ML20245J257
| ML20245J257 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/22/1989 |
| From: | Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-625, NUDOCS 8906300255 | |
| Download: ML20245J257 (3) | |
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Omatp Pub!!c Power District I
162; r16nmy Omaha Nebraska 68102 2247 402/536-4000 l
June 22, 1989 LIC-89-625 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555
Reference:
' Docket No. 50-285 i
Gentlemen:
SUBJECT:
Requested Safety Parameter Display System (SPDS) and Plant Modification Status following a conversation on June 21, 1989, between A. Bournia of NRC and i
members of my staff, the following completion status is submitted on SPDS and Plant Modifications, j
E 1.
OPPD has changed the origin of the STARTUP RATE bar graph to be consistent with the other variables on the SPDS screen.
This change was completed by l
the end of the 1988 refueling outage, i
2.
OPPD has added the designation "TRIPPABLE" to the Control Element Assemblies (CEA's) (# N0T FULL IN) to distinguish these rods from the Group N rods that will not display. This change was complete by-the end of the 1988 refueling outage.
OPPD has also changed the location that data is retrieved for the CEA's (#
NOT FULL IN) indication from.the CEA bottom lights to the syncros for a more accurate position indication not affected by burned out control board bul bs. This change also involved a software change to evaluate the number of rods fully inserted. This was completed by the end of the 1988 i
refueling outage.
3.
OPPD has added a "% WR" onto the Steam Generator Level bar graph to provide the operators with positive identification of these levels.
This change was completed by the end of the 1988 refueling outage.
4.
OPPD has added "GPM" to the Containment Spray Flow indications to show the units on this variable.
This change was completed by the end of. the 1988 outage.
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- 8 V. S.' Nuclear Regulatory Commission LIC-89-625
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.f Plant Modiff cations 1.
Modification FC 85-148, titled " Relocation of Containment Isolation Switches" was formally completed and approved on November 23, 1988.
2.
Modification FC 85-150,. titled " Diesel Generator Start and Breaker Switches and Emergency Operate Think Switch Guards", was formally completed and
-i approved on December 14, 1988.
If you have further questions on this matter or require additional information, please contact me or members of my staff.
Sincerely, i
c)co< u~
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K.-J.' orris Division Manager Nuclear Operations KJM/jak c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H.-Harrell, NRC Senior Resident Inspector 1
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