SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period

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Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period
ML20196F930
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/25/1999
From: Dimmette J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-99-103, NUDOCS 9907010012
Download: ML20196F930 (2)


Text

'

!; Commonweakh r.divm O>mpany

- Quad Cities Generating $tation f t . s 2 8"'10 206th Asenue North

  • Lordova, 11.61242 9'*40 Tel .w>4s u24 :

June 25,1999 l

SVP-99-103 1 1

1 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D C 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Results of Reactor Vessel Head Closure Stud Cumulative Fatigue Usage Factor Evaluation

References:

(1) Letter (SVP-99-062) from J. P. Dimmette, Jr. (Comed) to i

, USNRC, " Revision to Schedule for Analytically Demonstrating f/ l Predicted Reactor Vessel Head Closure Stud Cumulative Usage /g Factor," dated March 31,1999. '

(2) Letter (DSB-99029) from D.S. Braden (GE) to Comed, "RPV ,

Closure Stud Fatigue Usage Reduction Final Report GENE-B13- l 02010-00-30, Revision 0," dated May 20,1999.

[2f The purpose of this letter is to inform the NRC of the results of the subject evaluation as committed to in Reference (1). The evaluation consisted of analytically demonstrating that the Cumulative Fatigue Ucage Factor (CFUF) for the reactor vessel head closure studs will remain below 1.0 for the remainder of the current license period.

The results of the evaluation show the CFUF to be 0.73 for both Units 1 and 2 at the end of the current forty-year life (2012). This value for fatique usage is well below the allowable CFUF limit of 1.0 established in the ASME Section lli Code, and, as a result, justifies at least forty years of operation. Further conservatism could be removed from the evaluation to support plant life extension, if needed.

9907010012 990625 PDR P

ADOCK 05000254 pg A 11nicom Compan) ,

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,5 June 25,1999 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. W.J. Beck at (309) 654-2241, extension 3100.

Res ectfully, n

ykl AA%HO oel P. Dimmette, Jr.

ite Vice President Quad Cities Nuclear Power Station cc: ' Regional Administrator- NRC Region 111 NRC Senior Resident inspector- Quad Cities Nuclear Power Station 1

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