ML17300B061
| ML17300B061 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/04/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 161-00487-JGH-L, 161-487-JGH-L, TAC-65691, NUDOCS 8709170165 | |
| Download: ML17300B061 (8) | |
Text
REQULAT
.'NFORMATION DISTR IBUTIOl'YSTEM (BIDS )
ACCESSION NBR: 8709170165 DOC. DATE: 87/09/04 NOTARIZED:
NO DOCKET 0 FACIL:STN-50-528 Palo Verde Nuclear Stations Unit ii Arizona Publi 05000528 AUTH. NAME AUTHOR AFFILIATION HAYNES'. Q.
Arizona Nuclear Power ProJect (formerly Arizona Public Serv REC IP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk>
SUBJECT:
Foreards revised pages of reload analysis rept'orrecting inaccurate info re upper end fitting hold doujn plate design.
Proposed design change in ref rept will be implemented after Unit 1 Cycle 2 reload.
DISTRIBUTION CODE:
- 00ID COPIES RECEIVED: LTR g ENCL J SIZE:
3 TITLE:
OR Submittal:
General Distribution NOTES: Standardized plant.
05000528 REC IP IENT ID CODE/NAME PD5 LA LICITRA>E COPIES LTTR ENCL 0
1 RECIPIENT ID CODE/NAME PD5 PD DAVIS' COPIES LTTR ENCL 5
5 1
INTERNAL:
ACRS NRR/DEST/ADS NRR/DEST/MTB NRR/DOEA/TSB OGC/HDS1 RES/DE/EIB EXTERNAL:
EGSG BRUSKEs S NRC PDR NOTES:
6 6
1 1
1 1
0 1
1 1
1 1
1 ARM/DAF/LFMB NRR/DEBT/CEB NRR/DEBT/RSB NRR/PMAS/ ILRB LPDR NSIC 01 1
0 1
1 1
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 29 ENCL 26
Arizona Nuclear Power Project P.O. BOX 52034
~
PHOENIX, ARIZONA85072-2034 September 4,
1987 161-00487-JGH/IJM U. S. Nuclear Regulatory Commission Washington, D. C.
20555 ATTN:
Document Control Desk
Reference:
J.
G. Haynes letter (161-00321) to DCD (NRC), 6/29/87,
Subject:
Submittal of the Reload Analysis Report for Unit 1 Cycle 2
Dear Sir:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1
Docket No.
STN 50-528 (License NPF-41)
Submittal of the Reload Analysis Report for Unit 1 Cycle 2 Revision
, File:
87-B-056-026 Attached please find revised pages of the Reload Analysis Report (RAR), which contained inaccurate information regarding the upper end fitting hold down plate design.
The proposed design change described in the referenced Reload Analysis Report will not be implemented until after Unit 1 Cycle 2 reload, at which time all fuel fabricated for PVNGS will be modified as described in the referenced RAR.
If you have any questions, please contact W. F. Quinn at (602) 371-4087.
Very truly yours, JGH/LJM/mes Attachments cc:
- 0. M. De Michele E. E. Van Brunt, Jr:
G.
W. Knighton J.
B. Martin E. A. Licitra (w/attachments)
A. C. Gehr J.
R. Ball 8709i70ihS 870904--
PDR ADOCK 05000528 P
PDR J.
G. Haynes Vice President Nuclear Production gyral Ir>
Attachment to 161-00487 4.0 FUEL SYSTEM DESIGN
- 4. 1 MECHANICAL DESIGN 4.1.1
'...- Fuel Oesian With the exception of the design features listed below the mechanical design of the Batch D reload fuel assemblies is identical to the design of the Core 1 Batch C fuel assemblies that were modified to inc&ease the shoulder gap from 1.682 inches to 2 382
- inches, Reference 4-1.
No changes in mechanical design bases have occurred since the original fuel design.
The design features incorporated into Batch D were made to improve the fabricability and quality of the fuel and to improve the burnup capability of the poison rods.
The specific changes are discussed in the following paragraphs.
1.
Deleted tw 2.'The inspection envelope for the fuel bundle assembly has been changed, from a square of 8.230 inches per side for all of the bundle with exception of the vicinity around the upper most grid where a square of 8.250 inches per side is permissible to a square of 8.290 inches per side for the entire length of the fuel bundle.
This change will not affect any of the mechanical design considerations from the standpoint of structural behavior and integrity, fuel assembly bow, handling, interface or other considerations.
Furthermore, a reduction in the
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'0 Attachment to I'61:00487 page 2
12.0 References 12.1 1 ~
Section 1.0 References
~9 5 ~ 'h ~ 't
- (1;1).n "Palo Verde Nuclear Generating Station Unit No. 1, Final Safety Analysis Report," Arizona Public Service
- Company, Docket No. 50-528. ~
12.2 (1-2)
"Combustion Engineering Standard, Safety Analysis Report oCESSAR)",,'ocket
¹STN-50-470F.
~
0'11 Section 2.0 References None,.;-~e,:,;,
12.3 Section 3.0 References None
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1
~ $ ~
12.4 Section 4 '
References 1
'J N
(4-3;)
,~,"Palo Verde Unit 1 Fuel Design Report" NPSD-207"P November 1982.
(4-2)
Deleted (4-3) 'etter, A. E. Lundvall, Jr. to D. R. Hiller (Chief Operating Reactors Branch ¹3), "Calvert Cliffs Nuclea~
Power Plant Unit Nos.
1 and 2, Docket, Nos.
50-317 and 50-318, Request for Amendment",
December 31, 1984.
(4-4) ~
EPRI NP-3966-CCH, "CEPAW Hethod of Analyzing Creep Collapse of Oval Cladding Volume 5:
Evaluation of Interpellet Gap Formation and Clad Collapse in Hodern PWR Fuel Rods," April, 1985.
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