05000395/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-012/03L-0.Detailed Event Analysis Encl
ML20066A541
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/27/1982
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20066A544 List:
References
NUDOCS 8211060103
Download: ML20066A541 (3)


LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3951982012R00 - NRC Website

text

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' u, SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFric. 764 COLuusiA. south CAROUNA 29218 O. W. DixON, JR.

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October 27, 1982 s

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.- c Mr. James P. O'Reilly, Director 4

40 U.S. Nuclear Regulatory Commission 7 --]

Region II, Suite 3100 qR

- 101 Marietta Street, N.W.

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Atlanta, Georgia 30303 f

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Subject:

VirgilC.SummerNuclearStat1%

Docket No. 50/395 Operating License No. NPF-12

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Thirty Day Written Report LER 82-012

Dear Mr. O' Reilly:

Please find attached Licensee Event Report #82-012 for Virgil C. Summer Nuclear Station.

This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as a result of entry into. Action Statement (b) of Technical Spec'ification 3 3 3 1, " Radiation Monitoring Instrumentation," on September 28, 1982.

Should there be any questions, please call us at your convenience.

Very truly yours,

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Mr. James P. O'Reilly LER 82-012 Page Two October 27, 1982 cc:

V.C. Summer.

T.C. Nichol6, Jr.

G.H. Fischer O.W. Dixon, Jr.

H.N. Cyrus H.T. Babb D.A. Nauman M.B. Whitaker, Jr. -

W.A. Williams, Jr.

O.S. Bradham i

R.B. Clary M.N..Browne A.R. Koon H. Radin Site QA C.L.

Ligon (NSRC)

.G.J.

Braddick J.L. Skolds

'J.B.

Knotts, Jr.

B.A. Bursey I&E (Washington)

Document Management Branch NPCF File

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Mr. James P. O'Reilly LER No.82-012 Page Three October 27, 1982 DETAILED DESCRIPTION OF EVENT On September 28, 1982, with the Plant in Mode 3, RM-07 (Reactor Building High Range Monitor) experienced spikes that caused high radiation alarms.

Corrective action was initiated as described below.

On October 4, 1982, RM-G7 again experienced problems similar to those on September 28, 1982.

The radiation monitor was removed from service for trouble shooting.

The applicable Surveillance Test Procedure (STP) was performed satisfactorily, and the unit was returned to service on October 6, 1982.

PROBABLE CONSEQUENCES There were no adverse consequences.

RM-G7 is a High Range Accident Monitor, and the Plant had not achieved initial criticality; thus, eliminating the need for such-indication.

In addition, all abnormal indications were in the form of short duration spikes with no steady abnormal reading.

Therefore, the abnormality would not impair the ability of the instrument to perform its intended function.

Also, a redundant Reactor Building Area High Range Monitor (RM-018) was Operable.

CAUSE( S) 0F THE OCCURRENCE The cause has been determined by testing to be electrical interference in the detector cable.

The origin of this interference has not been determined.

IMMEDIATE CORRECTIVE ACTIONS TAKEN l

Subsequent to the September 28th incident, the applicable STP was satisfactorily performed.

After the October 4th incident, RM-G7 was removed from service for trouble shooting.

The results indicated the aforementioned cable problems.

The applicable STP was satisfactorily l

performed, and the monitor was returned to service on October 6, 1982, as allowed by the Technical Specification Action Statement.

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ACTION TAKEN TO PREVENT RECURRENCE l

The monitor was returned to service on October 7, 1982.

To date, no further spiking.ias occurred.

The licensee considers the Monitor OPERABLE, however, resolution to the problem is being pursued via Station Request for Engineering Evaluation (REE) No. 895.

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