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Omaha Public Power District 1623 HarnetJ Omaha, Nebraska 68102 2247 402 536 4000 March 10, 1987 LIC-87-032 U. S. fluclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
1.
Docket tio. 50-285 2.
f1RC Generic Letter 85-06 Quality Assurance for ATWS Equipment that is not Safety-related, April 16, 1985 3.
OPPD letter (R. L. Andrews) to flRC (H. R. Denton) dated October 11, 1985 (LIC-85-450) 4.
10 CFR 50.62 5.
flRC letter (W. A. Paulson) to OPPD (R. L. Andrews) dated February 12, 1987
SUBJECT:
Articipated Transient Without Scram (ATWS) Rule flodification Design Package for Diverse Scram System Gentlemen:
Pursuant to the requirements of 10 CFR 50.62.c(6), please find attached information describing the fort Calhoun Station ATWS modification for your review and approval.
The modification complies with the requirements of 10 CFR 50.62.c(2) to provide a Diverse Scram System (DSS) which is indepenJent from the existing reactor trip system.
In Reference 3, OPPD provided a schedule to install the Diverse Scram System during the 1987 refueling outage.
The 1987 refueling outage is scheduled to l
commence flarch 7, 1987.
l l
Reference 5 notified OPPD that the flRC has extended the deadline far implementation of the ATWS rule until the third refueling outage after July 24, l
1984.
This coincides with the 1988 refceling outage for fort Calhoun Statlon.
Accordingly, OPPD has rescheduled the operability of the ATWS nodification to l
coincide with the return of power operations after the 1988 outage.
l Because of the complexity of the AlWS modification, OPPD plans to perform a l
partial installation during the 1987 refueling outage.
Work which will be accomplished will be performed under the provisions of 10 CFR 50.59.
The system will not be completed or placed in service until the 1988 refueling g
flRC.
)Of outage, and then, only if the design has been reviewod and approved by the l \\
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1 U. S. Nuclear Regulatory Commission LIC-87-032 Page 2 j
OPPD is committed to provide pressure indicators consistent with ATWS pressure expectations. The commitment is to conform to the requirements of Regulatory Guide 1.97, Revision 2.
Two of the four channels included as part of the DSS modification will be used to provide the pressure indication required by Regulatory Guide 1.97. OPPD plans to complete this part of the DSS modifica-tion and to declare the pressure indicators operational prior to the return to power operations following the 1987 refueling outage.
If you have any questions or require additional information, please contact us.
Sincerely, Ada R. L. Andrews Division Manager Nuclear Production RLA/me Attachment c:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 R. D. Martin, NRC Regional Administrator W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector