ML19325C658
| ML19325C658 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/08/1989 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-11, NUDOCS 8910170151 | |
| Download: ML19325C658 (2) | |
Text
{{#Wiki_filter:% ~ ^ s c w n 9; ; e ' I Y f j~f f ~ r !,-/ '- O x4 1. snippmenori. PA 150774004 &~ tm 3.. I* .y. af NU.Eksw m mms October 8,'1989 .i i U..S. Nuclear Regulatory ~ Commission 7 Attn:. Document Control Desk .. ashington,.DC 20555 W c
Reference:
- Beaver. Valley Power Station, Unit No. 1
[ ~ Y,_ Docket-No. 50-334, License No. DPR-66 NRC Generic Letter 88-11 ., e , I t, i ' Gentlemen:- 'In.the preparation of our response to NRC Generic: Letter 88-11, ~' ~"NRC Position-'on Radiation Embrittlement at Reactor Vessel Materials. and' ~ Its -Impact: -on Plant Operations," a. typographical error occurred in. Table l'of-Attachment 1. Please-find <.the: corrected Table 1 attached. The correction . transposes' the.. surveillance capsul'e-data in parentheses-from- " Longitudinal: Welds (20.-714-A- B) Weld. Wire Heat 305414".to ?" Longitudinal 1 Welds (19-714 A &. B). Weld-Wire Heat 305424." The 3 correction ' identifies the surveillance weld as the intermediate shell longitudinal weld. and- ' brings it into agreement with other 'Edocumentation. These' corrections have been discussed with the Beaver Valley Project LManager and the reviewers assigned to. Generic Letter.88-11. EIf; there--are any questions concerning this submittal, please contact my office'. n very truly yours, a' D. Sieber Vice President ^ Nuclear Group Attachment cc: Mr. J. Beall, Sr. Resident Inspector Mr. W..T. Russell, NRC Region I Administrator i s 'Mr. P. Tam, Sr. Project Manager Mr. R. Saunders-(VEPCO) 8910170151 891006 gDR ADOCK 0500o334 sDe
+ g. , r f.. w, o' 4 ( g 1 r .v TABLE 1 ? p< p; M p 3 E # ~ ' BEAVER VALIEY UNIT 1 REACIOR VESSEL - BELTIJNE RB3ICH MATERIAL PIOPERTIES ,7 ms ' Ul', Cu- . Ni I(a); M. - (Wt. %) = (Wt.%). CF ('F) ('F) / r 1 M
- Intemediate Shell' Plate
.14- .62 100.5 43 34(b) 1 B6607-1
- c. y
' Intermediate' Shell Plate .14 .62 100.5 73 ' 34 (b) a (B6607-2= 34 (b) (167.9)(d) 27 Iower Shell Plate B6903-1 .20- .54 141.8 (17) 4 LIower Shell-Plate B7203.14' .57 98.65 20 34(b) Flongitudinal-Welds .28- .63 191.65 -56 65.5(c)- E (19-714 ' A&B) ~ (191.4) (44.05) -{ (l LWeld Wire Heat 305424 .1 -lCircumferential' Weld' .29 .07 132.9 ; 65.5(c) - l
- (11-714);
4 7: iWeld Wire Heat 90136 l>1 ilongitudinal! Welds: .34 -. 61 210.45 -56 65.5(c); 6: -(20-714 A&B) Weld Wire Heat 305414 1 \\ h l-f (a)j @eT initial:RTNDP (I) values for the plates are conservatively measured : values wheras 'the weld - values are cymric mean values,for 1' .? li M [Linde 1092 ard 0091 weld flux types (3]. r f 'y f M. (b) 2e standard deviation for the initial RT margin term for these j NDr materials is assumed to be zero since the initial RINDP values were k ' obtained from conservative (i.e., " upper bourd") test results. .i. L(c): Wese' are eximum " margin" - (M) values. We standard deviation for l is 28'F-for welds eXcept that og need not exceect 0.50 lx LARINDrr UA i times the mean value of ART mis exception can occur for these NDP. materials at low fluence values. (d) Numbers in ( ) corresponds to surveillance capsule data. i b b -}}