ML17056A511
| ML17056A511 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/14/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A512 | List: |
| References | |
| NUDOCS 8912210116 | |
| Download: ML17056A511 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POllER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1l3 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by IIiagara Mohawk Power Corporation (the licensee) dated May I, 1989, as amended Dune 15,
- 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the'ules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi 11 be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wi 11 not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
89i2210ii6 89i214TJ PDR ADOCK 05'000220 P.
2 (2)
Technical-S eci fications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 113
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 14, 1989
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as fo11ows:
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'71 Insert Pa es 71 73a
LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT 3.1.8 HIGH PRESSURE COOLANT INJECTION A~ti Atilt Applies to the operational status of the high pressure coolant injection system.
O~b ective:
To assure the capability of the high pressure coolant injection system to cool reactor fuel in the event of a loss-of-coolant accident.
4.1.8 HIGH PRESSURE COOLANT INJECTION A\\lit Applies to the periodic testing requirements for the high pressure coolant injection system.
~0b ective:
To verify the operability of the high pressure coolant injection system.
t~tfl a.
During the power operating condition*
whenever the reactor coolant pressure is greater than 110 psig and the reactor coolant temperature is greater than saturation temperature, the high pressure coolant injection system shall be operable except as specified in Specification "b" below.
- b. If a redundant component of the high pressure coolant injection system becomes inoperable the high pressure coolant injection shall be considered operable provided that the component is returned to an operable condition within 15 days and the additional surveillance required is performed' One Feedwater Pump blocking valve in one HPCI pump train may be closed during reactor startup when core power is equal to or less than 25K of rated thermal power.
At Aft ttli The high pressure coolant injection surveillance shall. be performed as indicated below:
a.
At least once er o eratin c cle Automatic start-up of the high pressure coolant injection system shall be demonstrated.
b.
At least once er uarter Pump operability shall be determined.
Amendment No.
113
'k
BASES FOR 3.1.8 ANO 4.1.8 HIGH PRESSURE COOLANT INJECTION During reactor startup with periods of low reactor water feed
- demand, one feedwater train is operated with a blocking valve closed downstream of the main flow control valve when core power is less than or equal to 25K of rated thermal power.
This allows the low flow control valve to control the reactor water flow during the startup period when feedwater flow demand is low.
Use of the low flow control valve provides more uniform feedwater flow which reduces thermal cycling at the reactor pressure vessel feedwater nozzles and in the feedwater piping as well as eliminating a severe service condition in the main flow control valves during reactor startup.
Under low feedwater flow conditions, the main flow control valves also experience high pressure drops and fluid velocities which shorten the valve's life and can cause plant transients due to control valve failure.
Reactor startup with one HPCI train available is acceptable since LOCA makeup requirements are reduced during startup because of lower reactor pressure, less decay heat.
and lower reactor power than assumed in LOCA analyses performed to Appendix K 10 CFR 50 requirements.
The other feedwater train (other HPCI.loop) with its blocking valve open would remain capable of supplying 3,800 gpm of feedwater upon automatic HPCI initiation at all reactor pressures.
Amendment No.
113 73a