ML20133P617
| ML20133P617 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/28/1984 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Denise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| IEB-79-02, IEB-79-14, IEB-79-2, LIC-84-271, NUDOCS 8508140393 | |
| Download: ML20133P617 (2) | |
Text
.
Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536-4000 g!;, g[T! (6, '
August 28, 1984 LIC-84-271
='
- vy
T SEP - 41984 Ma b'
Mr. R. P. Denise, Director Division of Resident, Reactor Project and Engineering Programs U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
References:
(1)
Letter from W. C. Jones to Mr. W. C. Seidle, dated July 29, 1982 (LIC-82-239).
(2)
Docket No. 50-285
Dear Mr. Denise:
IE Bulletins 79-02 and 79-14 The Omaha Public Power District's letter to the Commission, dated July 29, 1982, provided the final report regarding the subject IE Bulletins.
In that letter, the District stated that all necessary inspections, analyses and modifications at the Fort Calhoun Station resulting from the requirenents of the subject IE Bulletins were completed and updating of "as-built" piping isometric drawings would proceed. During the updating process two discrepan-cies were discovered.
The first discrepancy was a dimensional error in the Safety Injection System (SIS) piping, subsystem SI-192-A (Isometric D-4265).
Isometric Drawing D-4265 reflected that subsystem SI-192A was five feet shorter than what actually existed. These incorrect dimensions were used in the original analysis. Subsystem SI-192-A was reanalyzed using the correct dimensions, and the results indicated that a new restraint was necessary at an existing wall penetration. A new pipe restraint was installed during the 1984 re-fueling outage at the wall penetration as modeled.
The second discrepancy was in the Chemical and Volume Control System (CVCS) piping, subsystem CH-456-A (Isometric D-4234). A field check revealed that no restraint was installed at the location for WDS-326.
A review of his-torical data for WDS-326 indicated that it was added to the model as a new restraint. Research of historical data for subsystem CH-456-A revealed the existence of other restraints on the subsystem for which no credit was taken 850814o393 g4oggg
{DR ADOCK 050 5
/
45 5124 Employmen h EQ at opportunity h
-~
Mr. R. P. Denise August 28, 1984 Page Two in the model previously analyzed. The District perfomed a new analysis taking credit for the existing restraints in the model and deleting WDS-326 from the model. The results of this analysis indicated that pipe stresses and restraint loads were acceptable, and no modification or addition to the existing restraints was required.
Mr. L. A. Yandell, NRC Senior Resident Inspector, was notified on June 29, 1984, of the discrepancies noted above and the actions proposed, and taken, for their resolution.
The modification records close-out and piping isometric drawing update are continuing. The District is confident that the modification records close-out and isometric drawing update will ensure that discrepancies of this type are found and corrected.
Sincerely, khW R. L. Andrews Division Manager Nuclear Production RLA/CWN/rh-I cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. E. G. Tourigny, NRC Project Manager Mr. L. A. Yandell, Senior Resident Inspector
\\
1
_, _ _. _,