ML20214M556
| ML20214M556 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/27/1986 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-38019-JGH, DER-86-25, NUDOCS 8609110170 | |
| Download: ML20214M556 (4) | |
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_b Arizona Nuclear Power Project V
P O BOX 52034 e PHOENIX, ARIZONA 85072-2034 f,, //
August 27, 1986 ANPP-38019-JGH/LAS/DRL-92 fg U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Project Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. 50/530
Subject:
Interim Report - DER 86-25 A 50.55(e) Potentially Reportable Deficiency Relating To Containment Radiation Monitor RU-l File: 86-006-216; D.4.33.2
Reference:
(A) Telephone Conversation between R.
C. Sorenson and D. R.
Larkin on July 25,1986 (Initial Notification - DER 86-25)
(B) Telephone Conversation between R. C. Sorenson and D. R.
Larkin on July 29, 1986.
(Update to Initial Notification -
Dear Sir:
The NRC was notified of a potentially reportable deficiency in the ref-erenced telephone conversation.
At that time, it was estimated that a determination of reportability would be made within thirty (30) days.
(August 28, 1986)
Due to the extensive investigation and evaluation required, an Interim Report is attached.
It is now expected that this information will be finalized by November 3, 1986, at which time a complete report will be submitted.
Very truly yours, f
J. G. Hayhes Vice President Nuclear Production JGil/DRL:jle Attachment 8609110170 860827 cc: See Page Two PDR ADOCK 05000530 S
DER 86 Interim Report Hr. D. F. Kirsch Acting Director Page Two August 27, 1986 ANPP-38019-JGH/LAS/DRL-92.11 cc:
J. M. Taylor Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A. C. Gehr (4141)
R. P. Zinumerman (6295)
Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 1
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INTERIM REPORT - DER 86-25 POTENTIAL REPORTABLE DEFICIENCY ARIZONA NUCLEAR POWER PROJECT PVNGS UNIT 3 I.
Potential Problem Radiation monitor RU-l is required per PVNGS FSAR Section 5.2.5.1 and Technical Specification Section 3.4.5.1 to provide reactor coolant 4
pressure boundary (RCPB) leakage detection via containment atmosphere particulate and gaseous monitoring.
These methods of leakage detection are two of three methods PVNGS uses to meet the criteria of Regulatory Guide 1.45.
The other method is the sump level method.
All three methods are to be operable in Modes l' 2, 3 and 4 It was discovered that incorrect conversion factors were being used with the containment atmosphere particulate radiation monitor. The use of incorrect conversion factors caused erroneous radioactivity concentration readings, which affected the ability of the radiation monitor to function properly at its alarm setpoints.
i II.
Approach To and Status of Proposed Resolution Initial investigations indicate that an electronically programmable read only memory (EPROM) silicon chip with a different program was installed which required the use of different, manually entered, conversion factors. The use of incorrect conversion factors caused the containment atmosphere monitor to indicate incorrect containment particulate radioactivity levels which affected the monitors ability to detect reactor coolant leakage.
The problem resolution plan includes:
1.
Review of the methodology to procure, change hardware and associated i
software, including system validation and verification, with changes to identify root cause and appropriate corrective action.
i 2.
Development of a new calculation to verify the gas and particulate monitor's capability to detect a one GPM leak rate within one hour, as committed to by the FSAR snd demonstrated in the interim response to EER 86-SQ-ll7.
The parameters to be considered are:
Current RC Leak Rate, RCS Radioactivity Level, Reactor Power Level Stability, Current Radioactivity in the Containment.
3.
After the root causes are identified, applicability of the deficiencies to safety-related radiation monitors and other computer based systems will be investigated.
Corrective actions and reportability under 10CFR Parts 21 and 50.55(e) will be addressed.
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e As reported in LER 86-46, the correct conversion factors are now being used in the radiation monitors.
This allows continued safe operation of Units 1 and 2.
III. Projected Completion of Corrective Action and Submittal of the Final Report The complete evaluation and final report are forecast for November 3, 1986.
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