ML17313B009

From kanterella
Revision as of 07:36, 29 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1
ML17313B009
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 07/20/1999
From: Ide W
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17313B010 List:
References
102-04314-WEI-S, NUDOCS 9907270193
Download: ML17313B009 (8)


Text

CArZaoax REGULAluRY INFORMATION DISTRIBUTIOI~ SYSTEM (RIDS)

ACCESSION NBR:9907270193 DOC.DATE: 99/07/20 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528

-STET. 50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Stat'on, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION IDE,'8. E. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

C

SUBJECT:

Forwards recuested calculations performed to verify that increase in max radially averaged enrichment for fuel assemblies from 4.3 weight percent to 4.8 weight percent did not affect requirments for TSs 3.7.15,3.7.17 &, 4.3.1.

\

DISTRIBUTION CODE AOOID COPIES RECEIVED:LTR i ENCL TXTLE: OR Submittal: General Distribution J SIZE:

Q PLANT 05000528 E'OTES:STANDARDIZED Standardized plant. 05000529 0 Standardized plant. 05000530 R

RECIPIENT COPIES . RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD4.-2 1 1 FIELDS,M 1 1 INTERNAL: ACRS 1 1 LE CE E 0 1 1 NRR/DE/EEIB 1 1 NRR DSSA SPLB 1 1 NRR/DSSA/SRZB 1 1 NUDOCS-ABSTRACT 1 1 OGC/RP 1 0 EXTERNAL: NOAC 1 1 NRC PDR U

M E

N

.t 'tgii 5 NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTZON OR REDUCE THE NUMBER OF COPZES RECEIVED BY YOU OR YOUR ORGANIZATIONS CONTACT THE DOCUMENT LISTS CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPXES REQUIRED: LTTR 11 ENCL '0

I1 P

William E. lde Mail Station 7605 Palo Verde Nuclear Vice President TEL 602/3934116 P.O. Box 52034 Generating Station Nuclear Engineering FAX 602/3936077 Phoenix, AZ 65072-2034 102-04314-WEI/SAB/RKR July 20, 1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Reference:

Letter 102-04294-JML/SAB/RKR, dated June 8, 1999, from J.M. Levine, APS, to NRC, "Request for Amendment to Technical Specifications 3.7.15, Fuel Storage Pool Boron Concentration; 3.7.17, Spent Fuel Assembly Storage; and 4.3.1, Criticality"

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Docket Nos. STN 50-528/529/530 Response to NRC Request for Additional Information Regarding Request for Amendment to Technical Specifications 3.7.15, Fuel Storage Pool Boron Concentration; 3.7.17, Spent Fuel Assembly Storage; and 4.3.1, Criticality In a phone call with Arizona Public Service Company (APS) staff on July 13, 1999, the NRC staff requested that APS provide the calculations performed to verify that the increase in the maximum radially averaged enrichment for fuel assemblies from 4.3 weight percent to 4.8 weight percent did not affect the requirements for the new fuel storage racks, the new fuel elevator, the fuel upender and transfer machine, and the intermediate fuel storage rack. Attached are the requested calculations.

.2."/0002 PDR P 'DR 9907270(93 990720 AoaCX OS000Sae /

s

'll

~%

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Responses to NRC Request for Additional Information Page 2 No commitments are being made to the NRC by this letter. Please contact Mr. Scott Bauer at (623) 393-5978 if you have any questions or would like additional information regarding this matter.

Sincerely, WEI/SAB/RKR/rlh Attachments: 1. A-PV-FE-0107, Rev. 00, "APS New Fuel Rack Criticality Analysis for 5.0 w/o U-235 Value Added Fuel Pellet" April 15 1998

2. A-PV-FE-0108, Rev. 01, "APS Criticality Analysis for Fuel Handling Equipment" December 2, 1998 cc: E. W. Merschoff N. Kalyanam J. H. Moorman A. V. Godwin

l I

,jeff I

l l

ATTACHMENT1 A-PV-FE-0107, Rev. 00, "APS New Fuel Rack Criticality Analysis for 5.0 w/o U-235 Value Added Fuel Pellet" April 15 1998

l F