ML20085H577
| ML20085H577 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/23/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, ANPP-27622-BSK, DER-83-31, NUDOCS 8309120135 | |
| Download: ML20085H577 (3) | |
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August 23, 1983 ANPP-27622 BSK/RQT U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94556-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projecta Branci'. 1
Subject:
Final Repost - DER 83-31 A 50.55(e) Reportable Condition Relating to Temperature Rise In Diesel Generator Control Cabinet Could Exceed Design Requirements File:
83-019-026; D.4.3 3.2
Reference:
A) Telephone Conversation between T. Young and R. Tucker on May 5, 1983 B) ANPP-23953, dated June 6,1983 (Interim Report)
Dear Sir:
Attached is our final written report of the Reportable Deficiency under 10CFR50.55(e), referenced above.
Very truly yours SR A Lt.-
E. E. Vaa Brunt, Jr.
APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr./RQT:sn Enclosure cc: See Attached Page 2 8309120135 830823 gg PDR ADOCK 05000529 S
r e
U. S. Nuclear Regulatory Commission Page Two cc: Richard DeYoung, Director Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, 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 P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bi ngh am R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiore11i S. R. Frost J. Self Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339
et.
FINAL REPORT - DER 83-31 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
'PVNGS UNIT 1, 2, & 3 s I.
Desqription of Deficiency During start-up testing at full load, a rapid rise in temperature in the Diesel Generator's generator control cabinet-(not the engine control cabinet) was'noted. An estimated 120*F was reached. A test with thermocouples inside the cabinet with a recorder was performed on 4/15/83 with a 77*F ambient control room temperature. A temperature of 135*F in the cabinet was recorded. The test.was
. discontinued at the 135'F peak temperature. Under maximum design conditions (122*F) the internal cabinet temperature could exceed 190*F which may preclude satisfactory operations of the controls.
Subsequent operations show no indication of damage from the heat buildup during. the test period.
II.
Analys.is of Safety Implicati.ons This condition is considered reportable. The environmental qualification program will qualify components for normal and essential operation at 140*F.
Operation in excess of this t2nperature will reduce the qualified life. Excessive temperatures may cause failure during emergency conditions.
III. Corrective Action Inadequate consideration of the heat produced by generator control devices inside the cabinet was determined to be the cause of excessive heat build-up. Therefore, ventilation to maintain temperature below 140*F in each generator control cabinet will be provided by forced ventilation, and implemented by DCPs ISM, 2SM,
- 3CM-DG-032. The design change will be in accordance with Quality Class 'Q requirements.
In addition to reportability under 10CFR50.55(e), Bechtel PVNGS Project considers the deficiency to be reportable under the requirements of 10CFR Part 21 by the supplier. Deficiency Evaluation Report 83-31 addresses the reporting requirements specified under 10CFR 21.21.(b) (3) with the exception of sub part (vi) which requires the number and location (customer and/or facilities) of other possible defective equipment. A copy of this report will be sent to Cooper Energy Services requesting their review for reporting under 10CFR Part 21 including number and location of all components supplied.
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