05000302/LER-1978-017-01, /01T-0:on 780306,17 Loose Parts Identified as Coupling & Spider Assembly of BPR- B-47,discovered in B once-through Steam Generator.Caused by Assembly Failure. Corrective Action to Be Determined

/01T-0:on 780306,17 Loose Parts Identified as Coupling & Spider Assembly of BPR- B-47,discovered in B once-through Steam Generator.Caused by Assembly Failure. Corrective Action to Be Determined

ML19326A762
Person / Time
Site:	Crystal River
Issue date:	03/14/1978
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19326A757	List: 05000302/LER-1978-017, Forwards LER 78-017/01T-0 05000302/LER-1978-017-01, /01T-0:on 780306,17 Loose Parts Identified as Coupling & Spider Assembly of BPR- B-47,discovered in B once-through Steam Generator.Caused by Assembly Failure. Corrective Action to Be Determined
References
LER-78-017-01T, LER-78-17-1T, NUDOCS 8003030892
Download: ML19326A762 (2)

LER-1978-017, /01T-0:on 780306,17 Loose Parts Identified as Coupling & Spider Assembly of BPR- B-47,discovered in B once-through Steam Generator.Caused by Assembly Failure. Corrective Action to Be Determined

Event date:
Report date:
3021978017R01 - NRC Website

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[h SUPP1EMENTART INFORMATION h

Report No.:

50-302/78-17/01T-0

.l 2.

Facility:

Crystal River Unic #3 3.

Report Date:

14 March 1978 4.

Occurrence Date:

6 March 1978 (discovered 17 February 1978) 5.

Identification of Occurrence:

IDiscovery of loose parts in the "B" Once Through Steam Generator (OTSG) reported in accordance with Section (g) of Technical Specification 6.8.1.8._

6.

Conditions Prior to Occurrence:

Mode 1 operation.

7.

Description of Occurrence:

At 0005 on 17 February 1978 a constant alarm on the Reactor Diagnostic System (Loose Parts Monitor) occurred on the "B" OTSG. Inicial action taken was to monitor other i.

plant parameters for signs of degradation. Other plant parameters indicated no abnormalities. Investigation revealed apparent loose parts in.the tube sheet, region of the "B" OTSG and whose acise and vibration were dependent on' the reactor coolant flow produced by "2" reactor coolant pumps in loop "3".

. Subsequent. co this investiga-tion, a decision was made to operate the plant in "3" RC pump operation and reduce

. power to'less than 78% power in accordance with Tech Spec 3.4.1 Action Scacement a.

Investigation teams fz'on BW were called in an'd their analyzstion. confirmed the loose parts diagnosis. Preparations commenced for plant shutdown and subsequent inspection.

t of the "B" OTSG. The plant was taken off line at 2337 on 3 March 1978 and cooldown com-manced on 5 March 1978. At 1900 on 6 March 1978, inspection.of the "B" OTSG was made with video camera equipment and confirmation of approxinately 17 loose parts identified as parts of the coupling and spider assembly of burnable poison red (BPR) #B-47 vere scattered over the upper tube sheet. Preparations for further draindown and Reactor Vessel head removal cons nced and the Rasetor Vessel head was removed on 13 March 1978.

Inspection also revealed damage of varying degrees had occurred to many of the "3"

steam generator tube ends. Removal for inspection of the Planum is anticipated to be congleted by 15 March 1978. Rasults of the Plenum inspection and paths to be taken subsequent to this investigation will be forthcoming as an addendum to this report.

8.

Designation of Apparent cause:

As of this date, the apparent cause of this occurrence was due to a failure of the coupling and spider assembly of 3PR fB-47.

9.

Analysis of occurrenca:

The health and safety of the plant and general public were not cospremised as a result of this event.

10.

Corrective Action

Unknown at this time. As investigations continus, corrective action will be implemented as a result of the investigations.

' Failure Data:

First occurrence of this event.