ML17300B182
| ML17300B182 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/25/1988 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 192-00339-JGH-T, 192-339-JGH-T, 3-SR-87-006, 3-SR-87-6, NUDOCS 8802030004 | |
| Download: ML17300B182 (6) | |
Text
REGULA Y INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR: 8802030004 DOC. DATE: 88/01/25 NOTARIZED:
NO DOCKET
)
FACIL STN 50 530 Palo Verde Nuclear Station>
Unit 3> Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION HAYNES> J. G.
- rizona Nuclear Power Prospect
( formerly *rizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk>
SUBJECT:
Special Rept 3-SR-87-006: on 880117> loose-part instrumentation for more than 30 days. Calibr mill be performed by end of first outage. Periodic audio check eil l be performed unti 1 ins trument operable.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED: LTR I
ENCL Q SIZE:
TITLE:
- 50. 73 Licensee Event Report (LER)
> Incident Rpt>
etc.
NOTES: Standardized plant.
05000530 REC IP IENT ID CODE/NAME PD5 LA LIC ITR*> E COPIES LTTR ENCL 1
1 1
RECIPIENT ID CODE/NAME PD5 PD DAVIS> M CQP IES LTTR ENCL 1
1 1
1 INTERNAL:
ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB
- RM/DCTS/DAB NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB N
SIB REG FIL 02
/EIB RGN5 FILE 01 EXTERNAL:
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1 1
2 2
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1 1
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1 1
1 1
1 1
1 5
5 1
1 1
ACRS MOELLER AEOD/DSP/N*S AEOD/DSP/TPAB DEDRO NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/ ILRB RES TELFORD> J RES/DRPS DIR FORD BLDG HOY> A LPDR NSIC HARRIS, J 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
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1 1
1 1
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1 1
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1 1
1 NOTES:
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 48 ENCL 47
Artzona Nuclear Power Project P.O. BOX 52034
~
PHOENIX. ARIZONA85072-2034 192-00339-JGH/TDS/ JEM January 25, 1988 U.S. Nuclear Regulatory Commission NRC Document Control Desk Washington, 0.C.
20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVHGS)
Unit 3 Docket No.
STN 50-530 (License No. NPF-74)
Special Report 3-SR-87-006 File:
88-020-404 Attached please find Special Report 3-SR-87-006 prepared and submitted pursuant to Technical Specification 3.3.3.7.
Action Statement "a" and 6.9.2.
This report discusses the Loose-Part Detection Instrumentation being inoperable greater than 30 days.
If you have any questions, please contact T. D. Shriver, Compliance Manager at (602) 393-2521.
Very truly'yours, JGH/TDS/JEM/kj Attachment cc:
- 0. fl. DeMichele E. E.
Van Brunt, Jr.
J.
B. Martin J.
R. Ball E. A. Licitra A.
C.
Gehr INPO Records Center (al 1 w/a)
J.
G.
Haynes Vice President Nuclear Production 8802030004 880l25 PDR ADOCK 05000530 PDR
0 PALO VERDE NUCLEAR GENERATING STATION LOOSE-PART DETECTION INSTRUtlENTATION License No. NPF-74 Docket No. 50-530 Special Report No. 3-SR-87-006 This Special Report is being submitted pursuant to Technical Specification 3.3.3.7 ACTION "a" and Technical Specification 6.9.2.
This report addresses an event where the loose-part detection instrumentation was inoperab'le for more than 30 days.
The 30 day period for returning the system to an operable status was exceeded at approximately 0728 on January 17, 1988.
The loose-part detection instrumentation was originally declared inoperable pending the assimilation and evaluation of base line data.
The data was obtained during power ascension testing; however, the instrumentation has remained inoperable due to a high rate of spurious alarms.
The alarms have been verified, with a spectrum analyzer, to be spurious.
A site modification has been issued which requires modification of selected circuit cards.
The modifications are expected to reduce the spurious alarm rate.
Addtionally, ba some of the alarms are being cleared by adjusting the setpoints above th ckground noise.
Although this calibration technique is not considered a
e e
permanent corrective measure it will permit the indication of a dynamic change in the Reactor Coolant System.
Changes such as these may be indicative of a "loose part" and and alert the operators to take additional actions as necessary.
The instrumentation remains available for data collection.
In order to restore the loose-part detection instrumentation to an operable status the alarm circuitry must be calibrated from the installed sensors.
The sensors are located on reactor coolant piping and on the reactor vessel.
Therefore, the circuits cannot be calibrated while the unit is operating.
It is p lanned to have the loose-part detection instrumentation calibrated by the end of the first outage of sufficient duration which will permit the required access.
As a prudent measure the Shift Technical Advisors will periodically perform a
channel audio check until the instrumentation is returned to an operable status.
This check should detect noise changes in the Reactor Coolant System that may be indicative of a 'loose part.