ML17303B080
| ML17303B080 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/22/1988 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8805020275 | |
| Download: ML17303B080 (4) | |
Text
REQULATO INFORMATION DISTRIBUTION TEM (BIDS)
ACCESSION NBR:8805020275 DOC. DATE: 88/04/22 NOTARIZED:
NO DOCKET 0 FACIL:STN-50-529 Palo Verde Nuclear Stations Unit 2i Arizona Pub 1 i 05000529 AUTH. NAME AUTHOR AFFILIATION VAN BRUNT'. E.
Arizona Nuclear Power ProJect (formerly Arizona Public Serv REClP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Discusses visual insp of feedeater spargeri per 870701 submittal of piping verification test summary. Insp mill not be done. based on results of Units 1
8c 3 insp Zc summary of encl engineering review of design 5 operation parameters.
DISTRIBUTION CODE:
A047D COPIES RECEIVED: LTR
(
ENCL J SIZE:
TITLE:
OR Submittal:
Inservice Inspection/Testing/Relief from ASME Code NOTES: Standardized plant.
05000529 RECIPIENT lD CODE/NAME PD5 LA LICITRAiE INTERNAL:
ACRS AEOD/DSP/TPAB NRR/DEBT/MEB 9H NRR/PM*S/ILRB12 (r P~
01 EXTERNAL:
EQSG ROCKHOLDs H NL 007 HEMMING NSIC COPIES LTTR ENCL 1
0 1
1 10 10 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD5 PD DAVISiM AEOD/DOA ARM/DAF/LFMB NRR/DEBT/MTB 9H OQC 15-B-18 RES/DE/EIB LPDR NRC PDR COPIES LTTR ENCL 5
5 1
1 1
1 0
1 0
1 1
1 1
1 NOTES:
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 33 ENCL 30
K I
Pv c",<
~
~
II f
W S
p ~
I A
H H
F t
Docket No. 50-529 Arizona Nuclear Power Project P.O, BOX 52034
~
PHOENIX, ARIZONA85072-2034 161-00963-EEVB/SGB April 22, 1988 U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 ATTN: Document Control Desk
Reference:
Letter from J.
G. Haynes, ANPP, to USNRC Document Control Desk, dated July 1, 1987.
Subject:
PVNGS Piping Verification Test Summary.
Dear Sirs:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Change to Piping Verification Test Submittal Commitment File: 88-F-056-026 Pursuant to the correspondence referenced, the results of a visual inspection of the PVNGS Unit 2, Steam Generator ¹1, feedwater sparger were to be submitted upon completion.
Based upon the results obtained in identical tests performed on a steam generator in each of Units 1 and 3 and an engineering review of the design and operation parameters between Units 1-3, the Unit 2 inspection will not be performed.
A summary of this review is provided on the attachment.
This closes out our action on the referenced letter.
If there are any questions which pertain to this submittal, please contact Mr. A. C. Rogers of my staff at (602) 371-4041.
Very truly yo s,
E.
E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/SGB/ls Attachment cc:
J.
B. Martin E. A. Licitra T. J. Polich G.
W. Knighton A. C. Gehr (all w/attachment)
S8050a0275 880422 PDR ADOCK 05000529 8
Attachment REVIEW
SUMMARY
A review of the documentation regarding the design and testing for the auxiliary feedwater waterhammer test was accomplished.
The results of this review are as follows:
A review of the unit unique stress isometric drawings in Calculation 13-MC-SG-506R Rev.
4 was accomplished and only minor dimensional differences between support locations in each unit exist.
These differences are insignificant with respect to the supports'bility to resist the loads subj ected to the piping system during the hydraulic transient.
This conclusion is supported by the test results for the Steam Generator tested in Units 1 and 3 which show that the allowable loads as specified by test guideline PETG-6-XX-1 Rev.
3 were not exceeded during the transient and the subsequent inspection of the piping revealed no damage.
The pipe
- size, number/type of fittings and valves, and straight pipe lengths are the same for each unit and thus the hydraulic performance of the piping system is expected to be similar.
The test results support this conclusion in that the peak auxiliary feedwater flows during the transient were within six percent of 2047 GPM in any unit tested.
The forcing function resulting from the hydraulic transient will be the same
'for the feedring/aux.
feedwater piping combination in each unit provided that the configurations of the feedring/piping in each unit are geometrically similar and the flow conditions under which these components are operated are similar als'o.
- Hence, with equivalent feedring designs (i.e.,
constructed/inspected to the same
- codes, standards and specifications) in each unit it is expected that the loads to which the feedring was subjected during the transient and the resulting damage (if any) will be the same in each unit under the provisions stipulated above.
The existing design of the feedring in each unit has incorporated the use of J-tubes with the feedring and the horizontal auxiliary feedwater piping at the steam generator downcomer nozzle connection is minimized by utilizing a 90 degree elbow at this connection.
These design features were recommended in NUREG-0918 to mitigate steam generator waterhammer events.
NUREG-0918 reports that steam generators which have implemented said design features have not had damaging waterhammers to their feedrings in any operating PWR and the NRC has acknowledged the incorporation of these features as constituting an acceptable resolution to the safety issues pertinent to steam generator waterhammer.
1506K/0051K