ML20041B029

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Provides Documentation to Formally Close Out NUREG-0737 Item II.E.4.2.7 Re Automatic Closure of Containment Purge & Vent Isolation Valves on High Radiation Signal.Util Was in Compliance by 810701 Due Date
ML20041B029
Person / Time
Site: Fort Calhoun 
Issue date: 02/12/1982
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Clark R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM LIC-82-037, LIC-82-37, NUDOCS 8202230182
Download: ML20041B029 (1)


Text

Omaha Public Power District 1623 HARNEY 5 OMAHA. NEBRASMA 68102 e TELEPHONE S36 4000 E 402 0

February 12,198

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[J Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission 9

Office of Nuclear Reactor Regulation g7 Division of Licensing 4.

Operating Reactors Branch No. 3 Washington, D.C 20555

Reference:

Docket No. 50-285

Dear Mr. Clark:

Subject:

NUREG-0737, Item II.E.4.2.7 Documentation Discussion of TMI Item II.E.4.2.7 in Enclosure 3 to NUREG-0737, regard-ing automatic closure of containment purge and vent isolation valves on a high radiation signal, indicates that documentation for compliance is not required.

However, this letter is intended to provide documentation to formally close out Item II.E.4.2.7.

The District was in compliance by the July 1,1981 due date and an August 4,1981 telephone conversation between Mr. T. L. Patterson of the District and Mr. C. M. Trammell of the Commission confirmed the District's conformance.

Discussion of the District's purge and vent valve isolation system is provided below.

A ventilation isolation actuation signal (VIAS) is initiated upon detection of high containment radiation by one of several radiation monitors. VIAS initiates automatic closing of the pertinent containment purge and vent isolation valves, if open, except for the hydrogen purge isolation valves which are manually operated and are normally locked closed. Thus, containment integrity is maintained during an accident situation to prevent inadvertent releases of radiation to the environ-ment. The Fort Calhoun Station Technical Specifications, Tables 2.1 and 2.4, and the Fort Calhoun Station Final Safety Analysis Report, Section 7.3.2b and Table 5.9.1, provide the necessary operational description of VIAS to justify the District's compliance to the subject NUREG-0737 item.

Sincerely, g

W.C.f>

S' Jones Division Manager

/D Production Operations WCJ/KJM/TLP/RWS:jmm cc:

LeBoeuf, Lamb, Leiby & MacRae 8202230182 820212 PDR ADOCK 05000285 P

PDR

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