Part 21 Report - 1996-701

 
 
ACCESSION #: 9611200181

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                                                  SAP-132
                                                  ATTACHMENT II
                                                  Page 1 of 2
                                                  Revision 12

NOTIFICATION TIME   1553

FACILITY OR ORGANIZATION   Virgil C. Summer Nuclear Station   

UNIT   1

CALLERS NAME   M. Zaccone

CALL BACK #   301�816�5100  R. Karsch

EVENT TIME AND ZONE   N/A

EVENT DATE   05/30/96

POWER MODE BEFORE   75% Mode 1

POWER MODE AFTER   75% Mode 1

DESCRIPTION

Non�Conformance Notice 5481 reports the third failure of ITT BARTON
Model 763 pressure transmitters at V. C. Summer Nuclear Station
within a one week period.  In each case, a strain gage lead was
broken loose of its terminal pin.

Model 763 transmitters are used at V. C. Summer Nuclear Station to
provide protection signals based on pressurizer pressure;
specifically, reactor trip on high pressurizer pressure or reactor
trip and safety injection on low pressurizer pressure.  Each
transmitter was calibrated and installed as IPT00457RC, where two
failed after being in service for a short period of time, and one
failed prior to return to service.  An additional Model 763
pressure transmitter was obtained, calibrated and installed as
IPT00457RC.  V. C. Summer Nuclear Station ensured that the
associated application was restored to operable status. 
Reliability of pressurizer pressure transmitters is verified by
weekly monitoring and channel checks.�..h)..0*0*0*�.�..ԌITT BARTON has not
established a root cause for what appears to be
a repetitive failure of the Model 763 pressure transmitters. 
BARTON is in the process of evaluating the V. C. Summer Model 763
for failure analysis.

This report is being made pursuant to 10CFR Part 21.

                                                  SAP-1165
                                                  Attachment 1
                                                  Revision 0
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        SUBSTANTIAL SAFETY HAZARD (SSH) EVALUATION TRACKING SHEET
         (TO BE COMPLETED WITHIN 60 DAYS OF INITIAL DISCOVERY)*

TRACKING SHEET INITIATION DATE

*1.  GENERAL INFORMATION

Number  96007  Discovery Date 5/30/96  Date To Be Completed 7/29/96

Reviewer  Robert L. Justice, Jr.

Topic  Barton Model 763 pressure transmitter broken strain guage  
       leads.

How was topic first identified?  Transmitter failed (NCNE5479)

List correspondence, documents, telecons applicable to the
determination of the substantial safety hazard.

NCNE5479, NCNE5480, NCN5481; ITT Barton Failure Analysis Report
(#FA960701) and FSAR Chapter 15.

*2.  DISPOSITION

Determined to be potential SSH, reportable        YES       NO
per 10CFR21:  YES

Discussion/justification:

Failure of 2 of 3 pressurizer pressure transmitters would prevent
reactor trip and safety injection signals necessary to mitigate
design basis LOCA per Chapter 15 of the FSAR (Reference NCNE5479,
E5480, and 5481)

Signatures:    Reviewer                 Date  7/22/96
Appropriate Functional Manager          Date  7/23/96
Manager, Nuclear Licensing              Date  7/24/96
& Operating Experience

3.   Determined to be reportable per 10CFR21 by VPNO: (5-DAY LIMIT) 
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0910�(#h.��..h).0*0*0*�.�..Ԍ�4.   NRC INFORMED - SUBSTANTIAL SAFETY
HAZARD

     2 DAY NOTIFICATION

Notified by SCE&G (Name) M.J Zaccone        NRC (Name) R. Karsch
Time 1553                                   Date  7/31/96
Applicable Correspondence  NCN 5479, 5480, 5481

5.   30 DAY REPORT
Due Date
Letter to NRC                                Date
Applicable Correspondence

6.   MISCELLANEOUS INFORMATION

7.   PROGRAM TRACKING DOCUMENT, e.g., NCN, ONO, OPDR, MRF, CHPNR, 
     SHPPR, etc.

8.   CLOSEOUT
Signature                                    Date
Manager, Nuclear Licensing &
Operating Experience

Closed in RTS: Signature                     Date

Transmitted to Records Management            Date
Signature

NOTE:     If review cannot be completed within 60 days of discovery
date, an interim report must be submitted to the NRC within that
same 60 day timeframe.

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