ML17037B602
| ML17037B602 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/01/1978 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Dise D Niagara Mohawk Power Corp |
| References | |
| Download: ML17037B602 (6) | |
Text
Donk~t FEBRUARY 1 Docket No. 50-220 Niagara Hohawk Power Corporation ATTN:
Hr. Donald P. Disc Vice President Engineering 300 Erfe Boulevard )lest
- Syracuse, Hew York 13202 Gentlemen:
RE:
NINE tfILE POINT In a report titled "Evaluation of Incidents of Primary Coolant Release From Operating Boiling lfater Reactors" issued by the U. S. Atomic Energy Commission on October 30, 1972, the regulatory staff reported the results of a study of eight incidents, involving the unintentional discharge of primary coolant through safety and relief valves during reactor operatfon, which occurred at B)lR facilities during 1970 through 1972.
One of the staff recommendations resulting from this study was that the BWR feedwater control systems should be designed to automatically control reactor vessel water level during anticipated transients without flooding of the main steam line or the lines to other safety-related equipment.
The following suggested performance objectives for the GWR feedwater control
- system, which included considerations of both maximum and minimum water levels to be maintafned during anticipated transients, were identified by the staff:
1.
The maximum water level attained should not initiate isolation of any safety feature, such as the high pressure coolant injection system, or disable any system or component required for the orderly shutdown of the reactor, and 2.
the minimum water level attained should. not require the activation of arly safety system.
A recent event at a foreign certain reactor vessel high safety/safety-rel fef val ves containment.
reactor facility has demonstrated that, under water level conditions, damage may result to and other equipment 'located insfde the OFFICE~
SURNAME~
DATE~
NRC FQRM 318 (9-76) NRCM 0240 6 U 8, OOVERNMENT FRINTINO OFFICEI IOTS 02~24
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'EBRUARY 1 578 The installation of an automatic feedwater pump trip function on reactor-vessel. high water level for most operating BWR-3 and BMR-4 facilities has satisfied the intent of the staff's recommendations in this regard.
- However, we believe that several of the older operating BHR facilities, including your facility, have not yet incorporated this design. feature, i.e., automatic feedwater pump trip on high reactor vessel water level.'ccordingly, we request that you info~i us, within 30 days of receipt of this letter, of your intentions to install such a protective feature and provide us with your schedule for installation.
If you do not plan to install such a feature, we request that you provide us with your basis for not doing so.
Sincere'ly, Original slgn08 Pf'eorge Lear, Chief Operating Reactors Branch ¹3 Division of Operating Reactors cc:
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-. 3-cc:
Eugene B. Thomas, Jr.,
Esquire
- LeBoeuf, Lamb, Leiby 8 HacRae 1757 N Street, N.
W.
Washington, D.
C.
20036 Anthony Z. Roisman, Esquire
- Sheldon, Harmon and Roisman
~ 1025 15th Street, H.
W.
5th Floor Washington, D.
C.
20005 Oswego County Office Building 46 E. Bridge Street
- Oswego, New York 13126
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