ML15224B112

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Forwards Technical Review Rept AEOD/T703, Potential for Loss of Emergency Feedwater Due to Pump Runout During Certain Transients. Licensee Implemented & Planned Corrective Actions Adequate.No Further Action Planned
ML15224B112
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/16/1987
From: Wegner M
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Lam P
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML15224B113 List:
References
IEB-80-04, IEB-80-4, NUDOCS 8704270060
Download: ML15224B112 (1)


Text

March 1 1987 AEOD*03 MEMORANDUM FOR:

Peter Lam, Chief DISIRLBUTION:

Reactor Systems Section 2 PDR Reactor Operation Analysis Branch AEOD CF AEOD SF Office for Analysis and Evaluation ROAB CF of Operational Data MWegner PLain FROM:

Mary S. Wegner, Reactor Systems Engineer SRubin Reactor Systems Section 2 WLanning Reactor Operations Analysis Branch KBlack Office for Analysis and Evaluation MWilliams of Operational Data FHebdon CHel temes

SUBJECT:

TECHNICAL REVIEW REPORT:

POTENTIAL FOR LOSS OF EMERGENCY FEEDWATER DUE TO PUMP RUNOUT DURING CERTAIN TRANSIENTS The subject technical review report is enclosed for your information. The study was initiated as a result of the screening of an Oconee licensee event report (LER 86-010).

Our evaluation found that a lack of runout protection for the emergency feedwater (EFW) pumps could result in the loss of EFW function during certain design basis transients.

The lack of EFW pump runout protection, if uncorrected, could lead to a degradation or loss of EFW function during a steam line break accident.' The licensee's implemented and planned corrective actions were determined to be adequate. The issue of loss of EFW/AFW function due to pump runout for other plants has been adequately addressed in TEB 80-04 and industry action.

Hence AFOD plans no further action on this subject other than a followup review of the licensee's updated report scheduled for May 1987.

Mary S. Wegner, Reactor Systems Engineer Reactor Systems Section 2K Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data

Enclosure:

As stated cc w/enclosure:

T. Guynn, 0CM C. Brinkman, CE M. Virgilio, NRR R. Borsum, B&W H. Pastis, NRR L. Gifford, GE M. Beaumont, W T. Martin, IE H. Wong, IE L. Reyes, RII 8704270060~ 870316)

PDR ADOCK 05000269 S

PDR OFC etROAB SeSC:ROAB NAME :-MWegner:as :PLain -7RA DATE : 3/)G,/87

3/IL,/87 OFFICIAL RECORD COPY