SVP-99-062, Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period

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Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period
ML20205K001
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 03/31/1999
From: Dimmette J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-99-062, SVP-99-62, NUDOCS 9904120287
Download: ML20205K001 (2)
v • d • e


Text

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<a' 4 Quad Citits Generating Station 22710 2Wnh Asenue North Cordova,11. 612 il 9'40 Tel yNM 4-22 ii CORTtEd SVP-99-062 March 31,1999 U. S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, D C 20555 Quad Cities Nuclear Power Station, Unit I and Unit 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Revision to Schedule for Analytically Demonstrating Predicted Reactor Vessel Head Closure Stud Cumulative Usage Factor

Reference:

Letter from E. S. Kraft, Jr. (Comed), SVP-98-068, to USNRC, dated February 26,1998, " Reactor Vessel Closure Studs" The purpose of this 'etter is to inform the NRC of a revision to the schedule for analytically demonstrating that the Cumulative Usage Factor (CUF) for the reactor vessel head closure studs will remain below 1.0 for the remainder of the current license period. The CUF analysis was scheduled to be completed by March 31,1999, as described in the referenced letter.

Subsequent to the Site VP letter referenced above, Commonwealth Edison (Comed)

Company commissioned General Electric (GE) to perform an analysis of the Closure Stud Tensioning Process for Quad Cities Nuclear Power Station, Unit I and Unit 2, with regard to service stresses and fatigue usage. The analysis, GE-NE-B13-01989-02, Revision 0, confirmed that the CUF will reach 1.0 during 2002. D Based on the assurance that the CUF will remain below 1.0, Comed reprioritized the work being performed by the vendor to address other Comed significant work at LaSalle and Dresden Stations. This reprioritization resulted in the rescheduling completion of the remaining life calculation for our Reactor Pressure Vessel (RPV)

Oj studs until July 9,1999.

kO p " E M ib' L._ .2

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l USNRC 2 March 31,1999

SVP-99-062 '

If there are any questions or comments concerning this letter, please refer them to Mr. Wally Beck, Acting Regulatory Assurance Manager, at (309) 654-2241, extension 3100.

Sincerely

_ b JMCW oel P. Dimmette, Jr.

Site Vice President Quad Cities Nuclear Power Station cc: Regional Administrator-NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

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