ML20236X764
| ML20236X764 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/31/1998 |
| From: | Griesbach T, Marisa Herrera, Sauby M STRUCTURAL INTEGRITY ASSOCIATES, INC. |
| To: | |
| Shared Package | |
| ML20236X762 | List: |
| References | |
| SIR-98-079, SIR-98-079-R00, SIR-98-79, SIR-98-79-R, NUDOCS 9808100242 | |
| Download: ML20236X764 (17) | |
Text
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Report No.: SIR-98-079 Revision No.: 0 Project No.: PECO-23Q File No.: PECO-23Q-401 July 1998 Response to NRC Request for Additional Information Regarding Reactor Pressure Vessel Structural Integrity at Limerick Generating Station, Units 1 and 2 Preparedfor:
PECO Energy Company Preparedby:
StructuralIntegrity Associates,Inc.
San Jose, C lifornia Prepared by: $- c Date: ~l 2 9 9 Y W. J. Griesbach. ATI Consulting Reviewed by: Date: 3' b M. E. Sauby "
Approved by:
/
M. L. IIerrera Date: ?/bl/?l' 9808100242 980803 PDR ADOCK 05000352 P PDR f StructuralIntegrityAssociates,Inc.
, REVISION CONTROL SIIEET Document Number: SIR-98-079
Title:
Response to NRC Reauest for Additional Information Recardine Reactor Pressure 3 Vessel Stmetural Integrity at Limerick Generatine Station Units 1 and 2 Client: PECO Enercy Company SI Project Number: PECO-230 Section Pages Revision Date Comments All All A 7/24/98 Draft Issue 0 7/29/98 Final Issue f StructuralIntegrity Associates, Inc.
.___.______-_.._c- - - - - - - - - - - - - - - - - - - - - - ~ - - - ' - - - - - - - - - - - - " - ~ - - ~ - - - - - - - ' - - - - - _ -- -
Table of Contents Section Pace INTR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 . .....................
REOUEST 1: ASSESSMENT OF BEST-ESTIMATE CHEMISTRY.. . . . .................2 REOUEST 2: P-T LIMIT EVALUATION....... .................................. .............4 R EFEREN C ES : . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . .. . .. .. . . . . . . . . . . . . . . . . . . . ......................5 SIR-98-079. Rev. O iii StructuralIntegn.ty Associates, Inc.
INTRODUCTION This report presents the response to the U.S. NRC Request for Additional Information (RAI) l regarding reactor pressure vessel integrity at Limerick Generating Station, Units 1 and 2 (TAC l
Nos. MA 119/ and .MAi 198).
The RAI requests that PECO Energy re-evaluate the RPV weld chemistry values that have been previously submitted as part of the Limerick, Units 1 and 2 licensing basis in light of new information which has become available. Based on the new information, it will be determined if revisions to the Limerick, Units 1 and 2 RPV weld chemistries is needed.
The responses to the RAI requests are presented in the following pages. The response results of this evaluation indicate that there is no change in the limiting materials for P-T limits. Thus, there is no need to revise the P-T limit curves for Limerick, Units 1 and 2.
SIR-98-079, Rev. O I StructuralIntegrity Assc:iates, Inc.
I f
l REOUEST 1: ASSESSMENT OF BEST-ESTIMATE CHEMISTRY f The staff recently received the BWRyIP report " Update of Bounding Assessment of BWR2/6 Reactor Pressure Vessel Integrity Is. sues (BWRVIP-46) [1].
1 1
Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
1.
An evaluation of the bounding a::sessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds.
Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table i for each RPV beltline weld material. If the limiting material for your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
In addition, when evaluating weld chemistry data, you should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. A justification should then be provided for which assumption was chosen when the best-estimate chemistry was determined.
RESPONSE
Measured chemistry data for the Limerick, Units I and 2 vessel beltline weld heats were reexamined, including new data from a recent CB&I data search. Multiple test measurements were obtained for several submerged arc weld heats used in the beltline region of the Limerick 1 and 2 vessels. These weld heats are: S3986, IP4218,3P4000, and 5P6756. Evaluations of the best-estimate chemistries for these weld heats are given in Attachment 1. The chemistries of the rertaining beltline weld heats are based on single test measurements, and the best-estimate chemistry values for triese other welds remam: unchanged from prior evaluations. The data for the other beltline welds has been previously reported in the November 16,1992 Supplemental Response to Generic Letter 92-01 [2].
S TR-98-079, Rev. 0 2 StructuralIntegrity Associates, Inc.
The data in Attachment I were obtained from supplier CMTRs. The weld data were compiled for each individual heat, and data from unique weld sources were separated and assigned group tags.
For weld heat S3986, fourteen data measurements are available from twelve different weld sources as shown in Table A-1. Each weld source was assumed to be made from a single coil of weld wire. Average values were determined for each group, and the best-estimate chemistry values were determined from the average of the group averages. The calculated coil-weighted average and sample weighted average for copper and nickel weld chemistries are identical. Using these average values for the revised best-estimate chemistries produces a copper of 0.054 wt%
and a nickel of 0.960 wt% for heat number S3986. Table A-2 shows the revised best-estimate values for weld heat IP4218 of 0.057 wt% copper and 0.863 wt% nickel based on four separate test measurements. The dat3 for weld heat 3P4000 are shown in Table A-3 with a revised best-estimate copper of 0.020 wt% and nickel of 0.928 wt%. The evaluation for heat no. 5P6756 is shown in Table A-4 with a revised best-estimate copper of 0.083 wt% and a nickel value of 0.943 wt%.
Including these updated chemistry values, and using the revised projected EOL ID fluence based on i10% rerated power for Limerick, Units 1 and 2, the surface Adjusted Reference Temperature (ART) values were recalculated using the Regulatory Guide 1.99, Revision 2 method. The margin term,0 ,3 was also reevaluated in calcula,ing the ART value. According to Regulatory Guide 1.99, Revision 2, cafor welds is 28 F, or c ais equal to one-half of the calculated ARTuor, whichever is less.
Table 1(a) shows the best-estimate chemistries and surface ART values for the shop welds in the Limerick, Unit I vessel. This table includes revised best-estimate chemistries for weld heats 3P4000, S3986, and IP4218. The information for the limiting plate, heat number C7677-1, is also shown in Table 1(a). The calculated results for surface ART are based on an EOL peak 2
fluence level of 1.88x10'8 n/cm for 110% rerated power [2]. This rerated power fluence level applies to both Limerick Unit I and 2. It is noted that the ART values for all Limerick, Unit I shop welds are bounded by the ART value for the limiting plate of 94.5'F.
SIR-98-079, Rev. 0 3 gg,gggy,gy ggggg,;fy pgggg;gggg, pgg,
Table 1(b) shows the best-estimate chemistries and surface ART values for the field welds in the Limerick; Unit i vessel, including revised best-estimate chemistry for weld heat no. 5P6756. The calculated ART values in this table show that all Limerick, Unit i vessel beltline field welds are bounded by the ART value for the limiting plate of 94.5 F.
Table 2(a) shows the best-estimate chemistries and surface ART values for the shop welds in the I
Limerick, Unit 2 vessel. This table includes revised best-estimate chemistries for weld heat no.
3P4000. The information for the limiting plate, heat number B3416-1, is also shown in Table 2(a). From this table it is noted that the ART values for all Limerick, Unit 2 shop welds are {
bounded by the ART value for the limiting plate of 130.2"F.
Table 2(b) shows the best-estimate chemistries and surface ART values for the field welds in the Limerick, Unit 2 vessel. There are no revisions to the best-estimate chemistries for the field welds. The calculated ART values in this table show that all Limerick, Unit 2 vessel beltline field welds are bounded by the ART value for the limiting plate of 130.2 F.
REOUEST 2: P-T LIMIT EVALUATION
- 2. If the limiting material for your plant changes or if the adjusted reference temperature for the limiting material increases as a result of the above evaluations, provide the revised RTuor value for the limiting material. In addition, if the adjusted RTuor value increased, provide a schedule for revising the P-T limits. The schedule should ensure I that compliance with 10 CFR 50 Appendix G is maintained.
I l RESPONSE:
I I
There is no change in the limiting material., for P-T limits based on the revised weld chemistries for Limerick, Units 1 and 2. The limiting plate materials for both units are unaffected by this evaluation. Thus, there is no need to revise the P-T limit curves for Limerick, Units 1 and 2.
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REFERENCES:
l.
" Update of Bounding Assessment of BWR/2-6 Reactor Vessel Integrity Issues (BWRVIP-46)," EPRI TR-109727, December 1997.
2.
Philadelphia Electric Company, Letter to USNRC,
Subject:
Limerick Generating Station, Units 1 and 2 Supplemental Response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity, 50.54(f)," dated November 16,1992. SI File PECO-23Q-204
- 3. Limerick Updated Final Safety Analysis.
- 4. Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials," USNRC May 1998.
- 5. Letter from G. V. Kumar to Mr. T. E. Shannon, " Limerick Power Rerated Project Vessel Fracture Toughness - Revised Task Report," GE-NE, San Jose, CA, September 14,1993 (G93-PER-252)
=
- 6. Intentionally left blank.
- 7. SI File PECO-23Q-208, Weld Records for Limerick i found in record search at CB&l, November 1997.
8.
Si File PECO-23Q-204, Fax from Bob McCall (PECO) to T. Griesbach (ATI), forwarding copy of PECO Supplemental Response to GL 92-01 (Supp.1), dated November 16,1992, and Tables 5.3.3,5.3.4, and 5.3.5 of LSG UFSAR.
9 SI File PECO-23Q-216, Fax from T. Griesbach to Mike Sauby, dated July 23,1998 containing weld CMTRs.
- 10. SI Fik ?ECO-23Q-215, Fax from T. Griesbach to Mike Sauby, dated July 23,1998 containing weld CMTRs.
I 1. SI File PECO-23Q-210, Chemistry Report for Weld S3986, from WCAP-10861.
12.
SI File PECO-23Q-217, Fax from Tim Griesbach to Marcos Herrera, dated July 24,1998.
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