ML20093H915
| ML20093H915 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/11/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-29941-TDS, DER-84-11, NUDOCS 8407250400 | |
| Download: ML20093H915 (4) | |
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N Arizona Public Service Company RC' l% JVf. IG FM g-y July 11, 1984 ANPP-2994gDgTRB U. S. Nuclear Regulatory Comminaion Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Res:' dent Reactor Projects and Engineering Programs
Subject:
Final Report - DER 84-11 A 50.55(e) Reportable Condition Relating To Conduit Used In The PVMP Instrumentation Is Contaminated.
Pile: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between P. Johnson and T. Bradish on March 8, 1984 B) ANPP-29213, dated April 3,1984 (Interim Report)
C) ANPP-29602, dated May 25, 1984 (Time Extension)
Dear Sir:
Attached in our final written report of the deficiency referenced above, which han been determined to be Not Reportable under the requirements of 10CFR50.55(e).
Very truly yours,
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CLL 9LLL {%
E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVB/TRB:db Attachment cc:
See Page Two 8407250400 840711 gDRADOCK 05000528 PDR
.TE-27 >%
Mr. T. W. Bishop DER 84-11 Page Two ec:
Richard DeYoung, Director Of".ce of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.
D. B. Karner W. E. Ide D. B. Fasnacht A. C. Rogers L. A. souza D. E. Fowler T. D. Shriver C. N. Russo J. Vorees J. R. Bynuo J. M. Allen J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Pa tterson R. W. Welcher H. D. Foster D. R. Hawkinson L. E. Vorderbrueggen R. P. Zimmerman S. R. Frost J. Self D. Canady T. J. Bloom Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339 M A
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,c FINAL REPORT - DER 84-11 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNIT 1 I.
Description of Deficiency Combustion Engineering (CE) installed electrical conduit on the Control Element Assembly (CEA) shroud of the Unit i reactor to accommodate the Precritical Vibration Monitoring Program (PVMP) instrumentation. NCR SM-3729 documents the finding of chlorides, fluorides and other contaminants inside this conduit, which had not been properly cleaned prior to installation.
The PVMP instrumentation was designed for special tests and all of it, including the electrical conduit, will be removed from the Unit 1 CEA shroud prior to fuel load. Similar tests will not be conducted on Units 2 and 3.
II.
Analysis of Safety Implications CE has reviewed this deficiency with respect to the following conditions:
A. The contamination, if concentrated only within the conduit, would have been of a level that could have caused a failure of the instrumentation system.
Since the PVMP instrumentation is temporary and not safety-related, this condition does not constitute a safety-related deficiency.
B. Had the contamination escaped into the Reactor Coolant System it would have been absorbed, and the resulting concentration would have been far below the allowable limits given in Table 3.4-1 of CESSAR-F (Chapter 16).
C. A remote possibility exists that the contaminant could have worked its way through the conduit and concentrated in the vicinity of the instrumentation / core shroud tube interface during the RCS demonstration test. It is also possible, though unlikely, that stress corrosion cracking could have been induced at this interface. The RCS demonstration test will be conducted to demonstrate the adequacy of the modifications made to the reactor coolant syste.n equipment as a result of the problems encountered during hot functional testing. Post test inspection of the CEA shroud assembly is required and will be performed via CE site process sheets 652600. This inspection is specifically looking for cracking of the CEA shroud sesembly.
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Mr. T. W. Bishop ANPP-29941 Page Two Due to the short duration of the demonstration test and the absence of all but residual-stresses in the shroud tube it is believed that stress corrosion cracking could not have occurred.
If, however, a crack were to have been initiated it would either have been discovered during the post test inspection or if the crack were so small as to have escaped detection, it would not propagate cace the instrumentation was removed thereby returning the area of the instrumentation interface to a clean environment.
The condition described herein is evaluated as Not Reportable under 10CFR Part 50.55(e) and/or Part 21 since, if uncorrected, it would not have adversely affected the aafety of plant operations.
III. Corrective Action NCR SM-3729 has been dispositioned rework. The contaminated conduit has been removed and replaced with' verified Class B clean conduit.
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