ML20202G519
| ML20202G519 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/25/1986 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-35655-EEVB, DER-86-06, DER-86-07, DER-86-6, DER-86-7, NUDOCS 8604140414 | |
| Download: ML20202G519 (7) | |
Text
e.
4 RECEIVED
.:sc Arizona Nuclear Power Project gg gf,g g
~,,! II' l 0 P o. box 52934 e PHOENIX, ARIZONA 85072-2034 March 25, 1986 ANPP-35655-EEVBJr/LA$fNLk9T.11 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 Projects Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. 50/530
Subject:
Interim Report - DER 86-06 and 86-07 A 50.55(e) Potentially Reportable Deficiency Relating To Inadequate Wiring Lug Terminations File:
86-006-216; 86-056-026; D.4.33.2
Reference:
Telephone Conversation Between R. C. Sorenson and D. R. Larkin on February 21, 1986 (Initial Reportability - DER's 86-06 and 86-07)
'1
Dear Sir:
The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.
(March 24, 1986)
Due to the duplication of information and reporting involved, DER 86-07 is being combined with and transferred to DER 86-06, as discussed with Mr. R.C.
Sorenson of your office. An Interim Report is attached and it is expected that this inforeation will be finalized by April 25, 1986, at which time a complete report will be suomitted.
Very tru y urs, k.k. CALL MC C
E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/DRL/sh Attachment (s) cc: See Page Two tseugiqu414 B60325 l,
DR ADOCK 05000530 l
PDR hnA) '
4 DER 86-06 and 86-07 Interim Report Mr. D. F. Kircsh Acting Director ANPP-35655-EEVBJr/LAS/DRL-92.1L March 25, 1986 Page 2 cc:
J. M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 A. C. Gehr (4141)
R. P. Zimmerman (6241)
Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 i
w
)
1 INTERIM REPORT - DER 86-06 and 86-07 POTENTIAL REPORTABLE DEFICIENCY ARIZONA NUCLEAR POWER PROJECT PVNGS UNIT 3 I.
Potential Proble,m During the NRC CAT Inspection conducted in February, 1986, several potential deficiencies were discovered with vendor wiring in the battery chargers (Power Conversion Products) and the diesel gener-ator control panels (Cooper Energy Services).
Special CIP 698.0 and SWA 6742 were initiated to inspect vendor wire termination attributes that could affect safety in battery chargers 3EPKAH11, 3EPKBH12, 3EPKCH13, 3EPKDH14, 3EPKAH15 and 3EPKBH16. Special CIP 696.0 was initiated to inspect wire termi-nation attributes that could affect safety in diesel generator control panels 3JD6AB01, B02, B03 and 3JDGB01, B02 and B03.
The results of the inspections are documented on the Special CIP.
Deficiencies are noted in the following:
NCR's EG-7196 EG-7561 EG-7388 EG-7387 EG-7576 EG-7593 EG-7375 EG-7372 EG-7349 SWA-6868 The types of deficiencies discovered, which could affect safety, include the following:
Wire extended past the end of the lug so that it a.
interfered with proper seating of the screwhead or washer.
b.
Terminals not securely attached, Nicked or cut conductor strands (control wire only).
c.
d.
Improperly crimped lugs.
e.
Loose pin connections.
f.
Improper size of lug.
g.
Lugs bent in excess of 90*.
h.
Improper solder termination.
l
~
Interim Report - DER 86-06 and 86-07 Page 2 1.
Relay missing spring fasteners or having springs not fastened.
- j. Insufficient separation between Class "Q" and non-Class "Q" cables.
k.
Broken or damaged lugs.
II.
Approach To and Status of Proposed Resolution A.
Malfunction of the battery chargers would result in degradation of the Class 1E DC system. The Class lE.DC system is critical to safe operation of the Plant. The deficiencies identified which could affect the battery chargers are as follows:
Item (a)
Wire extending past the end of the barrel may interfere with complete surface-to-surface contact between the lug and terminal. This could result in localized heating which could further deteriorate the connection and possibly cause an open circuit.
Item (b)
Loose terminations may not provide adequate contact between lug and terminal. This could also result in circuit malfunction.
Item (c)
Wire with nicked or cut conductor strands can break away from the lug during additional hand-ling caused by rework or maintenance on the panel. This would result in open circuit.
Item (d)
Improperly crimped lugs can result in damaged or loose terminations with the same conse-quences as discussed above.
Item (c)
Loose and improperly soldered pin connectionc can increase the electrical resistance of the circuit. This could affect the control signals and cause malfunction of the equipment.
B.
The deficiencies identified below could cause malfunction of the diesel generator control panels. Malfunction of the diesel generator control panels would result in loss of standby AC power which is critical to safe shutdown of the Plant.
- tem (a)
Wire extending past the end of the barrel may interfere with complete surface-to-surface contact between the lug and terminal. This could result in localized heating which could further deteriorate the connection and possibly cause an open circuit.
Interim Report - DER 86-06 and 86-07 Page 3 l
Item (b)
Loose terminations may not provide adequate contact between lug and terminal. This could also result in circuit malfunction.
Item (c)
Control wires with nicked or cut conductor strands can break away from the lug during additional handling caused by rework or maintenance on the panel. This would result in an open circuit.
Item (d)
Improperly crimped lugs can result in damaged or loose terminations with the same conse-quences as discussed above.
Item (e)
Loose pin connections can increase the electrical resistance of the circuit. This could affect the control signals and cause misoperation of i
the equipment.
1 Item (f)
Use of improper size of lug can result in damaged or loose terminations with the same consequences as discussed in Items (c) and (d) above.
Item (g)
Lugs bent in excess of 90* can result in break away from the conductor during additional hand-ling caused by rework or maintenance on the panel with the same consequences as discussed in Item (c) above.
Item (h)
Improper solder termination can increase the electrical resistance of the circuit. This could affect the control signals and cause misoperation of the equipment.
Item (1)
Relays missing spring fasteners or having springs not fastened do not meet seismic requirements.
Item (j)
The cable separation condition identified is l
between a non-Class IE wire bundle entering the I
top of diesel generator panel 3JDGBB01 and a Class 1E wire way. A minimum of 6" of separation is required.
Item (k)
Broken or damaged lugs or peeling cf a contact surface may not provide adequate contact between lug and terminal. This could result in circuit malfunction.
~
1 Int: rim R: port - DER 86-06 and 86-07 Page 4 III. Projected Completion of Corrective Action and Submittal of the Final Report A.
Unit 3 nonconforming items determined not acceptable for the battery chargers were reworked under NCR EJ-7372.
B.
Unit 3 nonconforming items determined to be unacceptable for the diesel generator control panels will be reworked under NCR's:
EG-7196 EG-7375 EG-7387.
EG-7388 EG-7349 EG-7593 EG-7576 EG-7561 All work will be completed prior to fuel load.
C.
Wiring deficiencies on other equipment were discovered during construction and startup of Units 1 and 2.
The appropriate corrective action for most deficiencies identified was ini-tiated in all three units. Attachment I lists the major pieces of equipment in which deficiencies were identified and appro-priate reinspection and rework completed. ANPP is evaluating potential effects on other safety-related electrical equipment.
The evaluation and Final Report are forecast to be completed by April 25, 1986.
Y
-Attachment 1 DER 86-06 and DER 86-07 The workmanship of vendor internal wiring has been investigated for the following equipment:
Equipment Supplier Reference a.
Diesel Generator Cabinets Cooper Energy DER 82-36 (4/0 power cables)
Service Unit 1 - NCR EG-2165 Unit 2 - NCR EG-2292 Unit 3 - reworked by vendor prior to shipment b.
Switchgear General Electric DER 82-41 Corp.
DCP's 10E, 20E, 30E-PB-018' c.
Main Control Board Comsip, Inc.
DER 82-43 DCP's 10J, 20J-RM-091 Unit 3 - Bechtel Supplier Quality and Comsip were informed of this condition to preclude
. deficiencies in Unit 3 prior to shipment.
d.
Chiller Control Panel Carrier Air DER 82-78 Conditioning Corp.
DCP's 10E, 20E, 30E-EC-024 e.
Loadcenter
~ Brown Boveri DER 82-44 Electric Co.
DCP's 10E, 20E. 30E-PG-016 f.
Auxiliary Relay Cabinet Harlo Corp.
DER 83-43 Unit 1 - NCR SE-1574 Unit 2 - NCR SE-3148 Unit 3 - NCR EA-3548 3
-_