ML17303A636
| ML17303A636 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/29/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 161-00612-JGH-L, 161-612-JGH-L, TAC-56657, NUDOCS 8710300038 | |
| Download: ML17303A636 (6) | |
Text
REGULA'I INFORMATION DISTR IBUTIO YSTEM (RIDS)
ACCESSION NBR: 8710300038 DOC. DATE: 87/i0/2'7 NOTARIZED:
NO DOCKET 5 FACIL:>QTN-50-528 Palo Verde Nuclear Stations Unit ii Arizona Pub li 05000528 AV~>~NAME AUTHOR AFFILIATION.
HAYNES'. G.
Arizona Nuclear Power Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to request for addi info re method used to veriFg that stress values obtained Prom piping verilication test did not exceed limits o0 ASME Code Section III.
DISTRIBUTION CODE:
A047D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
Inservice Inspection/Testing NOTES: Standardized plant.
05000528 REC IP IENT ID CODE/NAME PD5 LA LICITRAiE INTERNAL:
ACRS AEOD/DSP/TPAB NRR/DEST/MEB NRR LRB 01 EXTERNAL:
LPDR NSIC NOTES:
COPIES LTTR ENCL 1
0 1
1 10 10 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD5 PD DAVIS> M AEOD/DOA ARM/DAF/LFMB NRR/DEST/MTB OGC/HDSi RES/DE/EIB NRC PDR COPIES LTTR ENCL 5
5 1
1 1
1 0
1 0
1 1
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 31 ENCL 28
4 r
0 Docket No.
STN 50-528 Arizona Nuclear Power Project P.o. BOX 52034
~
PHOENIX. ARIZONA85072-2034 October 29, 1987 161-00612-JGH/LJM U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk
Dear Gentlemen:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Unit 1 Piping Verification Test Summary
Response
to Request for Additional Information File: 87-B-056-026 Attached is ANPP's response to your questions concerning the method used to verify that the stress values obtained from the Piping Verification Test did not exceed the limits as defined in Section III of the ASME Code.
If you have any questions, please contact W. F. Quinn at (602) 371-4087.
Very truly yours, J.
G. Haynes Vice President Nuclear Production JGH/LJM/rw Attachment CC:
0.
M.
E. E.
G.
W.
J.
B.
E.
A.
AD C.
J.
R.
De Michele Van Brunt, Jr.
Knighton Martin Licitra (w/a)
Gehr Ball 8710300038 87l029 PDR ADOCK 05000528 P
~ J
~h~
attachment to 16$ -00612-JGH/LJM ATTACHMENT PVNGS steady state vibration test program consisted of obtaining vibration measure-ments in the following manner:
- 1) Preselected areas
- 2) areas where there appeared to be vibration and
- 3) areas randomly selected where measurements could be taken without disturbing the configuration of the pipe (i.e.,
removing the insulation etc.).
These vibration measurements were compared to an allowable screening cri-teria of 2.5 in/sec. velocity.
The allowable screening velocity is based upon ANSI/ASME OM-3-1982 where C C4 x 3.64 x 10 (0.8 SEL) 1 4 Vallowable C2K With C1 0 50 C2 2
1 K2 = 2.0 C3
=
13 C4 = 1.0 SEL = 4(20,000) 6
.2 Where V
= in/Sec and SEL (endurance stress" at 10 cycles)
= lb/in allowable Whenever the allowable screening velocity is
- exceeded, additional measurements are taken which include displacemen't versus time'races.
The deflection serves as design input to the respective piping computer model.
The resulting generate stresses caused by the imposed deflection is then compared to one half of the endurance limit.
An engineering evaluation was performed resulting with no cases exhibiting stress level larger than one half the endurance limit (10,000 psi) for all cases t at exceeded the allowable screening velocity.
it
~~
~~
l
/