ML20081H254
| ML20081H254 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/21/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20081H259 | List: |
| References | |
| NUDOCS 9503240147 | |
| Download: ML20081H254 (2) | |
Text
6 Commonw calth 111imn Company 1400 Opus Pl.n r ihmners Grme. II. M615 March 21, 1995 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Document Control Desk
Subject:
Braidwood Station Units 1 and 2 Analysis of Capsule X from the Reactor Vessel Radiation Surveillance Program NRC Docket Numbers: 50-456 and 50-457 The enclosed technical report, WCAP-14241, " Analysis of Capsule X from the Commonwealth Edison Company Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program," and WCAP-14228, " Analysis of Capsule X from the Commonwealth Edison Company Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program,"
are being submitted to you pursuant to 10 CFR 50, Appendix H,
" Reactor Vessel Material Surveillance Program Requirements."
Section III i
of Appendix H,
" Report of Test Results," requires a summary technical report to be submitted within one year after capsule withdrawal.
Capsule X was withdrawn from the Unit i reactor vessel on March 30, 1994, during the A1R04. Capsule X was withdrawn from the Unit 2 reactor vessel on May 3, 1994, during the A2b27.
Braidwood Technical Specification Surveillance Requirement 4.4.9.1.2 also states that the reactor vessel material irradiation specimens shall be removed and examined to determine changes in the material properties as required by Appendix H, in accordance with the schedule in Technical Specification Table 4.4.5.
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PDR ADOCK 05000456 P
PDR A Unwom company L
NRC Document Control Desk March 21, 1995 i
Comed's ISI/ Materials Group and System Material Analysis Department have reviewed the reports and found them acceptable based on the criteria in NRC Regulatory Guide 1.99, " Radiation Embrittlement of Reactor Vessel Materials," Revision 2.
The current Tech Spec heatup and cooldown curves are conservative and are not required to be updated at the present time.
l The Braidwood Unit 1 Capsule X specimens were irradiated to 2
1.144E+19n/cm (E > 1.0 MeV) after 4.234 EFPY.
The Braidwood 2
Unit 2 Capsule X specimens were irradiated to 1.126E+19n/cm (E > 1.0 MeV) after 4.215 EFPY.
L All measured 30 ft-lb Charpy energy transition temperature shifts are considered acceptable in accordance with NRC Regulatory Guide 1.99, Rev. 2.
The measured upper shelf energy decreases for the surveillance capsule materials for both units are less than Reg. Guide 1.99, Rev. 2 predictions, which is considered acceptable.
The materials exhibit adequate upper shelf energy for continued safe plant operation, and are projected to maintain an upper shelf energy greater than 50 ft-lb through 32 EFPY in accordance with 10CFR50 Appendix G.
I WCAP-14241 and WCAP-14228 summarizes the testing, data obtained and data analysis as performed by Westinghouse Electric Corporation for Commonwealth Edison Company (Comed).
Please note r
that it is permissible to distribute this report as necessary since it has been classified as non-proprietary by Westinghouse.
Please address any further comments or questions regarding this matter to this office.
[
S1'ncerely, is ?hl a c Denise M.
Saccomando Nuclear Licensing Administrator Attachments cc:
R. Assa, Braidwood Project Manager - NRR S. Dupont, Senior Resident Inspector - Braidwood J. Martin, Regional Administrator - Region III Office of Nuclear Facility Safety -IDNS I
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