ML20070D798
| ML20070D798 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/05/1994 |
| From: | Seiber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, TAC-M83431, TAC-M83432, NUDOCS 9407120339 | |
| Download: ML20070D798 (8) | |
Text
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Beaver VaHey Power Station Shippingport, PA 15077-0004 JOHN D. SIEBER (412) 393-5255 Senior Vice President and Fax (412) 643-8069 Chief Nuclear Ofhcer Nuclear Power Dmsion July 5, 1994 U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Generic Letter 92-01, Revision 1; RVID (TAC Nos. M83431/M83432)
By separate letters dated June 9, 1994 (one for each Unit), the NRC indicated its review of the Duquesne Light Company (DLC) response to Generic Letter 92-01, Revision 1,
was complete.
Tables were included which contain the requisite data for performing USE (upper-shelf energy) and PTS (pressurized thermal shock) evaluations.
It was requested that DLC verify that the information has been accurately entered into the summary file database designated as the RVID (Reactor Vessel Integrity Database).
Additionally, an open item for Unit i regarding the amounts of copper and nickel in welds fabricated using weld wire heat numbers 305424, 305414, and 90136 was identified.
The results of our verification of the RVID and our response to the open item are provided below.
Unit 1 A
reassessment of the use of the values contained in the Westinghouse Owners Group (WOG) database has resulted in a change to the amount of copper assigned to the weld fabricated using weld wire heat number 305414.
Table 14 of our July 8, 1992, response to Generic Letter.
92-01, Revision 1,
contained a
value
'0.35 percent copper for longitudinal weld 305414.
The value contained in the WOG database is 0.34 percent copper.
Recent correspondence with the Westinghouse Electric Corporation, which has provided technical support in responding to reactor vessel integrity issues, has verified the WOG database value as 0.34 percent copper.
As a result, a new Table 14 has been prepared and is included as Enclosure A to' replace the DEllVEIIING QU ALIT Y m
9407120339 940705 PDR ADOCK 05000334 P
PDR 1
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Beaver Valley Power Station, Unit No. 1 and No. 2 Generic Letter 92-01, Revision 1; RVID Page 2-existing Table 14 in our July 8, 1992, submittal.
This will result in the NRC's " Summary File for Pressurized Thermal Shock" for Beaver Valley Unit 1 to have the following revisions:
1)
The percent copper for the lower shell axial weld (heat no.
305414) should be revised to read "0.34."
2)
The Chemistry factor for the same weld should be revised to read "210.45."
The remainder of the file values have been checked and agree with the Duquesne Light Company records.
One open item regarding the amounts of copper and nickel in welds using weld wire heat numbers
- 305424, 305414, and 90136 was identified.
On September 10, 1993, a response to an NRC request for additional information was submitted.
The response to Question 2 noted that the mean values of the copper and nickel were found in the WOG database.
These are the best-estimate values for the Beaver Valley welds which were fabricated using the same heat number as the l
critical vessel weld; therefore, the mean value is acceptable as a best-estimate value.
Included with this submittal as Enclosure B are' the WOG database values for those wire heats applicable for the Beaver Valley reactor vessel welds.
Unit 2 A
review of the RVID for Beaver Valley Unit 2 has identified one error in the
" Summary File for Pressurized Thermal Shock."
The percent copper for the
" Circ.
weld" and
" Axial welds" should be "0.06."
This value is consistent with the data submitted in the initial response to Generic Letter 92-01, Revision 1, dated July 8,
- 1992, (Table 1).
The remainder of the file values have been checked and agree with the Duquesne Light Company records.
If you have any questions related to this submittal, please contact Mr. Steve Sovick at (412) 393-5211.
Sincerely, y jw J.
D.
Sieber cc:
Mr.
L. W.
Rossbach, Sr. Resident Inspector Mr.
T.
T. Martin, NRC Region I Administrator Mr.
G.
E.
Edison, Project Manager
ENCLOSURE A Revised Table 14
" Beaver Valley Unit 1 Adjusted Reference Temperature Values for 12/16/91-and End-of-License (32 EFPY) "
Instructions: Replace the existing Table 14 with the attached labeled
" Revised June 28, 1994" 4
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L Table 14 Beaver Valley Unit l' Adjusted Reference Temperature Values for 12/16/91 and End-of-License (32 EFPY)
CU NI IRTNDT 12/16/91 32 EFPY Beltline Material (WT%)
(WT%)
CF_
(*F)
Marcin ART f*F)
ART Inter. shell, B6607-1 0.14 0.62 100.50 43 34 182 210 I
Inter. shell, B6607-2 0.14 0.62 100.50 73 34 212 240 Lower shell, B6903-1, 0.20 0.54 141.80 27 34 209 249 using S/C data 167.81 27 17*
219 266 Lower shell, B7203-2 0.14 0.57 98.65 20 34 157 185 Long. weld, 305424,
- 0.28 0.63 191.65
-56 66 121 188 using S/C' data 191.33 44*
99 166 7
l Long. weld, 305414
. 0.34 0.61 210.45
-56 66 132 203 Circumferential weld 0.29 0.07 132.90
-56 66 148 186
- Margin was_ reduced according to methodology, specified in Reg. Guide 1.99 Rev. 2 [2].
23 Revised June 28, 1994 i
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ENCLOSURE B WELD CHEMISTRY J
Tables B-1 through B-3 provide the weld data output f rom the WOG Material Data 1
Base. Given are the searches of all available data for the wire heats ~ in j
Beaver Valley Unit I reactor vessel beltline region.
The pertinent material chemistries are given, along with the wire / flux identification,-the data source, and the plant identification.
The mean chemistry values are then calculated.
These mean values are used.in the RT analysis.
PTS "Weldchem Data Source" and Plant:
r CE Combustion Engineering McGuire Unit 1 DAP DLW Beaver Valley Unit i FCl Fort Calhoun Unit 1 MATSURV NRC Database ML2 Millstone Unit 2 MPC, DB Metal Properties Council Database SC Surveillance Capsule SL1 St. Lucie 1 i
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TABLE B-3 LOWER SHEi.L~ LONGITUDINAL WELD CHEMISTRY-WOG DATA BASE'MEAN WIRE HEAT 305414 i.E LECi REeoR, ID WIRE WIRE FLua FLUX WELDCIEN Cu Na P
Sa PLANT DESCRIPTION MAT TYPE TYPE LOT DATA SOURCE
--~~--------------
0202 305414 9-4 MOD LINDE 1092 3958 CE,WO O.360 0.600 0.012 0.150 DL W NOIELE TO INTER SHELL FCi SURVE ILt. ANCE WEL D 0203 305424 D-4 MOD LINDE 1092 3958 CE WQ O.350 0.640 0.013 0.240 DLW NO22L E TO INTER SHELL 0312 305484 3-4 MOD LINDE 1092 3954 FC1,6C O.350 0.600 0.043 0.140 DLW NOZILE 10 INIER SHELL FC1 SURVEILL ANCE WELD 0326 305414 S-4 MOD LINDE 1092 3947 CE WQ O.330 0.590 0.012 O.180 DLW L OWER SHELL LONG c723 3054t4 B-4 MOD LINDE 1092 3951 MPC.DB FC1.SC O.300 0.600 0.083 0.210 DL W NO2iLE 10 INTER SELL FCI SURVEILLANCE WELD eeman 0.338000 0.606000 0.082600 0.178000 std.dev.
0.023875 0.049494 0.000548 0.03271I 8
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