ML20042A664

Ro:Operating Procedures Will Be Revised to Require Operability of Safeguards Equipment Necessary to Mitigate Steamline Break Transient Prior to Heating RCS Above 350 F from Cold Shutdown

ML20042A664
Person / Time
Site:	Indian Point
Issue date:	03/11/1982
From:	Christopher Jackson CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8203230661
Download: ML20042A664 (2)

Text

_. o Ch:rl:s W, J:cks:n vo. N.ea Cor';ohd3te'l Ed%n Comgw:y r,f P&w 106. Inc Irdan f o nt Maton BroJ % y & [ Urn ey A w Ouc har:an_ fJ v' 10511 Te% hor *t Ot 4J 73 7-811t, March 11, 1982 RE: Indian Point Unit No. 2 Docket No. 50-247 q J\l l?] ~/..! ' n SC/ -/ /

Mr. Ronald C. Il a y n e s , Regional Administrator s \f g Office of Inspection and Enforcemen* , ,

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Region I -

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King of Prussia, PA 19406 \, "

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Dear Mr. Ilaynes:

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In accordance with the Technical Specifications of Facility Operating Licence No. DPR-26, the following confirms notification on March 9, 1982 to Mr. Walter Baunack of your office by Mr. John Basile of Con Edison of a potential Reportable Occurrence LER-82-010. This event is of the type defined in Technical Specification Section 6.9.1.7.1.f.

The steamline break accident analyses for Indian Point Unit No. 2 are presented in Section 14.2.5 of the FSAR, Cases analyzed assume that the unit is initially at hot shutdown conditions since these conditions result in the most conservative assessment of effects on the reactor core and coolant systems.

As part of the analyses, certain minimum engineered safe-guards equipment is assumed to operate to mitigate and terminate the transient. Presently, plant operating procedures require the necessary safeguards equipment to be operable prior to bringing the reactor critical but do not establish specific operability requirements for this eguipment when the reactor coolant system Thus, temperature exceeds 350 F and the reactor is not critical.

to provide clear direction for the plant operators, we shall revise our operating procedures to explicity require the opera-bility of safeguards equipment necessary to mitigate a steamline break transient prior to heating the reactor coolant system above 350 F from the cold shutdown condition.

8203230661 820311 gDRADOCK 05000247 PDR gt'l l

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Mr. Ronald C. Haynes March-11, 1982

. Consolidated Edison believes that'this report also satisfies the requirements of 10 CFR Part 21.

Very truly yours ,

J J

Charles W. Jackson Vice President Nuclear Power CWJ:ah cc: Mr. William Mcdonald, Director (2 copies)

Office of Management'Information and-Program Control c/o Distribution Services Branch DDC, ADM U. S. Nuclear Regulator 3 Commission Washington, D.C. 20555 Mr. T. Rebelowski, Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511 l

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