ML18059B005
| ML18059B005 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/25/1994 |
| From: | Rogers D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9405310214 | |
| Download: ML18059B005 (6) | |
Text
,*
consumers Power POWERINli MICHlliAN'S PROliRE55 Palisades Nuclear Plant:
27780 Blue Star Memorial Highway, Covert, Ml 49043 May 25, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 David W. Rogers Plant Safety and Licensing Director DOCKET 50~255 - LICENSE DPR PALISADES PLANT - INCONSISTENCIES IDENTIFIED DURING VERIFICATION OF INFORMATION PROVIDED IN RESPONSE TO GENERIC. LETTER (GL) 92-01, REVISION 1 As requested in the NRC's April 25, 1994 letter regarding information provided in response to GL 92-01, Revision 1, Consumers Power Company (CPC) has performed a review to confirm information entered in the NRC Reactor Vessel Integrity Database.
The April 25, 1994 NRC letter included two enclosures that report information previously submitted to the staff in Consumers Power Company (CPC) letters dated August 31, 1990 and July 3, 1992.
summarizes the information submitted by our July 3, 1992 letter with regard to Pressurized Thermal Shock. summarizes information submitted by our letters dated July 3, 1992 and August 31, 1990 in regard to upper shelf energy (USE).
The shaded information in the following table is that which is Palisades Plant specific, is different from information we submitted in our July 3, 1992 response to GL 92-01, and is inconsistent with the information reported in transmitted by the NRC's April 25, 1993 letter. The explanation of that inconsistency follows.
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9405310214 940525
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'i Belt line Heat Number IRT ndt Method of Chemistry
%Cu
%Ni Identification Identification Determining Factor IRT ndt Plate D-3803-1 C-1279 tJ"F Plant in Specific 0.24 0.51 Plate D-3803-2 A-0313
{.sij*F MTEB 5-2 160 0.24 0.52 Plate D-3803-3 C-1279
~§*F
~l@L.
'mie8lf:fo U'.-0.
0.24 0.50 Plate D-3804-1 C-1308 O"F MTEB 5-2 128.8 0.19 0.48 Plate D-3804-2 C-1308
- M*F MTEB 5-2 131 0.19 0.50 Plate D-3804-3 B-5294
¥.!H*F MTEB 5-2 82 0.12 0.55 Lower Shell 346009 Axial Welds
-56"F Generic g@
~W:l§ lift 3-112 A/C The initial RTNor value provided in CPCo's July 3, 1992 response to Generic Letter 92-01 was intended to represent a bounding plate. Actual values of initial RTNor for each beltline plate and surveillance program material were submitted to the NRC on May 23, 1978.
Those values are listed in the above*
table for plates D-3803~2, D-3804-1, D-3804-2 and D-3804-3~ Plates D-3803-1, D-3803~3 and the reactor vessel surveillance program material were fabricated from the same heat of* material; therefore, the initial RTNor of the surveillance material is used for plates D-3803-1 and D-3803-3.
The chemistry factor derived from surveillance data was conservatively determined to be
-150°F in CPC's June 5, 1992 PTS submittal. Therefore, the chemistry factor for plates 0-3803-1.and D-3803-3 should *be no greater than 150°F.
The da.tabase for we 1 d wire Heat No. 348009 *used in the 1 ower she 11 axi a 1 we 1 ds of the Palisades reactor vessel (RV) has been expanded since our June 5 and July 3, 1992 submittals.
Northeast Utilities (NU) has removed and analyzed an additional Millstone 1 surveillance capsule. Their 300 degree capsule report (GE-NE-523-165-1292, Rev. 1) includes a reevaluation of previous surveillance program results. The information from the Millstone 1 surveillance weld, which was fabricated with weld wire heat number 348009 with nickel addition, is applicable to the Palisades reactor vessel lower shell axial seams. contains an assessment of the effect this information has on welds fabricated with weld wire heat number 348009 w{th nickel addition. transmitted by the April 25, 1994 NRC 1 etter summarized information in. the NRC database in regard to Upper Shelf Energy (USE) from CPC submittals dated August 31, 1990 and July 3, 1992.
The shaded information in the following table indicates information that is inconsistent with that reported in Enclosure 2.
8eltline Heat (l/4)T Un irradiated Method of I dent ifi cation Number USE at USE Determining EOL Unirradiated USE Plate D-3803-1 C-1279
)4
- u11 Direct Plate D-3803-2 A-0313 II 87 Ill Plate D-3803-3 C-1279
)#:
- 111 Direct Plate D-3804-1 C-1308 I.I
~.:}..
- ~
72 I.II Plate D-3804-2 C-1308 I!
76 S.5.%
Plate D-3804-3 8-5294 I.I
- .:)... :
73 Shell SS
- 1:1:1:
Plant Lower 348009 Sister Axial Welds
=:*:-::;:;.::
3-112 A/C The unirradiated USE submitted by CPC on August 31, 1990 and reported in are longitudinal values reduced by 65%.
The surveillance material from plate D-3803-1 (which is from the same heat as plate D-3803-3) was directly determined ln the transverse direction and was most recently submitted in our T-330 and W-290 surveillance capsules report of Octobe~ 31, 1984.
Therefore, that is the USE value for plates D-3803~1 and D-3803-3 in the table a.bove.
In our Au9ust 31, 1990 submittal, it was demonstrated using Palisades and Indian Pornt 3 surveillance data (.both having a copper content of 0. 24%) that Palisades' beltline plates are conservatively represented by the 0.15% copper line on Figure 2 of Regulatory Guide (RG) 1.99, Rev. 2.
All the Palisades RV beltline pl~tes have a copper content ~ 0.24% and the value of the USE of those plates should be bounded by the value of USE derived by using the percent reduction indicated by the 0.15% copper curve in Figure 2 of RG 1.99, Rev. 2.
The l/4T EOL USE values derived by using the 0.15% copper curve from Figure 2 of RG 1.99 Rev. 2 are those reported in the above table except for the actual result reported for plates D-3803-1 and D-3803-3.
The values in the above table for those plates are the same as the P~lisades surveillance results.
The USE values for weld wire heat 348009 in the above table result from new data obtained from the Millstone 1 surveillance program.
As mentioned previously, the database for weld wire Heat No. 348009 has been expanded by more recent results obtained by Northeast Utilities (NU).
NU has removed and analyzed the Millstone 1 300 degree reactor vessel surveillance capsule and reevaluated the results from the 210 degree capsule.
The revisions for welds fabricated with weld wire Heat Number 348009 are described in Attachment 1.
-~~~r Ooavid W Rogers Pl ant Safety and Licensing Di rector CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 WELD WIRE 348009 +Ni 200 ADDITION MILLSTONE 1 SURVEILLANCE CAPSULE May 25, 1994 2 Pages
WELD WIRE HEAT 348009 + Ni 200 ADDITION The Millstone 1 300 degree surveillance capsule report contains new and revised infor,mation concerning welds fabricated with weld wire heat number 348009 with nickel addition.
The Charpy energy curves for unirradiated conditions and from the 210 degree capsule have been replotted and the fluence for the 210 degree*capsule has been recalculated.
The changes are listed below.
C.apsule Fluence Upper Shelf ART NOT (oF)
Identification (10 19n/cm 2 )
Energy (ft-lb)
Initial 111 210~
0.039 108 22 300° 0.066 88 76 The reduction in USE is plotted on Figure 2 from Regulatory Guide 1.99, Rev.
- 2.
The data is bounded by the 0.25% copper curve for welds.
CPCo has used this curve for predicting the reduction in USE for welds fabricated with weld*
wire heat number 348009 with nickel addition.
Three additional chemical analyses are included in the 300 degree capsul*e report and are incorporated in the best estimate chemistry determination below.
Weld.
Mill stone 1 Surveillance Weld H B Robinson 2 Torus to Dome Weld I Best Estimate I Copper (%)
0.19
- 0.20
. 0.19 0.20 0.19 0.18 0.14 0.12 0.. 20 0.21 0.20 0.18 0.19 Qjf,ijp lif:?,g, QMli 0.202 0.180 0.182 0.183 Mean Weld.
Copper (%)
0.187 Nickel (%)
0.86 0.95 0.96 0.99 1.06.
1.09 1.30 1.06 0.94 0.99 I 0.75 0.84 Mean Weld Nickel *(%)
0.80.
I I
This-results in a revised chemistry factor of 203°F for welds fabricated with weld wire heat number 348009 with nickel addition. A least squares fit of ARTNoT versus fluence for the Millstone I surveillance weld results in a chemistry factor of 174°F.
203°F conservatively represents the subject welds.
Note that a copper content from a procedure qualification weld reported in our June 5, 1992 submittal has been excluded from the weld chemistry determination. That chemistry measurement was taken from a draft report. The final report indicated that the subject weld deposit was an experiment that did not clearly document if the copper coating was included on the weld wire.