ML20027E209

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Informs of Event Re Fuel Assembly Degradation While in Spent Fuel Storage Pool.No Specific Recommendations Available as Root Cause Not Identified.Need for Monitoring Fuel in Spent Pool to Detect Stress Corrosion
ML20027E209
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 10/22/1982
From: Seyfrit K
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
AEOD-E242, TAC-49353, NUDOCS 8211120259
Download: ML20027E209 (2)


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UNITED STATES l

"k NUCLEAR REGULATORY COMMISSION I

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OCT 2 21982 l

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MEMORANDUM FOR: Darrell G. Eisenhut. Director i

i Division of Licensing Office of Nuclear Reactor Regulation

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FROM:

Karl V. Seyfrit, Chief l

Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data i

SUBJECT:

FUEL ASSEMBLY DEGRADATION WHILE IN THE SPENT FUEL

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STORAGE POOL i

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Reference:

1.

Memorandum, E. J. Brown, to Karl V. Seyfrit, " Fuel

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Assembly Degradation While in the Spent Fuel Pool," dated October 21,1982, AE00/E242.

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The purpose of this memorandLm is to inform you of an event that involved degradation of fuel assemblics while in the spent fuel storage pool at l

Prairie Island. Theenclosure(Reference 1)describestheeventandcontains i

a brief AE00 evaluation of the event.

The mode of failure was identified as i

stress corrosion cracking of the 304SS top nozzle of the fuel assembly but the root cause appears to be unresolved. The primary safety concerns are:

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1) the mode of degradation appears to be new to fuel assemblies and occurs in the spent fuel pool. 2) the degradation may not be readily detectable 3) the l

degradation resulted in separation of the top nozzle from the remainder of l

the fuel assembly while transferring the assembly in the spent fuel pool, and i

4) the degradation may be generic with the potential for dropped fuel assem-blies and resultant fission product release.

AE00 does not have specific recommendations for immediate action related to j

correcting the problem because the root causes have not been. identified.

i However, we believe a reasonable approach to reduce undue risk would be for i

NRR to consider implementing the following items:

1)

Notify licensees that may have plans for imminent transfer of l

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' Westinghouse fuel in the spent fuel pool.

Individual project. managers

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could probably accomplish this through the resident inspectors.

j Although we do not have evidence of the phenomenon with fuel supplied by other vendors, it may be worthwhile to notify all PWR licensees.

.__...;2).. Review the.need,for and. feasibility of monitoring. fuel in the spent fuel.

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. pool to detect stress 'corrosibn ' cracking.

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'Darrsll G. Eisenhut '

3) Review the adequacy of current guidance and/or the need for and feasibility of developing additional guidance for transfer (elevation, path,'etc.) of fuel assemblies in the spent fuel pool.
4) Review whether spent fuel pool water chemistry specifications are adequate.

AE00 plans to report this event in the next issue of Power Reactor Events and to send a report to foreign countries through tho HEA Incident Reporting System (IRS).

S Karl V. Seyfrit. Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data ec:

L. Rubenstein, NRR R. Hattson, NRR W. V. Johnston, NRR R. H. Vollmer, NRR G. C. Lainas HRR D. Dilanni. NRR

0. D. Parr, NRR V. Benaroya, NRR C. H. Berlinger, NRR R. A. C1 ark, NRR Distribution:

M. Tokar, NRR E. Brown, ROAB J. Crooks, AE0D K. Seyfrit, ROAB /

D. Zukor, AE00 C. Michelson, AEOD W. Lanning, AEOD C. Heltemes, AEOD AE0D/Subj File i

AE0D/Chron File AE0D/ Reading File Central File l.

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