ML20083G786
| ML20083G786 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/28/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-28301-BSK, DER-83-33, NUDOCS 8401040344 | |
| Download: ML20083G786 (5) | |
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ftECEiVED tCC Arizona Public Service Company P.o. BOX 21666 e PH X. ARIZO.yA 85036 EC -9 L9 D 59 November 28, 1983 ANPP-28301-BSK/KCP REW,*i'lls c U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Atter. tion: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs
Subject:
Final Report - Revision 1 - DER 83-33 A 50.55(e) Reportable Condition Relating to CE AKR-50 Breakers with EC-1 Trips May Have A Generic Defect Which Could Cause A Malfunction File: 83-019-026; D.4.33.2 Ref erence: A) Telephone Conversation between T. Young and R. Tucker on May 25, 1983 B) ANPP-24170, dated June 24,1983 (Final Report)
Dear Sir:
Enclosed is revision one of the subject Deficiency Evaluation Report under the requirements of 10CFR50.55(e). This revision lists the specific.nonconformance reports and breakers included in the corrective action plan.
Very truly your k
q c \\r d. \\
CUL.L
%R E. E. Van Brunt, Jr.
APS Vice President, Nuclear Projects Management ANPP Project Director EEVB/KCP:ru Attachment.
cc: See Page Two 8401040344 831128 gDRADOCK 05000530 PDR h t? ' 7 \\
c' Mr. *f. W. Bishop DER 83-33 Page Two
-cc:
Richard DeYoung, Director
. Office of Inspection and -Enforcement U. S.-Nuclear Regulatory Commission Washingt'on, D.'C..20555 T. G. Woods,~Jr.
G.~C. Andognini-J. A. Roedel
. D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide-J. Vorees J. R. Bynum D. D. Green
~P.
P..Klute A. C. Gehr
.W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500
. Atlanta, GA 30339
~ FINAL REPORT - REVISION 1 - DER 83-33
PVNGS UNIT 3 I,-
' Description of Deficiency As. documented by APS Memo ANPM-16183-JTB/SLK dated, 4-29-83 (Attachment 1 - See Reference (B)), General Electric (GE) notified
. APS of a generic defect ~in GE model AKR-50 circuit breakers with an' EC-1. trip device' which could prevent proper operation of the tripping device.. GE had previously notified the Nuclear Regulatory Commission of this defect per GE to NRC letter, dated 6-15-82 (Attachment. 2 - See Reference (B)). -. Attachment 2 also identifies
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two additional defects in their model AKR-30 and-AKR-50 circuit breakers. APS was. notified.of these two additional defects per GE Service ' advice 175-CPD 9.11, as indicated in APS Memo
- ANPM-16317-JTB/SLK dated, 5-18-83 ( Attachment 3 - See Reference B).
1.
Failure of AKR-30 and AKR-50 low voltage' power circuit -
breakers to close upon command due to failure of an
' incompletely hardened steel part in the breaker operator.
2.
Failure of. AKE-30 and AKR-50 low voltage power circuit breakers to close upon: command due to failure of the molded case of a switch in the breaker closing circuitry. The failure is caused by improper curing of the molded case which encloses the switch mechanism.
. 3.
Spurious tripping the EC-1 trip device on the AKR-50 low hk
. voltage power circuit breakers due to failure of ground break relay components.
The failure is caused.by a manufacturing defect in the silicon ' controlled rectifier used in the ground break relay.
The subject breakers are used in.the following equipment for each unit at PVNGS:
Reference Bechtel
- B reaker '
Equipment Breaker Number Drawing (s)
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AKR-50 Class IE Battery Breaker PKA-M4102 13-E-PKA-002 AKR-50 Class IE Battery Breaker PKB-M4202 13-E-PKA-005 AKR-50 Class IE Battery Breaker PKC-M4302 13-E-PKA-004 L
^ LAKR-50 Class IE Battery Breaker PKD-M4402 13-E-PKA-007 i
AKR-30
. Class Reactor Trip Switch TCB-1 and 13-E-SBB-001 and
.AKR-30 circuit Breakers TCB-2 N001-13.03-166-1 i
1.
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T.W. Bishop.
Final Report (Rev. 1)
-Page 2 II.
Analysis of' Safety Implications-
'l.
Defects 1 and 2 The first and second defects described in " Condition Description" (an incompletely hardened steel part in the breaker operator and an-improperly cured molded switch mechanism case, respectively) each result in a failure of the circuit breaker ( AKR-30 and AKR-50) to close upon command.
For the-Class lE battery circuit breakers (model WKR-50), FSAR
-Technical Specification 16.3/4.8.2.3 (DC Distribution-Operating) requires all-four Class-IE battery banks to.be energized and operable (i.e., capable of performing its design function) for plant. operation. Should.
the Class-IE battery breakers fail to close in preparation-for
~
startup, the technical specification would not be met, precluding the plant from starting up.
During plant operatio'n, these breakers are normally closed and are not operated.
For the reactor trip switchgear circuit breakers (model AKR-30), these circuit breakers must be closed -before control rods can be withdrawn and the plant operated. These breakers
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are only opened af ter the control rods have been inserted and the reactor is being shut down.
Since these two defects, if lef t uncorrected, would not adversely affect the safety of operations of the plant during the lifetime of the plant, they are evaluated as not reportable under. the requirements of 10CER50.55(e).
Defect 3
-The ' third defect described in " Condition Description" (a manufacturing defect in the silicon controlled rectifier used in the ground break relay) could result in spurious tripping A
of the EC-1 tripping device on the circuit breaker. This Qt defect, which exists in the model AKR-50 breakers, could result in a loss of a Class IE battery, which provides a backup source of power for the Class IE 125V DC power system.
This condition is evaluated as reportable under the requirements of 10CFR50.55(e) since, if lef t uncorrected, the
. operation of the safety-related 125V DC system could be impaired and the deficiency represents a significant deviation from performance specifications.
E 6-T. W. Bishop Final Report (Rev. 1)
DER 83-33 Page Three III. Corrective Action Bechtel Construction will use the nonconformance report system
- to
. have the three identified breaker defects corrected prior to fuel load in each unit. The process of sequentially repairing the breakers at GE and at the jobsite is outlined in Attachment 3 (See Reference (B)).
The PVNCS Project also considers " Defect 3' to be reportable under the requirements of 10CFR Part 21.
As indicated by Attachments 2 and 4 (See Reference (B)), GE has notified the NRC of this defect and thic report therefore satisfies all project reporting requirments.
A copy of this report will be transmited to the Bechtel Construction Manager to assure that the corrective action plan is properly coordinated.
Unit 1 Unit 2 Unit 3 NCR NO.
Brk. No.
NCR No.
Brk. No.
NCR No.
Brk. No SE-2182 M41 through SE-1974 M41 EJ-2905 M41 M44 SE-1933 M42 M42 SE-2272 E01B SE-2270 M43 M43 SBA M44 M44 SBB E01B ZT-3082 E01B AC03 EJ-3081 AC03 BCO3 BC03 Spare Breakers NCR No.
Qty.
EJ-2906 2
SE-2271 3
1