05000395/LER-1983-008, Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl

From kanterella
Jump to navigation Jump to search
Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl
ML20072G388
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/17/1983
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20072G390 List:
References
NUDOCS 8303240596
Download: ML20072G388 (2)


LER-2083-008, Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl
Event date:
Report date:
3952083008R00 - NRC Website

text

s l}

C' r

SOUTH CAROLINA ELECTRIC Sc GAS COMPANY ,,

POST OFFICE 7e4 'g cotuusia sours canotium asais ty '4 4 Rio y4

[,' ,,,,',*, "j,"' March 17, 1983 Tp NvCLEAR OPERATIONS j# p ((

Mr. James P. O'Reilly  ?- t(s'.h' Regional Administrator ,

U.S. Nuclear Regulatory Commission ,,

Region II, Suite 2900 e 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 83-008, Revision 1

Dear Mr. O'Reilly:

Please find attached Revision 1 of Licensee Event Report #83-008 for Virgil C. Summer Nuclear Station. This Thirty Day Report was previously submitted on February 21, 1983, in compliance with Technical Specification 6.9.1.13.(b) and addressed an entry into Action Statement 15 of Technical Specification 3.3.2, " Engineered Safety Feature Actuation System Instrumentation," on January 27, 1983. This revision addresses an additional entry into Action Statement 6 of Technical' Specification 3.3.1, " Reactor Trip System Instrumentation," which was not previously documented.

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

Ver truly yours, O. W. ixon, Jr.

CJM:OWD/dwf/fjc Attachment cc: V. C. Summer G. J. Braddick T. C. Nichols, Jr.,/O. W. Dixon, Jr. J. C. Miller E. C. Robarts J. L. Skolds H. N. Cyrus J. B. Knotts, Jr.

Group / General Managers B. A. Bursey R. B. Clary I&E (Washington)

C. A. Price Document Management O. S. Bradham' Branch A. R. Koon INPO Records Center D. A. Lavigne NPCF C. L. Ligon (NSRC) File (Lic./Eng.)

' OVL'iCIAL COQ.f, 8303240596 830317 PDR ADOCK 05000395 l

5 pop &

l L.

F- 1 N$ l l

Mr. James P. O'Reilly LER No.83-008, Revision 1 Page Two March 17, 1983  ;

DETAILED DESCRIPTION OF EVENT On January 27, 1983, with the Pltnt in Mode 1, the Main Control Board indication (PI-486) for Staam Generator "B" Steam Pressure decreased approximately 100 psig as compared to redundant channels. The " Steam Line Hi DP" alarm was also received at the time of the observed discrepancy in pressure indication. The channel was declared inoperable at 0800_ hours, and the bistables placed in the trip condition within one (1) hour in compliance with Action Statement 6 of Technical Specification 3.3.1 and Action Statement 15 of Technical Specification 3.3.2.

The entry into Action Statement 6 of Technical Specification 3.3.1 was necessitated because Steam Generator "B" Steam Pressure provides density compensation for the steam flow portion of the Steam /Feedwater Flow Mismatch and Low Steam Generator Water Level circuitry -identified in Table 3.3-1, Item 14.

PROBABLE CONSEQUENCES There were no adverse consequences as South Carolina Electric and Gas Company (SCE&G) complied with the Action Statements of the applicable Technical Specifications.

CAUSE(S) OF THE OCCURRENCE The cause of the occurrence is attributed to a plugged transmitter-sensing line.

IMMEDIATE CORRECTIVE ACTIONS TAKEN The inoperable channel was placed in the tripped condition within one (1) hour in accordance with Action Statement 6 of Technical Specification 3.3.1 and Action Statement 15 of Technical Specification 3.3.2. The initial investigation indicated that the failure of pressure transmitter PT-486 to reflect the process pressure was due to a plugged sensing line. The sensing line blockage was cleared by applying back pressure through the transmitter valve manifold. Steam Generator "B" Steam Pressure indication returned to normal upon - the completion of the flushing activity. The channel was declared operable at 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> on January 27, 1983, upon the satisfactory performance of a Channel Check.

i ACTION TAKEN TO PREVENT RECURRENCE The licensee plans no further action in regards to this isolated event other than the normal surveillance testing.

)