05000280/LER-1980-073-03, /03L-0:on 801205,discrepancies Discovered in Documenting Performance of Periodic Tests PT-18.8 & 19.1. Caused by Operations Personnel Oversight.Personnel Reinstructed & Improved PT Mgt Sys Developed

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/03L-0:on 801205,discrepancies Discovered in Documenting Performance of Periodic Tests PT-18.8 & 19.1. Caused by Operations Personnel Oversight.Personnel Reinstructed & Improved PT Mgt Sys Developed
ML18139A968
Person / Time
Site: Surry Dominion icon.png
Issue date: 01/05/1981
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A966 List:
References
LER-80-073-03L-02, LER-80-73-3L-2, NUDOCS 8101090661
Download: ML18139A968 (3)


LER-1980-073, /03L-0:on 801205,discrepancies Discovered in Documenting Performance of Periodic Tests PT-18.8 & 19.1. Caused by Operations Personnel Oversight.Personnel Reinstructed & Improved PT Mgt Sys Developed
Event date:
Report date:
2801980073R03 - NRC Website

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/ rr::m /During an adminstrative review of completed Periodic Test (PT) procedures, discrepan-

'[9J)) !cies in the documenting of the performance of PT-18.8 and 19.1 were noted.

Failure to

((II] !perform these PT's is contrary to the ASME XI ISI program and T.S.4.5.A.5 respectively

[]I[] land reportable per T.S.6.6.2.b'(3).

The affected cpmponents did meet the required ac-

[]J]:] 1ceptance criteria when the next scheduled PT was. performed.

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((ill 1safety of the public* were not affected.

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ATTACHMENT 1 SURRY POWER DOCKET NO:

REPORT NO:

EVENT DATE:

e STATION UNIT NO. 1 50-280 80-073/03L-0 12/05/80

1.

EVENT DESCRIPTION

MISSED PERIODIC TESTS e

During an administrative review of completed Periodic Test (PT) procedures, certain discrepancies in the documenting of completed PT's were noted.

The following is a description of the.discrepanci1:s:(1) PT-18.8 (charging pump component Cooling & Service Water pump ASME Section IX Testing) Cannot be doc-umented as being completed during the months of April and May 1980 (2) PT-19.1 (RWST CAT MOV Cyclying) cannot be documented as being completed prior to exceeding 350°F/450 psig on May 10, 1980.

Failure to perform PT-19.1 is contrary to Technical Specification 4.5.A.5.

P'.Ji'_:...18.8 is part of the ASME SECTION XI program that has been submitted to NRR for approval.

However, PT-18.8 is not currently a Technical Specification requirement.

The above events are being reported pursuant to Technical Specification 6. 6. 2. b (3) *-

2.

PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT EQUIPMENT PT-18.8 The.availability and operability of the components covered by t1iis PT are subject ta:a:.Technica.l.Specifica:tion~*Lcp.r :As>such:;.,1any*-.failure:.-to perf*orm their intended function is documented by Station Deviation reports and associated LER's.

These components are listed in the "Minimum Equipment List" which will document their availibity.

This checklist is performed daily during reactor operation.

In ad-dition, Equipment Rotation-records indicates that these components were operable during the months*of April and May.

These components were operable, however, the Failure to performe the assigned PT's resulted in a loss of data that could be used to schedule pump maintenance.

P.T-19,. l Technical Specification 4.5 has provision for the waivering of this PT during extended reactor shutldowns provided that it is performed prior to reactor start up.

This PT was sucessfi.ily completed in March and should have been performed prior to exceeding 350°F/450° psig at 2215 hrs on May l'O, 1980.

However, the PT was performed a few hours later on May 11, 1980 and the components operated satisfactory.

The above components did meet the required acceptance criteria when periodic testing was performed and supplementary information for PT-18.8 is available to prove.that.the respective components were operable.

Therefore, the health and safety of the public were not affected.

3.

CAUSE

The cause of the events was due to an oversight on the part of operations personnel.

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4.

IMMEDIATE CORRECTIVE ACTION

The immediate corrective action was to verify that periodic testing had been performed on the affected components since the start up of Unit No. 1 in May 198Q.

5.

SUBSEQUENT CORRECTIVE ACTION All available documentation was reviewed in an attempt to locate any evidence of the completion of the missing PT's.

6.
  • ACTION TAKEN TO PREVENT RECURRENCE An imp1:oved Periodic Test Management System is. under development.

This system should reduce the possibility of overdue PT's going unidentified past their grace period.

This system, using~ in house computer, should be operational early in 1981.

In ~ddition, a seperate individual has been assigned to oversee the conduct of the Operational PT program.

7.

GENERIC IMPLICATIONS None