ML17300A751
| ML17300A751 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/01/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 1-SR-87-013, 1-SR-87-13, 192-00185-JGH-T, 192-185-JGH-T, NUDOCS 8704200317 | |
| Download: ML17300A751 (6) | |
Text
REGULATO FORMATION DISTRIBUTION M (R IDS)
ACCESSION NBR: 8704200317 DOC. D*TE: 87/00/0}
NOTARIZED:
NO DOCKET FAC IL STN50528 Palo Verde Nuclear Station>
Unit
- 1. Arizona Pub li 05000528 AUTH. NAME AUTHOR AFFILIATIOIN HAYNES'. G.
Arizona Nuclear Pouer Prospect (former lg *rizona Public Serv RECIP. NAME RECIPIENT AFFILIATION MARTINpJ. B.
Reg i on 5> Office of Director
SUBJECT:
RO 1-SR-87-013: on 870130 fuel bldg vent ilati on sos high range monitor RU-145 was declared inoperable while in Mode
- 5. On 870304 monitor RU-}46 uas declared
=inoperable while in Mode
- 3. No caused identifi ed.
DIBTRIBUTION CODE:
IEOID COPIEB RECEIVED: LTR I
ENCL t
BIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: Standardized plant. M. Davis> NRR: }Cg.
05000528 REC IP IENT ID CODE/NAME PD5 LA LICITRA.E INTERNAL: ACRS DEDRO NRR ROE M. L NRR/DOE* DIR NRR/DREP/RPB
/ILRB EQ Fi RGN5 FILE 01 EXTERNAL:
LPDR NSIC NOTES:
COPIES LTTR ENCL 1
0 1
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RECIPIENT ID CODE/NAI'IE PD5 PD DAVIS. M AEOD EINF LIEBERM*N NRR/ADT NRR/DREP/EPB I'HR/DRIS DIR CGC/HDSl RES SPEISi T I'.RC PDR COP IES LTTR ENCL 1
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'1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25 ENCL 24
Arizona Nuclear Power Project P.o, BOX 52034
~
PHOENIX, ARIZONA85072-2034 192-00185-JGH/TRB/TJB April 1, 1987
-Mr. John B, Martin, Regional Administrator Office of Inspection and Enforcement U.S.
Nuclear Regulatory Commission Region V
1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368
Subject:
Palo Verde Nuclear Generating Station Unit 1
Docket No.
STN 50-528 (License NPF-41)
Special Report 1-SR-87-013 File:
87-020-404
Dear Mr. Martin:
Attached. please find a Special Report 1-SR-87-013 prepared and submitted pursuant to Technical Specifications 3.3.3.9 and 6.9.2.
This report discusses the inoperability of the Fuel Building Radiation Monitor for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Tf you have any questions, please contact Tom Bradish, Compliance Supervisor at (602) 932-5300, Ext. 6936.
Very'truly yours, J.
G.
Hay es Vice President Nuclear Production JGH/TRB/TJB/cld Attachment cc:
0.
M. DeMichele E. E.
Van Brunt, Jr.
R.
P.
Zimmerman R.
C. Sorenson E.
A. Licitra A. C. Gehr lNPO Records Center (all w/a) g 05000528 i7 870401 FIDR ADOC 8
l
PALO VERDE NUCLEAR GENERATING STATION Special Report 1-SR-87-013 RADIATION MONITORING UNIT NOT RESTORED WITHIN 72 HOURS Docket No.
STN 50-528 License No.
NPF-41 This special report is required by Palo Verde Unit 1 Technical Specifications 3.3.3.9, Table 3.3-13, ACTION 42-b and 6.9.2 for a Radiation Monitor which 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 Fuel Building Ventilation System High Range Monitor (RU-146) was initially declared inoperable as 'a result of the Fuel Building Ventilation System Low Range Monitor (RU-145) being declared inoperable.
RU-145 was declared inoperable due to alarms which were verified to be spurious by subsequent sampling.
Since RU-145 supplies sample flow to RU-146, the malfunction of RU-145 caused RU-146 to be declared inoperable.
RU-145 was declared inoperable at 1617 MST on January 30, 1987 with Palo Verde Unit 1 in Mode 5 (COLD SHUTDOWN).
However, Technical Specification Table 3.3-13 does not require that RU-145/RU-146 be operable until Mode 4 (HOT SHUTDOWN) which was entered at 1604 on March 1, 1987 following the recent outage.
At 1604 on March 4,
- 1987, Palo Verde Unit 1 was in Mode 3 (HOT STANDBY) when RU-146 had been inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The Pre-Planned Alternate Sampling Program was initiated as an interim compensatory measure as required by Technical Specification Table 3.3-13, Action 42-A.
This measure included the utilization of a portabl>> area radiation monitor.
Engineering personnel conducted troubleshooting of RU-145, in accordance with approved work documents, to determine the cause of the spurious alarms.
No root cause could be identified.
RU-145 has been monitored since entering Mode 4 and has been observed to be operating satisfactorily.
Following successful completion of the appropriate Surveillance Testing, both monitors were returned to service on March 30, 1987.
Should RU-145 exhibit similar problems, further troubleshooting will be conducted to try and determine a root cause.
~le J
I I
I II