ML20092A965
| ML20092A965 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 09/01/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20092A968 | List: |
| References | |
| NUDOCS 9509110259 | |
| Download: ML20092A965 (2) | |
Text
,
T*$
Osmnunnu ralth lihwn 0>mpany ne opam t hew nors Grose, IIM515 September 1,1995 Office of Nuclear Iteactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Independeat Verification of Byron /Braidwood D4 Steam Generator Tube Support Plate Differential Pressures During Main Steam Line Break NRC Docket Numbers:50-454 and 50-456
Reference:
Commonwealth Edison Company Meeting with the Nuclear Regulatory Commission dated August 17,1995 The Reference meeting was held between the Nuclear Regulatory Commission (NRC) and the Commonwealth Edison Company (Comed) to discuss Comed's proposed Technical Specification Amendment pertaining to Byron and Braidwood applications for a 3 Volt Interim Plugging Criteria (IPC). At that meeting, the Staff and Comed briefly discuss the viability of Comed submitting an independent verification of the steam generator hydrodynamic load model during main steam line break (MSLB) conditions. The attached, " Independent Verification of Byron /Braidwood D4 Steam Generator Tube Support Plate Differential Pressures during Main Steam Line Break," is submitted to support that request.
This document contains a methodology to determine the peak loads on the upper tube support plate that would result from a design basis MSLB event. This methodology is based solely on first principles and has no reliance on computer i
codes. The results obtained compare favorably with those obtained via computer simulation, and provide a basis to assess the margin of safety utilized in the analyses of tube support plate (TSP) loads. It can be concluded that the factor of two used in the analyses of TSP loads. It can be concluded that the factor of two used in the structural assessment results in a physically bounding pressure drop, even allowing for typical uncertainties in two phase pressure drop prediction.
110040
)
O nla\\bybwdtstmgen\\ipchealc h0(
9509110259 950901 PDR ADOCK 05000454 p
PDR Ik A Unionn nin7an3
i NRC Document Control Desk September 1,1995 If you have any questions, please contact this ofIice.
S' cerely, r'
i 4
e n/
f u,,wLo J
Denise M. Saccomando Nuclear Licensing Administrator Attachment ec:
D. Lynch, Senior Project Manager-NRR R. Assa, Braidwood Project Manager-NRR G. Dick, Byron Project Manager-NRR S. Ray, Senior Resident Inspector-Braidwood H. Peterson, Senior Resident Inspector-Byron H. Miller, Regional Administrator-RIII Oflice of Nuclear Safety-IDNS K:nla\\bytwd\\stmgen\\ipchcalc