ML20092A745
| ML20092A745 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/22/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20092A747 | List: |
| References | |
| NUDOCS 9509110177 | |
| Download: ML20092A745 (2) | |
Text
o>mmonw caith litiwn company 1-tmlOpus Place i>ow ncrs Gnn e.11 60s i s August 22, 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 and Evaluation of Pressurized Thermal Shock NRC Docket Numbers: 50-456 and 50-457 The enclosed technical reports: WCAP-14242, " Evaluation of Pressurized Thermal Shock for Braidwood Unit 1 and WCAP-14229,
" Evaluation of Pressurized Thermal Shock for Braidwood Unit 2."
This report is being submitted the Staff you pursuant to 10CFR50.61.
Updated pressurized thermal shock evaluations were performed to include material data obtained from the analysis of Braidwood Unit 1 surveillance Capsule X (WCAP-14241) and Braidwood Unit 2 surveillance Capsule X (WCAP-14228).
The calculated RTns will remain below the 10CFR50.61 screening values through the projected 32 EFPY end-of-license fluence.
The calculations were performed using both 10CFR50.61 and Reg. Guide 1.99, Rev. 2, Position 2 methodologies.
Girth weld WF562 is the limiting beltline material for both units.
Please address any further comments or questions regarding this matter to this office.
Si
- erely, 9/l
.~ (
Denise M.
Saccomando Nuclear Licensing Administrator
Enclosures:
1.
WCAP-14242 2.
WCAP-14229 cc:
R. Assa, Braidwood Project Manager - NRR S. Ray, Acting Senior Resident Inspector - Byron H. Miller, Regional Administrator i
Office of Nuclear Facility Safety -IDNS Rinla uwnpt a 1. { '.
9509110177 950822 PDR ADOCK 05000456 g(
P PDR A rnicom company a
\\
April 13, 1995 l
To: M.A. Gorski SEC Braidwood Station
References:
- 1. WCAP-14242, Evaluation of PressurizM Wennal Shock for Byaidwood Unit 1, March 1995.
- 2. WCAP-14229, Evaluation of Pressurized Thennal Shock for
)
Braidwood Unit 2, March 1995.
"'he referenced documents have been reviewed by SMAD-Metallurgy and NETS personnel.
The document should be submitted to the NRC as required by 10CFR50.61.
Stmmarv Uodated FTS evaluations were performed to include material data 03tained from the analysis of Braidwood Unit i surveillance capsule X (WCAP-14241) and Braidwood Unit 2 surveillance capsule The calculated RT will remain below the X (WCAP-14228).
10CFR50.61screeningvaluesthroug@theprojected32EFPYend-of-license fluence.
The calculations were performed using both 10CFR50.61 and Recy. Guide 1.99, Rev. 2, Position 2 methodologies.
Girth weld WF562.is the limiting beltline material for both units.
</IY-
.L7t >'
M.M. Chynoweth SMAD-Metallurgy hwn# h T.D. Spry
/
NETS-S/G & RV Projects cc. Station Manager, Braidwood SEC Manager, Braidwood J.C.
Blomgren, NETS 95LOOO79.M
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