View source for L-98-133, Forwards Response to Request for Addl Info Re GL 92-01,Rev 1,Suppl 1 for Reactor Vessel Structural Integrity

{{Adams
| number = ML20236Q052
| issue date = 07/09/1998
| title = Forwards Response to Request for Addl Info Re GL 92-01,Rev 1,Suppl 1 for Reactor Vessel Structural Integrity
| author name = Jain S
| author affiliation = DUQUESNE LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000334, 05000412
| license number = 
| contact person = 
| document report number = GL-92-01, GL-92-1, L-98-133, NUDOCS 9807170288
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 20
}}

=Text=
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Beave Valley Power Station l                                                     Shippingport, PA 15077-0004
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i S    r       esident -                                                                 Fax     4-Nuclear Power Divis6on                                            July 9, 1998 L-98-133 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 1
                                                       ~
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==Subject:==
Beaver Valley Power Station, Unit No. I and No. 2
!                            BV-1 Docket No. 50-334, License No. DPR-66 l                            BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information                                        !
Generic Letter 92-01, Revision 1, Supplement 1                                        l
!                            Reactor Vessel Structural Integrity The enclosed information is provided in response to a request for additional l      - information (RAI) dated April 8,1998, regarding reactor pressure vessel (RPV) integrity l        st Beaver Valley Power Station Unit Nos. I and 2. This response is a follow-up to
       ' earlier submittals by Duquesne Light Company (DLC)' on August 6,1996, and             _
!        supplemented on March 14,1997 and June 5,1997, in which DLC performed a revised pressurized thermal shock (PTS) analysis for the Unit I reactor pressure vessel per the requirements 'of ~ 10 CFR 50.61. This evaluation determined the PTS reference temperature (RTm) value for Unit I to be 264.5 F at end oflife (EOL). On October 7, 1997, the NRC sent a safety evaluation report (SER) on the PTS assessment for Unit 1                      ;
that did not agree with the assumptions for fluence and margin term used in the DLC submittal. The NRC SER evaluation produced a slightly higher RTm value of 267.8 F                         i
: l.       for the limiting plate at EOL.
l           .
Following these submittals, additional RPV information has become available from
       . the Combustion Engineering Owners Group (CEOG) for vessel welds fabricated by                             !
Combustion Engineering as documented in CEOG report, CE NPSD-1039, Revision 02.
As a follow-up to the previous submittals and the CEOG report, DLC has been requested                     :
to assess the impact of revised best-estimate chemistries for vessel beltline welds and to consider the need to revise previous evaluations of RPV integrity. For comparison, this                   i response also includes the requested tables for Unit I using the assumptions from the
       ' NRC SER.
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[.,        Beaver Valley Power Station, Unit No. I and No. 2
  ,        Response to Request for Additional Information i          Generic Letter 92-01, Revision 1, Supplement I Reactor Vessel StmeturalIntegrity Page 2 The enclosure provides the requested information and reanalysis for Beaver Valley _
Power Station Unit Nos. I and 2. Because the additional CEOG weld data does not
,          affect the limiting plates in either vessel, the previous evaluations for PTS, PT limits and l          overpressure protection remain valid for both units.
Sincerely,
                                                                                                    ~
                                                                                       ~
J_ ^ "-
Sushil C. Jain
,          Enclosure l
l l          c:     Mr. D. S. Brinkman, Sr. Project Manager Mr. D. M. Kern, Sr. Resident Inspector l                 Mr. H. J. Miller, NRC Region I Administrator i
i l
l l
l

9 Enclosure
,                                              Beaver Valley Power Station, Unit Nos. I and 2 i
Response to Request for AdditionalInformation Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity l

== Introduction:==

The NRC issued Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01,                                 ,
,                  Rev.1, Supp.1), " Reactor Vessel Structural Integrity" in May 1995. The purpose of this GL was to request licensees to identify, collect, and report any new data pertinent to the analysis of the structuralintegrity of their reactor pressure vessels (RPVs) and to assess the impact of those data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the                        .
Code of Federal Regulations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to                                     l 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy
;                  (USE) evaluations), and any potential impact on low temperature overpressure protection (LTOP) limits or pressure-temperature (PT) lhnits.
Since then, additional RPV information has become available from the Combustion Engineering Owners Group (CEOG) for vessel welds fabricated by Combustion Engineering as documented in a CEOG report [1] and a recently updated CEOG analysis [10]. As a follow-up to                           i the Generic Letter and the CEOG report, Duquesne Light Company (DLC) has been requested to                            )
:                  assess the impact of revised best-estimate chemistries for vessel beltline welds and to consider the                    ;
need to revise previous evaluations of RPV integrity. If there is no impact or if questions in this                   i request for additional information (RAI) do not apply for Beaver Valley Unit Nos. I and 2, the                          l NRC requests certification that previously submitted evaluations remain valid.                                          j l                  

==Background:==

By {{letter dated|date=August 2, 1996|text=letter dated August 2,1996}}, as supplemented March 14,1997 and June 5,1997, DLC submitted a reassessment of the PTS analysis for the Beaver Valley Unit 1 vessel [2]. A Safety Evaluation regarding PTS assessment for Unit I was issued on October 7, 1997 [3]. In that evaluation, the NRC staff did not concur with all aspects of the DLC analysis. However, the NRC staff did concur with the conclusion that the PTS reference temperature (RTrrs) value for the Unit I limiting material remains below the PTS screening criteria limit through end-of-life (EOL).
An evaluation of pressurized thermal shock for Unit 2 was performed in February 1997 [4].
This response analyzes the information in the CEOG report for the Unit I and Unit 2 vessel beltline welds to determine the impact on these prior vessel integrity evaluations.

;           Enclosure
    .'      Response to Request for AdditionalInformation Generic Letter 92-01, Revision 1, Supplement 1
,           Reactor Vessel Structural Integrity l
Page 2
* l Response to NRC PAI Regarding Reactor Pressure Vessel Integrity for Beaver Valley Power Station Unit Nos. I and 2:
RAISection 1.0 Assessment of Best-Estimate Chemistry Based on the information in the CEOG Report CE NPSD-1039, Revision 2, "Best-Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," and in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
Reauest 1     An evaluation of the information in the reference above and an assessment ofits applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds. Based upon this reevaluation, supply tle information necessary to completely fill out the data requested in Table 1 for each RPV        l beltline weld material. A!so provide a discussion for the copper and nickel values chosen for each weld wire heat noting what heat-specific data were          !
I included and excluded from the analysis and the analysis method chosen for determining the best-estimate. If the limit;ng material for your vessel's PTS /PT limits evaluation is not a weld, include the information requested in Table 1 for  j the limiting material also. Furthermore, you should consider the information       l provided in Section 2.0 of this RAI on the use of surveillance data when           !
responding.
Response 1 Urut 1 There are three weld heats in the Unit I vessel beltline, 305424, 305414, and 90136.
Best-estimate copper and nickel chemistries for these weld heats were reevaluated using the      ,
method recommended in the CEOG report (see Tables 4-1 through 4-3). A comparison with the        i previously-reported vahas is shown below:
Reactor Vessel Weld and                     Previous Values [2i        CECG Values tu Beltline R.egion Material                  Cu wt%       Ni wt%      Cu wt%       Ni wt%
Interm. Shell Long Welds 19-714A/B Heat #305424, Linde 1092 T,9e Flux          0.263         0.632       0.273       0.629 Lower shell Long. Welds 20-714A/B Heat #305414, Linde 1092 Type Flux          0.338         0.606       0.337       0.609 Circumferential Weld Il-714 l             Heat #90136, Linde 0091 Type Flux           0.278         0.071       0.269       0.070 l
l m

Enclosure I
    .?-    , Response to Request for Additional Information Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel StaucturalIntegnty                                                                                            i Page 3 I
The revised best-estimate chemistries are included in Table 1-1. The revised chemistries are slightly different than the previously reported values. These differences are not significant and have no effect on the limiting plate. Updated Adjusted Reference Temperature values are computed for these welds along with the information and calculated values for limiting plate heat C6317-1. The surveillance data results were used to determine the chemistry factor (CF) value for the surveillance weld and plate materials. The results in Table 1-1 reflect the revised fluence and proposed margin term from the recent PTS nbmittal for Unit 1[2].
For comparison, the NRC best-estimate values from the recent safety evaluation report (SER) are presented in Table 1-2 [3]. The best-estimate chemistries in this table have been updated to include the CEOG recommended values [1]. There is no change in the RTm value for liuiting plate heat C6317-1.
Unit 2 There is one weld heat in the Unit 2 vessel beltline, heat no. 83642. Best-estimate copper and nickel chemistries for this weld heat were evaluated here using the method recommended in the CEOG report with a revision based on reanalysis of data validity.                               A comparison with the previously-calculated values is shown below:
Reactor Vessel Weld and                    Previous Values W                                Revised Values Beltline Region Material                  Cu wt%                         Niwt% Cu wt%                Ni wt%
Axial and Circumferential Welds Heat #83642, Linde 0091 Type Flux           0.05                          0.u7  0.047                 0.085 The revised best-estimate chemistries are included in Table 1-3. The revised chemistries are slightly different from the previously reported values, and are different from the CEOG recommended value for this heat because the measured chemistries from the Unit 2 surveillance weld material (excluded from the CEOG analysis) were determined to be valid (see Table 4-4).
These differences do not affect the weld CF since the surveillance data results were used to determine the CF value for the surveillance weld material. Updated Adjusted Reference Temperature values are computed for this weld along with the information and calculated values forlimiting plate heat C0544-1.
MISecelon 10 Eval = dan ami Ure ofSurnillance Data 1.
I Since the evaluation of surveillance data rely on both the best-estimate chemical composition of the RPV weld and the surveillance weld, the information in the CEOG report may result in the need to revise previous evaluations ofRPV integrity (including LTOP setpoints and PT limits) per the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50.

Enclosure
  ?                              Response ts Request for Additional Information Generic Letter 92-01, Revision 1, Supplement 1 l
Reactor Vessel Structural Integrity Page 4 Based on this information and consistent with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
Reauest 2 that (1) the information listed in Table 2, Table 3, and the chemistry factor from the surveillance data be provided for each heat of material for which surveillance weld data are available and a revision in the RPV integrity analyses            j (i.e., current licensing basis) is needed or (2) a certification that previously submitted evaluations remain valid. Separate tables should be used for each heat of material addressed. If the limiting material for your vessel's PTS /PT limits evaluation is not a weld, include the information requested in the tables for the limiting material (if surveillance data are available for this material).
Resnonse 2 Unit 1 DLC believes that the previously submitted suneillance results for Unit I remain valid. The results for surveillance weld heat 305424 are given in Tables 2-1 and 3-1. The results for surveillance plate heat C6317-1 are given in Tables 2-2 and L2. These tables include the utility best-estimate fluence values and TANIi curve-fitted results (2].
Because of differences in the NR>." staffs evaluation of fluence [3], the results for surveillance weld heat 305424 according to the SER are given in Tables 2-3 and 3-3. The results for surveillance plate heat C6317-1 using NRC best-estimate fluences are given in                                                                  l Tables 2-4 and 3-4.
Unit 2 The results for suneillance weld heat 83642 are given in Tables 2-5 and 3-5. This is the same information that was presented in the PTS evaluation for Unit 2 [4]; DLC believes                                                                 l that these suncillance results remain valid.                                                                                                               !
RMSecdon 3.0 PTS /PTLimit Evaluadon Reauest 3 If the limiting material for your plant changes or if the adjusted reference                                                                     l temperature (ART) for the limiting material increases as a resuh of the above                 1 evaluations, provide the revised RTrrs value for the limiting material in                     j accordance with 10 CFR 50.61. In addition, if the adjusted RTwr value                         l increased, provide a schedule for revising the PT and LTOP limits. The                         l schedule should ensure that compliance with 10 CFR Part 50, Appendix G, is tesmiestmi,ned,

Enclosure
      ?               Response to Request for Additional Inform:. tion Generic Letter 9241, Revision 1, Supplement 1 Reactor Vessel Structural Integrity Page5 '
Resnonse 3                                                                                           {
Based on this evaluation, the vessel weld chemistry factors and ART values are only slightly changed by the revised best-estimate chemistries, and no new information has become           '
available on the limiting plate materials of either Unit's reactor vessel. Therefore, the previously submitted analyses for PTS, PT limits and LTOP remain valid for Beaver Valley Unit Nos. I and 2.

==References:==

[1] "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds,"
Prepared for the C-E Owners Group, CE NPSD-1039, Revision 2, June 1997.
[2] " Evaluation of Pressurized Thermal Shock for the Beaver Valley Unit i Reactor Vessel,"            i Westinghouse' Electric Corp., WCAP-14543, June 1996.
[3] Safety Emluation Reganiing Pressurized 7hermal Shock (PTS) Assessment for Beaver
                            ' ValleyPower Station, Unit No.1, US Nuclear Regulatory Commission, October 7,1997.
[4' . Evaluation    of Pressurized Thermal Shock for Beaver Valley Unit 2," West'mghouse Electric Corp., WCAP-14784, Rev. 2, Februaiy 1997.
[5] " Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit No.1                  J Reactor Vessel Radiation Surveillance Program," Westinghouse Electric Corp., WCAP-9860, January 1981.      ,
[6] " Analysis of Capsule U from the Duquesne Light Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Westinghouse Electric Corp., WCAP-10867, September 1985.
[7] " Analysis of Capsule W from the Duquesne Light Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Westinghouse Electric Corp., WCAP-12005, November 1988.                                                                                  !
[8] " Analysis of Capsule U from the Duquesne Light Company Denver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," Westinghouse Electric Corp., WCAP-124%,
September 1989.
[9] " Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel' Radiation Surveillance Program," Westinghouse Electric Corp., WCAP-14484,              l February 1996.                                                                                  i l
[10] ." Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best               i Estimate Copper and Nickel Content," Prepared for the C-E Owners Group, CENPSD-1119, Revision 00, Draft Report, June 1998.                                                    !
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Enclosure Response to Request for AdditionalInformation Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity
* Page'9 Facility: Beaver Vallev 1 Table 2-1: Weld Heat 305424 CapsuleID      Cu                   Ni                                   Irradiation               Fluence        Measured         Data Used in (including                                                          Temperatum                            2 (x1028n/cm )        ARTuur        Assessing Vessel source)                                                                             (*F)                           (*F)             (Y or N)
VI51      0.26              0.62                                                   546         0.3160)          157.80)                       Y'                            I UM1       0.26              0.62                                                   546         0.690n)          164.40)                       Y WM        0.26              0.62                                                   546         0.9150)          185.60)                       Y CF fitted = 196.4 'F Table 3-1: Weld Heat 305424 Capsule ID          Cu     NI         Irradiation                                                 Fluenm     Measured   Adjusted        Predicted                            (Adjusted -
(including                        Temperature                                                      Factor     ARTwor    ARTwer            ARTuur                             Prodicted) source)                                          (O                                                          (F)            ff)          (F)                           ARTNur (F)
            ~
Visi         0.26   0.62                     546'                                            O.684       157.8. 157.8             134.3                                23.5 UM1          0.26   0.62                     546                                             0.8 % . 164.4     164.4             175.9                               -11.5 4
WR           0.26   0.62                      546                                             0.975      185.6     185.6             191.5                                -5.9
                 ") capsule fluences determined from Beaver Valley 1 PTS evaluation [2]
C) measured ARTurrvalues from TANH curve-fit [2]
l l
\                                                                                                                                _ _ .                   _____-_______________ - - -

Enclosure
        .                  Response to Requ:st for AdditionalInformation Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity
                    -' Page'10 Facility: Beaver Valley 1 Table 2-2: Plate Heat C6317-1 Capsule ID                             Cu                        Ni               Irradiation    Fluence    Measured         Data Used in (including                                                                      Temperature             2 (x1018n/cm )    ARTNur       Assessing Vessel source)                                                                           (*F)                      (*F)           (Y or N)
VrLM                           0.20                     0.54                    546        0.316m      137.8m               Y Vorm                           0.20                     0.54                    546        0.316m      128.2m               Y.
Urt i 'l                       0.20                     0.54                    546        0.690m      131.8m               Y UtrM                           0.20                     0.54                    546        0.690m      118.9m               Y Wnm                             0.20                     0.54                    546        0.915m       179.9m              Y Worm                            0.20                     0.54                    546        0.915m       147.8m              Y CF fitted = 163.4 F Table 3-2: Plate Heat C6317-1 Capsule ID                       Cu                    Ni                  Irradiation               Fluence  Measured    Adjusted    Predicted      (Adjusted -
(induding                                                                Temperature                  Factor    ARTwar    ARTNor       ARTNur         Predicted) source)                                                                          (*F)                           (*F)      (*F)         (*F)       ARTNDT ( F)
VnN                         0.20                  0.54                         546                 0.684      137.8     137.8        111.7           26.1 i
VtrW                        0.20                  0.54                         546                 0.684      128.1     128.1        111.7            16.4    j UrtN                        0.20                  0.54                         546                 0.8%       131.8     131.8        146.4           -14.6 UtrN                        0.20                  0.54                         546                 0.8%       118.9     118.9        146.4           -27.5    ,
4 Wnn                          0.20                 0.54                          546                 0.975     179.9     179.9        159.3            20.6    ;
l                   Wtin                        0.20                  0.54                          546                 0.975     147.7     147.7        159.3           -11.6 L
l W capsule fluences determined from Beaver Valley 1 PTS evaluation [2]
* measured ARTmyr values from TANH curve-fit [2]
L--

Encl sure
    .'.         Response to Request for Additional Information Generic Letter 92 01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity
* Page'l1 Facility: Beaver Valley 1 Table 2-3: Weld Heat .305414.
Capsule ID      Cu         Ni       Irradiation    Fluence     Measured                                      Data Usedin (including                        Temperature  (x101' n/cm2)   ARTNor                           Assessing Vessel source)                              (*F)                       (*F)                                                       (Y or N)
V         0.26       0.62          546        0.3400)        157.8                                                              Y U         0.26       0.62          546        0.6880)        164.4                                                              Y W         0.26       0.62          546        1.0580)        185.6                                                              Y CF fitted = 191.92 'F Table 3-3: Weld Heat 305424 CopsuleID        Cu      Ni     Irraaation      Fluenm   Measured     Adjusted    Predicted                                                    (Adjusted-(including                     Temperature       Factor    ARTNur     ARTNur         ARTNur                                                     Predicted) source)                          (*F)                     (*F)       (*F)                       (*F)                                        ARTuur (*F)
V          0.26   0.62         546          0.703      157.8      157.8               134.9                                                  22.9 U          0.26'  O.62         546          0.895      164.4      164.4                171.8                                                  -7.4 W          0.26    0.62        546           1.016     185.6      185.6               194.9                                                   -9.3
( ) capsule fluences determined from NRC SER Regarding PTS Assessment for BV-1 [3]
_ - _ . - - - _ _ _ _ - . . _ - - _ _ _ _ _ _ _ _ _ _ _ -               .. w

Enclosure
   ..L           Response to Request f;r Additional Information Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural Integrity
* Page'12 Facility: Beaver Vallev 1 Table 2-4: Plate Heat C6317-1 Capsule ID      Cu         Ni        Irradiation    Fluence     Measured         Data Used in (including                          Temperature             2 (x101' n/cm )    ARTm         Assessin6Vessel source)                                (*F)                       (*F)           (Y or N)
Vn.         0.20       0.54           546       0.3400)         137.8              Y Vtr         0.20       0.54           546        0.3400)        128.1              Y Un.         0.20       0.54           546        0.6880)        131.8              Y Ut.r        0.20       0.54           546        0.6880)        118.9              Y W n.        0.20       0.54           546        1.0580)        179.9              Y Wtr         0.20       0.54           546-       1.0580)        147.7              Y CF fitted = 159.9 F Table 3-4: Plate Heat C6317-1 Capsule ID        Cu    - Ni     Irradiation      Fluence  Measured     Adjusted    Predicted      (Adjusted -
(including                      Temperature        Factor   ARTm        ARTm         ART m          Predicted) source)                           (*F)                      (*F)       (*F)         (*F)       ARTm (*F)
Vn.         0.20    0.54         546           0.703     137.8       137.8       112.40)           25.4 Vor         0.20    0.54         546           0.703      128.1      128.1       112.40)          .15.7 Un.         0.20    0.54         546           0.895      131.8      131.8       143.10)           -11.3 Utr         0.20 -  0.54         546           0.895      118.9      118.9       143.10)           -24.2 W n.         0.20   0.54         546            1.016     179.9      179.9       162.40)            17.5 i
Wtr          0.20   0.54         546            1.016     147.7      147.7       162.40)           -14.7 "3 determined from NRC SER Regarding PTS Assessment for BV-1 [3]
I h
b

l.
Enclosure l  .                Response to Request for Additional Information i                   Generic Letter 92-01, Revision 1, Supplement I                                                                                                  !
Reactor Vessel Structural Integrity
* Page'13 Facility: Braver Vallev 2 Table 2-5: Weld Heat 83642 l
Capsule ID      Cu       Ni                  Irradiation                                    Fluence    Measured        Data Used in (br.luding                            Temperature                                        (x10" n/cm2)    .iRTer      Assessing Vessel terxe)                                                        (*F)                                        (*F)          (Y or N)
UM          0.08     0.07                                  546                          0.6010)        3B2)              Y               f VM          0.08     0.07                                  546                           2.640)       25.50)             Y CF fitted = 15.2 F l
Table 3-5: Weld Heat 83642                                                                                       l Capsule ID            Cu  Ni    Irradiation                               Fluence                   Mansured    Adjusted   Predicted      (Adjusted -
(including                     Temperature                                    Factor                 ARTer      ARTwr       ARTer          Predicted) source)                           (*F)                                                               (*F)       (*F)        (*F)       ARTer (*F)
UM            0.08    0.07       546                                       0.857                    3.6        3.6         13.0            -9.4 VM             0.08   0.07       546                                           1.26                 25.5      25.5         19.1             6.4
                    ") capsule fluences determined from Beaver Valley 2 PTS evaluation [4]
(23 measured ARTmyr values from TANH curve-fit [4]

             .D
        ,.                 Enclosure .                                                                                                                                                              !
Response to Request for Additional Information                                                                                                                           l Generic Letter 92-01, Revision 1, Supplement 1
                       ,   . Reactor Vessel Structural Integrity
                         . Page 14
                                                      ' Table 4-1: Evaluation of Chemistry for Weld Wire Heat No. 305424 3s5424                                                                           Jos. sees Type sies                                       new muchmeios ce                   se                                                         sta Les Mugher 3000                                 Au Co      Au PN      BoL # at ut%               wen                                            CE955003E5       l OOURCEla l NEDORT/AMALYS5             osee Tao     we%        we%        Caes crue s                                        asse       eme          n       ,
0.m                G e4                                                     VADD l      WDCe#         l         DB180       e                                         l oree a                                        e.aes I sme I           :     l 0 30         _0 se .                                              ,_w uD          1      WDC46s0 1               Ones        b                                         1 osee e                                       e.Ses I asan I          e     l J 0 36                0 62                                                     VAUD        WDC4651             WCAb100s7       o en                O m?                                                       vAuD        WDC4ss2             WCAbl0Off       e 0 31             Oml                                                        VAUD        WDC-183p             MET 46-305     e 0.31             0 $34                                                      VAUD        WDC 1840             MBTh305        e O s2             Osu                                                        vAUD        WDC48:1              herT46-303     o Ost               asia                                                       vAuD        Winspes              narT4s-203     e 01os              0 as                                                       vAUD        WDC-ISO              MFT46-M        e 019$                0 St                                                     VAUD        WDC-IS44             MET 46-303     a 0 240               0 61                                                     VAUD        WDC4841 -            WTed 203       a 0 34s               0.00                                                     VAUD        WDC 1846             METM305         e 02w               O sse                                                      vAUD        WDC4847              MET 46-303     e 0 234             0 991                                                      YADO        WDCISS               MET 46-203      e 0 341             O e04                                                      VAUD        WDMSW                MFT46-303       e O 241             0 SSB                                                      VAUD        WDC-lWO              latTM303       e
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0.23s             O sei                                                      vAuD        WDC-lost             *sT4s-3e       e                                         j 02M               0 194                                                      VAUD        WDC-1892             MET 46233      e 0 233             0 001                                                      YAUD        WDC-1953             MET 46-303     e f
0.235               0 Sp                                                     VAUD        WDC4354              MET 46-303      e j
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DEIT46-305      e 0 34             0 807                                                      VAUD        WDC-10$$          ,, nST48-303      e 0.23p             e 804                                                      VAUD        WDC-1988             MET 48-20B      e 0 346                 Os                                                     VAUD        WDC4857              h5T430S         o 0 134             O ses                                                      VAUD        WDC-18EB             MET 46-303      e anos       e .                                                                           sowse.Weemiss Auer.                  1 (se Weese s Am As                                                                                    On                     75              ;    Ce          PG Ce                    fle                                                                SJ55                  8.80              . 0373       4.415                ,
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        . A e
     ,         Enc 1ssure Response to Request for Additional Information Generic Letter 92-01, Revision 1, Supplement 1
             . Reactor Vessel Structural Integrity                                                                                               )
Page 15 Table 4-2: Evaluation of Chemistry for Weld Wire Heat No. 305414 3ss414                              IJmes test Type Pts                                          New Evatmamm                 l Cu          M                         Shslad Neuber and?                                  As Cu        Au Mt       Est e of we%        we%      CEFEBeDREE         l SDURCE LEL l REPORTsANALYes        Creep Ten       we%          we%         Cass aeen, e                                        uM           e.mo          i 0.D         0 Se        VAUD           l    WDC4el3       l       12320         e crew b    ,                                   eJoe I       e.ses   l     :      1 0 se        O Se        vAUD                WDC46M             TR444CM402       b 0 30        0 Se        VAUD                WDC4637            TRC4dCM-e02      b 0 30        0 00        VAIJD               WDC463e            TRO4dCW.002      b 0 30        0 en        VAMD                WDC4630            TROMCM402        b 6M          0 GO        VAUD                WDC4640            M44dCM402        b 0 31        0 00        VAUD                WDC464)            TR440CW.002      b 0 t'        0 60        VAUD                WDC4642            TR44dCM402       b D .1        c el        VAIJD               WDC4643            TR44dCM402       b 0 30        0 61        VAUD                WDC4644            MoMCM402         b 0 31        0 61        YAUD                WDC4649            TROMCM402        6 O SS        0 65       -VAUD                WDC4647               IEsde         b 0 35        0 00        VAUD            ,   WDC464e               IMD49         b cese e                                        eJee 1       e.ees 1              I OM           06         VAUD            l   WDC4634       l       13923         e   '
ceem e                                        eJes I       e.eae   1     :      1 0 35        0 64        VAUD           l    WDC46BS       l       Dess          e Q                                              SampleWsWess Aw                         CesWeMass Ageren At s                                       Co                 M                        Co            M C.          x                                  e.u,               un                      A. C.        A. M eJt7       e.As Table 4-3: Evaluation of Chemnistry for Weld Wire Heat No. 90136                                                       ,
I sol 36                             IJmes tese Type Peu                                           New Deutsamms Co        - fe          Vestems plum Ems Ne$se                                            As Ce        Am MI       Est e of we%        ush      G IBROGREE          I 80tillCE LE        REpoRTiANALYeS Geese Tag       we%          we%         CoAs Osse e                                        SJe8 0 30                    VAUD            1    W3C-lO4      l       INF3          e (sem b                                        eJPe 7               I     i      l 0 30                   VAUD            ]    W ml435      l       imer          b Graus e
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GJ     l             1     8      l VAUD                 WDC-t 579            DOM           e 0 16 VAUD' VA!JD WDC-ISe0 WDC-1182 D 0997 D'03 8 a
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0 17                   VAUD                 WDC-IS84             D10389        e 0 le                   VAUD                 WDC-1 $$$            D OM2         e e le                   VAUD                 WDC- 506             DOM 4         e 0 20                   VAUD                 W30-   557           D0961         e (eem s                                        eJee   l              l     t    _j 0 30                   VAuD             i   Wm    une i          - , .         e (ses  po                                      8.316  l     4A1e i        I      I O 22        0M          VAJD                 W3C- G6              Die 646       e                                                ,
0 21       eM          VAJD                 E 3C- 47             Dies 30       e                                                :
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1 i

l Enclosure Response to Request for AdditionalInformation                                                                                                                                            i Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel StmeturalIntegrity l                     Page 16 l                                                                                                                                                                                                              {
Table 4-3: Evaluation of Chemistry for Weld Wire Heat No. 90136 (cont.)
90136                                               tJue,see Type nas                                                                                 msw paiemenen Os           PG                                            Mas 14 Namsher 3947                                                                        Aug Co    Ave. NI    Est. # at
_ we%           we%   Cf PEDIGREE                              l SOL'IICE I.R    l ktPORTIANALYS5                                                Grew Tam  we%       we%        Cess Grung j                                                                              e.3437    3.gseg         3 0 20         0 05       VAUD                                     WDC-1467                   114-MCM 004                                           1 0 20         0 05       VAUD                                     WDC-1448                   TRS MCM-0D4                                           6 0 30         0 05       VAUD                                     WDC-1449                   TRf-MCM4lD4                                           j                                   I 0 21         OW         VAUD                                     WDC-1470                   TRJ-WCM4104                                           j 0 22       1 005        VAUD                                     WDC-1471                   TRf-WCM41De                                           l 0 22         06S        VAUD                                     WDC-1472                   TR#-MCM4lD4                                           j                                   j 0 197         W          VAUD                                     WDC-1473                       WCAP 12751                                        1                                   j 0 21         0 06       VAUD                                     WDC-1414                   TR4-MCM-004                                           1 0 22         0 06       VAUD                                     WDC 1475                   TR4 4eJ4-004                                          j 0 22         0 06       VAUD                                     WDC-1476                   TRf-MCM4]D4                                           i 0 32         0 06       VAUD                                     WDC 1477                   TRJ MCM4104                                           1 0 32         0 06       VAUD                                     WDD 1478                   TRS-MCM-004                                           i                                   l 0 44         0 06       VAUD                                     WDC-1479                   TRf-MCM-004                                           j 0 20s         1 06       VAUD                                     WDC-1400                       WCAP 12751                                        1 0 238         0 07       VAUD                                     WDC-14sl                       WCAP 12751                                        j 0 341         0 07       VAUD                                     WDC-1482                       WCAP-12751                                        1 0 23         0 11       VAUD                                     WDC-1484                              Diod86                                     )
0.25         0 06       VAUD                                     WDC-14B*                              D10GB7                                     1 0 20         0 06       VAUD                                     WDC 1490                              D64374                                     1 0 22         0 06       VAUD                                     WDC 1491                              Ds4394                                     j 0 23         0 06       VAUD                                     WDC-14F2                              D44395                                     j                                    -
0 23         0 06       VAUD                                     WDC-1493                              D64396                                     I                                    l 0 23         0 06       VAUD                                     WDC-1494                              D44398                                     1 0 24         0 06       VAUD                                     WDC-1493                              D44397 0 32         0 06       VAUD                                     WDC-1496                              D44310 0 15         0 07       VAUD                                     WDC-1497                              D44379 0 16         0 07       VAUD                                     WDC-1498                              D44379                                     1 0 18         0 07       VAUD                                     WDC-1499                              D64377                                     j 0 15         0 07       VAUD                                     WDC-IS00                              D44380                                     1 0 19         0 07       VAUD                                     WINJ-lM1                              D64392                                     i 0 20         0 07       VAUD                                     WDC-IS02                              D44376                                     1 0 20         0 07       VAUD                                     WDC_lS4                               Dt4390                                     1 0 20         0 07       VALID                                    WDC-1904                              D64391                                     t 0 30         0 07       VAUD                                     WDC-I SOS                             D443P3                                     t 0 23         0 07       VAUD                                     WDC-IS06                              D64375                                     j 0 23         0 07       VAUD                                     WDC-1$07                              Ds43e6                                     6 0 29         0 07       VAUD                                     WDC-1SGB                              D44346                                     i 0 29         0 07       VAUD                                     WDC-1909                              Ds4101                                     i 0.3         6.01       VAUD                                     WDC-ISIO                              D64349                                     1 0 31         0 07       VAUD                                     WDC-ISil                              D64382                                     1 0 32         0 05       VAUD                                     WDC-IS12                              D44371                                     }
0 23         0 0D       VAUD                                     WDC-IS13                              D64387                                     1                                   j 0.29         0 00       VAUL,                                    WDC-ISid                              D64364                                     j                                   l 03          0 00       VAUD                                     WDC-lSIS                              D64MS                                                                          l 0 32         0 00       VAUD                                     WDC-lS16                              D64372 0 23         010        VAUD                                     WDC-Isl1                              De4384 0 23         0 :0       VAUD                                     WDQl3                                 D64381                                     1 0 29         0 0        VAUD                                     WDC-ISl9                              De4MB                                      j
                       , 0 23         0 t        VAUD                                     WDC-1320                              D6435                                      j
__0 24         0$         VAUD                                     WDC-IS21                              D64363                                      1 42          0 06       VAUD                                     WDC-IS26                              DsetED                                     j 0 22         0 06       VAUD                                     WDC-IS27                              D44501                                      f 0 22         0 06       VAUD                                     WDC-IS2B                              D64932                                     j 0 22         0 06       VAUD                                     WDC-1$29                              D440B4                                     1 0 22         0 06       VAUD                                     WDC-1S30                              D49004                                     1 0 23         0 06       VAUD                                   --W )C-IS$1                              Deess3                                     i 0 23         0 06       VAUD                                     W)C-IS$2                               DaS003                                     1 0 21         0 06       VAUD                                     W )C-I S33                            DeSO49                                      1 0 23         0 86       VAUD                                     WDC-IS34                              D450SO                                      1 l

      ?
    ,        Enclosure Response to Request for Additional Information Generic Letter 92-01, Revision 1, Supplement 1
          . Reactor Vessel St;ucturalIntegrity Page 17 Table 4-3: Evaluation of Chemnistry for Weld Wire Heat No. 90136 (cont.)
90ln                                 IJm6e test Typs Hus                                    New Eveimonen (a                           NI                    Mus IAt Nimmber 3947                           Avs. Co    Asa M1      Esf 8 et we%                            es%        ' g PEDIGREE     SDURCE I.E        REPORTIANALYSIB Grew Tag  we%        we%         Cots 0 24                         0 06  ,,
VAUD              WDC-ISSS        des 003        1 0 24                         0 06            VAUD              WDC 1536        des 004         1 0 24                         0 06            VAUD              WDC-t S37       D45020          i 0 24                         0 06            VAUD              WDC-1535        D45028          j 0 24                         0 06            VAUD              WDC-1939        des 029         i 0 24                         0 06            VAUD              WDC-1540        D45029          i O!1                          0 06            VAUD              WDC-IS41        D85049          1 0 24                         0 06            VAUD              WDC-1$42        De5010          1 0 15                         0 07            VAUD              WDC IS43        DN980           j O ll                         0 07            VAUD              WDC-IS44        D45000          1 0 16                         0 07            VAUD              WDC-1349        des 000         1 0 18                         0 07            VAUD              WDC-IS46        DN970           i 0 18                         0 07            VALID             WDC-1947        D44979          1 0.19                          0 07           VAUD              WDC-154W        D44978          j 0 19                        0 01            VAUD              WDC-1549        D49002          1 0 19                         0 07           VAI.lD            WDC-1990        DeSO45          j 0 20                         0 07           VAUD              WDC-ISSI        DN977           1 0 20                         0 07           VAUD              WDC-IS$2        D89001          j 0 20                         0 07            VAUD             Wr-1953         des 00:         1 0 20                         0 07            VAUD             W3C-14e         D49FM           1 0 20                         0 07    ~
VAUD             WX'-IS$$        D49027          1 0 20                         0 07            VAUD             Wr-ISS6         DeSee?          i 0 20                         0 07            VALID            WE-l S S1       De9048          1 0 21                         0 07            VAUD             Wr ISSS         des 001         i 0 24                         0 07            VAUD             W 3C-IS$9       DeSO26          j 02%                          0 01            VAUD             WDC-IS60        des 026         1 0 21                         0 07            VAUD             W3C-IS61        DeSO47          i 0 39                         0 07            VAUD             W3C-IS62  ,      DN971 0 38                         0 07            vAuD             W )c-ISO  i     Dae72 0 13                         00s             VAUD             WDC-IS64        D49046 0 16                         0 Os            val y            W r-1%$         fx1025 0 16                         0 08            VAUD             Wr sS66          D49025 0 16                         0 03            VAUD             W $\l567         DeSO46 0 23                         0 10            VAUD             WDC-ISS          DNeid 0 24                         0 10            VAuD             WDC-ISe          944P75 0.38                                        VAUD             WDC-IS72         D1025$
Cave e                               SJ2e   l            l     1    l
                 - 0 32                                                        VAUD    l        WDC-ISW1  [      Ulurw           I cree e                               e.se   l            l     1    l 0 16                                        VAus    l        WDC-tw2   l      DiawS         m Gene o                               e.ase  1            l     t    1 0 15                                        VAUD    l        wuc-IS7S  l      U50er2         m Gree e                               4 968  l            l     t    l 0 36                                        VAIJD   l        WDC-1574  l      U15p13         e Gree p                               SJte   !            I     a    j 0 31                                        VAUD    I        WDC-IS75  1      DIO14          p Grau e                               e.tst  l            l     4    1 0 15                                        VAUD    I        WDC-IS76  i      Dies 22         e Ske pts                                         SammteWeW Aw                    Cd WeW Aserey As s.                                        os              is                  ou          pe
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    . Encl::sure                                                                                                                                                                                                                                                                    I Response to Request for Additional Information Generic Letter 92-01, Revision 1, Supplement 1
        . Reactor Vessel Structural Integrity Page 18 l
Table 4-4: Evaluation of Chemistry for Weld Wire Heat No. 83642 83642                                                          unde see Type n.:                                                                                                                                                            New r h.se.
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            -         e          c erDu:we                                     I soenceta i urosmmves                                         G,           r.s                                                     e                                           e         cwe G,     s-                                                                                                                      e ees                                        e.e=         i
_ 0 08      0 07          INVAUD*                                       WDC-1175         WCAP 1240s                                      s' Group a                                                                                                                        e.ees                                  l    S.ese  l      t     l 0 05      0 06            VAUD                                        WDC-1196           D23932                                         s 0 00      0 07            VAUD                                        WDC 1197     l     D23S49                                         s Greep b                                                                                                                       e.e43                                  l     e.133 l      3     l 0 04      0 19            VAUD                                        WDC-1176           Dl4234                                         b 0 04      0 06            VAUD                                        WDC-1177           Dl4235                                         b 0 05      0 16            VAUD                                        WDC-Il78           D14236                                         b Greep a                                                                                                                        r. 940                                 j     e.870 l      1     l 0 04      0 04            VAUD                                        WDC-Il19           D14925                                         e 0 04       01             VAJJD                                        WDC 1100          D14926                                         e Gesey e                                                                                                                        e.ees                                 l e ses l          t     l 0 0$      0 04            VAUD                                     l  WDC-lle2     l   WCAP 9228                                        e Group i                                                                                                                        e.eJ7                                 l     4.40  l      t     l 0 04      0 06            VAUD                                        WDCII4             Dl64 S9                                        f 6 01      0 06            VAUD                                         WDC-lle$          Dl6460                                          f 0 04      0 01            VAUD                                         WDLallV,          D14461                                         f Geear s                                                                                                                        4.ees                                 I a ees I          a     1 0 04      0 00            VAUD                                         WDC llt?          D137e4                                         g 0 04      0 09            VALID,                                       WDC-Ilse          D13783                                         g cree, b                                                                                                                         e.ede                                 I e se7 i          n     l 0 05      0 07            V Al.lD                                      WDC-lie 0         Dl41el                                         h 0 04      0 00            VAUD                                         WDC-ll90          D141$ 8                                       h 0 01       Ol             VAUD                                         WDC-Il91          Di m                                           b 0 01      0 11            VAUD                                         WDC-Il92          D23e%8                                        h 0 03      0 12            VAUD                                        WDC-1191           D23ee$                                         h 0 03      0 07            VAUD                                        WDC ll94           Dl41&2                                        h 0 03      0 13            VAUD                                        WDC-119$           D14132                                        h Greup a                                                                                                                        4.e44                                 l            l     8     l 0 04                      VAUD                                     j   W1X'-119e   l     Dl3139                                         i Nuta mammred data kan flueve Valley 3 sovellenes weld desernmand to be wahd duen Stampes                                                                 Smauple teW Aurer                                                                                                    Ces wow Average A4                                                                   Ce                N1                                                                                                              ou                                       M Ce         PIB                                                          4A44             e.e77                                                                                                        4 ede                                       e.e77 4 447     4.ees i
I
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