ML17304A637

From kanterella
Jump to navigation Jump to search
Special Rept 2-SR-88-002:on 880912,radiation Monitor Inoperable for Greater than 72 H.Preplanned Alternate Sampling Program Initiated to Monitor Fuel Bldg Ventilation Sys When Needed
ML17304A637
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 10/11/1988
From: Haynes J
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00418-JGH-T, 192-418-JGH-T, 2-SR-88-002, 2-SR-88-2, NUDOCS 8810180005
Download: ML17304A637 (8)


Text

C :a AC CELERATED FFRIBUTION DEMON ATION SYSTEM

'I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8810180005 DOC.DATE: 88/10/11 .NOTARIZED: NO DOCKET 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 2-SR-88-002:on 880912,radiation monitor inoperable for greater than 72 h.,

Inci ent Rpt,g etc.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE: I TITLE: 50.73 Licensee Event Report (LER),

D NOTES:Standardized plant. 05000529 8

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 DAVIS,M 1 CHAN,T 1 1, INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 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 NRRMRZS SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 1 1 RES TELFORD,J 1 1 RES/DBIR DEPY 1 1 RES/DSIR/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL EG&G WILLIAMSg S 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 NOTES: 1 1 A

NCTE R) ALL "RIDS" R1XIPIERIS:

HZASE HELP US K) KKRJCE %ASTE! CXRKLCT %HE DOCX3MEÃZ CONTROL DESK, RQQN Pl-37 (EXT. 20079) TO EIZMINATE YOUR MNE ESCA DISTRIBUTION I2IBTS HK DOCEKNTS YOU DON'T NEEDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 48 ENCL 47

1 t

~ ~ C 4 ~ E. '4 Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00418-JGH/TDS/JJN October ll, 1988 S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

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

Special Report 2-SR-88-002 File: 88-020-404 Attached please find Special Report 2-SR-88-002 prepared and submitted pursuant to Technical Specifications 3.3.3.8 ACTION 42b and 6.9.2. This report discusses a radiation monitor inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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

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

E. E. Van Brunt, Jr.

J. B. Hartin T. J. Polich M. J. Davis A. C. Gehr INPO Records Center 88101S0005 881011 PDC

I 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-88-002 This Special Report is being submitted pursuant to Technical Specification 3.3.3.8=ACTION 42(b) and Technical Specification 6.9.2, to report an event in which the Radioactive Gaseous Effluent Monitors (Fuel Building Ventilation System Low Range Monitor RU-145 and High Range Monitor RU-146) were inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. As anticipated prior to the event, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit for returning to operability was exceeded at approximately 1000 HST on September 15, 1988. Pursuant to Technical Specification 3.3.3.8 ACTION 42(a) the Preplanned Alternate Sampling Program was initiated to monitor the Fuel Building Ventilation System when needed.

Radiation Monitors RU-145 and Ru-146 were declared inoperable to perform the eighteen month Surveillance Test (ST) 36ST-9Sgll "RU-145/146 Calibration Test." The ST was reviewed prior to implementation and determined that the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit would likely be exceeded before the ST and related work could be completed. The coordination of Haintenance and Engineering personnel was planned to support 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage in an attempt to complete the work within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit.

At 1000 HST on September 12, 1988, Palo Verde Unit 2 was in mode 1 (POWER OPERATION) at approximately 100 percent power when monitors RU-145 and RU-146 were declared inoperable. RU-145 and RU-146 work as a pair with RU-145 being the low range monitor and RU-146 being the high range monitor. Normal configuration consists of RU-145 operating and RU-146 in standby. When Ru-145 reaches a predetermined setpoint, RU-146 starts and RU-145 goes to standby.

Since RU-145 and RU-146 work in tandem, RU-146 must be declared inoperable if RU-145 is inoperable.

During testing, the RU-145 detector response was determined to be unsatisfactory. Corrective action to troubleshoot, and rework or replace components as required was initiated under an approved work order. A spare detector was installed and calibrated.

During subsequent testing, the sample pump flow indication was unsatisfactory. The flow electronics were adjusted to the maximum permitted in the ST. Corrective action to troubleshoot, and rework or replace components as required was initiated under an approved work order. The System Engineer reviewed the Technical Manual and the flow transmitter was properly calibrated.

When RU-145 was returned to the remote position, a "High Reading" alarm locked in. Corrective action to troubleshoot, and rework or replace components as required was initiated under an approved work order. Troubleshooting determined that a spurious actuation of the check source was causing the high reading. A modification to the check source circuitry was installed in accordance with an approved work and design change document.

Page 2 Special Report 2-SR-88-002 During testing of RU-146, the power supply voltage was determined to be unsatifactory. Corrective action to troubleshoot, and rework or replace components as necessary was initiated under an approved work order. The circuit pad on the display board was repaired in accordance with an approved engineering document. The display board and a new power supply were installed.

During subsequent testing of RU-146, the check source on channel 1 would not operate properly. Corrective action to troubleshoot, and rework or replace components as necessary was initiated under an approved work order. The linkage, which moves the check source, was binding. All five check sources were tested. Channels 3 and 5 also did not operate properly. The linkages for channels 1, 3, & 5 were removed, reworked, reinstalled and reterminated satisfactorily.

During subsequent testing of RU-146, the sample pump motor started cycling on and off. Corrective action to troubleshoot, and rework or replace components as necessary was initiated under an approved work order. Troubleshooting determined that the "hand-over" circuit was causing the pump to sta'rt. This circuit starts the operation of RU-146 when RU-145 reaches a predetermined setpoint. The problem was determined to be that the ST specifies lifting two leads, but a third lead should have been lifted until RU-146 was calibrated.

The ST was changed and the lead was lifted.

Following the completion of the calibration ST, a functional test was performed. During the performance of the functional test, sample flow was determined to be unsatisfactory. Corrective action to troubleshoot, and rework or replace components as necessary was initiated under an approved work order. Troubleshooting determined that plastic cartridges installed did not provide adequate sealing. Replacement metal cartridges and new O-.rings were installed in the sample holder in accordance with an approved engineering document. The functional test was successfully completed. On September 23 at approximately 0852 HST, RU-145 and -146 were declared operable.

[l I)