ML20237G978
| ML20237G978 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/11/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8708170007 | |
| Download: ML20237G978 (1) | |
See also: IR 05000285/1987005
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AUG 11'1387
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In Reply Refer To:
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Docket: 50-285/87-05..
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50-285/87-08)
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Omaha Public Power District
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ATTf4:
R. L..Andrews, Division Manager-
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Nuclear Production
1623 Harney' Street-
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Omaha, Nebraska
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Gentlemen:
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Thank.you for your letter of July.6,1987, in response to.our telephone
request for. assurance of completion of.short-term commitments. ,
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Sincerely,
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. Orig!nct S1;;ned By :
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. J. E. Gagilardo
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J. E. Gagliardo.. Chief .
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Reactor Projects' Branch
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W. G. Gates, Manager
Fort Calhoun Station
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P. 0. Box 399
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Fort Calhoun, Nebraska
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Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae
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Omaha Public Power District
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July 6, 1987
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LIC-87-431
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Mr. J. E. Gagliardo, Chief
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Reactor Projects Branch
U. S. Nuclear Regulatory Commission
Region IV
611 Ryan Plaza Drive. Suite 1000
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Arlington, TX 76011
Dear Mr. Gagliardo:
SUBJECT:
Inspection Reports 87-05/87-08, Completion of Short Term
Commitments
Reference:
(1) Docket No. 50-285
(2) Let'ar from 0 PPD (R. L. Andrews) to NRC (J. E. Gagliardo)
dated May 22, 1987 (LIC-87-347)
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Pursuant to a telephone request from Mr. Hunter of your staff, this letter
serves to provide assurance that short term commitments made in Reference (2)
were completed.
Because of some ambiguity in the Reference (2) items,
clarification is provided where appropriate. The items and final disposition
are as follows:
1.
Modification MR-FC-81-180 was presented to the System Acceptance
Committee (SAC) on May 26, 1987, and was accepted.
OPPD is aware that
during the week of May 25-29, 1987, Mr. Les Gilbert again reviewed this
modification.
His findings, which are to be documented in Inspection
Report 87-13, were factored into a subsequent engineering review,
including third party approval.
2.
Repairs to the Emergency Feedwater Storage Tank were completed, results
of radiography performed were acceptable, sandblasting was conducted,
the painting was completed, and a hydrotest was conducted with
satisfactory results.
3.
Welding performed on Critical Quality Element equipment during the 1987
refueling outage was conducted using qualified welders using qualified
weld procedures. Additionally, the welder / weld qualification records
were researched back to 1973.
From our review it was determined that
there was one welder on one weld whose continuity of qualification could
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not be established.
The weld is on a pipehanger on the CVCS.
The
records of inspection for this weld were reviewed and the weld was
determined to be adequate.
(The weld .fas established to have been made
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in 1981.) +70 7 aa ootcr-
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Mr. J. E. Gagliardo
Page Two
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LIC-87-431
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The ten (10) Main Steam Safety Valves have been acceptably installed.
The concern in this area was overstressing of the studs juring
reinstallation because of the use of a slugging wrench f astead of torque
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values. A new procedure was written to achieve preload rtress values
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below code allowable via measurement of stud elongation.
The studs on
the 10 main steam. safeties were replaced. Additionally, the effort
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required to tighten the new studs to the appropriate preload via
elongation measurements indicates that overtightening in the past is
extremely unlikely.
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5.
Pressurizer Safety Valve Flange Stud torque values. The torque values
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used were verified to provide below code allowable stress values.
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6.
Lubricant in Limitorque operators that are included in the Fort Calhoun
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Station Electrical Equipment Qualification program was changed or
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verified to be Exxon Nebula EP-0.
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7.
The containment vent fan motor and cables were meggered with
satisfactory results. The containment vent fan blade torque and blade
angle settings were verified. The correct values had been specified in
the procedure and were field verified.
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8.
There were 181 Maintenance Ordens (M0's) specified in Reference (2).
Of
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these, 41 did have torque values specified.
This information was
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relayed to the Resident Inspector and to Region IV management. Of the
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remaining 140 M0's, engineering evaluations were prepared and are being
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maintained internally.
If you or your staff have additional questions concerning this matter, please
do not hesitate to contact us.
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Sincerely,
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R. L. Andrews
Division Manager
Nuclear Production
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LeBoeuf, Lamb, Leiby & MacRae
1333 New Hampshire Ave., N.W.
Washington, DC 20036
A. Bournia, NRC Project Manager
D. R. Hunter, NRC Region IV
P. H. Harrell, NRC Senior Resident Inspector
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