ML17305B009
| ML17305B009 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 08/16/1990 |
| From: | James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 192-00695-JML-T, 192-695-JML-T, 2-SR-90-005, 2-SR-90-5, NUDOCS 9008240199 | |
| Download: ML17305B009 (8) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM 1
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LTR ENCL SIZE:
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50.73/50.9 Licensee Event Report (It S
05000529
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NOTES:Standardized plant.
ACCESSION NBR:9008240199 DOC.DATE: 90/08/16 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 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 2-SR-90-005:on 90071~9,post accident sampling operable greater than 7 day RECIPIENT
,ID CODE/NAME PD5 LA PETERSON,S.
INTERNAL ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 iIRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL:
EGGG BRYCEIJ.H LPDR NSIC MAYS,G NUDOCS FULL TXT NOTES:
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RECIPIENT ID CODE/NAME PD5 PD TRAMMELL,C.
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NOTE TO ALL"RIDS" RECIPIENTS:
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PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOiVI P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROMi DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 36 ENCL 36
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JAMES M. LEVINE VICE PRESIDENT NUCLEAR PRODUCTION Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034
~
PHOENIX. ARIZONA85072-2034 192-00685-JML/TRB/SBJ August 16, 1990 U.
S. Nuclear Regulatory Commission Attention:
Document Control Desk Mail Station Pl-37 Washi'ngton, DC 20555
Dear Sirs:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No.
STN 50-529 (License No. NPF-51)
Special Report 2-SR-90-005 File 90-020-404 Attached please find Special Report 2-SR-90-005 prepared and submitted pursuant to Technical Specifications 3.3.3.8 ACTION 42(b) and 6.9.2.
This report discusses a radiation monitor being inoperable for greater than 72'ours.
")I, If you have any questions, please contact T. R. Bradish, Compliance Manager at (602) 393-2521.
Very truly yours yP~
JML/TRB/SBJ/dmn Attachment (all with attachment) cc:
W. F.
Conway J
~ B. Martin D.
H.
Coe CD M. Trammell A. C. Gehr A. H. Gutterman IMPO Records Center 900S240199 900S16 PDR ADOCK 05000
'9 S
PALO VERDE NUCLEAR GENERATING STATION UNIT 2 Post Accident Sampling System Inoperable Greater Than 7 Days License No. NPF-51 Docket No. 50-529 Special Report 2-SR-90-005 Initial Conditions'n July 19, 1990 Palo Verde Unit 2 was in Mode 1
(POWER OPERATION) with the Reactor Coolant System (RCS) at normal operating temperature and normal operating pressure.
escr tion of Event This Special Report is being submitted pursuant to Technical Specification 3.3.3.8 ACTION 42b and Technical Specification 6.9.2 to report an event in which the Plant Vent System High Range Effluent Monitor (RU-144) was inoperable 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 /> period for returning the monitor to service was exceeded at approximately 0840 MST on July 19, 1990.
On July 16, 1990 at approximately 0840 MST, the Plant Vent System Low Range Effluent Monitor (RU-143) and High 'Range Effluent Monitor (RU-144) were taken out of service in order to perform scheduled surveillance testing which included the 18 month channel calibration.
The radiation monitors, RU-143 and RU-144, work as a pair.
- The low range effluent monitor is normally in service and continuously monitors the plant vent exhaust.
RU-144 is automatically started when RU-143 reaches a predetermined setpoint.
RU-144 is provided for tracking radioactive effluents during postulated accident scenarios.
The surveillance test was successfully completed on July 29,
- 1990, and RU-143 and RU-144 were returned to service at approximately 0815 MST.
Cause of Event'ecause of the length of the surveillance test procedure, the surveillance could not be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Previous performances of this surveillance test also required more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to complete but did not result in any Special Reports because the radiation monitors had been inoperable prior to the surveillance test performances P
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NRC Document Control Desk Page 2
Special Report 2-SR-90-005 Corrective Actions'he surveillance test was successfully completed and RU-143. and RU-144 declared operable on July 29, at approximately 0051 MST.
An evaluation is being performed to determine if the surveillance test can be streamlined.
If streamlining cannot r'educe the performance
- time, a revision to the Technical Specification ACTION requirement may be pursued.
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