05000316/LER-2076-004, Re Potential for Fuel Clad Stress Cracking

Re Potential for Fuel Clad Stress Cracking

ML18219C369
Person / Time
Site:	Cook
Issue date:	02/18/1976
From:	Jurgensen R Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1976-004-00
Download: ML18219C369 (7)

LER-2076-004, Re Potential for Fuel Clad Stress Cracking

Event date:
Report date:
3162076004R00 - NRC Website

text

NRC FOAM 195 I2,79 I U.S. NUCLEAR REGULATORYC~ISSION NRC DISTRI UTION FDB PART 60 DOCKET MATERIAL DOCKET NUMOFR 50-315 FILL NUMSCR INCXDENT REPORT TO:

J.G.

Keppler

"" M'ndiana 8 Michigan Power Co.

Bridgman, Michigan R.W. Jurgensen 'ATEOF DOCUMENT 2-18-76 DATE RECEIVED 2-3-76 Ql ETTER OOBIGINAL GOOPY QNOTOBIZED

'6 UN C LASS IF I E D Ctr. trans the following.......

PROP INPUT FOAM NUMEEB OF COI'IES RECEIVED 30 ENCLOSU BE R/0 0'6-04, on 1-20-76,-,Concerning Potential for fuel clad stress cra'cking.......,

(30 Cys, Received)

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INDIAIN 8f NICHIGAItI POPOVER COIÃPAIVY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 18, 1976 Mr. J.G.

Keppler, Regional Direc Office of Inspection and Enforce United States Nuclear Regulatory Region III 799 Roosevelt Road Glen Ellyn, MI 60137 4

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Dear Mr. Keppler:

Operating License DPR-58 Docket No. 50-315 Attached for your information is Reportable Occurrence:

RO-50-315/76-04 Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 3, Section 2.a.9 requires that we report the "discovery during plant life of conditions not specifically considered in the Safety Analysis Report or Technical Specifications that require remedial action or corrective measures to prevent the existence of an unsafe condition".

Mr. K.R. Baker, NRC -

RO: III inspector, was informed of this event on January 22, 1976.

Since that time this problem has been discussed with the NRC Staff and at our recent ACRS hearing on our full power license application.-

Section 2.a.9 of Regulatory Guide 1.16, Revision 3, would normally require a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written followup to our report to Mr. Baker.

However, we do not know whether any action will eventually be required as a result of this

problem, Because of this we are filing this report as a Thirty Day Written Report since this problem has "lesser immediate importance" than those described under the Twenty-Four Hour Written Report category.

Sincerely,

.W. Ju n

Plant ag

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Listed on following page.

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RO 50-315/76-04 February

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( 30 copies)

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,Su lement to RO 50-315/76-04 Event Descri tion On January 22, 1976, we informed Mr. K.R. Baker, NRC Region III Inspector, that representatives of Westinghouse Electric Corporation had informed the American Electric Power Service Corporation that Westinghouse had been conducting an evaluation of fuel pellet-clad interaction and the potential for fuel clad failures in high power density (6.7 Kw/foot) reactors due to this phenomena.

Subsequently, on February 5, 1976, this subject was discussed during the 190th General Meeting of the Advisory Committee on Reactor Safeguards in connection with the request for a full power license for the Donald C.

Cook Nuclear Plant Unit l.

At that meeting, we reported that Westinghouse was attempting to correlate pellet clad interaction data from test reactors and test fuel with coomerical reactor operating conditions, but that no failures due to pellet-clad interaction in Westinghouse commerical reactors in normal operation or under ANSI N18.2 Condition II transients had been experienced.

Furthermore, we reported that the recent Westinghouse correlation indicates that there should be no fuel failures in Donald C.

Cook Nuclear Plant Unit 1

at 100 percent power during normal operation or during the ANSI N18.2 Condition II transients.

This subject will receive continuing investigation by the NRC Staff and by Westinghouse.

We will keep abreast of this 'work.