ML20140G996

Documents Conclusions Reached During ACRS 122nd Meeting Re Midland Plant Units 1 & 2 Request for Exemption to Allow Certain Const & ESF Instrumentation for Indian Point 2

ML20140G996
Person / Time
Site:	Dresden, Indian Point, Midland, 05000000
Issue date:	06/17/1970
From:	Fraley R Advisory Committee on Reactor Safeguards
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
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 8510080357
Download: ML20140G996 (2)

Text

[

1 j

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 June 17, 1970 Dr. Peter A. Morris, Director Reactor Licensing EttR0ltp1RON OF ITEMS DISCUSSED DURING THE 122ND ACRS MEETING This memorandum is to document the conclusions reached during the 122nd ACRS Meeting with respect to the items noted:

Midland Plant Units 1 & 2 Request for exemption to all.ow certain construction: The Committee concluded that this item can be handled by the nee,1 story Staff.

2.

Indian Point Nuclear Generating Unit No. 2 g

Reactor Protection and Engineered Safety Feature Instrumentation and Controls:

(Ref. Special Report to the ACRS, Indian Point Nuclear Generating Unit No. 2, Operating License Review.)

i With regard to the overtemperature AT" trip set points with a.

less than four loops in service: For Indian Point Unit 2 and other Westinghouse reactors already approved for oper-ation, the AT set points need not be automatically reset.

For future plants (plants subsequent to Turkey Point were tentatively identified) the ACRS supports the Staff position that automatic reset, or the equivalent, is to be required.

b.

With respect to the panels for manual control of engineered safety features, the Committee agreed that modifications of these already-built panels is not justified.

c.

With respect to the scram by pass test switches, the Committee suggested that DRL should investigate the adequacy of the. proposed arrangement.

3.

Dresden Nuclear Unit 2

~

Use of Furnace Sensitized Stainless Steel Safe Ends: The l

Fo/ A-P 5401 B l'2.Y 8510000357 850930 1

PDR FOIA BRUNNER85-602 PDR

c P. A. Morris -

• I Committee believes that the proposed inspection of three safe ends during the current shutdown is inadequate. Rather, the Comittee believes the minimum inspection should include two core spray nozzle safe ends, two recirculation inlets, and two recirculation outlet safe ends during thic shutdown, and the remainder during the proposed October 1970 outage. Inspection of additional safe ends during this outage in lieu of the October outage is permissible. (Additional discussion of this matter is planned for the Committee's 123rd meeting.)

i 4.

Anticipated Transients with Failure to Scram for PWR's The Comittee concurred in the draf t list of transients and Ossociated conditions dated May 15, 1970.

(Ref: P. A. Morris memo to R. F. Fraley, dated June 1,1970.)

R. F. Fraley Executive Secretary i

x 1;

4-h a

4 e

w I

w