ML20052B734

Forwards Mark I Long-Term Program Plant-Unique Analysis. Primary Containment Pressure Chambers Meet ASME Boiler & Pressure Vessel Code Stress Limits

ML20052B734
Person / Time
Site:	Peach Bottom
Issue date:	04/28/1982
From:	Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20052B735	List: ML20052B734 ML20052B742
References
RTR-NUREG-0661, RTR-NUREG-661 NUDOCS 8205030515
Download: ML20052B734 (1)

Text

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RECE)ygg 1 PHILADELPHIA ELECTRIC COMPANY I ApR801982 b

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2301 M ARKET STREET P.O. BOX 8699

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Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station, Units 2 and 3

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r Docket No. 50-277 and 50-278

Dear Mr. Eisenhut:

Pursuant to the commitment in the June 29, 1981, Mark I owners' Group Status Report, you will find enclosed ten (10) copies of the Peach Bottom Atomic Power Station Unit 2 and 3 Mark I Containment Program Plant Unique Analysis. This report is based on loads and acceptance criteria identified in NUREG 0661 dated July, 1980.

This report demonstrates that the primary containment suppression chambers (tori) meet the stress limits of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and, therefore, meet the original intended margins of safety specified in General Design Criterion 50 of Appendix A to 10 CFR Part 50.

With completion of the current Unit 2 refueling outage, all torus modification work will be completed. Some additional work asuociated with restraining torus attached piping is still underway. We anticipate that this work will be completed in compliance with the end date identified in the latest NRC orders.

Very truly yours,

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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699

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             .. . 7.5.""I27.'.U..                                                  April 28, 1982 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Subj ect:  Peach Bottom Atomic Power Station, Units 2 and 3 Docket No. 50--277 and 50-278

Dear Mr. Eisenhut:

Pursuant to the commitment in the June 29, 1981 Mark I Owners' Group Status Report, you will find enclosed ten (10) copies of t teach Bottom Atomic Power Station Unit 2 and 3 Mark I Containment Program Plant Unique Analysis. This report is based on loads and acceptance criteria identified in NUREG 0661 dated July, 1980. This report demonstrates that the primary containment suppression chambers (tori) meet the stress limits of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and, therefore, meet the original intended margins of safety specified in General Design Criterion 50 of Appendix A to 10 CFR Part 50. With completion of the current Unit 2 refueling outage, all torus modification work will be completed. Some additional work associated with restraining torus attached piping is still underway. We anticipate that this work will be com:leted in compliance with the end date identified in the latest NRC orders. Very truly yours, n A /~% Enclosures __}}