ML17310A895

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Special rept:1-SR-93-008:on 940103,fuel Bldg Ventilation Sys High Range Radiation Monitor Inoperable for Period Greater than 72 Hours.Caused by Difficulties in Installing Mod 1-FJ-SQ-060
ML17310A895
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 01/03/1994
From: James M. Levine
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1-SR-93-008, 1-SR-93-8, 192-00870-JML-B, 192-870-JML-B, NUDOCS 9401120148
Download: ML17310A895 (6)


Text

ACCELERATED DISTRIBUTION DEMOb+RATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9401120148 DOC.DATE: 94/01/03 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 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) R

SUBJECT:

Special rept:1-SR-93-008:on 940103,fuel bldg ventilation sys high range radiation monitor inoperable for period greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Caused by diff'.culties in installing Mod 1-FJ-SQ-060. D TITLE: 50.73/50.9 Licensee Event Report (LER), J Incident Rpt, etc.

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

NOTES:STANDARDIZED PLANT 05000528 A

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDV LA 1 1 PDV PD 1 1 HOLIAN,B 1 1 TRAN,L 1 1 D

INTERNAL: ACRS 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB '1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRI L/RPEB 1 1 NRR/DRSS/PRPB 2 2 N~SSA SPLB 1 1 NRR/DSSA/SRXB 1 1

~RE 02 1 1 RES/DSIR/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EGGG BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 NRC PDR- 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE1"W 1 1 NUDOCS FULL TXT 1 1 A

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P,O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 JAMES M. LEVINE 192-00878-JML-BAG-R JR VICE PRESIDENT NUCLEAR PRODUCTION January 3, 1994 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-37 Washington, D.C. 20555

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528(License No. NPF-41)

Special Report 1-SR-93-008 File:,94-020-404 Enclosed please find Special Report 1-SR-93-008 prepared and submitted pursuant to the PVNGS Offsite Dose Calculation Manual requirements and Technical Specification 6.9.2. This report discusses the Fuel Building Ventilation System High Range Radiation Monitor being inoperable for a period greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Should you have any questions, please contact Burton A. Grabo, Supervisor, Nuclear Regulatory Affairs, at (602) 393-6492.

Sincerely, JML/BAG/RJR/rv Enclosure cc: W. F. Conway (all with enclosure)

B. A. Faulkenberry K. E. Johnston INPO Records Center 100058

'7401120148 940103 PDR ADOCK 05000528 S PDR

PALO VERDE NUCLEAR GENERATING STATION UNIT 1 Fuel Building Ventilation System High Range Radiation Monitor (RU-146) Inoperable License No. NPF-41 Docket No. 50-528 Special Report 1-SR-93-008 Initial Conditions

/

On December 16, 1993, Palo Verde Unit 1 was in Mode 1 (POWER OPERATION) operating at approximately 85 percent power with spent fuel stored in the Fuel Building (FB) fuel storage pool.

Descri tion of Event This special report is being submitted pursuant to the PVNGS Offsite Dose Calculation Manual (ODCM) and Technical Specification (TS) 6.9.2 to report an event in which the FB Ventilation System High Range Radiation Monitor (RU-146).was inoperable for a period 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 minimum number of high range radiation monitor channels to an OPERABLE condition was exceeded at approximately 0500 MST on December 16, 1993.

ODCM Section 2.1 requires that a high range radiation monitor with a minimum of one noble gas, iodine, and particulate sample channel, and one sample flow rate measuring device be OPERABLE during MODES 1, 2, 3, and 4, or when irradiated fuel is in the fuel storage pool RU-146 consists of a set of three particulate and iodine samplers and a

~

dual channel noble gas monitor along with the associated pumping and flow control system. This forms the high range portion of the FB exhaust discharge post accident monitoring required by NUREG-0737 and Regulatory Guide 1.97, Rev 2. The purpose of these monitors is to assess releases through FB Essential Ventilation Exhaust under post accident conditions.

NRC Document Control Desk Special Report 1-SR-93-008 Page 2 of 2 Cause of Event At approximately 0500 MST on December 13, 1993, RU-146 was removed from service for the installation of modification 1-FJ-SQ-060. Installation of modification 1-FJ-SQ-060 will allow operation of RU-146 when the Low Range Radiation Monitor, RU-145, is out of service. This modification includes a change in the sampling system arrangement, modification of computer software, and the modification, removal, and replacement of detectors and associated hardware. As a result of difficulties experienced in the installation of this modification, RU-146 was inoperable greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Corrective Action ODCM ACTIONS 41 and 42, "operate the Fuel Building Essential Ventilation System while moving irradiated fuel" and "initiate the preplanned alternate sampling program," were entered at approximately 0500 MST on December 13, 1993. Plant Modification LDCP 1-SJ-SQ-060 was completed and RU-146 was returned to service at approximately 0532 MST on December-18, 1993.