ML20244C807

Forwards ACRS Repts Re Dresden Units 2 & 3 & Millstone Point Bwrs for Info & Guidance in Preparation of Technical Info in Support of Application for Provisional Ol.Special Consideration of Adequacy of ECCS for Util Suggested

ML20244C807
Person / Time
Site:	Nine Mile Point
Issue date:	10/20/1966
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Pratt M NIAGARA MOHAWK POWER CORP.
Shared Package
ML17055E652	List: IA-89-101, Informs of Completion of Review of Application by Niagara Mohawk Power Corp for Conversion of Util Provisional OL to full-term OL During ACRS 740905-07 Meeting.Concurs in Subj License Conversion IA-89-114, Confirms 740624 Meeting Re Author Review of Util SER & Concurrence Subj to Revs Discussed ML20244C683 ML20244C712 ML20244C715 ML20244C728 ML20244C740 ML20244C768 ML20244C776 ML20244C791 ML20244C807 ML20244C810 ML20244C813 ML20244C816 ML20244C818 ML20244C821 ML20244C825 ML20244C827 ML20244D471 ML20244D475 ML20244D485 ML20244D499 ML20244D512 ML20244D553 ML20244D969 ML20244D979 ML20244D984 ML20244D995 ML20244E011 ML20244E026 ML20244E032 ML20244E123 ML20244E128 ML20244E141 ML20244E163 ML20244E184 ML20244E223 ML20244E231 ML20244E248 ML20244E270 ML20244E353 NUREG-1125, Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in Pdr.Acrs Rept Subj to Request Published in NUREG-1125,Vol 2, Compilation of ACRS Repts
References
FOIA-89-101, FOIA-89-114 NUDOCS 8904200426
Download: ML20244C807 (2)

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• W October 20,19k Y

Docket No. 50-220

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Niagara Mohawk Power Corporation 300 Er'e 2oulevard West I 30* p l

Syracuse 2, New York {

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yL Attention: Mr Minot H. Pratt Vice President and Chief Engineer f d

Gentlemen:

Since Rep'ila tory Staf f and ACRS review of the Nine Mile Point reactor applicatl n for a construction permit, the Commission has issued Construction Permits for the Dresden Unit 2, Millstone Point and Dresden.

0 Unit 3 boiling water reactors. The reports of the ACRS on these reactors indicate several of the major safety considerations that will need to be evaluated in depth during the forthcoming provisional operating license review for the Nine Mile Point reactor. Accordingly, copies of these letters are herewith transmitted to you for your information and guidance in the preparation of the technical information in support of an application for a provisional operating license.

Although it would be desirable to have the topics outlined in these letters discussed in detail in the Final Safety and A:alysis Report, we recognize that printing and filing schedules miphe preclude this. In any event, we j believe it appropriate that you now consider developing the scope of the i information on these topics that will eventually be required.

As a result of the recent Dresden Unit 3 review, significant changes in l

/ the design of the engineered safeguard systems for tnis facility were proposed. These changes involve increasing the effectiveness _and reli-ability of the emergency core cooling systens. The increased capability N

V and reliability results from providing a "Icw pressure, high capacity" (corefloodingsysteminadditiontoandasa" backup"tofheredund, m -< g ant ,y

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October 20, 1966 1

.L Niagara Mohawk Power i Corporation .,.

11 Further, al"high pressure, low capacity" coolant injection system will j

be provided for inventory makeup in the event of small primary system' I ruptures in which the primary system would not depressurize rapidly.  ;

One of the two Emergency Condencers was deleted to permit this change j to be made. The " backup" system will be automatici d? pressurization of .{

the primary system. To further. increase overall station safety, pro- i visions will be included to supply service water to the main steam condenser in order to provide a continuous supply of makeup water for the feedwater system. In regard to emergency power for the engineered safeguard systems, the capacity of the emergency diesel generators will be increased over that originally proposed.

In recognition of the importance of emergency core cooling systems, as evidenced by the above, we believe you should give special consideration to the adequacy of such engineered safeguards for your reactor.

Sincerely yours, O

Petcr A. Morris, Director Division of Reactor Licensing

Enclosures:

As stated above cc: Mr. Arvin E. Upton LeBoeuf, Lamb & Leiby 1821 Jefferson Place, N. W.

Washingbon 6, D. C.

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