ML20113H599

From kanterella
Jump to navigation Jump to search
Identifies Typos in Reactor Vessel Surveillance Capsule Repts Submitted on 810123 & 840425 for Capsules W-225 & W-265,respectively.Corrections Listed.Identification of Typos Has No Impact on Any PTS-related Submittals
ML20113H599
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/31/1992
From: Gates W
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-92-229R, NUDOCS 9208050071
Download: ML20113H599 (1)


Text

.

l Omaha Public Power Distdct 444 South 16th Street Mall Omaha, Nebraska 68102-2247 July 31, 1992 402/636-2000 LIC-92-229R U. S. Nuclear Regulatory Comission Attn: Document Control Desk Mail Station PI-137 Washington, D.C.

20555

References:

1.

Docket No. 50-285 2.

Letter from 0 PPD W. C. Jones to NRC (H. R. Denton) dated January 23, 1981 LIC-81-00ll 3.

Letter from OPPD W. C. Jones to NRC (D. G. Eisenhut) dated

~-

April 25, 1984 ( 10-84-124)

Gentlemen:

SUBJECT:

Reactor Vessel Surveillance Capsule Report Typographical Errors During recent reviews of reactor vessel material records, OPPD identified typographical errors in the reactor vessel surveillance capsule reports for sules W-225 (Reference 2) and W-265 OPPD contacted Cap / Combustion Engineering, the preparer (Reference 3).of these reports, and confirmed the ABB discrepancies by comparison with the original fabrication records.

Page 6 (Table III-2) of report TR-0-MCM-001, Revision 1, for Capsule W-225 (Reference 2) and page 6 (Table III-2 265 (Reference 3) incorrectly reported) of report TR-0-MCM-002 for Capsule W-the wire heat numbers for welds 3-410A and 3-410C as "12008, 13252, 27204". The correct wire heat numbers are "12008, 13P51, 27204".

Additionally, page 8 of report TR-0-MCM-002 for Capsule W-265 (Reference 3),

footnote b, incorrectly reported the wire heat number of the surveillance weld as "30541".

The correct wire heat number is "305414".

Identification of the typographical errors has no impact on any of OPPD's Pressurized Thermal Shock related submittals or analyses since the correct wire heat numbers and the associated material properties were used in subsequent applications.

If you should have any questions, please contact me.

Sincerely n.) hr W. G. Gates Division Manager Nuclear Operations WGG/grc c:

LeBoeuf, Lamb, Leiby & MacRae J. L. Milhoan, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident Inspector S. D. Bloom, NRC Acting Project Manager 9208050071 920731 PDR ADDCK 05000285 I

P PDR cs-su4 Yv v v,u anpkwen tngportuncy 8[

I

//o

- - - - - - - -