ML17304A726

Special Rept 2-SR-88-006:on 881014,72 H Limit for Operability Exceeded for Containment Bldg Atmosphere Process Monitor.Caused by Error in Procedure.Procedure Corrected

ML17304A726
Person / Time
Site:	Palo Verde
Issue date:	11/07/1988
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00430-JGH-T, 192-430-JGH-T, 2-SR-88-006, 2-SR-88-6, NUDOCS 8811150133
Download: ML17304A726 (8)

Text

ACCZ~~~DL~PVXR5 BI~AARK(RIR ACCESSION NBR:8811150133 DOC.DATE: 88/11/07 NOTARIZED: NO D'OCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION HAYNES,J.G. Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Special rept:on 881011,radiation monitoring unit inoperable for greater 72 h.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR i ENCL / SIZE:

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 CHAN,T 1 1 DAVIS,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 QE 02 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN5 FILE 01 1 1 EXTERNAL'G&G WILLIAMSI S 4 4 FORD BLDG HOY,A 1 1 R H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISIJ 1 1 NSIC MAYS,G 1 1 NOTES: 1 1 S

h TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 43

PALO VERDE NUCLEAR GENERATING STATION Radiation Monitoring Unit Inoperable For Greater than 72 Hours License No. NPF-51 Docket No. STN 50-529 Special Report No. 2-SR-88-006 This Special Report is being submitted pursuant to Technical Specification (T.S.) 3.3.3. 1 ACTION 27 and T.S. 6.9.2 to report an event in which the Containment Building Atmosphere Process Honitor (RU-1) was inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit for operability was exceeded at approximately 1036 HST on October 14, 1988. Pursuant to T.S. 3.3.3. 1 ACTION 27b the moveable air monitor (RU-53) was placed on line.

At approximately 1036 MST on October 11, 1988, Palo Verde Unit 2 was in Node 1 (POWER OPERATION) at approximately 100 percent power when RU-1 was taken out of service to perform Surveillance Test (ST) 36ST-9S005, "Radiation Honitoring Calibration Test for Baseline Process Monitors."

During the performance of the ST, the Single Channel Analyzer (SCA) amplifier board could not be adjusted within specifications. An approved work order was issued to troubleshoot and either rework or replace components as required.

The SCA amplifier board was replaced and satisfactorily retested. A Root Cause of Failure, Engineering Evaluation Request has been initiated.

The performance of the ST requires the utilization of several radioactive sources including a 0.5 microcurie, Cesuim-137 source and a 0.5 microcurie, Barium-133 source . These sources are utilized to calibrate RU-1's response.

During the performance of the ST, the technician performing the test observed unexpected responses. The technician reviewed the procedural steps and determined that an incorrect source was utilized in a portion of the RU-1 calibration. The technician had been appropriately using an approximately 0.5 microcurie, Cesuim-137 source for calibration. However, during subsequent sections of the procedure, the technician did not switch the Barium-133 source for the Cesium-137 source as required by the procedure. The applicable steps were successfully r eperformed using the correct source. The delay associated with this error was approximately 45 minutes. The procedures were reviewed by the Unit 2 Instrument and Control Supervisor and were determined to be adequate regarding this aspect. However, a procedure error was identified during the subsequent performance of the ST as discussed in the following paragraph.

During the subsequent performance of the ST, the sample flow rate was determined to be low, An approved work order was issued to troubleshoot and either rework or replace components as required. Troubleshooting determined that an automatic bypass valve was fully opened causing the low sample flow rate. Further investigation determined that the approved ST procedure had been revised in error. The voltage power supply leads were supposed to be conriected to the flow transmitter leads to ensure the bypass valve closed.

Instead, the procedure instructed that voltage power supply leads shall be connected to the terminals where the flow transmitter leads had been lifted.

The procedure was changed to correct the error.

Bl 1 2 502 33 885 107 gp22 ADOCJ( 05000529 PNU i/(

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Special Report 2- 006 Page 2 The procedure had been revised to incorporate enhancements. However, the error occurred when the step to connect the voltage power supply was incorporated into the preceeding step. The procedural error was reviewed and determined that the performance of the procedure could not result in the monitor being returned to service in an inoperable condition.

Upon completion of the work order and appropriate surveillance test, RU-1 was restored to an operable status on October 14, 1988 at approximately 1500 HST.

The monitor was out of service for approximately 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> and 24 minutes.

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Arizona Nuclear Power Project P,O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00430-JGH/TDS/JJN November 7, 1988 U. S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 (License No. NPF-51)

Special Report 2-SR-88-006 File: 88-020-404 please find Special Report 2-SR-88-006 prepared and submitted

'ttached pursuant to Technical Specifications 3.3.3. 1 ACTION 27 and 6.9.2. This report discusses an inoperable radiation monitoring unit.

If you have any questions, please contact T. D. Shriver, Compliance Manager at (602) 393-2521.

Very truly yours, J. G. Hayn s Vice President Nuclear Production JGH/TDS/JJN/kj Attachment cc: D. B. Karner (all w/a)

f. f. Van Brunt, Jr.

J. B. Hartin T. J. Polich H. J. Davis A. C. Gehr INPO Records Center

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