ML20140G985

Notifies of ACRS Subcommittee on Midland Plant 700610 Meeting in Washington,Dc to Discuss Atws,Design Approaches, Addl Primary Sys Safety Valve Capacity & Process Steam Purity & Monitoring

ML20140G985
Person / Time
Site:	Midland, 05000000
Issue date:	05/14/1970
From:	Mckinley J Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
Shared Package
ML19255C661	List: IA-85-602, Forwards Revised Schedule for ACRS Subcommittee on Midland Plant 820429 Meeting in Washington,Dc to Discuss Util Remedial Action Re Soils & Structural Settlement Issues. Related Info Encl IR 05000330/1977002 ML19255C660 ML20133D109 ML20140B741 ML20140B746 ML20140B751 ML20140B759 ML20140G820 ML20140G826 ML20140G835 ML20140G840 ML20140G846 ML20140G850 ML20140G856 ML20140G862 ML20140G868 ML20140G873 ML20140G878 ML20140G886 ML20140G891 ML20140G901 ML20140G906 ML20140G912 ML20140G916 ML20140G928 ML20140G933 ML20140G938 ML20140G942 ML20140G947 ML20140G951 ML20140G955 ML20140G961 ML20140G968 ML20140G973 ML20140G978 ML20140G985 ML20140G990 ML20140G996 ML20140H002 ML20140H008 ML20140H013 ML20140H020 ML20140H024 ML20140H028 ML20140H035 ML20140H040 ML20140H045 ML20140H052 ML20140H057 ... further results
References
FOIA-85-602 NUDOCS 8510080341
Download: ML20140G985 (1)

Text

.

$f I

May 14, 1970 7,

l l

ACRS Members AGENDA POR JUNE 10, 1970 SUBCatetITTEE MgETING ON THE WN.AMD PLANT The meeting will be held at 1717 E Street N. W., Washington, D. C.

in Room 1046. The tentative schedule for Wednesday, June 10, 1970 is:

8:30 A.M. -- Executive Session 9:00 A.M. -- Meeting with the Regulatory Staff i

10:00 A.M. -- Meeting with Consumers Power Company 12:00 NOON -- LUNCH 1:00 P.M. -- Continus meeting with Consumers Pouer Company 4:00 P.M. -- Caucus 4:30 P.M. -- Adjourn Topies to be discussed include:

1.

Anticipated transients with a failure to scram. The transients to be considered include:

(a) Trip of all four coolant pumps (b) Trip of all hotw il pumps (c) Loss of offsite pc,ver l

(d) Loss of load with the control system inoperative l

l 2.

The amount of additional primary system safety valve capacity and baron poison addition rate required to mitigate the conseques:es of the events postulated in item 1 above.

3.

Design approaches that might be useful if a decision is made to provide for a failure to scram. Consideration should be given to feasibility, practicability, and potential effect on other engineered safety features, e.g. diesel generator capacity.

4.

Process steam purity and monitoring.

w Topics may be added to or deleted from the above list at the discretion of the Subcommittee Chairman.

J. C. L',ti:My,.i J. C. McKinley j

Staff Assistant s

omer >

ACRS N.

sunnauc >....J. 4...Norphy..JCH:DP 5/14/7 8510080341 850930 oAvr >

PDR FDIA h/A-If" 01-Form AEC-518 (Rev. 9-53) AECM 0240

• u. s. o BRUNNER85-602 PDR B/So

- _