05000302/LER-1983-018-01, /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

/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: 05000302/LER-1983-018-01, /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
References
LER-83-018-01T, LER-83-18-1T, TAC-51556, NUDOCS 8305050025
Download: ML20023B409 (2)

LER-1983-018, /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

Event date:
Report date:
3021983018R01 - NRC Website

text

,

NRC FORM 3ss U.S. NUCLEAR REGULATORY COMMI LICENSEE EVENT REPORT EXHIBIT A 2

CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

1 l F l L l Cl Rl Pl 3 l@isl 0 l 0l -l 0 l 0 l 0l 0l 0 l -l 0 l 0 l@l 4 l 1l 1 l 1l 11@l l

l l O i s7 CAT se @

l 7

a e

uCENsEE CODE i4 uCENsE NuwaER 23 2e uCENsE TwE ao CON'T M QI 01 510l -l 013l 012 l@l 0141 Il 318 l 3)@l 0 l 412 l 718 l 3l@

O i 7

4 60 61 DOCKET NUMSER 68 69 EVENT OATE 74 75 REPORT OATE 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

O 6 l

l ITTT11 I

r3Tal l I

'CTE YOE su!CSEE su'sEE sEE*0EE CowPONENT CODE l R l A l@ W@ W@ I Xl Xl XI Xl Xl XI@ W@ [Z_j @

O e 7

8 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVislON.

LE R/RO EVENT YEAR REPORT NO, CODE TYPE NO.

NU ER 2%

22 23 24 28 27 3

29 30 31 32 P

T M

HOURS TT POR US.

La MAN A RER QW@ W@

W@

l 01 0l01 01 W@

lNl@

W@ l Bl 011 l 5 l@

33 34 JS 36 37 40 41 43 43 44 4;

CAuSE DESCRIPTION AND CORRECTIVE ACTIONS h IThe cause of these indications is unknown at this time.

Investications are !

i O 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 I

7 8 9 80 A

• % POWER OTHERsTATus 01 O Y

DISCOVERY OEsCRIPTION

@ W@ l 0101 Ol@l NA l W @l Inspection of RV internals.

l 7

ag, 4, 12 u

44 4e 4e e0 W @ Wgl AMOUNTOF ACMVITY @ l LOCADON OF RELEASE @

RELEAsEO OF RELEASE NA l

NA l

i a PERSONNEL ExdREs OEsCRiPnON@

NUweER TYPE l 0 l 0l Ol@W@l i 7 NA I

' ' PERsONNE'L'auu2Es OEsCRiPnON@

NuueER 1010l Ol@l NA P

i a 7

ii n

.o ITTil W @ M^"R0!ON *'"" @

' w" T E l

NA l

7 e,

io 8305050025 830427 EsCRIPHON @

PDR ADOCK 05000302 NRC USE ONLY E LldE61 S

PDR l lllllrIllllll issu 7

3 9 to 68 69 80 NAME OF PREPARER

'I - I' EUfC' (904) 7W6486 PHON E:

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:

[

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.

l l

i i

l 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

\\

l