ML19296D876

Forwards Addl Info for NRC Review of Facility near-site Study.Includes Necessary Data for Concrete to Reinforcing Steel Weight Ratios & Fsar,Sections 5.1-44,45 & 6.1-4

ML19296D876
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	03/04/1980
From:	Naughton W COMMONWEALTH EDISON CO.
To:	Reeves E Office of Nuclear Reactor Regulation
References
NUDOCS 8003130393
Download: ML19296D876 (7)

Text

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Commonwealth Edison one First National Plaza. Chicago. Illinois

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Address Reply to: Post Office Box 767 Chicago, Illinois 60690 March 4, 1980 Mr. Edward Reeves, Project Manager Operating Reactors - Branch 1 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Zion Station Units 1 and 2 Additional Response to Request for Additional Design Information NRC Docket Nos. 50-295 and 50-304

Reference:

February 20, 1980 letter from W.

F. Naughton to E. Reeves

Dear Mr. Reeves:

Per Reference (a), Commonwealth Edison Company provided the NRC Staff certain design information for the Staff to utilize in its review of the Zior;/ Indian Point Near Site Study.

The attached information supplements that transmitted in Reference (a).

Enclosed is the necessary data for concrete to reinforcing steel weight ratios for containment, primary shield wall, base mat, crane wall, reactor pit, reactor keyway and finish.

Concrete mass is in terms of total weight in kips for each item.

Material specifications for liner plate rebar and concrete, composition of aggregate are also included.

In addition, a copy of the FSAR section showing missile protection criteria is included.

Please address any additional questions that you might have to this office.

Very truly yours, William F. Naughton Nuclear Licensing Administrator Pressurized Water Reactors Enclosure 2158A S003180.,;g 3 q 3

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" 3 l h) h f hAk The major portion uf the predteted nettlements of t/2" to 3/4" for the-containment teulldinh will have taken place prior to the startup of plant operation.

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's. l. 2. 6 MI:;;;l f.1-: l'noTlu; TION

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5.1.2.6.1 Reactor Containment

}iissile protection for the containment liner is provided to comply with the following criteria:

I The containcent and liner are protected from loss of function due a.

to damage by such missiles as, might be generated in a loss-of-coolant

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accident. for break sizes up to and including the double-ended severance O

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. f a reactor Joolant pipe.

o b.

Components required to =sintain containment integrity to ceet the site criteria of 10 CFR 100 are protected against loss of function due to damage by such missiles defined below.

The missile protection necessary to coet the above criteria was dev~ eloped and i=ple=ented using the following considerations:

The Reactor Coolant System is surrounfed by reinforced concrete and a.

steel structures designed to withstand the forces asscelat,d with double-end'cd rupture of a main reactor coolant pipe and des)gned to stop the missiles.

b.

The structural design of the missile shiciding takes into account both static and impact loads.

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}!1ssile velocities were calculated considering both fluid and ecchanical c.

driving forces which can act during misslic generation.

d.

Components of the Reactor Coolant System were examined to identify and to classify missiles according to size, shape and kinetic encray for purpones of analyzing their effects.

s.1 5.1-44

4 7

pg The components examined includcd:

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All valve stems up to and including the largent sir.c to be used.

b.

All valve bonnets c.

All instrument thimbles

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d.

Various type and sizes of nuts and bolts sN e.

Complete control rod drive mechanisms I

f.

' Reactor vessel head bolts Edssiles originating from sources external to the reactor contain=ent are discussed in Section 5.1.2.2(g).

5.1.3

' DESIGN ANALYSIS

-5.1.3.1 ceneral The containment was analyzed by a finite element computer program for individual

. loading cases of dead load, live load, wind, earthquake, temperature, and pressure.

Stress plot's were made by summing the stresses from required combinations of loading cases and the areas of high stresses were identified.

The modulus of elasticity at these locations was modified to account for the non-linear stress-strain relationship at high compression and to account for cracking in areas of high tension. The containment was then reanalyzed by the computer where sufficient areas required modification.

The forces and shears were su=med over the cross section and the total moment, axial force and shenr were determined.

From these values, the straight,line elastic stresses were computed and compared with the allowabic values. The ACI-318-63 code design methods and allowabic stresses were used for concrete and pecceressed and non-prestressed reinforcing steel except as noted herein.

-J 5.L-45

t. \\ C'J t'.> b 6 -

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Minn!!e Protection

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Criterion: Adequate protection for thouc engineered nafety features, the failure of which could caune an undue rink to the henith and safety of the public, shall be provided a;;ainst dynamic effects and missilea that mi;;ht result f rom plant ~1uipment failures.

A loss-of-coolant accident or other plant equipment failure might result in dynamic effects or nissiles. For engineered safety features which are required to ensure safcty in the event of such an accident or equipment failure, protection is provided primarily by the provisions which are taken in the design to prevent the generation of missiles.

In addition, protection is also provided by the layout of plant equipment or by missile barriers in certain cases.

Reference is cade to Section 5.1.2 for a discussion of missile protection.

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Injection oaths leading to unbroken reactor coolant loops are protected against damage as a result of the eaximum reactor coolant pipe rupture by layout and structural design considerations. Injection lines penetrate the main. missile barrier, which is the loop compartment wall, and the injection headers are located in the missile-protected area between the loop co=partment wall and the containment wall.

Individual injection lines, connected to the injection header, pass through the barrier and then connect to the loops.

Separation of the individual injection lines is provided to the maximum extent practicabic.

Movement of the injection line, associated with rupture

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of a reactor coo 1 ant loop, is accccuodated by line flexibility and by the

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design of the pipe supports such that no damage outside the loop compartment

'is possible.

Engineered Safety Features Performance Caesbility Criterion: Engineered safety features, such as the emergency core cooling system and the containment heat removc1 system, shall provide sufficient performance capability to accommodate the failure of any singic active component without resulting in undue risk to the health and safety of the public.

Each enginccted safety feature provides suf ficient performance capability to accoembdate any ningle failure of an active component and still function (I

in a manner to avoid undue risk to the health and safety of the public.

4 6.1-4

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