ML20024A225

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Discusses 830412 Meeting W/Utils Re Damage to Reactor Thermal Shield Support Lugs at St Lucie 1.Safety Evaluation Concluding That Continued Operation Justified Encl
ML20024A225
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/01/1983
From: Clark R
Office of Nuclear Reactor Regulation
To: William Jones
OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20024A226 List:
References
NUDOCS 8306160159
Download: ML20024A225 (2)


Text

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  1. cket File g}$-Q / D Local PDR ORB #3 Rdg D.Eisenhut Docket No. 50-285 JUN 1 1983 JHeltemes RAClark PKreutzer (3)

Mr. W. C. Jones OELD Division Manager, Production NSIC Operations E.L. Jordan Omaha Public Power District J.M. Taylor (1) 1623 Harney Street ACRS (10)

Omaha, Nebraska 68102 ETourigny Gray File Dear Mr. Jones CDSellers Llois

SUBJECT:

THERMAL SHIELD CONCERNS - FORT CALHOUN STATION, UNIT NO.1 On April 12, 1983, a meeting was held with representatives of the NRC staff, Florida Power and Light (FP&L), North east Utilities, Maine Yankee Atomic Power Company, and Onaha Public Power District. The purpose of the meeting was to discuss the event at FP&L's St. Lucie Plant, Unit No.1, where significant damage to the reactor thermal shield support lugs and positioning pins was identified. During that meeting, we re-quested that you justify the continued operation of the Fort Calhoun Station in view of the damage to the St. Lucie thermal shield and its support system which was reported at the meeting by representatives of FP&L. As requested, you responded on April 26, 1983, and provided the desired information.

We believe that it is important for you to carefully follow and monitor the course of the investigation into the failure mechanism at St. Lucie 1.

You should be prepared to provide any additional analyses that may be identified as a result of that investigation to support your justi-fication for continued operation.

Our Safety Evaluation of your submittal is enclosed. As indicated in our evaluation, we have concluded that continued operation at this time of the Fort Calhoun Station. Unit No.1, is justified. We note from your submittal that you have initiated a plant specific analysis, to be completed by June 15, 1983, of the effects of the complete loss of the thermal shield support and a drop of the thermal shield.

It is requested that the results of this analysis be provided to the staff for review, i

Sincerely, Onginal signed bg j

Robert A. Clark m.:

l Robert A. Cl rk, Chief 8306160159 830601 Operating Reactors Branch #3 PDR ADOCK 05000205 Division of Licensing P

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Enclosure:

i As stated i

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cc:

Marilyn T. Shaw, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D. C.

20036 Mr. Jack Jensen Chainnan, Washington County Board of Supervisors Blair, Nebraska 68023 U.S. Environmental Protection Agency Region VII ATTN: Regional Radiation Representative 324 East lith Street

, Xansas City, Missouri 64106 Metropo.litan Planning Agency ATTN: Dagnia Prieditis 7000 West Center Road Omaha, Nebraska 68107 Mr. Larry Yandel.1 U.S.N.R.C. Resident Inspector P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator Nuclear Regulatory Commission, Region IV

.1 Office of Executite Director for Operations 611 Ryan Plaza Dr Arlington, Texas (veSuite1000 76011

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