ML18093B518

LER 89-012-00:on 890218,reactor Trip on Turbine Trip Occurred W/Power Above Permissive P-7 While Work in Progress on Turbine Impulse Chamber Pressure Transmitter.Caused by Personnel Error.License Change approved.W/890315 Ltr

ML18093B518
Person / Time
Site:	Salem
Issue date:	03/15/1989
From:	MILLER L K, POLLACK M J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-012, LER-89-12, NUDOCS 8903240213
Download: ML18093B518 (4)

Text

NAC Fo<111 -(9-831 U.S. NUCLEAR REGULATORY OMI NO. JU0-0104 LICENSEE EVENT REPORT ILER) EXPIRES: B/3111111 l'ACILITY NAME (11 I Salem Generating Station -Unit 1 I DOCKET NUMIER 121 o I 5 Io IO IO I 21712 1 loF 01 3 TITLE l'I Reactor Trip on Turbine Trip Due To Personnel Error EVENT DATE !151

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".IUMBER 6 I 0 I 9 3 I 31 9 1-1 41 0 12 12 COMf'LETE ONE LINE FOR EACH COMl'ONENT FAILURE DEICRlll!D IN THll REl'OllT 1131 CAUSE SYSTEM COMPONENT I I I I I I I I MANUFAC* TUR ER I I I I I I SYSTEM I I . COMPONENT I I I I I I MANUFAC* TUR ER I I I I I I EXPECTED IUPPLEMENTAL REPORT EXPECTED 11'1 MONTH DAY YJAR SUBMISSION I DATE (151 n YES (If yt1 0 complotw EXPECTED SUIJMISSION DATE/ I Aa'TRACT ro 1400 ,,,..... i.* .. oppro*lmor.ly fiftoon 1lngl**IPK*

typowrltr.n linrnl 11111 On 2/18/89, a reactor trip occurred.

At the time of the event, reactor power was at 10-e Amps (Critical).

The trip signal was the result of a Turbine Trip with power above permissive P-7 (10% power). Work in progress included functional testing of the turbine impulse chamber pressure transmitter.

The root cause of this event has been attributed to personnel error. An I&C Technician performing the transmitter functional test did not comply with the procedure requirements.

Contrary to the requirements of the procedure, the technician did not notify supervision when the status panel indications were not correct and continued performing the procedure.

The technician was not aware that the continuance of the procedure would result in a trip. When the bi-stables are tripped, as a result of functional testing, a signal indicating reactor power above P-7 is generated.*

If the Turbine is not latched, as was the case in this event, a reactor trip will occur. Maintenance Department management has completed a review of this event and has completed appropriate corrective disciplinary action with the individual(s) involved.

This event w.ill be reviewed with Maintenance Department personnel stressing the need for procedural compliance.

I&C procedures associated with the turbine impulse pressure transmitter channels have been modified to indicate that a reactor trip will occur if these procedures are performed with the turbine not latched. Training programs will be modified as applicable.

I NRC For111-(9-831 8903240213 890315 PDR *ADOCK 05000272 S PNU l-y.

I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 89-012-00 PAGE 2 of 3 Energy Industry Identification System (EIIS) codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE:

Reactor Trip On Turbine Trip and P-7 due to personnel error Event Date: 2/18/89 Report Date: 3/15/89 This report was initiated by Incident Report No.89-096. CONDITIONS PRIOR TO OCCURRENCE:

Mode 2 Reactor Power 10-9 Amps -Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

On February 18, 1989 at 1404 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.34222e-4 months <br />, a reactor trip occurred.

At the time of the event, reactor power was at 10-9 Amps (Critical).

The first out annunciator indicated the trip was the result of a Turbine Trip with power above permissive P-7 (10% power). Work in progress included functional testing of the turbine impulse chamber pressure transmitter PT506. The Nuclear Regulatory Commission was notified of the actuation of the Reactor Protection System (RPS) {JCJ at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> on February 18, 1989 in accordance with the Code of Federal Regulations lOCFR 50. 72 (b) (2) (ii). APPARENT CAUSE OF OCCURRENCE:

The root cause of this event has been attribuied to personnel error. The I&C Technician performing the PT506 functional test did not comply with the requirements of the procedure.

The procedure requires review and documentation of status panel indications.

If these indications are not correct, continuation with the procedure is not allowed pending notification of I&C supervision.

The I&C technician did not notify I&C supervision when the status panel indications were not correct and continued performing the procedure.

The technician was not aware that the continuance of the procedure would result in a trip. ANALYSIS OF OCCURRENCE:

As indicated in the Description of Occurrence Section, functional testing of PT506 was in progress in accordance with procedure lIC-2.6.025.

When the bi-stables are tripped, as a result of testing, a signal indicating reactor power above P-7 is generated.

If the

• LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 89-012-00 PAGE 3 of 3 Turbine is not latched, as was the case in this event, a reactor trip will occur. The Reactor Trip, on turbine trip, is designed to avoid steam generator safety valve actuation in the event the turbine should trip with reactor power level greater than ten percent. This trip is anticipatory and is included as part of good engineering practice and prudent design. No credit is taken in any of the safety analyses for this trip. This event involved no undue risk to the health or safety of the public. The. RPS functioned as designed to trip the reactor upon a turbine trip with a signal indicating that reactor power level was greater than 10%. Due to the automatic actuation of the RPS, this event is reportable in accordance with the Code of Federal Regulations lOCFR 50. 73 (a) (2) (iv). CORRECTIVE ACTION: Maintenance Department management has completed a review of this event and has completed appropriate corrective disciplinary action with the individual(s) involved.

Maintenance Department management will review this event with department personnel stressing the need for procedural compliance.

The functional testing and surveillance procedures associated with the turbine impulse pressure transmitter channels, -PT505 and PT506, have been modified to indicate that a reactor trip will occur if these procedures are performed with the turbine not latched. The PSE&G Nuclear Training Center will review this .event and will modify training programs as applicable.

A license change to the Technical Specifications has been approved.

This license change replaces the P-7 reactor trip/turbine trip function, at 10% rated thermai power, with the P-9 function.

The P-9 function will allow the automatic block of a reactor trip on turbine trip when rated thermal power is below 50%. Since the power level for P-9 is derived from the Nis and not turbine impulse pressure, as is P-7, this event cannot occur. The P-9 function will be installed upon completion of design change(s) associated with the license change which are scheduled to be done this next refueling outage beginning April 15, 1989. MJP:pc SORC Mtg.89-021 General Manager -Salem Operations

• Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-012-00 March 15, 1989 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery.

• MJP:pc Distribution The Energy People Sincerely yours, L. K. Miller General Manager -Salem Operations

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