ML19308C955

Provides Supplemental Rept on Review of Midland CP Application Amends,Completed at 700917-19 ACRS Meeting 125

ML19308C955
Person / Time
Site:	Crane, Midland
Issue date:	09/23/1970
From:	Hendrie J Advisory Committee on Reactor Safeguards
To:	Seaborg G US ATOMIC ENERGY COMMISSION (AEC)
References
TASK-TF, TASK-TMR NUDOCS 8002110694
Download: ML19308C955 (2)

Text

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ADVlid'f COMMITTEE ON RE/.CTOR $mFEGUARDS

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September 23, 19.70 n

Hono'rable Glenn T. Seaborg Chairman U. S. Atomic Energy Com:Aission Washington, D. C.

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Subject:

SUPPLEMENTAL REPORT ON MIDLAND PLANT UNITS 1 AND 2

Dear Dr. Seaborg:

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At its 125th meeting, September 17-19, 1970, the Advisory Cournittee on Reactpr Safeguards completed its review of emendments to the application f.

by the Consumers Power Company to construct the Midland Plant Units 1

'.3 and 2.

This proj'ect was ti-, subject of a report to you dated June 18, 1970 The review was reor ned in consideration of additional submittals

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by the applicant proposing an increase i,n the Jesign pressure of the-

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containment structure and the addition of a sys.em of reboilers for the generation of steam to be' exported to the Dow Chemical Compan'y. These,

i "y changes were considered at a Subcommittee necting held in Washington, D. C. on September 14, 1970. The Committee had the benefit of discussion

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with representatives and consultants of the Consumers Power Company,

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Babe 6ck and Wilcox Company, Bechtel Corporation, Dow Chemical Company, and the AEC Regulatory Staff. The Committee also had the benefit of the documents listed.

The applicant has revised downward his estimate of the free volume and

. internal surface area of the containment structure and has revised upward to 60 psig the calculated peak containment pressure reached in

,' the unlikely event of a loss of co,olant accident. The containment

.l J..j design pressure bas been raised to 67 psig to provide a suitable margin above the peak accident pressure, and an increased number of prestress-l Q:

ing tendons will be provided in the containment structrre to accom:nodate p

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[_Q the increased pressure. No changes in the structural design criteria O

are proposed. The Committee believes these changes are satisfactory.

tI In the earlier design the export steam was taken from the secondary side T.,

• of.the main steam generators and might contain traces of radioactive leakage from the primary system. The applicant now proposes to use this steam in a system of shell and tube rebollers to generate tertiary steam for export to the Dow Chemical Company. Secondary steam condensate l'".

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from the reboilers is returned to the turbine condenser hot well while j'-

feed water for the tertiary side of the reboilers is supplied by con-densate from @: tertiary steam which is supplemented as required by

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-Honorable Glenn T. Seaborg deptemner z.s, t*>/o

. demineralized unte'r froin Lake Ifuron.

Blowdown from the reboilers is normally routed to the Dow waste treatment system for disposal to the

. river but may be sent to the radwaste' system of the nuclear plant. if secon'dary to tertiary leakage is detected.

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The applicant proposes to install monitoring and analytical facilities

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to determine the Icvels of radioactivity in the export steam as described in the June 18, 1970,' letter; these include an on-line analyzer for gannua activity and sensitive low level beta counting equipment for analysis of sampics of the condensed steam. The applicant expects that the tertiary e

steam delivered to Dow will contain no more radioactivity than the treated

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,,make-up water from Lake !! uron.

Recycling tertiary steam condensate may result in some slight concentration of naturally occurring radioactivity in the reboiler system but is not expected to effect the validity of the comparison between steam and make-up water radioactivity as a sensitive in'dication of Icakage in the rebo11ers. If detectable leakage occurs.

corrective action bill be taken in the plant or delivery of export steam will be terminated.

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h.1 The applicant agrees to demonstrate the analytical equipment. and pro-cedures in* development programs to be carried forward during construction of the Midland Plant.

The Committee believes that the proposed system of reboilers will provide (l

substantial additional assurance that Icakage of' primary system radio-

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activit.y into the export steam can be maintained at an extremely low and insignificant level and that the export steam can be maintained essentially at natural background levels. The detailed procedures for monitoring and control of, the reboiler system should be developed during construction in a manner satisfactory to the Regulatory Staff. The Conmittee wishes

- to be.kept informed.

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., N The Committee bel'ieves that the above items can'be resolved during con-R; struction and if due consideration is given to these items and to the

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items referred to in l'ts June 18, 1970 report, the nuclear units proposed p;;j for the Midland Plant can be' constructed with reasonable assurance that p e'<

they can be operated without undue risk to the health and safety of,the public.

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Sincerely yours,

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Joseph M. Tiendrie L;4 "-5

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, References 1.

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1) Amendments 14~-18 to the License Application h

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