ML20128B383
| ML20128B383 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/14/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-85, REF-PT21-85-296-000 ANPP-32831-TDS, DER-85-14, PT21-85-296, PT21-85-296-000, NUDOCS 8507030214 | |
| Download: ML20128B383 (3) | |
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- e' RECBVED ltRC Arizona Nuclear Power Pro e t P O DOx 02034 e PHOENIX. ARIZONA 85072-i REGONVitA June 14, 1985 ANPP-32831-TDS/PJC l
l U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 l
At te.nt ion :
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
Subject:
Final Report - DER 85-14 A 50.55(e) Reportable Condition Relating to Low Lube Oil Trip of Emergency Diesel Generators File:
85-019-026; D.4.33.2
Reference:
A) Telephone Conversation between L. E. Miller and P. Coffin on April 8, 1985 B) ANPP-32532, dated May 1, 1985 (Interim Report)
Dear Sir:
Attached is our final written report of the Reportable Deficiency under 10CFR 50.55(e), referenced above. The 10CFR 21 Evaluation is also included.
i Very truly yours, CE C L 9L E. E. Van Brunt Executive Vice President Project Director EEVB/PJC/jb Attachment cc: See Page Two l
l 8507030214 850614 PDR ADOCK 05000528 S
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ANPP-32831-TDS/h,KC Mr. D. F. Kirsch DER 85-14
- Page Two l
cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 D. B. Karner
'W.
E. Ide D. B. Fasnacht A. C. Rogers L. A. Souza D. E. Fowler T. D. Shriver C. N. Russo B. S. Kaplan J. R. Bynum J. M. Allen D.~Canady A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher H. D. Foster D. R. Hawkinson R. P. Zimmerman M. L. Clyde B. T.. Parker T. J. Bloom D. N. Stover l
J. D. Houchen J. E. Kirby Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, CA 30339 l
l i
FINAL REPORT - DER 85-14 DEFICIENCY EVALUATION 50.55(e)
ARIZONA NUCLEAR POWER PROJECT (ANPP)
PVNGS UNITS 1, 2, 3 I.
Description of Deficiency During pre-operational review, it was discovered that with the diesel generator in the emergency mode, one out of two independent low oil pressure signals will trip the diesel generator output breaker.
This is not in accordance with the FSAR Section 8.3.1.1.4.3 commitment, which states the low lube oil pressure trips are one out of two taken twice.
Furthermore, it violates paragraph B.3 of NRC Branch Technical Position ICSB 17 (PSB), which states that for diesel generator protective trips, other than engine overspeed and generator differential, coincident logic is required.
Evaluation With a single failure of an oil pressure sensor, this condition can result in a loss of an emergency diesel generator.
The root cause of this deficiency is determined to be an incorrect connection of the four low lube oil pressure contacts as depicted on the Bechtel design drawing. This is considered an isolated design error attributable to oversight since the requirement to provide this logic is unique to the diesel generator low lube oil trip circuitry.
II.
Analysis of Safety Implications Based on the above analysis, this condition is evaluated as reportable under 10CFR 21 and 10CFR50.55(e).
If this condition were to remain uncorrected, it would represent a significant safety condition.
III. Corrective Action DCP's 10E-DG-047, 2SE-DG-047 and 3CE-DG-047 were issued to revise design drawings and to rewire the four diesel generator low lube oil trip contacts as one out of two taken twice. Unit I diesel generators have been rewired.
Unit 2 and 3 dicacis will be completed prior to Mode 6.
IV.
References A)
FSAR Section 8.3.1.1.4.3 B) NRC Brach Technical Position ICSB 17 (PSB) Diesel Generator Protective Trip Circuit Bypasses C)
DCP's 10E-DG-047, 2SE-DG-047 and 3CE-DG-047 D) NCR SE-5658 E)
Drawing 13-10407-MM018-151 F)
Drawing 13-E-PEB-001