GO2-97-077, Forwards WNP-2 RPV Surveillance Matls Testing & Analysis, Rept,Iaw 10CFR50,App H.Util Evaluated Surveillance Matl Test Results to Determine Whether Analyses in NEDO-32205 Are Applicable to WNP-2 Reactor Vessel Matl
| ML17292A828 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/24/1997 |
| From: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17292A829 | List: |
| References | |
| GO2-97-077, GO2-97-77, NUDOCS 9705050163 | |
| Download: ML17292A828 (11) | |
Text
CATEGORY 1 REGULATO.
INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9705050163 DOC.DATE: 97/04/24 NOTARIZED:
NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397
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UTH.NAME AUTHOR AFFILIATION RRISH,J.V.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards "WNP-2 RPV Surveillance Metis Testing
& Analysis,"
rept,IAW 10CFRSO,App H.Util evaluated surveillance matl test results to determine whether analyses in NEDO-32205 are applicable to WNP-2 reactor vessel matl.
DISTRIBUTION CODE:
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TITLE: OR/Licensing Submittal: Reactor Vessel Matl Surveillance Rpt App H, E
NOTES:
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E NOTE TO ALL "RIDS" RECIPIENTS:
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WASHINGTONPUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ Richlaud, Washington 99352-0968 April24, 1997 G02-97-077 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 SUBMITI'ALOF "WNP-2 RPV SURVEILLANCEMATI<MIALSTESTING ANDANALYSIS"REPORT Letter GI2-95-220, dated September 15, 1995 NRC to JV Parrish (SS),
"Applicability of General Electric Topical Report, NEDO-32205, Revision 1, To'he Washington Public Power Supply System (WPPSS)
Nuclear Project No. 2 (WNP-2) (TAC No. M90064)"
In accordance with the Code of Federal Regulations, Title 10, Appendix H to Part 50, the Supply System hereby submits the "WNP-2 RPV Surveillance Materials Testing and Analysis" report.
In addition to the report, the Reference requested the Supply System to evaluate the surveillance material test results to determine whether the analyses in NEDO-32205 are applicable to the WNP-2 reactor vessel material.
The results of this assessment are included with the submittal of the surveillance test report. The required submittals are discussed below.
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Appendix H Report The attached report, "Washington Public Power Supply System WNP-2 Surveillance Materials Testing and Analysis," (Attachment 1) contains the results of the surveillance capsule testing that was performed in accordance with 10 CFR Part 50, Appendix H.
The surveillance capsule was withdrawn from the reactor vessel during the Spring 1996 outage. The capsule was sent to General Electric for testing and analysis. The results of this work are contained in the report.
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Page 2 SVBMITTAL OF "WNP-2 RPV SURVEILLANCE MATERIALS TESTING AND ANALYSIS"REPORT The following discussion summarize the results of the analyses.
The 30 ft-lb shifts and changes in upper shelf energy (USE) are well within the values predicted by Regulatory Guide 1.99, Rev. 2.
From the surveillance test results it is clear that after 11 cycles of operation, the 30 ft-lb shifts and the USE of the base plate and the weld show little change after accumulating a peak irradiation fluence (E>
1 MeV) of 1.55 x 10'/cm at 7.2 effective fullpower years (EFPY) (normalize full power of 3323 Mwt, the reactor was at uprated power level of 3486 Mwtfor Cycle 11 from June 9, 1995 to March 2, 1996).
The adjusted reference temperature (ART) values for the reactor vessel beltline materials are expected to remain within the temperature and USE limits of 10 CFR 50 Appendix G (( 200 degrees Fahrenheit and ) 50 ft-lb., respectively) for at least 32 EFPY ofreactor operation.
The current pressure temperature limitcurves still bound the results of the General Electric report, The limiting beltline plate material ART based on the General Electric analysis is 83.8 degrees Fahrenheit for 32 EFPY. WNP-2's current pressure temperature limitcurves for 32 EFPY use an ART of 99.9 degrees Fahrenheit.
Even though our current curves are still bounding, the Supply System willsubmit to the NRC within two years of this letter new pressure temperature limitcurves for WNP-2 utilizing the results of the surveillance materials testing and analysis report.
NEDO-32205, Revision 1 Applicabilityto WNP-2 The Reference requested the Supply System to assess the applicability of NEDO-32205, Revision 1.
The NEDO is still applicable to WNP-2 since the surveillance material specimens are not machined from the limiting plate heat of material.
The heat of material used in the surveillance program demonstrated an increase in USE during the testing as documented in Attachment 1.
However, no credit was taken for these results when evaluating the limitingplate material or weld material to the guidelines of Regulatory Guide 1.99, Rev. 2.
The results of the assessment to NEDO-32205, Rev. 1, show that the limiting plate material and weld material are still bounded by the equivalent margin analysis as developed in the NEDO document.
The USE for the reactor vessel beltline materials are expected to remain within limits of 10 CFR 50 Appendix G for at least 32 EFPY of reactor operation.
The results of these assessments are documented on the Plant ApplicabilityVerification Form (Attachments 2 and 3).
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Page 3 SUBMITTAL OF "WNP-2 RPV SURVEILLANCE MATI<2KVS TESTING AND ANALYSIS"REPORT The attached documents complete the requirements identified in 10 CFR 50, Appendix H and WNP-2's assessment ofNEDO-32205, Rev.
1 and its applicability.
Respectfully J
. Parrish Chief Executive Officer MailDrop 1023 Attachments cc:
EW Merschoff - NRC RIV KE Perkins, Jr. - NRC RIV, WCFO TG Colburn, NRR NRC Sr. Resident Inspector - 927N DLWilliams - BPA/399 PD Robinson - Winston &Strawn
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<<4 Attachment 2
SUBMITTAL OF "NNP"2 RPV SURVEILLANCE MATERIALS TESTING AND ANALYSIS" REPORT EQUIVALENT MARGIN ANALYSIS PLANT APPLICABILITYVERIFICATION FORM FOR WNP-2 BWR 3-6 PLATE Surveillance Plate USE:
%CU Capsule Fluence
= 1.55X1017 n/cm2 Measured
%-Becreace-=
increased 3X (Charpy Curves)
R.G.
1.99 Predicted
% Decrease
=
(R.G. 1.99, Figure 2)
Limitin Beltline Plate USE:
%CU =
.15K 32 EFPY Fluence
=3.86X1017 n/cm2 R.G. 1.99 Predicted
% Decrease
=
(R.G. 1.99, Figure 2)
Adjusted
% Decrease
=
NA (R.G. 1.99, Position 2.2) 11
% < 21%,
so vessel plates are bounded by equivalent margin analysis
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i Attachhent 3
SUBMITTAL OF "WNP-2 RPV SURVEILLANCE MATERIALS TESTING AND ANALYSIS" REPORT EQUIVALENT MARGIN ANALYSIS PLANT APPLICABILITYVERIFICATION FORM FOR WNP-2
~RR
- II<<
Surveillance Weld USE:
%Cu
=
.03%
pp I
pl
=~17 Measured
% decrease=
(Charpy Curves)
R.G.
1.99 Predicted
% Decrease
=
(R.G. 1.99, Figure 2)
Limitin Beltline Weld USE:
%Cu
=
.10 32 EFPY Fluence R.G. 1.99 Predicted
% Decrease
=
12K (R.G. 1.99, Figure 2)
Adjusted
% Decrease
=
NA
,(R.G.'.99, Position 2.2) l2 /. < 34%,
so vessel welds are bounded by equivalent margin analysis
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