld heat # BOLA, capsule X 144.0 150 D.
Comments on the Upper Shelf Energy (USE) Summary Report 1.
In a letter dated July 1,1992, SNC provided transverse USE values for Farley 1 that were estimated per the 65% method of MTEB 5-2; these values are included in RVID2. Historic Westinghouse test data for the unirradiated plates makes this use of estimated values unneatsary. Both sets of USE values are given below.
Unirradiated USE Values (ft-lb)
Material Estimated value from July 1,1992 letter Historic (now in RVID2)
Westinghouse Data Intermediate Shell Plate B6903-2 99.00 97 Intermediate Shell Plate B6903-3 87.00 100 Lower Shell Plate B6919-1 86.00 91 Lower Shell Plate B6919-2 86.00 97 2.
For Farley I lower shell plate B6919-1 (heat C6940-1), RVID2 uses surveillance data for calculations. As documented in WCAP-14689 Rev. 4, this surveillance plate data is not credibic.
3.
For Farley 2 intermediate shell axial weld 19-923A (heat IIODA), RVID2 indicates that surveillance data is available. SNC is not aware of any available surveillance data for this weld, although surveillance data is given in WCAP-14689 for weld 19-923B (heat BOLA).
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