ML18086B040

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Forwards Revised Operator Requalification Training Program Incorporating Operating Experience Review of 800611 St Lucie Event.Revision Will Allow Operators to Prevent Reactor Vessel Voiding During Natural Circulation Cooldown
ML18086B040
Person / Time
Site: Salem  PSEG icon.png
Issue date: 11/16/1981
From: Uderitz R
Public Service Enterprise Group
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML18086B041 List:
References
GL-81-21, NUDOCS 8111200654
Download: ML18086B040 (2)


Text

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Public Service Electric and Gas Company Richard A. Uderitz 80 Park Plaza, Newark, NJ 07101 201-430-7380 Mailing Address: P.O. Box 570, Newark, NJ 07101 Vice President Nuclear November 16, 1981 Mr. Darrell G. Eisenhut, Director Division of Licensing Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NATURAL CIRCULATION COOLDOWN GENERIC LETTER NO. 81-21 SALEM GENERATING STATION UNIT NOS. 1 AND 2

Dear Mr. Eisenhut:

Our review of the St. Lucie Unit No. 1 event of June 11, 1980, led to the development of procedures and training which will enable our operators to prevent, or recpgnize and mitigate reactor vessel voiding during natural circulation cooldown.

In January 1981, instructions based on Westinghouse Owners Group guidelines were appended to Salem Unit Nos. 1 and 2 Emergency Instructions; EI-4.9, Station Blackout; and EI-4.15, Loss of Component Cooling. These appendices provide in'structions necessary to place the plant in Cold Shutdown while on natural circulation following either a blackout or loss of the Component Cooling System. The cooldown rate is limited to 20-25°F/hr.; a soak at 350°F is included to allow reactor vessel head temperature to dissipate; and, Reactor Coolant System pressure is reduced, following the soak, at less than 750 psi/hr.

A computer analysis was conducted which concluded that, using the station natural circulation proceduresi no voiding in the reactor vessel head will occur; and, during Salem Unit No. 2 Startup Test Program, a natural circulation cooldown was conducted to verify boron mixing and cooling capability while on natural circulation.

Although the cooldown test did not continue through to Cold Shutdown, it did provide recorded data supporting the procedural capability to cool down in a controlled manner without void formation in the reactor vessel head.

The supplies of condensate grade auxiliary feedwater have been verified more than adequate to support the natural circulation cooldown procedures.

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Mr. Darrell G. Eisenhut, Director U.S. Nuclear Regulatory Commission 11/16/81 Operating Experience Review of the St. Lucie event was incorporated into our formal Salem Operator Requalification Training Program on January 20, 1981. Copies of the Lesson Plan, Instructors Lesson Plan and St. Lucie Study Assignment Sheets are attached for your review.

Additional guidance from Westinghouse Owners Group has been received and is presently being reviewed for possible methods by which we can further enhance our natural circulation cooldown procedures and training program. As new information becomes available, it will be carefully considered for inclusion in our ongoing effort to upgrade plant operations and safety.

If you have any further questions, we will be pleased to discuss them with you.

Sincerely, Attachments