05000302/LER-1983-017, Forwards LER 83-017/01T-0.Detailed Event Analysis Encl

Forwards LER 83-017/01T-0.Detailed Event Analysis Encl

ML20079Q160
Person / Time
Site:	Crystal River
Issue date:	05/02/1983
From:	Henry P FLORIDA POWER CORP.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20079Q166	List: 05000302/LER-1983-017, Forwards LER 83-017/01T-0.Detailed Event Analysis Encl 05000302/LER-1983-017-01, /01T-0:on 830418,during Surface & Visual NDE of Reactor Head & Internals,Lifting Devices Revealed Several Indications on Tripod,Turnbuckle & Latchblock.Caused by Improper Mfg.Indications Repaired
References
3F-0483-03, 3F-483-3, NUDOCS 8305110380
Download: ML20079Q160 (2)

LER-1983-017, Forwards LER 83-017/01T-0.Detailed Event Analysis Encl

Event date:
Report date:
3021983017R00 - NRC Website

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May 2,1983 3F-0483-03 Mr. James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission Of fice of Inspection & Enforcement 101 Marietta Street N.W., Suite 2900 Atlanta, Ga. 30303

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Licensee Event Report No.83-017

Dear Mr. O'Reilly:

Enclosed please find Licensee Event Report No.83-017 and the attached supplementary information sheet, which are submitted in accordance with Technical Specification 6.9.1.8.i.

This report supplies follow-up information to the prompt report, dated April 18,1983.

Sincerely,

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U.S. Nuclear Regulatory Commission l

Washington, D.C. 20555 l

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8305110380 830502 l

DR ADOCK 050003og pMW JD General Office not Thirty fourtn street soutn. P O Box 14042. st Petersburg. Florida 33733 813-866-5151

SUPPLEMENTARY INFORMATION REPORT NO:

50-302/83-017/01 T-0 FACILITY:

Crystal River Unit #3 REPORT DATE:

May 2,1983 OCCURRENCE DATE:

April 18,1983 IDENTIFICATI'ON OF OCCURRENCE:

Non-destructive examination (s) of the reactor vessel head and internals lifting devices identified welds with indications of possible defects.

This was reported to the Nuclear Regulatory Commission on April 18,1983, per Technical Specification 6.9.1.8.i.

CONDITIONS PRIOR TO OCCURRENCE:

MODE 6 (REFUELING)

DESCRIPTION OF OCCURRENCE:

Florida Power Corporation (FPC), in the NUREG-0612 "6 Month Report", identified the tripod as a specir.1 lifting device used to carry heavy loads over the Decay Heat Removal System and Spent Fuel. FPC committed to perform appropriate Non-destructive Examinations on the device in lieu of a load test as required by ANSI Nlte.6. On February 10, 1983, a Magnetic Particle Test was performed on all load bearing welds of the tripod, turnbuckles, and latchblocks prior to their use in Refuel IV. Four indications were found on the tripod, one on the turnbuckle and one on the latchblock. In addition, the inspector noted that several welds which would be unlikely to pass visual weld examination (s) due to undercut, porosity and cold lap.

DESIGNATION OF APPARENT CAUSE:

The defects in the tripod were apparently caused by improper manufacturing controls. The root cause was probably the vastly escalated importance of the tripod which was designed and manufactured as a tool but is now being treated essentially as a safety-related device.

ANALYSIS OF OCCURRENCE:

1 Analysis of the consequencies of various load drops are underway in support of the NUREG-0612 "9 Month Report" which is scheduled for completion late this year. Until this analysis is complete, it is considered inappropriate to speculate as to the likely results of failure.

Furthermore, it is not known if the identified defects would have resulted in actual failure.

CORRECTIVE ACTION

The tripod was repaired (i.e., rewelded certain questionable welds, replaced the turnbuckles) and a load test was performed on March 25,1983. The tripod was satisfactorily tested at 255 tons (which was incorrectly stated as 225 tons in the prompt report). A Magnetic Particle test performed on March 26,1983 indicated no defects.

FAILURE DATA:

This is the 19th event reported under Technical Specification 6.9.1.8.i.