ML20057E681
| ML20057E681 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 10/05/1993 |
| From: | Simpkin T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20057E682 | List: |
| References | |
| NUDOCS 9310130030 | |
| Download: ML20057E681 (2) | |
Text
E v.
Crmmenw::lth Edi:cn 1400 Opus Place Downers Grove, illinois 60j15 October 5,1993 Dr. Thomas E. Murley, Director Office of Nucicar Reactor Regulation
'U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Zion Station Units 1 and 2 Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events - 10 CFR 50.61' Response to NRC Request for Additional Information NRC Docket Nos. 50-295 and 50-304
References:
(a)
May 22,1992 letter from S.F. Stimac to T.E. Murley (b)
December 2,1992 letter from C.Y. Shiraki to T.E. Murley (c)
January 28,1993 letter from S.F. Stimac to T.E. Murley (d)
September 1,1993 letter from T.W. Simpkin to T.E. Murley
Dear Dr. Murley:
Reference (a) provided Commonwealth Edison Company's (CECO's) re-assessment of end oflife adjusted reference temperature, pressurized thermal shock (RT
,) values for Zion Units 1 and 2. Reference (b) transmitted the staffs g
request for additional information (RAI) related to the reference (a) submittal.
CECO's response to the RAI was transmitted via reference (c).
In a meeting held on June 9,1993, CECO discussed the performance of a modified analysis utilizing improved analytical techniques. The modified analysis necessitated additional testing, which is now complete.
fF"M k:nlazzion: nrm A
. k q
(,
9310130030 931005 b
i PDR ADOCK 05000295 p
5 P
PDR d
7
, e
(..
L With reference (d), CECO provided for staff review the summary report which demonstrates that the Zion reactor vessels do not exceed the end-of-life PTS j
screening criteria.
j l
The purpose of this letter is to transmit report BAW-2202, " Fracture j
Toughness Characterization of WF-70 Weld Material." This report details the j
development of the methodology utilized in performing the pressurized thermal shock evaluation for Zion Station.
Please direct any questions you may have to this office.
i Sincerely, i
tw
,M T.W. Simpkin t
Nuclear Licensing Administrator i
Enclosure t
ec:
J.B. Martin, Regional Administrator - RIII (w/o Enclosure) l C.Y. Shiraki, Project Manager - NRR (w/ Enclosure)
J.D. Smith, Senior Resident Inspector - Zion (w/o Enclosure) i e
l
?
I t
l i
I 3
i i
i k:nlartion:nre:"1
)
. -