ML20054H950
| ML20054H950 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/21/1982 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8206250245 | |
| Download: ML20054H950 (10) | |
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t Docket No. 50-29
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LICENSEE:
YANKEE ATOMIC ELECTRIC COMPANY- (YAEC) 4 FACILITY:
Yankee Nuclear Power Station
SUBJECT:
SIDMARY OF MAY 11, 1982 MEETING CONCERNING S'YSTEMATIC EVALUATION PROGRAM (SEP) TOPICS FOR YANKEE On May 11, 1982, members of the staff met with representa ves of YAEC.
The purpose of the meeting was to discuss a proposed new dedicated shutdown system for the Yankee Nuclear Power Station. A summary of f
the discussion follows and a list of attendess is enc 3esed.
1
/5 Yankee Dedicated Shutdown System
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As a result of several evaluations completed as part of the Systematic
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Evaluation Program (SEP), YAEC has determined that additional; decay heat removal capability would be desirable at Yankee..The evaluations -
which identified this need concerned themselves with the' effects of-
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natural phenomena on the plant and other possible commou. mode failure v
l mechanisms. Although Yankee already has several redu=Aant and diverse means available for decay heat removal, the installatica of a dedicated safe shutdown system was deemed desirable.
The new system would consist of at least one diesel-engine driven. pump, which would be mounted on a trailer. The pump would take a suction from the fire water storage tank, which is located at a distance from the- }
remainder of the plant, and would provide both make-up to the primary system
,I and emergency feedwater to the steam generators to remove decay heat.
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Additional system design assumptions and objectives are described in After the licensee's presentation of the basic system, design, members of the staff asked questions and ' discussed the potential of the system, 7
The staff agreed that the idea of a dedicated shutdown system was very promising and discussed past staff *F o val of such systems at other reactor sites. The licensee agreea % formally propose installation of the system, and provide a m e de ail.cd design description.
4ginal Signed By 4
Ralph Caruso, Project Menager B206250245 820621 Operating Reactors Branch #5 PDR ADOCK 05000029 Division of Licensing
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s a 2*1'1982 Mr. James A. Kay
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cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108 U. 5. Environmental Protection Agency Region I Office ATTN:
Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 Massachusetts Department of Public Utilities ATTN:
Chairman Leverett Saltonstall Building Government Center 100 Cambridge Street Boston, Massachusetts 02202 Resident Inspector C'
Yankee Rowe Nuclear Power Station c/o U.S. NRC P. O. Box 28 Monroe Bridge, Massachusetts 01350 Ronald C.. Haynes, Regiona1' Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 I
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Encloc.ura 1 k
LIST GF ATTENDEES R. lierman NRC R. McKenna iikC l
R. Caruso NRC l
M. Boyle NRC A. Kadak YAEC J. Thayer YAEC S. Fournier YAEC
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U Docket NRC PDR Local PDR ORB Reading G. Lainas T. Ippolito, ORAB - MS 545 Project Manager OELD IE (1)
R. Herman E. McKenna R. Caruso NSIC ACRS (10)
M. Schaaf S. Vaiga D. Vassallo R. Clark J. Stalz t
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Enclexura 2 SYSTEM ASSUMPTIONS
. SYSTEM DESIGN SOLELY FOR SEISMIC EVENT.
. PRIMARY PRESSURE BOUNDARY REMAINS INTACT (I.E., NO LOCA OCCURS)
AND ECCS OPERATION IS NOT REQUIRED.
. REACTOR SHUTDOWN (SCRAM) HAS OCCURRED.
. ALL OTHER MEANS OF ADDING WATER TO THE STEAM GENERATORS AND MAIN COOLANT SYSTEM HAVE BEEN RENDERED INOPERABLE.
. NON-RETURN VALVES HAVE CLOSED T0 ISOLATE MAIN STEAM SYSTEM.
. LOSS OF BOTH ON-SITE AND OFF-SITE AC POWER HAS OCCURRED.
. SYSTEM MUST BE OPERABLE WITHIN 30 MINUTES FOLLOWING A SEISMIC
- EVENT WHICH DISABLES ALL OTHER COOLING SYSTEMS,
. SYSTEM MUST BE CAPABLE OF OPERATING FOR THREE (3) DAYS WITHOUT BRINGING IN ADDITIONAL MAKEUP WATER OR DIESEL FUEL.
. SYSTEM DESIGNED TO SUPPLY 200 GPM AT 1200 PSIG; 150 GPM TO STEAM GENERATORS AND 50 GPM TO PRIMARY SYSTEM.
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INSTRUMENTATION NEEDED TO MONITOR PLANT PARAMETERS DURING SYSTEM OPERATION WILL BE PROVIDED BY EXISTING OR NEW INSTRUMENTS.
(SEE LIST)
PUMP AND DRIVE WILL BE TRAILER MOUNTED EQUIPMENT.
SYSTEM IS INDEPENDENT OF ALL OTHER SYSTEMS EXCEPT FIRE, BLOWDOWN, AND CHARGING.
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INSTRUMENTATION MAIN COOLANT PRESSURE MAIN COOLANT TEMPERATURE
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PRESSURIZER LEVEL STEAM GENERATOR LEVEL (4 CHANNELS)
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SUMMARY
REACTOR COOLANT PRESSURE B0UNDARY SEISMIC SECONDARY BOUNDARY SEISMIC PUMPING SYSTEM PIPING SEISMIC PUMP AND DRIVER TRAILER MOUNTED WITH FLEXIBLE CONNECTIONS TO SUCTION AND DISCHARGE PIPING i
ASSUMED THAT ALL PRIMARY MAKEUP AND SECONDARY FEED FROM OTHER SOURCES NOT AVAILABLE.
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