ML20072P727
| ML20072P727 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/17/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-23273-RQT, DER-82-39, NUDOCS 8304040358 | |
| Download: ML20072P727 (4) | |
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_,.iT Docket No. 50-523/529/530
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1 50.55(e) Report ETEPED m
Arizona Public Service Company
' P o. Box 21666. PHOENIX, ARIZONA 85036 U3!!!a23 m p y, March 17, 1983 ANPP-23273-RQT/BSKWic:c. & -
U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. D. M. Sternberg, Chief Reactor Projects Branch 1
Subject:
Interim Report - DER 82-39 A 50.55(e) Potentially Reportable Deficiency Relating to CE Valve Limit Switches (Class lE) May Be Below Maximum LOCA Flood Level In Containment File: 83-019-026 D.4.33.2
Reference:
(A) Telephone Conversation between G. Hernandez and G. Duckworth on July 30, 1982 (B) ANPP-21722, dated August 30, 1982 (Interim Report)
(C) ANPP-22138, dated October 28, 1982 (Time Extension)
(D). ANPP-22824, dated January 26, 1983 (Time Extension)
Dear Sir:
The NRC was notified of a potentially reportable deficiency in Reference (A), an Interim Report was transmitted by Reference (B), a Time Extension was requested by Reference (C), and a Time. Extension was requested by Reference (D). At that time, it was estimated that a Final Report would be available by March 25, 1983.
Due to the extensive investigation and evaluation required, a revised i
Interim Report is attached. It is now expected that this information I
will be finalized by May 17, 1983, at which time a complete report will 4
be submitted.
I Very truly yours, CttL ntLL-E. E. Van Brunt, Jr.
APS Vice President i
Nuclear Projects Management ANPP Project Director EEVBJr/RQT:db i
Enclosure cc: See Attached Page 2 C304040358 830317 PDR ADOCK 05000528 l
S PDR l
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b U. S. Nuclear Regulatory Commission March 17, 1933
. Attention:
Mr. D. M. Sternberg, Chief ANPP-23273-RQT/BSK Page 2-cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.'C.~20555 T. G. Woods, Jr.
J. A. Roedel D. B. Fasnacht-G. C. Andognini J. R. Bynum A. C. Rogers-B. S. Kaplan W. E. Ide J. Vorees P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. !!. Grant D. R. llawkinson L. E. Vorderbrueggen G. A. Fiorelli 1
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INTERIM REPORT - DER'82-39.
cPOTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNIT 1 I.
POTENTIAL PROBLEM The following. Class lE Electrical Equipment were. identified by APS as having been installed in Unit 1 at or below the maximum containment flood level (elevation 90'-6"):
Tag No. (Valve) 1E Equipment Tag No.
Item 1 SIA-UV-651 Limitorque - VM0 Item 2 CHA-UV-506 NAMCO Limit Switch CHA-ZSH-506 Item 3 CHA-UV-506 NAMCO Limit Switch CHA-ZSH-506 Item 4 SIA-UV-682 NAMCO Limit Switch SIA-ZSH-682 Item 5 SIA-UV-682 NAMCO Limit Switch SIA-ZSH-682 Per C-E Letter V-CE-16734, the following Post Flood Operability Requirements (DBE) apply to this equipment as noted:
a.
Valve Tag #SI-651 and VM0 shall be operable for one (1) year post DBE.
b.
Valve Tag #CH-506 shall close on CIAS signal, operate up to thirty-six (36) hours post DBE or fail to required closed position.
Valve Tag #SI-682 shall operate for thirty-six (36) hours c.
post'DBE or fail to required closed position.
d.
NAMCO Limit switches for valves CH-506 and SLI-682 are required to provide valve position indication for duration of post DBE period.
Further investigation has lead to the identification of additional Unit 1 Class lE Equipment Components installed at or below the maximum containment flood level.
II. APPROACH TO AND STATUS OF PROPOSED RESOLUTION The post-LOCA containment flood level calculation is currently under review for verification of the maximum containment flood level elevation of 90'-6".
The Post Flood Operability Requirements for each identified component are likewise being verified.
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Following verification of the above,'each component-currently" identified to be. installed at or below the maximum containment flood level will be addressed on a case by' case basis. All EA-170 model limit switches inside the. containment are to be replaced with EA-180 limit switches, which are identical to those utilized in-the C-E qualification program, per C-E letter V-CE-17838. Alternatives currently under consideration for'other components requiring action are relocation and qualification for submergence.
III. PROJECTED COMPLETION OF CORRECTIVE ACTION AND SUBMITTAL OF TIIE FINAL REPORT Evaluation of this condition and submittal of the~F'inal Report-is forecast to be completed by May 17, 1983.
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