ML19341A990

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Forwards Parameter,Inc Rept IE-121, Metallurgical Analysis, W/Attachment a Stress Analysis of Failed Steam Generator Support Bolts from Prairie Island,Unit 1
ML19341A990
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 01/23/1981
From: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19341A991 List:
References
NUDOCS 8101290742
Download: ML19341A990 (1)


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UNITED STATES

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Docket No. 50-282 JAN 0 31981 MEMORANDUM FOR:

J. G. Keppler, Director, Region III FROM:

E. L. Jordan, Deputy Director, Division of Resident and Regional Reactor Inspection, IE

SUBJECT:

INVESTIGATION OF STEAM GENERATOR SUPPORT BOLTING FAILURE PRAIRIE ISLAND NUCLEAR PLANT, DPR 42 Enclosed for your information is a copy of our consultants report, No. IE-121, on the independent metallurgical and stress analysis performed on several failed steam generator support bolts removed from Prairie Island Unit 1.

The results of our consultants analysis indicate the apparent cause of failure was due to a 3 tress corrosion iaechanism which is in essentially good agretment with Westinghouse's failure analysis summarily reported in the licensee's supplemental LER R0-80-25 (Rev.1) of December 3,1980.

We have reviewed the licensee's c.orrective actions and inservice inspection plan, as described in ' he above LER, with respect to both units 1 and 2.

We believe such countermeasures both prudent and appropriate lono-term solutions to prevent recurrence of the problem.

If you have any questions concerning the enclosed report, please contact us.

f L.

rdan, Deputy Director Divi n of Resident and Regional Reactor Inspection Office of Inspection and Enforcement

Enclosure:

Parameter Inc. Report IE-121,12/8/80 (IE Contract NRC-05-80-251, Task 05) 81012 go jfj a

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