ML17298A517

Advises That Fuel Sys Complies W/Requirements of NUREG-0852, SER Re Final Design of Std Nuclear Steam Supply Ref Sys Cessar Sys 80, Suppl 1

ML17298A517
Person / Time
Site:	Palo Verde
Issue date:	08/16/1983
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0852, RTR-NUREG-852 ANPP-27582-WFQ, NUDOCS 8308220123
Download: ML17298A517 (6)

Text

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83/08/16 NOTARI'ZED:

NO DOCKET FACIL!'STN.b0 528 rPalo verde Nuclea'r Stations'Uni;t 1r'r)zona Publ i 05000528'STN.50 529 XPalo 9er de Nucl ear Stat'ionr Unit 2r Ar izona Publ i 05000529'STN~50~530 Palo verde Nuclear Station~Unit<<3<Arizona Publi 05000530"AUTH', NAME, AUTHUR AFFILIATION VAN BRUNTrE,E, Arizona Public Service Co.<<RECIPBNAME RECIPIENT AFFILIATION.KNIGHTONg G~Licensing Branch 3

SUBJECT:

Advises<<that fuel sys complies w/requinements of NUREG 0852/"SER.re Final Design of Std Nuclear Steam Supp'ly Ref Sys CESSAR Sys 80'" Suppl 1, DISTRIBUTION CODE: B00$S<<COPIES RECEIVED:LTR ENCL"SIZE~.EE=.TITLE: Licensing"Submittal:

PSAR/FSAR Amdts 8, Related Correspondence NOTES:Standardized,p)ant

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-WFQ/TFQ Director of Nuclear Reactor Regulation Attention:

Mr.George Knighton, Chief Licensing Branch No.3 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3 Docket Nos.STN-50-528/529/530 File: 83-056-026; G.1.01.10

Reference:

NUREG-0852,"Safety Evaluation Report related to" the Final Design of the Standard Nuclear Steam Supply Reference System CESSAR System 80", Supplement No.1, dated March, 1983.

Dear Mr.Knighton:

In regard to fuel rod mechanical fracture analysis, the referenced document stated: "Applicants referencing CESSAR must certify that this analysis for their fuel system conforms to the acceptance criteria given in Section 4.2.1.2(g)." NUREG-0852, Supplement No.1, Section 4.2.1.2(g) states: "Mechanical fracturing of a fuel rod could potentially arise from an externally applied force such as hydraulic load or a load derived from core-plate motion.To preclude such failure, CE stated in a letter dated January ll, 1982, that rod fracture stress limits shall be in accordance with the criteria given in Table 9-1 of CENPD-178, Revision 1 (August 21, 1981),"Structural Analysis of Fuel Assemblies for Combined Seismic and Loss-of-Coolant Accident Loading." The review of CENPD-178, Revision 1 and the criteria given in Table 9-1 have been completed and found acceptable.

Consequently, this issue is resolved.*8308220123 8308i6 PDR ADOCK 05000528 A PDR

Mr.G.W.Knighton Page 2 PVNGS PSAR Section 4.2.3.1.4 provides the results of the Structural analysis of PVNGS fuel assemblies for combined Seismic and LOCA loading.The results indicate that the allowable stresses indicated in CENPD-178, Revision 1, were not exceeded.This certifies that the analysis for the PVNGS fuel system conforms to the criteria given in NUREG-0852, Supplement 1, Section 4.2.1.2(g).

Please contact me if you have any questions on this matter.Very truly you E.E.Van Brunt, Jr.APS Vice President Nuclear Projects Management ANPP Project Director EEVB/TPQ/sp cc: E.A.Licitra A."C.Gehr

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