ML17056B216
| ML17056B216 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1990 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| TAC-76932, NUDOCS 9101090194 | |
| Download: ML17056B216 (8) | |
Text
December 31, f990 Docket No. 50-220 Mr.
B. Ralph Sylvia Executive Vice President, Nuclear Operations Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT:
CHANGE TO THE BASES FOR TECHNICAL SPECIFICATION SECTIONS 3.1.8 AND 4.1.8 FOR NINE MILE POINT UNIT NO.
1 (TAC NO. 76932)
By letter dated June 5, 1990, Niagara Mohawk Power Corporation (the licensee),
proposed a change to the Nine Mile Point Unit No.
1 (NMP-1) Bases for Technical Specifications Sections 3.1.8 and 4. 1.8 - High Pressure Coolant Injection (HPCI).
The proposed change revises the minimum required flow for the HPCI system from 3800 gpm (design flowrate) to 3420 gpm in order to take into account a
10$ flow degradation of the pumps with operation.
This 105 flow degradation is consistent with the flow degradation provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
The staff has reviewed the proposed change to the Bases for Sections 3.1.8 and 4.1.8 and offers no objection.
Enclosed is a copy of the revised Bases page 73.
All staff activities related to TAC No. 76932 are considered complete.
Sincerely, ORIGINAL SIGNED BY)
Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
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Docket No. 50-220 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 31, 1990 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT:
CHANGE TO THE BASES FOR TECHNICAL SPECIFICATION SECTIONS 3.1.8 AND 4.1.8 FOR NINE MILE POINT UNIT NO.
1 (TAC NO. 76932)
By letter dated June 5, 1990, Niagara Mohawk Power Corporation (the licensee),
proposed a change to the Nine Mile Point Unit No.
1 (NMP-1) Bases for Technical Specifications Sections 3.1.8 and 4.1.8 - High Pressure Coolant Injection (HPCI).
The proposed change revises the minimum required flow for the HPCI system from 3800 gpm (design flowrate) to 3420 gpm in order to take into account a
lOX flow degradation of the pumps with operation.
This 10% flow degradation is consistent with the flow degradation provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
The staff has reviewed the proposed change to the Bases for Sections
- 3. 1.8 and 4. 1.8 and offers no objection.
Enclosed is a copy of the revised Bases page 73.
All staff activities related to TAC No. 76932 are considered complete.
Sincerely,
Enclosure:
As stated Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects
-- I/II Office of Nuclear Reactor Regulation cc w/enclosure:
See next page
0
'll
Mr. B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.
1 CC:
Mr. Mark J. Wetter hahn, Esquire
- Bishop, Cook, Purcell 8 Reynolds 1400 L. Street, N.W.
Washington, D. C.
20005-3502 Supervis'or Town of Scriba R.
D.
¹4
- Oswego, New York 13126 Mr. Joseph F. Firlit Vice President - Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, New York 13093 Mr. Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Mr. Kim Dahlberg
.Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093
'r. Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Charlie Donaldson, Esquire 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 Division, System Operations 3 Empire State Plaza
- Albany, New York 12223
a
'I I.
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 available 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 s ra to be effective.
One set of high pressure coolant injection pumps consists of a condensate
One set of pumps is capable of delivering 3,420 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 Q
be considered.
a.
The HPCI System shall be capable of meeting at least 3,420 gpm flow at normal reactor operating pressure.
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 3,420 gpm at a reactor pressure of approximately 270 psig.
The capability of the condensate, feedwater booster and motor driven feedwater pumps will be demonstrated by their operation as part of the feedwater su'pply 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.
Revised October 1,
19&6, May 23, 1989 0301S (proposed) 73
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