ML20028C977
| ML20028C977 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 12/23/1982 |
| 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, DER-82-75, NUDOCS 8301140363 | |
| Download: ML20028C977 (4) | |
Text
,
.- [",'
' Dock 1t Nosi 50-528/529/530.
50.55 (d) t t
Arizona Public Service Company L /993 jg,h P.O. box 21666 '. PHOENIX, ARIZONA 85036 December 23, 19 % gfq,I,165-ANPP-22586-GHD/BSK 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:
. Final Report - DER 82-75 A 50.55(e) Reportable Deficiency Relating to Unit 1 Refueling Water Tank Suction. Strainers Improperly Secured Due to Oversize Bolt Holes File: 82-019-026 D.4.33.2
Reference:
(A) Telephone Conversation between P. Narbut and G. Duckworth on November 24, 1982
Dear Sir:
Attached, is our final written report. of the Reportable deficiency, under
[
10CFR50.55(e), referenced above.
I Very truly yours, OA.
g l
E. E. Van Brunt, Jr.
APS Vice President l
Nuclear Projects Management ANPP Project Director EEVBJr/GIID:db -
l l
cc: See Attached Page 2 l
I
{
8301140363 821223 gDRADOCK 05000528 PDR m
+-
~ g_'
i l1 1
U. S.' Nuclear, Regulatory. Commission:
December 23, 1982-Attention: :Mr. D. H.:Sternberg, Chief-
- ANPP-22586-GHD/BSK
'Page 2 cc:-Richard DeYoue3,-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 J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen
.G. A. Fiorelli P. P. Klute' Lynne Bernabei, Esq.
Harmon & Weiss 1725 "I" Street, NW Washington, D. C. 20006 R. L. Greenfield Assistant Attorney General Bataan Memorial Building i
[
Santa Fe, New Mexico 87503 l
l
= - - - -
m-=-
p,
.g 3
?
w 1
+
', ( ; *J 'I FINAL' REPORT'- DER 82-75 i
~
DEFICIENCY EVALUATION'50.55(e)
ARIZONA-PUBLIC SERVICE COMPANY (APS)
PVNGS UNIT 1
-1.
. DESCRIPTION.OF' DEFICIENCY Assembly and installation problems were encoun' ered with the :
t
~a Refueling Water Tank Filter-Frame Assembly,:and.it was turned-over for=startup with the following deficiencies:
1..
3/8" holes are specified for screen clips and.1/4-20 studs; however,isome holes on the' frame were oversized,=and the L1/4-20 nuts were pulling through the holes. :Bechtel Construction ~ installed washers to overcome this condition, but did not fully' complete the: Installation to specification =
requirements since not all the' excessive gaps were removed.
~
~
The condition was. ultimately corrected 11n conjunction with #4
~
below by Bechtel NCR NN-1497, which was dispositioned to weld the grating tolthe angle frame (3 sides and bottom)..The top.
side did not'have oversized holes.,
2.-
The -rubber boot is not. glued as specified by Grano Steel' Corporation drawing;No.-C220-38-1. A review of-this requirement-indicates that the glue ~was specified by Grano-as-an. assembly aid and has no impact on the installed screen.
- 3.. Two 1/4-20 stainless steel studs 1were broken due'to galled threads. This condition was repaired per FCR 48720-C by welding a new' stud or bolt to.the frame. Also,'the FCR specifies ~that a compound such as Never-Seez Nickel Special Anti-Galling compound be used with the threaded fastners.
4 Maximum' total gap was found to exceed the Combustion Engineering criteria of 0.09 inch. This condition was corrected by welding as indicated in #1 above.
II.
ANALYSIS OF SAFETY IMPLICATIONS This condition is evaluated as reportable; if left uncorrected, the gaps in the filter assembly could possibly preclude the refueling l
-water suction piping, the LPSI and/or the Containment Spray Pumps from performing their intended safety function, since the maximum i
allowable particle size for the core is 0.09 inch. However, a definitive analysis of this potential failure mode was not L
performed since the condition was corrected. This condition is L
attributed to lack of specific assembly instructions, and insufficient in process'and final inspection by Bechtel.
t I
I i
c h
.e 4;
i 1
- .;~
JIII. CORRECTIVE ACTION 1.;
Field Change Request's (FCR's) 48720-C, 48721-C;'and 48722-C have been approved for Bechtel Engineering to provide for -
repair, replacement of the' studs and angle clips, and'use of washers if required..These FCR's'will be incorporated into
. supplier drawing numbers C-220-36,~39, and 40 to. provide
- corrective action and,the.necessary assembly and/or: repair-instructions.
'2.
. A copy of this. report will be transmitted to the'BechteliSite Construction ~ Manager to preclude recurrence on Units 2 and'3.
3.
-The supplier, Grano Steel, has been contacted concerning the
- oversized holes, and a copy;of this report will be transmitted'to preclude recurrence of this condition.
m
?
ms-
-a