ML20205R975
| ML20205R975 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/20/1986 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-36637-EEVB, NUDOCS 8606060062 | |
| Download: ML20205R975 (4) | |
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MCE!vic Arizona Nuclear Power Project P.O BOX 52034 e PHOENIX, ARIZONA 85072-2034
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May 20, 1986 ANPP-36637-EEVB/LAS/DRL-92.11 I!GrGN V P.T 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)
Units 1, 2, 3 Docket Nos. 50-528, 529, 530
Subject:
Deficiency Evaluation Report Revisions File: 86-019-026; D.4.33.2
Dear Sir:
In reviewing information and implementing the corrective action to resolve deficiencies identified in Deficiency Evaluation Reports submitted to the NRC, a few changes in the reported information or corrective action being accomplished have been identified. Attached is a summary description and evaluation of the impact of these changes which may be substantive.
'1 hose changes which are identified and evaluated as not substantive, e.g. typographical errors, have been so noted in our files.
If you have any questions on this matter, please contact W. E. Ide of my staff.
Very truly yours, OLLL d LCd E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/DRL/kp Attachments cc: See Page 'Ivo 8606060062 860520 ADOCKODOO{g8-DR 80
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Mr. D. K. Kirsch Acting Director DER Revisions i
ANPP-36637-EEVB/LAS/DRL-92.11 Page Two cc:
J. M. Taylor, Director Office of Inspection and Enforcement j
U. S. Nuclear Regulatory Commission l
Washington, D. C.
20555 A. C. Gehr (4141)
R. P. Zimmerman (6295)
Records Center Institute of Nuclear Power Operations i
1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 i
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Attachment Page 1 of 2 Summary of DER Revisions DER No. l Original Deficiency or Commitment l Summary of Change l
Impact of Change 82-80 l A review of the qualification testl Ten additional circuits, per l No impact - all work to l report for EPA instrument channel l unit, were found to have the l replace these components l terminal blocks, supplied by l deficiency, and Combustion l has already been l Conax Corporation, has revealed l Engineering (Conax Corporation) l completed.
l surface conductivity measurements,l identified that the effects of I
l after DBE simulation, which I degradad insulation resistance ofl l directly affects Post Accident l terminal blocks could be elimina-l l Monitoring Instrumentation (PAMI) l ted by replacing affected EPA l
l system performance.
l terminal blocks with splices l
l l utilizing AMPS Special Industries l l Corrective Action identified the l crimp connectors and Raychem's l
l changeout of 168 (56 per unit) RTDI heat shrinkable insulating kits. l l pressure and level transmitter l ANPP committed to correct the l
l circuits, identified by Combustion l deficiency on DCP 1SE-SE-033, l
l Engineering.
l 2SE-SE-033, and 3CE-SB-033.
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l 83-70 1 During surveillance inspection of l Separation between the Class 1E, l No impact - The work was l the unit 1 and 2 Emergency Re-l 48VDC power circuit and its l either completed or l sponse Facility -(ERF) isolation l non-1E power circuit does not I determined as not l cabinets, it was revealed that I serve a safety-related function. I required.
l certain internal / external wiring / l The dry contact signals from l
l cabling did not meet the Class 1E l Class 1E devices are connected l
l separation criteria of IEEE-384.
l through the isolation cabinets tol l
l ERFDADS which is a non-lE system.l l Corrective Action, item 1.B.2, l In order to meet the separation l l called for the installation of a l requirements at the 1E device, l
l metal barrier to separate inter-l train oriented power cable is l
l nal Class IE and Non-1E wiring l used.
However, the_ source of l
l when the 48VDC power supply l power is from a non-1E power l
l_ drawers are extended.
l supply, through isolation fuses. l l
l The loss of the power circuit, l
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l which results in the loss of the l l
l connected 1E signals, would only l l
l affect the non-1E plant monitor-l l
l ing system. Also, the power l
l l circuit is properly fused so the l l
A Attachment Page 2 of 2 Summary of I:ER Revisions DER No. l Original Deficiency or Commitment l Summary of Change l
Impact of Change 83-70 l
l failure of the powers supply l
Continued l l circuit would not affect any 1E l l
l device function. Therefore, not l l
l providing separation between the l l
l train oriented power cable and l
l l the non-1E system does not l
l l degrade any class IE system belowl l
l an acceptable level. This con-l l
l dition was documented on drawing l l
l J-106-224, NCR's SE-5968, and l
l l SE-5969 for Unit 2 NCR IJ-6308 l
l l for Unit 3.
Unit 1 meets the l
l l
l separation criteria as previouslyl l
l thought to be required.
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84-74 l During startup testing of the l After inspection of the Unit 3 l No impact - the Unit 3 l
l Class 1E 120 VAC inverters in l SCR's under SWA 4447 (Work Order l SCR's were not deficient.
l l Unit 3, it was determined that i 115674) it was determined that l
l l GEC 364 SCR's had not yet been l the SCR's were no'. deficient and l l replaced with GEC 384 SCR's.
l no further rep'.acement of the l
l l components, in Unit 3, would be l
l Corrective Action, item C, called l required.
l 1 for the replacement of-GEC 364 l
l l SCR's with GEC 384 SCR's in all l
l l three Units.
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