ML20023B409

LER 83-018/01T-0:on 830413,preliminary Repts Received from B&W Indicating That 51 of 120 Upper Core Barrel Bolts Ultrasonically Tested May Be Defective.Cause Unknown. Investigation Underway.Supplemental Rept Will Be Written

ML20023B409
Person / Time
Site:	Crystal River
Issue date:	04/27/1983
From:	Bufe J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20023B400	List: ML20023B399 ML20023B409
References
LER-83-018-01T, LER-83-18-1T, TAC-51556, NUDOCS 8305050025
Download: ML20023B409 (2)

Text

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NRC FORM 3ss U.S. NUCLEAR REGULATORY COMMI LICENSEE EVENT REPORT EXHIBIT A 2 CONTROL BLOCK: l 1

l l l l l 6lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 O i l 7 a le F l uCENsEE L l ClCODE Rl Pl 3 l@isl 0 l 0l -luCENsE i4 0 l NuwaER 0 l 0l 0l 0 l -l 230 l 2e0 l@l 4 l TwE 1l 1ao l 1ls7 CAT se @ l l 11@l uCENsE l CON'T O i 7 4 M QI6001 510l -l 013l 61 DOCKET NUMSER 012 l@l 680141 69 IlEVENT 318 OATE l 3)@l 0 l 412 74 75 REPORT OATE l 718 l 3l@ 80 EVENT DESCRIPTION AND PRO 8A8LE CONSEQUENCF3 h l C 2 ISince April 13, 1983, FPC received preliminary reports from B & W indicating l r5Til I that 51 of 120 upper core barrel bolts ultrasonically tested may be defec- l  ;

f7TTIItive. FPC has embarked on a testine procram for those reactor vessel bolts I f0Tiil Ilisted in the attachment. I i

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36 37 40 41 43 43 44 4; CAuSE DESCRIPTION AND CORRECTIVE ACTIONS h i O IThe cause of these indications is unknown at this time. Investications are !

E l underway to determine the cause of these indications. A supplemental reportl

, Iwill be made when the results of testing are available. I 1 a l I mi 8 9 7

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SUPPLEMENTARY INFORMATION REPORT NO: 50-302/83-018/0lT-0

( FACILITY: Crystal River Unit #3 REPORT DATE: April 27,1983 OCCURRENCE DATE: April 13,1983 IDENTIFICATION OF OCCURRENCE:

Florida Power Corporation has received a preliminary report from Babcock & Wilcox indicating that numerous reactor vessel internal bolts ma , te defective. The possible failure of these bolts is being reported as required by Technical Specif! cation 6.9.1.8.i.

CONDITIONS PRIOR TO OCCURRENCE:

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MODE 6 (Refueling)

DESCRIPTION OF OCCURRENCE:

I l On April 13, 1983, Florida Power Corporation received a preliminary report from Babcock &

Wilcox indicating 25 of 61 upper core barrel bolts ultrasonically tested may be defective.

l Since April 13, Florida Power Corporation has found additional defect indications on reactor vesselinternal bolts as a result of extensive ultrasonic testing. The preliminary results of the tests are described on the attachment.

DESIGNATION OF APPARENT CAUSE:

The cause of these indications is unknown at this time.

ANALYSIS OF OCCURRENCE:

The examinations completed to date are considered preliminary; therefore, it is considered inappropriate to analyze the safety significance at this time.

CORRECTIVE ACTION:

Investigations are underway to provide additional data and to determine the cause of any failures that are identified. A supplemental report will be made when additional information becomes available.

FAILURE DATA:

This is the 18th event reported under Technical Specification 6.9.1.8.i.

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l REACTOR VESSEL INTERNAL BOLTS PRELIMINARY RESULTS OF ULTRASONIC TESTS l

BOLT LOCATION TOTAL NO. OF BOLTS NO. OF BOLTS TESTED NO. OF INDICATIONS Upper Core Barrel 120 120 51 Lower Core Barrel 120 108 4 l Flow Distributor to Lower Grid 120 114 0 Upper Thermal Shield (Upper Restraint Block) 60 60 0 i

l Lower Thermal Shield 96 96 71 Surveillance Holder Tube 72 72 25 i

Guide Block No results yet i

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