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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.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=

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Arizona Public Service Company P.O. SOX 21666 ~ PHOENIX. ARIZONA 85036 August 16, 1983 ANPP-27582 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, with 1982, that rod fracture the criteria given in stress limits shall be in accordance 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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