ML17055E732
| ML17055E732 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/23/1989 |
| From: | Slosson M Office of Nuclear Reactor Regulation |
| To: | Burkhardt L NIAGARA MOHAWK POWER CORP. |
| References | |
| TAC-72195, NUDOCS 8906010098 | |
| Download: ML17055E732 (6) | |
Text
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-"Docket No. 50-220 Mr. Lawrence Bur khardt III Executive Vice President, Nuclear Operations Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 The inspection team identified that the calculation supporting the flow rate did not account for the higher elevation of the feedwater nozzles from the condenser hotwell.
As indicated in the Bases, during reactor startup and shutdown, only the condensate and feedwater booster pumps are in operation at reactor pressures below approximately 400 psig.
The motor driven feedwater pump is in standby.
However, if the HPCI initiation signa'i occurs, the feedwater pump would automatically start.
The HPCI system is designed to provide a reliable source of high pressure injection in the event of a small line break.
However, it does not have a source of emergency power and is not considered in the accident analyses for the plant.
Based on the above, the staff agrees with the licensee's conclusion that the Bases change will not reduce the margin of safety and merely corrects an error in the current Bases.
Enclosed is a copy of the revised Bases page 73.
This concludes the staff's action with respect to TAC No. 72195.
t May 23, 1989 DISTATION Q'ODD PNRC P
R PDI=1 Rdg Local PDR SVarga BBoger RCapra CVogan MSlosson RBenedict OGC DHagan EJordan BGrimes TMeek (4) llJones
Dear Mr. Burkhardt:
JCalvo ACRS (10)
- OJohnson, RI
SUBJECT:
BASES CHANGE TO TECHNICAL SPECIFICATION SECTIONS 3.1.8 AND 4.1.8 FOR NINE MILE POINT UNIT NO.
1 (TAC NO. 72195)
By letter dated February 13, 1989, Niagara Mohawk submitted a proposed change to the Bases for the Nine Mile Point Unit 1 Technical Specification Sections 3.1.8 and 4.1.8.
The change corrects an error in the Bases.
The current Bases indicates that the condensate and feedwater booster pumps can deliver 3800 gallons per minute at pressures up to approximately 450 psig.
The licensee has indicated that a review of the pump curves shows that the pumps can deliver 3800 gallons per minute of feedwater to the reactor at pressures up to approximately 270 psig.
The error was discovered during an NRC Safety Systems Functional Inspection conducted September 12, 1988 through October 7, 1988.
GPA/PA ARM/LFMB Original signed by
Enclosure:
Revised Page 73 cc:
See nex't page I PROPOSED CHANGE TAC 72195j Marylee M. Slosson, Project Manager Project Directorate I-1 Division of Reactor Projects I/II
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~-,Mr. L. Burkhardt III Niagara Mohawk Power Cor ration Nfne M
Pofnt Nuclear Station, Unit No.
1 CC:
Mr. Troy 8. Conner, Jr., Esqufre Conner 5 Wetterhahn-Sufte 1050
'747 Pennsylvania
- Avenue, N.
W.
k'ashfngton, D. C.
20006 Mr. Frank R. Church, Supervisor Town of Scrfba R.
D, g2
- Oswego, New York 13126 Mr, James L. Wfllfs General Supt.-Nuclear Generation Nfagar a Mohawk Power Corpor ation Nine Mile Point Nuclear Station Post Office Box 3~
- Lycomfng, New York 13093 Pesfdent Inspector U. S.
Nuc1ear Regulatory Comnfssfon Post Office Box 126
- Lycomfng, New York 13093 Mr. Gary D. Wilson, Esqufre Niagara Mohawk Powt.r Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U. S. Nuclear Regulatory Comaissfon 475 Allendale Road King of Prussfa.
Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Mr. Kfm Dahlberg Unft 1
S tati on Super fntendent Nine Mile Pofnt Nuclear Station Post Of<fee Box 32 I ycomfng, New York 13093 Mr. Peter E. Francfsco, Lfcensfng Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Charlie Donaldson, Esouire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul D. Eddy State of New York Department of Public Service Power Dfvfsfon, System Operations 3 Empire State Plaza
- Albany, New York 12223
BASES FOR 3.1.8 AND 4.1.8 HIGH PRESSURE COOLANT INJECTION The High Pressure Coolant Injection System (HPCI) is provided to ensure adequate core cooling in the unlikely event of small reactor coolant line break.
The HPCI System is required for line breaks which exceed the capability of the Control Rod Drive pumps and which are not large enough to allow fast enough depressurization for core spray to be effective.
One set of high pressure coolant injection pumps consists of a condensate
One set of pumps is capable of delivering 3,800 gpm to the reactor vessel at reactor pressure.
The performance capability of HPCI alone and in conjunction with other systems to provide adequate core cooling for a spectrum of line breaks is discussed in the Fifth Supplement of the FSAR.
In determining the operability of the HPCI System, the required performance capability of various components shall be considered.
a.
The HPCI System shall be capable of meeting its pump head versus flow curve.
b.
The motor driven feedwater pump shall be capable of automatic initiation upon receipt of either an automatic turbine trip signal or reactor low-water-level signal.
c.
The Condenser hotwell level shall not be less than 57 inches (75,000 gallons),
d.
The Condensate storage tanks inventory shall not be less than 105,000 gallons.
e.
The motor-driven feedwater pump will automatically trip if reactor high water level is sustained for ten seconds and the associated pump downstream flow control valve is not closed.
During reactor startup and shutdown, only the condensate and feedwater booster pumps are in operation at reactor pressures below approximately 400 psig.
The feedwater pump is in standby.
However, if the HPCI initiation signal
- occurs, the feedwater pump would automatically start.
Calculations show that the condensate and feedwater booster pump alone are capable of providing 3800 gpm at a reactor pressure of approximately 270 psig.
The capability of the condensate, feedwater booster and motor driven feedwater pumps wi 11 be demonstrated by their operation as part of the feedwater supply during normal station operation.
Stand-by pumps will be placed in service at least quarterly to supply feedwater during station operation.
An automatic system initiation test will be performed at least once per operating cycle.
This will involve automatic starting of the motor driven feedwater pumps and flow to the reactor vessel.
0301S (proposed) 73
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