ML20199B251

Forwards Plant Calculations That Addresses Peak Main Steamline Break Pressure of 46.33 Psig & Max Strain in Containment Liner Due to Surface Temp of 273 F

ML20199B251
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	11/05/1997
From:	Shiraki C NRC (Affiliation Not Assigned)
To:	Capra R NRC (Affiliation Not Assigned)
Shared Package
ML20199B255	List: ML20199B251 ML20199C398
References
NUDOCS 9711180255
Download: ML20199B251 (3)

Text

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November 5, 1997 s.

MEMORANDUM TO: Rober1 A. Capra, Director Project Directorate ill 2 Division of Reactor Projects . Ill/lV office of Nuclear Reactor Regulation FROM: Clyde Y. Shiraki, Senior Project Man 9ger ORIGINAL SIGNED Ms Project Directorate ill 2 Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation

SUBJECT:

EVALUATION OF ZION CONTAINMENT SHELL FOR MAIN STEAMLINE BREAK As part of its analyses for a steam generator tube plugging amendment, Commonwealth Edison Company (Comed) performed containment response analyses which showed the limiting pressure following a postulated main steamline break (MSLD)is 40.33 psig. The limiting loss-of c.oolant accident containment peak pressure is 30.24 psig. Thus, with respsct to containment peak pressun , the containment peak pressure response following a MSLB will be the limiting design basis accident. The 40.33 psig following a MSLB is very close to the containment design limit of 47 psig and merits analysis by the staff.

In addition, the calculation shows that the containment peak sulface temperature will reach 271.30 degrees Fahrenheit, which exceeds the Zion Station Updated Final Safety Analysis Report Post Accident Environment Figure 0.21 value of 271 degrees Fahrenheit. Zion Station environmental qualification personnel evaluated the higher temperature and determined that it is acceptable. The validity of this determination should also be evaluated by the staff.

Attached is a Zion Nuclear Station calculation that addresses 1) the peak main steamlins break pressure of 46.33 psig, and 2) the maximum strain in the containment liner due to a surface temperature of 273 degrees Fahrenheit, which is slightly higher than the peak surface tem 9erature of 271.36 degrees Fahrenheit. This calculation will be forwarded to the appropriate technical branches for evaluation.

Docket Nos. 50 205 and 50 304

Attachment:

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November 5. 1997 MEMORANDUM TO: Robert A. Capra, Director Project Directorate lil 2 Division of Reactor Projects -lilllV office of Nuclear Reactor Regulation FROM: Clyde Y. Shiraki, Senior Project Manager ORIGINAL SIGNED BY:

Project Directorate 1112 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation

SUBJECT:

EVALUATION OF ZION CONTAINMENT SHELL FOR MAIN STEAMLINE BREAK As part of its analyses for a steam generator tube plugging amendment, Commonwealth Edison Company (Comed) performed containment response anahses which showed the limiting pressure following a postulated main steamline break (MSLB)is 46.33 psig. The limiting loss-of coolant accident containment peak pressure is 39.24 psig. Thus, with respect to containment peak pressure the containment peak pressure response following a MSLB will be the limiting design basis accident. The 46.33 psig following a MSLB is very close to the containment design limit of 47 psig and merits analysis by the staff.

In addition, the calculation shows that the containment peak surface temperature will reach 271.36 degrees Fahrenheit, which exceeds the Zion Station Updated Final Safety Analysis Report Post Accident Environment Figure 6.21 value of 271 degrees Fahrenheit. Zion Station environmental qualification personnel evaluated the higher temperature and determined that it is acceptable. The validity of this determination should also be evaluated by the staff.

Attached is a Zion Nuclear Station calculation that addresses 1) the peak main steamline break pressure of 46.33 psig, and 2) the maximum strain in the containment liner due to a surface temperature of 273 degrees Fahrenheit, which is slightly higher than the peak surface temperature of 271.36 degrees Fahrenheit. This calculation will be forwarded to the appropriate technical branches for evaluation.

Docket Nos. 50 295 and 50-304

Attachment:

As stated Distribution:

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%...../p November 5, 1997 MEMORANDUM To: Robert A. Capra, Director Project Directorate 1112 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation FROM: Clyde Y. Shiraki, Senior Project Manager Project Directorate ill 2 Division of Reactor Projects . Ill/IV Office of Nuclear Reactor Regulation

SUBJECT:

EVALUATION OF ZION CONTAINMENT SHELL FOR MAIN STEAMLINE BREAK i

As part of its analyses for a steam generator tube plugging amendment, Commonwealth Edison Company (Comed) performed containment response analyses which showed the limiting pressure following a postulated main steamline break (MSLB) is 46.33 psig. The limiting loss-of-coolant accident containment peak pressure is 3g.24 psig. Thus, with respect to containment peak pressure, the containment peak pressure ret Nnse following a MSLB will be the limiting design basis accident. The 46.33 psig following a MSLB is very close to the containment design limit of 47 psig and merits analysis by the staff.

In addition, the calculation shows that the containment peak surface temperature will reach 271.36 degrees Fahrenheit, which exceeds the Zion Station Updated Final Safety Analysis Report Post Accident Environment Figure 6.21 value of 271 degrees Fahrenheit. Zion Station environmental qualification personnel evaluated the higher temperature and determined that it is acceptable. The validity of this determination should also be evaluated by the staff.

Attached is a Zion Nuclear Gtation calculation that addresses 1) the peak main steamline break pressure of 46.33 psig, and 2) the maximum strain in the containment liner due to a surface temperature of 273 degrees Fahrenheit, which is slightly higher than the peak surface temperature of 271.36 degrees Fahrenheit. This calculation will be forwarded to the appropriate technical branches for evaluation.

Docket Nos. 50 295 and 50 304

Attachment:

As stated

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