05000395/LER-1982-063, Forwards LER 82-063/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-063/03L-0.Detailed Event Analysis Encl
ML20083M333
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/19/1983
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20083M336 List:
References
NUDOCS 8302010139
Download: ML20083M333 (2)


LER-1982-063, Forwards LER 82-063/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3951982063R00 - NRC Website

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SOUTH CAROLINA ELECTRIC & GAS COMPANY post OFFICE 764

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. :. g COLUMelA. SOUTH CAROLINA 29218 O. W. DixON. JR.

VsCE OMESsDENT uuCtE4 o.E.Tio3..' / 9 '25 All. 2I January 19, 1983 Mr. James P.

O'Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street, N.W.

Atlanta, Georgia 30303

SUBJECT:

Virgil C.

Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 82-063

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-063 for Virgil C. Summer Nuclear Station.

This Thirty Day Report is required by Technical Specification 6.9.1.13.( c) as a result of not satisfying the surveillance requirements ' of Technical Specification 4.4.8, " Reactor Coolant System, ~ Specific Activity,"

on December 20, 1982.

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

Very truly yours, O. W. Di on, HCF:OWD:dwr Attachment cc:

V.

C.

Summer A.

R. Koon T. C. Nichols, Jr.

G.

D. Mof fatt E.

C.

Roberts Site QA

0. W.

Dixon, Jr.

C. L. Ligon (NSRC)

H. N. Cyrus G.J. Braddick H. T. Babb J. L. Skolds D.

A. Nauman J. B. Knotts, Jr.

M.

B. Whitaker, Jr.

B.

A. Bursey W.

A. Williams, Jr.

I&E (Washington)

O.

S. Bradkam Document Management Branch R. B. Clary INPO Records Center M. N. Browne NPCF File

  1. 5 FiCIALCOPY 8302010139 830119 gDRADOCK05000

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t Mr. Jamec P. O'Reilly LER No.82-063 Page Two January 19, 1983 DETAILED DESCRIPTION OF EVENT On December 20, 1982, while in Mode 1, the Plant underwent a power transient from 5% to 21% thermal power between the hours of 0400 and 0500.

Per Technical Specification 4.4.8, Table 4.4-4(4b), an Isotopic Iodine Analysis is required to be performed between two and six hours following a thermal power change exceeding 15% of the rated thermal power.

This surveillance was not performed as required within the Technical Specification time limit.

PROBABLE CONSEQUENCES There were no adverse consequences as no fuel degradation has occurred at the Plant.

This is supported by an isotopic analysis that was performed with acceptable results at 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br /> on December 20, 1982.

CAUSE(S) OF THE OCCURRENCE The event is attributed to inadequate. communication measures between the Control Room personnel and the Chemistry Department.

Chemistry personnel were not notified to perform an Isotopic Iodine Analysis prior to the power transient.

i IMMEDIATE CORRECTIVE ACTIONS TAKEN An Isotopic Iodine Analysis was performed at 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br />.

The results were acceptable.

ACTION TAKEN TO PREVENT RECURRENCE A computer program has been developed which monitors specific plant parameters needed by the Chemistry Department.

One of these parameters, the Reactor power level, will be monitored to determine if power transients necessitate an isotopic analysis.

This will be done at least every four hours to allow compliance' with the Technical Specifications when such transients exist.

Additionally, a procedure is currently being approved to help ensure that " contingency type" Technical Specification j

Surveillance Requirements are satisfied.

The Licensee plans to have this procedure approved by January 31, 1983.

i