ML17305A318
| ML17305A318 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/17/1989 |
| From: | James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 192-00537-JML-T, 192-537-JML-T, 3-SR-89-007, 3-SR-89-7, NUDOCS 8910260245 | |
| Download: ML17305A318 (9) | |
Text
SUBJECT:
Special rept 3-5R-89-007:on 890930,radiation monitoring unit inoperable for greater than 72 h.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED:LTR + ENCL +
SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER),~IncidenMRpt, etc.
D 05000530 S
N6TES:Standardized plant.
'l
.ACCELZRATED DJS1EUTJON DEMONSTRON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) j'CCESSION NBR:8910260245 DOC.DATE: 89/10/17 NOTARIZED:
NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION LEVINE,J.M.
Arizona Public Service Co. (formerly Arizona Nuclear Pover RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
RECIPIENT ID CODE/NAME PD5 LA DAVISiM.
INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/iCSB 7
NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DS IR/EIB COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 RRp/~~PB 10 REG ~
02 RGN5 FILE 01 COPIES LTTR ENCL 1
1 2
2 1
l.-
2 2
1 1
1
. 1 1
1 1
1 1
1 2
2 1
1 1
1
/
h EXTERNAL: EG&G WILLIAMSiS 4
LPDR 1
NSIC MAYS,G NUDOCS FULL TXT 1
NOTES:
4 L ST LOBBY WARD 1
NRC PDR 1
NSIC MURPHYgG.A 1
1 1
1 1
1 1
1 1
h TOTAL NUMBER OF COPIES REQUIRED:
LTTR 39 ENCL 39
t
'I
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P 0 BOX 52034
~
PHOENIX, ARIZONA85072.2034 192-00537-JML/TDS/DAJ October 17, 1989 U. S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C.
20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station Unit 3 Docket No.
STN 50-530 (License NPF-74)
Special Report 3-SR-89-007 File:
89-020-404 Attached please find Special Report 3-SR-89-007 prepared and submitted pursuant to Technical Specification 3.3.3.8 and 6.9.2.
This report discusses the inoperability of a radioactive gaseous effluent monitor.
If you have any questions, please contact T.
D. Shriver, Compliance Manager at (602) 393-2521.
Very truly yours, JGH/TDS/DAJ/kj Attachment H.
L vine ice President Nuclear Production cc:
.W. F.
Conway J.
B. Hartin E.
E.
Van Brunt, Jr.
T. J. Polich M. J.
Davis A. C.
Gehr INPO Records Center (all w/a) 891026op45 EI91017 PDA ADOCV, 05Q S
j
PALO VERDE NUCLEAR GENERATING STATION Radiation Monitoring Unit Inoperable for Greater Than 72 Hours License No.
NPF=74 Docket No.
STN 50-530 Special Report 3-SR-88-007 DESCRIPTION OF WHAT OCCURRED:
A.
Initial Conditions:
B.
C.
At approximately 2138 MST on September 30,
- 1989, Palo Verde Unit 3 was in Mode 5
(COLD SHUTDOWN) during a refueling outage.
Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):
Event Classification:
Special Report required pursuant to Technical Specification 3.3.3.8 ACTION 42 P
This Special Report is being submitted pursuant to Technical Specification 3.3.3.8 ACTION 42b and Technical Specification 6.9.2 to report a condition wherein the Plant Vent System Radioactive Gaseous Effluent High Range Monitor (RU-144) 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 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> interval for returning the monitor to service elapsed at approximately 2138 MST on September 30) 1989.
At approximately 2138 MST on September 27,
- 1989, RU-144 was removed from service in order to implement an approved design modification and install new software in order to enhance the monitor's performance.
Pursuant to Technical Specification 3.3.3 '
ACTION
- 42a, the Preplanned Alternate Sampling Program was initiated to monitor the Plant Vent System effluent as needed.
Following the installation of the design and software
- changes, RU-144 was returned to service at ap'proximately 1955 MST on October 3, 1989.
RU-144 was out 'of service approximately six (6) days.
Status of structures,
- systems, or components that were inoperable at the start of the event that contributed to the event:
Other than RU-144 being out of service as described in Section I.B, no structures,
- systems, or components were inoperable which-contributed to this event.
Special Report 3-SR-89-007 Page 2
D.
Cause of each component or system failure, if known:
Not applicable - no component or system failures were involved.
E.
Failure mode, mechanism, and effect of each 'failed component, if known:
Not applicable - no component failures were involved.
F For failaras,of components with multiple functions, list of systems or secondary functions that were also affected:
Not applicable
- no component failures were involved.
G.
For failures that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the
-train was returned to service:
Not applicaMe - no'failures
-were involved.
H.
Method of discovery of each component or system failure or procedural error:
Not applicable
- there were no component or system failures or
.procedural errors.
I.
Cause of Event:
As described in Section I.B, 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 /> in order, to implement design,and software changes needed to improve the performance of the monitor.
J.
Safety System
Response
Not applicable - no safety system responses occurred and.none were necessary.
K.
Failed Component Information:
Not app1icable
- no component failures occurred.
II.
ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
There were no safety consequences or implications resulting from. this event.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous ef53uents.
There.are two.separate radioactive gaseous effluent monitoring systems:
the low range effluent monitors for normal plant
))
Special Report 3-SR-89-007 Page 3
radioactive gaseous effluents ahd the high range effluent monitors for post-accident plant radioactive gaseous effluents.
The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions.
The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the'low range monitors.
There were no accident conditions requiring the operation of RU-144.
If an accident had occurred alternative sampling capability existed and was implemented as described in the Preplanned Alternate Sampling Program.
III.
CORRECTIVE ACTIONS:
Not applicable
- no corrective actions are necessary.
'I l