ML20209E985

Forwards Revs to Deficiency Evaluation Repts (Der), Consisting of Rev 1 to DER 82-01,Rev 1 to DER 83-40,Rev 1 to DER 84-29,Rev 2 to DER 85-23 & Rev 1 to DER 86-04,reflecting Changes in Reported Info or Corrective Actions

ML20209E985
Person / Time
Site:	Palo Verde
Issue date:	08/26/1986
From:	Hayes J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-37985-WEI, DER-82-01, DER-82-1, DER-82-40, DER-83-40, DER-84-29, DER-85-23, DER-86-04, DER-86-4, NUDOCS 8609120007
Download: ML20209E985 (4)

Text

-

' s.

Arizona Nuclear Power Project P.O. BOX 52034 o PHOENIX. ARIZONA 85072-2034 August 26, 1986 kg ANPP-37985-WEI/LA M -92.11 v

U. S. Nuclear Regulatory Commission Region V q /~, // )

1450 Maria Lane - Suite 210 4' pE q ,

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: 86-006-216; 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. Those 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. 3. Ide.

Very truly yours, l

C)h &f--

! J. G. Haynes Vice President Nuclear Production JGH/DRL:kp

! cc: See Page Two i

l l

l l

i u

8609120007 860026 8 (L 7 ,

DR ADOCK 0000

I Mr. D. F. Kirsch Acting Director DER Revisions ANPP-37985-JGH/LAS/DRL-92.11 Page Two cct 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 1

1 4

4 I

i l

Attechmest PagS 1 ef 2 Summary cf DER Rivioi m .

DER No. l Original Deficiency or Commitment l Summary of Change l Impact of Change 82-01 1 APS purchased and replaced Excore l Due to noise problems with the l No impact - Corrective ANPP l Neutron Monitoring System cable 'l cable, which was installed, l Action has been completed.

Rev. 1 l with cable which met attenuation l changes were made in the pre- l l requirements. l amplifier and additional cable l l l changes were made. l l l l 83-40 , CE and Westinghouse determined I Subsequent to this report, in l No impact - Corrective ANPP ll that replacement of lower bearing l resolution of DER 83-61, a deci- l Action has been completed.

Rev. 1 l housings on the Unit 1, 2, and 3 l sion was made to replace all the l l LPSI and CS pumps with a new de- l 500 horse power LPSI pump drive l l sign lower bearing housing was l motors with 800 horse power l l necessary. New housings are beingl motors like the Containment Spray l l installed. I pumps. In order to complete l l l testing in Unit 1, the decision l l l was made to substitute the l j l l Unit 3, 800 horse power, Contain-l

! l l ment Spray pump motors for the l l

l l Unit 1, 500 horse power, LPSI l

! l l pump motors. The modifications l l l to install the new design lower l l l bearing housing were completed l l l for Unit 1 LPSI pumps "A" and "B"l l and Containment Spray pumps "A" l

~

l l l and "B" per DCP ISM-SI-134 a'nd l l l Unit 2 Containment Spray Pump "A"l l l per DCP 2SM-SI-134. The remain- l l l ing pump motors, Unit 2 LPSI l l l pumps "A" and "B", Unit 2 Con- l l l tainment Spray pump "B", Unit 3 l l l LPSI pumps "A" and "B", and l l l Unit 3 Containment Spray pumps l l "A" and "B", had the new design l l l lower bearing housing installed' l l l prior to delivery to the jobsite.]

l l l 84-29 l The corrective action called for l The corrective action for Units I No impact - Corrective ANPP l the complete replacement of l 1, 2, and 3 was changed fron l Action to either repair Rev. 1 l plasite lining for carbon steel l complete replacement of-all l or replace plasite lining l epoxy lined Diesel Generator l plasite lining to repair or re- l in Units 1, 2, and 3 has l Tanks. l place the lining. l been completed.

l l l g ' pig AU

., o._,

]

Attcchment Paga . 2 ef 2 i Summary of DER RSviolens ,

DER No. l Original Deficiency or Commitment l Summary of Change l Impact of Change 85-23 1 On three (3) separate dates, dur- l The replacement of the existing l Unit 1 will be resched-ANPP l ing testing, the Unit 1 diesel l valves TV-265, TV-266, TV-267, l uled .for completion i Rev. 2 l generators failed to attain the l and TV-268 with center dead l during the next available l required voltage, frequency, and l spot valves, AMOT Corp. model no.1 outage after receipt of l speed within ten (10) seconds as l 4021C11C/4021C11C7, which have l material from the vendor, l is required by Technical specifi- l been recalibrated to 105'F with- l since this deficiency

, l cation 4.8.1.1.2.a.4 During l out the thermal wells will occur l affects test mode start j l evaluation of the problem it was l in the future per W/O's 103848 l of the Diesel Generator

l noted that a portion of the con- l and 122350. l there is no affect on l l trol air is routed to the turbo- l l safety for this delay.

l l charger manifold temperature con- l l

. l trol valves, TV-265, TV-266, l For Unit 2, since the correct l No impact on Unit 2, since j l TV-267, and TV-268. When a diesell model valves were already in- l rework has already been

! l start signal (Test Mode) is ini- l stalled, the valves were re- l completed.

' l tiated, air is not vented from thel calibrated to 105*F, as specifiedl l "0FF" side and admitted to the l when not using thermal wells. l

! l "0N" side of the fuel control l l j l cylinder fast enough to enable thel For Unit 3, the correct valves l Unit 3 work will be com-l Diesel Generator to start in l have been installed and will be l pleted per SFR 3DG-024 l ten (10) seconds. The installed l recalibrated, per SFR 3DG-024, tol prior to fuel load.

l valves are the valve port overlap l 105'F, as specified when not l

l type which bleed continuously. l using thermal wells. l l l The original commitment was to l l l l replace the existing valves, l l

! l TV-265, TV-266, TV-267, and TV-268l l l with center dead spot valves, AMOTl l l Corp. model no. 4021C11C. Letter l l l,

l No. ANPP-34307-EEVB/MAJ/98.07 l l

! l dated December 20, 1985 stated l l t l l that the final corrective action l l l of valve replacement would occur l. l -

l l during the first outage for Units j

! l 1 and 2, and prior to fuel load )

l l for Unit 3. l l

I l-

) 86-04 1 The corrective action originally l Due to an engineering oversight, l No impact - The supports ANPP l stated that there were fifty- l during the drawing review pro . l in Units 1 and 2 have

! Rev. 1 l four (54) seals, in Unit 2 and l cess,.an additional seal was l been installed and Unit 3 l l forty-two (42) seals in Unit 3 l found to require support in Units l will be done concurrent

! l identified as requiring support. l 2 and 3 to ensure its integrity l with the normally sch- '

l l as a fire and/or radiation I eduled. installation of the l

l l barrier. l seals prior to fuel load.

I l- l

_ . _ . .