ML20090G820

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Notifies of Intent to Revise 840423 Tech Spec Change Request 110 Following NRC Review & Comment Re Operation of Closed Containment Isolation Valves
ML20090G820
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/23/1984
From: Ken Wilson
FLORIDA POWER CORP.
To: Silver H
Office of Nuclear Reactor Regulation
References
WPA-84-0413, WPA-84-413, NUDOCS 8407250378
Download: ML20090G820 (1)


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POST OFFICE BOX 219 - CRYSTAL RIVER, FLORIDA 32629 - TELEPHONE: (904) 795-3802 Power CoR POR A TION

[p 9g July 23,1984 WPA 84-0413 Mr. Harley Silver, Project Manager Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014

Dear Mr. Silver:

SUBJECT:

Technical Specification Change Request No.110 (TSCRN),

Operation of Closed Containment Isolation Valves On April 23,1984, Florida Power Corporation submitted TSCRN-110 concerning operation of closed containment isolation valves. Since submittal, a Technical Specification amendment and further reviews have indicated a need for clarlilcation.

The basis for operation of the steam generator sample valves (CAV-4,5,6, and 7) was to comply with Specification 2.4.1.0.

With the implementation of the Radiological Effluent Technical Specifications (RETS), this is no longer true. However, due to a need to monitor and control Secondary Side chemistry as recommended by the staff and the OTSG vendor, Florida Power Corporation still requests allowance to operate these valv..s.

The basis for operation of Reactor Coolant System (RCS) sample valves (CAV-1,2,3, and 126) was to monitor and maintain RCS activity within Technical Specification limits. CAV-1, however, is used to sample and vent non-condensible gases from the pressurizer. This is necessary to prevent establishing a "hard" bubble in the pressurizer, making RCS pressure control more difficult.

Florida Power Corporation intends to supplement or revise TSCRN-110 as appropriate following NRC Staff review and comment.

Please do not hesitate to contact me at (904) 795-3802, extension 119, if I can be of assistance.

Sincerely,d%

K.R. Wilson, Supervisor Site Nuclear Licensing KRW:nrk

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Mr. V. Panciera Mr. T. Stetka is '0 8407250378 840723 PDR ADOCK 05000302 P

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