ML20009A203

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Informs That Evaluation & Other plant-specific Data Re Safety & Relief Valve Testing Program Will Be Submitted by 810807,in Response to NUREG-0737,Item II.D.1
ML20009A203
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/01/1981
From: Baynard P
FLORIDA POWER CORP.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 3-071-01, 3-71-1, NUDOCS 8107090229
Download: ML20009A203 (1)


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  1. 3-071-01 File:

3-B-5-a Mr. Harold R. Denton Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

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Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG 0737 - Item II.D.1 Safety and Relief Valve Testing Program

Dear Mr. Denton:

NUREG-0737, Clarification of TMI Action Plan Requirements, Item II.D.1 requires a safety and relief valve testing program to qualify reactor coolant safety and relief valves under expected transient and accident conditions.

It further requires a report on the results of this testing and plant specific submittals confinning the adequacy of safety and re-lief valves, based on the test program, by July 1, 1981.

This submittal satisfies for Florida Power Corporation that requirement for all testing completed through June 19, 1981.

By letter dated July 1, 1981, R. C.

Youngdahl (Consumers Power Co.)

transmitted the Interim Data Report for the EPRI PWR Safety and Relief Valve Test Program.

This report summarizes the test data collected to date on relief and safety valves.

Crystal River Unit 3 has a Dresser Industries Model 31533VX-3 Electromatic Relief Valve and two Dresser Industries Model 31739A safety valves.

Relief and safety valves repre-sentative of the above valves are being tested as part of the EPRI program.

We will submit evaluations and other plant specific data by August 7, 1981.

-7 D N Very truly yours, s

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