ML17296B300
| ML17296B300 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 03/16/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-17484-BSK, NUDOCS 8103240364 | |
| Download: ML17296B300 (10) | |
Text
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~ V REGULAT INFORMATION DISTRIBUTION YSTEM (RIDS)
ACCESSION NBR:8103?40364 DOC ~ DATE! 81/03/16 NOTARIZED:
NO DOCKE FACIL:STN-50-528 Palo Verde Nuclear *StatlonP Un) t ii Arizona Publ i 0500 STN-50, 529 Palo Verde Nuclear StationP Unit 2P Arizona Publi 05000529 STN 50 530 Palo Verde Nuclear StationP Unit 3r Arizona Publi 05000530 AUTH BYNAME AUTHOR AFFILIATION VAN BRUNTiE,E.
Arizona Public Service Co, RECIP ~ NAME RECIPIENT AFFILIATION SPENCERpG
~ ST Region rli Dallas<
Reactor Construction 8 Engineering Sup
SUBJECT:
Final deficiency rept-re cable tray supports not meeting drawing requireirrent
~ Caused by drawing misinterpretation.
Structural notes L instructions re-cable tray installation revised for clarity.
DISTRIBUTION CODE:
BOI9S COPIES RECEIVED:LTR rENCL J 'IZE:
TITLE: Construction Deficiency Repor t'10CFR50
~ 55E)
NOTES:Standardized
- Plant, 1 cy:C Grimes Standardized
- Plant, 1 cytC Grimes Standardized Plant.i cy'.C Grimes 05000528 05000529 05000530 RECIPIENT ID CODE/NAME.
ACTION:
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PHOENIX, ARIZONA 85036 March 16, 1981 ANPP-17484-BSK/JAR U.
S. Nuclear Regulatory Commission Region V Walnut Creek Plaza Suite 202 1990 North California Boulevard Walnut Creek, California 94596
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CPA~)~~I Attention:
Mr. G.
S. Spencer, Chief Reactor Construction and Engineering Support Branch
Subject:
Final Report A 50.55(e)
Reportable Condition Relating to Cable Tray Supports Not Meeting,,TIrawing Requirements File:
81-019-026; D:4.33.2
Reference:
(1) Telephone Conversation between J. Eckhardt and B. S. Kaplan on December 11, 1980 (DER 80-39)
(2). Interim Report, ANPP-17061-BSK/JAR, dated January 12, 1981
Dear Sir:
Attached, is our final written report of the reportable deficiency, under 10CFR50.55(e) referenced above.
EEVBJr/BSK:skc Attachment Very truly your C(
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E.
E. Van Brunt, Jr.
APS'Vice President Nuclear Projects ANPP Project Director ti(
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U. S. Nuclear Reg tory Commission Attention:
Mr. G.
S. Spencer, Chief ANPP-17484-BSK/JAR March. 16, 1981 Page 2
CC ~
IVictor Stello, Jr., Director
Office of Inspection-and-Enforcement U. S. Nuclear Regul'atory Commission Washington, D.
C.
20555 A. C. Gehr Snell
& Wilmer R. L.
D. B.
W. E.
J.
M.
A. C.
J.
A.
W. H.
W.
G.
W. J.
R. L.
R.
W.
D. R.
Robb Fasnacht Ide Allen Rogers Brand Wilson Bingham Stubblefield Patterson Welcher Hawkinson
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FINAL,REPORT REPORTABLE DEFICIENCY 50. 55 (e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS /fl, 82 AND /33 I.
Descri tion of Deficienc During close-out of APS Quality Assurance Finding SQA-63-F8, it was observed that several. outstanding conditions exist with regard to completed cable tray installations.
Examples of these problems in the Unit I Auxiliary Building which do not meet Drawing 13-E-ZAC-043 are:
1.
The transverse brace and the vertical support member for H22 form an angle of 25o (30o-60o is required by Note 22B on Drawing 13-E-ZAC-043).
2.
The support brace for H34 has been reversed on the vertical support member and the included angle is less than 30o.
3.
The longitudinal brace shown on Drawing 13-E-ZAC-036 and,the support brace shown on Detail 2A-2, Drawing 13-E-ZAC-047, have been omitted from the support.
P
-These conditions are attributed to a combination of drawing complexities, drawing revisions'uring the construction period, and structural notes and instructions which were not interpreted as per Engineering intent by Bechtel Construction.
Surveillance activity of the completed installations in Unit 1, using the latest drawing revisions as the basis, has indicated that a number of mandatory corrections are required to bring the installations
-into compliance with design intent.
II.
Anal sis of Safet Im lication This condition is considered to be reportable'ince if these
'onditions were left uncorrected, some cable trays and their supports would very likely be subject to stresses that exceed design allowables during a seismic event at locations where the critical support braces have been omitted.
A specific analysis of these conditions was not performed since the conditions are being reworked to comply with the design drawings.
III. Corrective Action 1.
The structural notes and instruction on the cable tray
'nstallation drawings have been revised for clarity and to provide definitive instructions.
Engineering has been assured that these notes and instructions are acceptable and understood by Construction.
l I
I
Final Report Page 2
2.
Unit 1 is undertaking a reinspection of all previously accepted Class 1E tray and supports.
The inspection will cover configuration of supports and the proper application of bracing details using the revised design drawings.
Any discrepancies found will be reworked per
" Work Plan Procedure 251.0 or documented and dispositioned on a Nonconformance Report per Work Plan Procedure 5.0.
3.
Units f/2 and
//3 cable tray installations have not been completed, but will comply with the latest drawing revisions for inspections and final acceptance.
Revised Drawin s 13-E-ZCC-031, Rev.
11 13-E-ZCC-032, Rev.
12 13-E-ZCC-034, Rev.
9 13-E-ZCC-037, Rev.
5 13-E-ZAC-045, Rev.
9 13-E-ZAC-046, Rev.
12 13-E-ZAC-047, Rev.
8 13-E-ZAC-048, Rev.
6 13-E-. ZAC-055,, Rev.
6 13-E-ZAC-059, Rev.
3 13-E-ZAC-060, Rev.
4 13-E-ZAC-062, Rev.
6 13-E-ZAC-074, Rev.
5 13-E-ZJC-021, Rev.
10 13-E-ZJC-022, Rev.
13-E-ZJC-023, Rev.
13-E-ZJC-024, Rev.
13-E-ZJC-026, Rev.
13-E-,ZJC-027, Rev.
13-E-ZJC-028, Rev.
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