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: j. 1 CHAN,T                                  1    1        DAVIS,M                  1      1 INTERNAL: ACRS MICHELSON                        ~  1    1        ACRS MOELLER              2      2 ACRS WYLIE AEOD/DSP/TPAB 1    1        AEOD/DOA                  1,    1 1    1      AEOD/ROAB/DSP            2      2 ARM/DCTS/DAB                            1    1      -DEDRO                    1      1 NRR/DEST/ADE 8H                        1    1        NRR/DEST/ADS      7E      1      0 NRR/DEST/CEB 8H                        1    1        NRR/DEST/ESB      8D      1      1
: j. 1 CHAN,T                                  1    1        DAVIS,M                  1      1 INTERNAL: ACRS MICHELSON                        ~  1    1        ACRS MOELLER              2      2 ACRS WYLIE AEOD/DSP/TPAB 1    1        AEOD/DOA                  1,    1 1    1      AEOD/ROAB/DSP            2      2 ARM/DCTS/DAB                            1    1      -DEDRO                    1      1 NRR/DEST/ADE 8H                        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 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            NRR DRIS/SIB 9A NUDOCS-ABSTRACT RES/DSIR/EIB 1
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HELP US 'IO REDUCE HASTE!                CGHXACT 'IHE, DQCX2KNT CGÃHK)L DESK, RXN Pl-37 (EXT. 20079) K) EZZMZHATE YOUR NAME PKH DIPHGBUTIGH LISTS POR DOCK%HIS YOU DGNIT NEED TOTAL NUMBER OF COPIES REQUIRED:, LTTR                          47  ENCL      46


II Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00441-JGH/TDS/RJR January 9, 1989 U. S. Nuclear Regulatory Commission NRC  Document Control Desk Washington, D.C. 20555
II Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00441-JGH/TDS/RJR January 9, 1989 U. S. Nuclear Regulatory Commission NRC  Document Control Desk Washington, D.C. 20555
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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 2-SR-88-009 This Special Report is submitted in accordance with Technical Specifications 3.3.3.8 ACTION 42(b) and 6.9.2 for an event in which the Condenser Vacuum Pump/Gland Seal Exhaust High Range Effluent Monitor (RU-142) and Plant Vent High Range Effluent Monitor (RU-144) were inoperable for greater than 72 hours. The 72 hour limit for operability was exceeded at approximately 0700
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 2-SR-88-009 This Special Report is submitted in accordance with Technical Specifications 3.3.3.8 ACTION 42(b) and 6.9.2 for an event in which the Condenser Vacuum Pump/Gland Seal Exhaust High Range Effluent Monitor (RU-142) and Plant Vent High Range Effluent Monitor (RU-144) were inoperable for greater than 72 hours. The 72 hour limit for operability was exceeded at approximately 0700 HST and 0630 HST    respectively  on December  9, 1988.
-
HST and 0630 HST    respectively  on December  9, 1988.
At approximately 0630 MST on December 6, 1988, with Palo Verde Unit 2 in Mode 1 (POWER OPERATION) at approximately    100 percent power, the Condenser Vacuum-Pump/Gland Seal Exhaust low and high range monitors (RU-141 and RU-142) were declared inoperable due to intermittent spiking on the low range monitor.
At approximately 0630 MST on December 6, 1988, with Palo Verde Unit 2 in Mode 1 (POWER OPERATION) at approximately    100 percent power, the Condenser Vacuum-Pump/Gland Seal Exhaust low and high range monitors (RU-141 and RU-142) were declared inoperable due to intermittent spiking on the low range monitor.
At approximately 0700 HST on December 6, 1988 the Plant Vent Monitor (RU-143 and RU-144) were also declared inoperable due to intermittent spiking on the low range monitor.
At approximately 0700 HST on December 6, 1988 the Plant Vent Monitor (RU-143 and RU-144) were also declared inoperable due to intermittent spiking on the low range monitor.

Latest revision as of 04:19, 4 February 2020

Special Rept 2-SR-88-009:on 881206,condenser Vacuum Pump/ Gland Seal Exhaust Low & High Range Monitors Declared Inoperable Due to Intermittent Spiking on Low Range Monitor. Monitors Left Inoperable for Troubleshooting of Problem
ML17304A867
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 01/09/1989
From: Haynes J
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00441-JGH, 192-441-JGH, 2-SR-88-009, 2-SR-88-9, NUDOCS 8901170430
Download: ML17304A867 (8)


Text

ACCELERATED DISI'RIBUTION DEMONSTRATION SYSI'Eg REGULRT( INFORMATION DISTRIBUTIOSTEM ('RIDE)

ACCESSION NBR:8901170430 DOC.DATE: 89/Ol/09 FACIL:STN-50-529 Palo. Verde Nuclear Station, Unit 2, Arizona Publi NOTARIZED: NO'OCKET g 05000529 AUTH. NAME AUTHOR AFFILIATION HAYNES,J.G. Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME'ECIPIENT AFFILIATION Document Control Branch (,Document Control Desk)

SUBJECT:

Special Rept 2-SR-88-009:on 881206,condenser vacuum pump/gland seal exhaust monitors declared inoperable.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR I ENCL I SIZE:

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

r NOTES:Standardized plant. 05000529 h

RECIPIENT ID CODE/NAME PD5 LA COPIES .

LTTR ENCL 1 1

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II Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00441-JGH/TDS/RJR January 9, 1989 U. 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-88-009 File: 89-020-404 Attached please find Special Report 2-SR-88-009 prepared and submitted pursuant to Technical Specifications 3.3.3.8 and 6.9.2. This report discusses the inoperability of RU-142 and RU-144.

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

Very tr y yours, J. G. Haynes Vice President Nuclear Production JGH/TDS/RJR/kj Attachment cc; D. B. Karner (all w/attachments)

E. E. Van. Brunt, Jr.

J. B. Hartin T. J. Polich H. J. Davis A. C. Gehr INPO Records Center 8~011704gp 8eoipe 85000529 o

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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 2-SR-88-009 This Special Report is submitted in accordance with Technical Specifications 3.3.3.8 ACTION 42(b) and 6.9.2 for an event in which the Condenser Vacuum Pump/Gland Seal Exhaust High Range Effluent Monitor (RU-142) and Plant Vent High Range Effluent Monitor (RU-144) 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 />. 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 0700 HST and 0630 HST respectively on December 9, 1988.

At approximately 0630 MST on December 6, 1988, with Palo Verde Unit 2 in Mode 1 (POWER OPERATION) at approximately 100 percent power, the Condenser Vacuum-Pump/Gland Seal Exhaust low and high range monitors (RU-141 and RU-142) were declared inoperable due to intermittent spiking on the low range monitor.

At approximately 0700 HST on December 6, 1988 the Plant Vent Monitor (RU-143 and RU-144) were also declared inoperable due to intermittent spiking on the low range monitor.

In each case the monitors work as a pair with RU-141 and RU-143 as the low range monitors and RU-142 and RU-144 as the high range monitors. Normal configuration consists of the low range monitors operating with the high range monitors in standby. When the low range monitors reach their maximum range, the high range starts and the low range detector and electronics are isolated. The high range monitors are provided for tracking radioactive effluents during postulated accident scenarios. The high range monitors must be declared inoperable when the low range monitors are inoperable.

Pursuant to Technical Specification 3.3.3.8 ACTION 37, the Preplanned Alternate -Sampling Program (PASP) was initiated at approximately 0712 HST and 0645 respectively on December 6, 1988. Implementation of the PASP will continue until the radiation monitoring units are returned to service.

The term "spiking" as used in this report is defined as an apparent rise in current level which is causing the radiation level to appear to increase although no actual rise in radiation exists.

ANPP has. been experiencing these spikes since licensing of the units. In each case previously, act'ions were taken to troubleshoot and correct the problems as they occurred. Additionally, overall recommendations were made and plant changes instituted on the basis of the spiking being caused by a grounding problem. When incorporated into the units, these plant changes have not fully resolved the spiking problem.

On December. 6, 1988, a decision was made to leave RU-141 and RU-143 inoperable in Unit 2 for troubleshooting to determine and correct the root cause. The troubleshooting efforts to date have been directed at determining the initiating cause of the spiking by modifying the noble gas detector in RU-143. This has been accomplished by:

Special Report 2-SR-88-009 Page 2 I) Supplyi'ng control power from a source independent of the other detectors.

2) Isolating any cabling common with the other detectors.

This action is being done with the objective of localizing the initiating event. To date this effort has not been effective in determining the cause.

Due to the-recurring nature of this problem, ANPP expects to continue its troubleshooting in an effort to. locate and correct the cause. =Additionally, when the cause is corrected, ANPP will evaluate the corrective action to improve reliability in the Unit I and Unit 3 monitors.

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