ML20235W942

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Provides Revised Formal Response to NRC Operational Safety Assessment.Adu Sys Incorporates Pressure Relief Valves & Not Rupture Disks as Previously Reported.Routine Testing Program Will Be Implemented to Ensure Operability
ML20235W942
Person / Time
Site: Westinghouse
Issue date: 07/13/1987
From: Loch E
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Stohr J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8707230785
Download: ML20235W942 (1)


Text

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Nucley Fuel Dmdon Westinghouse

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Electric Corporation Drawer R Columbia Saum Carohna 20250

603 776 2610 July 13, 1987 O

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U. S. Nuclear Regulatory Commission c:

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ATTN:

Mr. 3. Philip Stohr, Director Division of Radiation Safety and Safeguards 55 Region II 101 Marietta Street, N. W.

Atlanta, Georgia 30323 Gn Gentlemen:

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SUBJECT:

NRC Inspection Report No. 70-1151/87-01 Westinghouse Letter Dated May 21, 1987 In the above-referenced letter, Westinghouse responded to the NRC Operational Safety Assessment.

Regarding Response No. 22 (IFI 87-01-29),

we herein provide a revised formal response to this item.

In our initial letter, we erroneously reported that there were no pressure relief devices in either the ADU or IDR vaporization systems.

Although this Js true for the IDR system (these vaporizers operate at ambient pressures), the ADU system does incorporate pressure relief valves and not rupture disks as previously reported.

For these valves, a routine testing program will be implemented to ensure operability.

We apologize for this error.

If you have additional questions, please contact me at the above aodress or telephone me at (803) 776-2610, Extension 3301.

Sincerely, kESTItCHOUSE ELECTRIC CORPORATION k

E. P. Loch, Manager Columbia Plant lb WP1487E:3p.32

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