ML19242C576

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Requests Addl Info to Suppl Previous Response to IE Bulletin 79-06B.Addl Info Necessary for Completion of Safety Evaluation
ML19242C576
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/26/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Short T
OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 7908130036
Download: ML19242C576 (3)


Text

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JUL 2 G 1979 Docket No.50-235 Mr. Theodore E. Short Assistant General Manager Omaha Public Power District 1623 Harney Street Omaha, Nebraska

Dear Mr. Short:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING IE BULLETIN 79-068 We have reviewed your responses to IE Bulletin 79-06B for the Fort Calhoun Plant which were transmitted by letters dated April 23 and June 15, 1979.

Our review of your responses has led us to believe that you have a general understanding of our concerns arising from the TMI-2 incident in relation to their implications to the oMration of the Fort Calhoun Plant.

Nevertheless, we have discovered some deficiencies in your responses which must be resolved before we issue our safety evaluation for the Fort Calhoun Plant. The resol-ution of these deficiencies is contingent upon receiving complete and accept-able responses to the questions in inclosure 1.

As a result of our ccitinuing review of the TMI-2 incident, we may impose other corrective actions in addition to those in IE Bulletin 79-068.

In the interim, if you need any clarification of the enclosed questions, please contact Mr. I. Villaiva, the staff's assigned project manager for Bulletins and Orders involving C-E designed reactors.

Mr. Villalva may be reached on (301) 492-7745.

In order to ensure a timely response to the items in the enclosure, we pre-viously transmitted to you a facsimile of said enclosure via telephone.

Accordingly, we request that responses to the items in the enclosure be for-warded to this office approximately two weeks after receipt of the enclosure, but no later than August 10, 1979.

Sincerely, fl l 4). tv/.f' R. W. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors

Enclosure:

Request for Additional Information a'

cc w/ enclosures: See next page i

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Onaha Public Power District gut ~, G 1979 cc:

flargaret R. A. Paradis LeBeeuf, Lamb, Leiby & IlacRae 1757 N Street, N.W.

Washington, D. C.

20036 Blair Public Library 1663 Lincoln Street Blair, Nebraska 68008 W

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REQUEST FOR ADDITIONAL INFORMATION REGARDING IE BULLETIN N0.79-06B FORT CALHOUN, UNIT 1 DOCKET N0. 50-285 As a result of the review of the OPPD responses to Bulletia No.79-06B, we find that the following additional information is required. The item numbers correspond to the bulletin action items and the related licensee response.

2.

Revise your response to confirm implementation of procedures for natural circulation. Also review the availability and use of instrumentation to monitor core conditions under forced or natural circulation modes of operation.

6.b Revise your response to commit to the requirements of paragraph 6.b as clarified below and to use the same criteria for continued opera-tion of the charging pumps as those used for the HPI pumps.

"After 50F subcooling has been achieved, termination of high pressure safety injection (HPI) operation prior to 20 minutes is only permissible if it has been determined that continued operation would result in an unsafe plant condition, e.g., attaining pressure /

temperature conditions that could jeopardize vessel integrity or that could have the potential for opening the PORVs or safety valves so as to discharge water or a two-phase fluid consisting of water and steam."

6.d Revise your response to summarize the additional information and instructions given to operators.

7.

Revise your response to provide assurance that all locked safety related valves are positioned and maintained in the appropriate position through all modes of operation.

9.

Revise your response to provide assurance of explicit notification of the status of safety related systems when shift change occurs.

11.

Revise your response to summarize your review of procedures for dealing with hydrogen in containment.

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