ML20211A628
| ML20211A628 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/29/1986 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-36697-EEVB, DER-86-17, NUDOCS 8606110255 | |
| Download: ML20211A628 (6) | |
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IECElVEU f(3C Arizona Nuclear Power Project 3 E -3 P.1 G 23 P O. box 52034 e PHOENIX, ARIZONA 85072-2034 May 29, 1986 ANPP-36697-EEVh/f1h/bkI'-92.11 U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, 3 Docket Nos. 50/528, 529, 530
Subject:
Interim Report - DER 436-17 A 50.55(e) Potentially Reportable Deficiency Relating To Carbon Steel Guides in Stainless Steel Cate Valves File: 86-006-216; D.4.33.2
Reference:
Telephone Conversation between R. C. Sorenson and D. R. Larkin on April 29, 1986 (Initial Reportability - DER 86-17)
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. (May 29, 1986)
Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by June 12, 1986, at which time a complete report will be submitted.
Very truly yours,
. 9*
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528 S
PDR E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/DRL:kp Attachments cc: See Page Two
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DER 86 Interim Report Mr. D. F. Kirsch Acting Director 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 (6295)
Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 l
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INTERIM REPORT - DER 86-17 POTENTIAL REPORTABLE DEFICIENCY ARIZONA NUCLEAR POWER PROJECT (ANPP)
PVNGS UNIT 1, 2, 3 I.
Potential' Problem During the Unit 3 91FL-3SIO2 flushing operation, bright metallic particles were detected in the flush strainers. Following disassembly and inspection of 20 Unit 3 valves and chemical analysis of guide rail samples, it was determined that four (4) Unit 3 Safety-Injection valves had low alloy steel (AISI 4140 or 4150) guides instead of the required 316 stainless steel.
These four valves were Combustion Engineering supplied 10 inch Borg-Warner gate valves, nos. 3J-SIA-HV-684, 685, 687 and 688.
i II.
Approach To and Status of Proposed Resolution A) Unit 2 Manufacturing Data The low alloy steel guides welded into the foer Unit 3 valves were part of a shipment of fourteen 10" guides received at Borg-Warner on May 4, 1979. The guides were part of a single purchase order which also included four guides for two 20" valves, which were received by Borg-Warner on November 9,1978 and twenty guides for ten 20" valves received from the same supplier on May 16, 1979. Thus this one purchase order limits the faulty material to 10" and possibly 20" gate valves.
I Concerning Unit 2 10" gate valves, Table 1 is a listing of CE generated manufacturing data, showing valve numbers, corresponding serial numbers, and guide welding dates. Table I clearly shows that all valves were welded before Borg-Warner received the incorrect lot of guides on May 4, 1979. Therefore, based on manufacturing data, no problems are expected in Unit 2.
Table I.
Unit 210" Porg-Warner Cate Valve Data 3
l Valve No.
Serial No.
Date Welded Inspected / Material SI-684 36192 11/17/78 i
SI-685 36188 12/07/78 Yes/316 l
SI-687 36189 03/22/79 SI-688 36190 09/22/78 i
l SI-689 36193 03/26/79 SI-693 36191 11/20/78 SI-694 36195 12/06/78 Yes/316 i
SI-655 36194 03/22/79 l
SI-435 35795 09/26/78 SI-447 35794 09/26/78 SI-470 35645 09/28/78 SI-402 35646 09/23/78 I
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DER 86 Interim Report Page Two Concerning the two 20" gate valves which were welded af ter receipt of the suspected faulted guides at Borg-Warner on 11/09/78, one of the two, valve 686, was examined and found to have the right material. The second valve, 969, which was not examined, was welded the same day (11/20/78). Since it was welded the same day it is concluded to have the correct material. Table II shows manufacturing and Inspection data for Unit 2 20" Borg-Warner gate valves.
Table II.
Unit 2 20" Borg-Warner Valve Data Valve No.
Serial No.
Date Welded Inspected / Material SI-683 36186 10/25/78 Yes/316 SI-692 36187 10/25/78 SI-686 43831 11/20/78 Yes/316 SI-696 43832 11/20/78 CH-530 36196 10/23/78 CH-531 36197 10/23/78 A total of six 20" valves have been examined: four in Unit 3 and two in Unit 2.
All were found to have correct valve guide material. Based on this sample and the fact the guides for 20" valves would require larger bar stock than for 10" valves, the project position is that it is unlikely that low alloy steel guides were furnished for any 20" valves.
B) Unit 1 Manufacturing Data A review of Table III shows that all the 10" valves designated for Unit I were welded well before Borg-Warner received the incorrect batch of 10" valve guides on 5/04/79. Therefore, based on manufacturing data, no problems are expected in Unit 1 10" Borg-Warner gate valve guide material.
Table III. Unit 1 10" Borg-Warner Cate Valve Manufacturing Data Valve No.
Serial No.
Date Welded SI-684 28630 04/20/78 SI-685 28635 04/20/78 SI-687 28639 04/20/78 SI-688 28640 04/20/78 SI-689 28637 04/26/78 SI-693 28648 04/24/78 SI-694 28641 05/12/78 SI-695 28642 05/15/78 SI-435 24995 06/27/77 SI-447 24996 06/28/77 SI-470 24994 06/30/77 SI-402 24993 06/27/77
DER 86 Interim Report Page Three Concerning Unit 1 20" Borg-Warner gate valves, all of the 20" guides except one was welded before receipt of the suspect 20" guides at Borg-Warner on 11/09/78 and 05/16/79. CE has not located the weld date for that one valve but its serial number is next in line to a 20" valve welded on 08/25/77, approximately 14 months prior to the receipt of any 20" guides from the suspected vendor on 11/09/78. Therefore, the project believes that it is unlikely that there are any valve guide material problems for 20" Borg-Warner gate valve guides in Unit 1.
Table IV shows manufacturing data for Unit 1 20" Borg-Warner gate valves.
Table IV.
Unit 1 20" Borg-Warner Valve Data Valve No.
Serial No.
Date We,1ded SI-683 26053 09/24/77 SI-692 26054 09/30/77 SI-686 26443 03/13/78 SI-696 26444 03/29/78 CH-530 26154 08/25/77 CH-531 26155 Unknown C) Unit 3 Manufacturing Data Concerning Unit 3 10" gate valves, Table V shows that all valves welded after receipt of the suspected faulty guides at Borg-Warner on May 4, 1978 have been inspected.
Table V.
Unit 3 10" Borg-Warner Cate Valve Data Valve No.
Serial No.
Date Welded Inspected / Material SI-684 49408 07/12/79 Yes/CS SI-685 49409 07/11/79 Yes/CS SI-687 49410 07/12/79 Yes/CS SI-688 49411 07/11/79 Yes/CS l
SI-689 40412 7/21&23/79 Yes/316 SI-693 40413 7/21,7/23 Yes/316 8/21,8/27/79 i
l SI-694 49414 10/07/80 Yes/316 SI-695 49415 10/09/80 Yes/316 SI-435 35643 09/26/78 Yes/316 SI-447 35644 09/15/78 Yes/316 SI-470 35642 10/03/78 NO SI-402 35641 09/27/78 NO l
Concerning the six 20" gate valves in Unit 3, Table VI shows that four were inspected and found to have the correct material. Since the carbon steel guides have only been found in 10" valves and four out of the six suspect 20" valves were inspected, it is unlikely that carbon steel guides were furnished for any 20" valves in Unit 3.
I
~ DER 86 Interim Report Page Four Table VI.
Unit 3 20" Gate Valve" Data Valve No.
Serial No.
Date Welded Inspected / Material SI-683 51735 08/29/79 Yes/316 SI-692 51734
'08/14/79 Yes/316 SI-686 51864 09/30/79 Yes/316 SI-696 51865 09/05/79 Yes/316 CH-530 49738 04/09/79 No CH-531 49737 04/10/79 No D) Summary Four 10" gate valves supplied by Borg-Warner were found in Unit 3 to have carbon steel guides. Manufacturing data and field inspections indicates this deficiency is restricted to the four identified valves.
The root cause of this deficiency is still under investigation and evaluation.
III. Projected' Completion of Corrective Action and Submittal of the Final Report The guide rails of the four Unit 3 deficient valves SJ-684, -685, -687 and
-688 have been removed and replaced by rails of the correct material (Reference NCR SP-6408). The work was accomplished to original specification requirements using approved procedures.
The complete evaluation and Final Report are forecast for June 12, 1986.
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