ML17300B232

From kanterella
Jump to navigation Jump to search
Suppl 1 to Special Rept 3-SR-89-003:on 890215,72 H Limit for Inoperability of Condenser Evacuation Sys high-range Effluent Monitor (RU-142)exceeded.Design of Subj Evacuation Sys Reviewed & Addl Electric Resistance Heating Installed
ML17300B232
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 12/21/1989
From: James M. Levine
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00607-JML-T, 192-607-JML-T, 3-SR-89-003, 3-SR-89-3, NUDOCS 9001050297
Download: ML17300B232 (6)


Text

AC CEM RATED DJWRIBUTION DZSTRIBUTI DE M 04 S XTIO~i SYSTEM REGUL Y INFORMATION SYSTEM (RIDS)

ACCESSION NBR:9001050297 DOC.DATE: 89/12/21 NOTARIZED: NO DOCKET ¹ FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECiPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Special rept 3-SR-89-'003:on 891221,inoperability of radioactive effluent monitor.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Standardized plant. 05000530 S

RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME 'TTR ENCL PD5 LA 1 1 PD5 PD 1.'

DAVIS,M. 1 1 D

INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 AEOD/DOA 1 1 D

AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 S NRR/DET/EMEB9H3 1 1 NRR/DET/ESGB 8D 1 1 NRR/DLPQ/LHFBll 1 1 NRR/DLPQ/LPEB10 1 1 '

NRR/DOEA/OEABll 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 NRR/DST/SPLB8D1 1 1 SRXB 8E 1 NUDOCS-ABSTRACT 1 1 02 1 1 RES/DSIR/EIB 1 . 1 RGN5 FILE 01 1 1 EXTERNAL EG&G WILLIAMSi S 4 4 L ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSIC MAYSgG 1 1 NSIC MURPHYiG.A 1 1 NUDOCS FULL TXT 1 1 NOTES:

S h

D D

MIE 'IO ALL "RIDS" RECIPZERIS S

PLEASE HELP US 'IO REDUCE HASTE! CXNI'ACT 'IHE DOCUMEKZ COHIROL DESK, RDCN Pl-37 (i%I'. 20079) K) ELIKBQTE KCR NME PKK DIPHUEPZZCN LISTS FOR DOCUMEMIS YOU DGNiT NEED!

TOTAL NUMBER OF COPIES REQU1RED: LTTR 39 ENCL 39

Arizona Public Service Company PAI.O VERDE NUCLEAR GENERATING STATION P,O BOX 52034 ~ PHOENIX, ARIZONA85072.2034 192-00607-JML/TRB/JJN December 21, 1989 JAMES M, LEVINE VICE PRESIDENT NUCLEAR PRODUCT IDN U. S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

. Unit 3 Docket No. STN 50-530 (License No. NPF-74)

Supplement to Special Report 3-SR-89-003 File: 89-020-404 Attached please find Supplement Number I to Special Report 3-SR-89-003 prepared and submitted pursuant to Technical Specification 3.3.3.8 ACTION 42(b) and 6.9.2, This report discusses the inoperability of a radioactive effluent monitor.

If you have any questions, please contact T. RE Bradish, Compliance =Supervisor at (602) 393-3531.

Very truly yours JHL/TRB/JJN/kj Attachment cc: W, F. Conway (all w/a)

J. B. Hartin T. J. Polich H. J. Davis A. C. Gehr 9001 050297 8%1225 PDR ADOCK 05000530 8 PNU

0 l

l

PALO VERDE NUCLEAR GENERATING STATION Radiation Monitoring Unit Inoperable for Greater Than 72 Hours License No. NPF-74 Docket No. STN 50-530 Special Report No. 3-SR-89-003-01 This Special Report is submitted in accordance with Technical Specification 3.3.3.8 ACTION 42(b) and 6.9.2 for an event in which the Condenser Evacuation System high range effluent monitor (RU-142) 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 inoperability was exceeded at approximately 1710 MST on February 15, 1989. Pursuant to Technical Specification 3.3.3.8 ACTIONS 37 and 40, the Preplanned Alternate Sampling Program (PASP) was initiated at approximately 0300 MST on February 15, 1989.

At approximately 1710 MST on February 12, 1989 RU-142 was declared inoperable as a result of the Condenser Evacuation System low range effluent monitor (RU-141) being declared inoperable due to grab sample results inconsistent with monitor indication. Radioactive effluent monitor RU-141 continuously monitors the condenser vacuum pump/gland seal exhaust for gaseous activity resulting from primary to secondary leakage. Monitors RU-141 and RU-142 work as a pair with RU-141 as the low rang monitor and RU-142 as the high range monitor. Normal configuration consists of RU-141 operating with RU-142 in standby. Low range monitor RU-141 automatically starts RU-142 and initiates filtration of the condenser vacuum pump/gland seal exhaust whenever the monitor regi ster s a HIGH-HIGH alarm condition. RU-142 is provided for ,

tracking radioactive effluents during postulated accident scenarios. RU-142 must be declared inoperable when RU-141 is inoperable.

An approved work document was initiated to troubleshoot the cause of the inconsistent RU-141 indication. During troubleshooting, it was identified that the inconsistent indication was caused by damage to the detector. Water vapor entrained in the sample stream would condense in the detector chamber (coldest point in the system) and cause damage to the detector.

RU-141 and RU-142 are not being returned to service until long-term corrective action can be taken. PVNGS has experienced several instances wherein moisture buildup has resulted in Condenser Evacuation System radioactive effluent monitor improper operation. In order to correct this problem, PVNGS engineering personnel with the assistance of an independent consulting firm are reviewing the design of the system. Based upon the engineering evaluation, appropriate design modifications will be prepared and implemented. The long-term corrective actions are described in a supplement to Unit 3 LER 530/88-08.

In the interim, additional electric resistance heating has been installed. It is anticipated that the monitors will be returned to service by January 15, 1990. However if the additional heat tracing is unsuccessful, the long term corrective measures will be implemented in the next outage of sufficient duration based on the availability of parts which are expected to be delivered by approximately May 1990.

0 ~ l

>I