ML17056B287
| ML17056B287 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/11/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B288 | List: |
| References | |
| NUDOCS 9102150275 | |
| Download: ML17056B287 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA-'OHAWK-POWER CORPORATION DOCKET-N0.-50-220 NINE-NILE"POINT -NUCLEAR-STATION
. UNIT. I AMENDMENT-TO-FACILITY-OPERATING-LICENSE Amendment No.
123 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara mohawk Power Corporation (the licensee) dated November 6, 1990, 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 rules 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 will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will 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:
91021 50278 910211 DR ADDCN 05000220 PDR
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
123, 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications
~AACi Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
February 11, 1991
ATTACHMENT-TO-LICENSE -AMENDMENT.
AMENDMENT-NO;-i 23-TO-FAGILITY"OPERATING LICENSE-NO..-DRR-63 DOGKET. NOi"50-220 Revise Appendix A as fo11ows:
Remove-Pa es 205 235 Insert-Pa es 205 235
Table 3.6.2c INSTRUMENTATION THAT INITIATES OR ISOLATES EMERGENCY COOLING Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels per Operable Tri S stem d
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable EMERGENCY COOLING INITIATION (1)
High-Reactor Pressure
< 1080 psig (b)
X X
(2)
Low-Low Reactor Water Level 5 inches (b)
(Indicator Scale)
X X
EMERGENCY COOLING ISOLATION (for each of two systems)
(3)
High Steam Flow Emergency Cooling System 2 (a)
< 11.5 psid Amendment No. ~ 349 123 205
BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION The set points included in the tables are those used in the transient analysis and
~
the accident analysis.
The high flow set point for the main steam line is 105 psi differential.
This represents a flow of approximately 4.4x10'b/'hr.
The high flow set point for the emergency cooling system supply line is
< 11.5 psi differential.
This represents a flow of approximately 9.8x10 lb/hr at rated conditions.
Normal background for the main steam line radiation monitors is defined as the radiation level which exists in the vicinity of main steam lines after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more of sustained full rated power.
The dose rate at the monitor due to activity from the control rod drop accident of Appendix E or from gross failure of one rod with complete fission product release from the rod would exceed the normal background at the monitor.
The automatic initiation signals for the emergency cooling systems have to be sustained for more than 10 seconds to cause opening of the return valves.
If the signals last for less than 10 seconds, the emergency cooling system operating will not be automatically initiated.
The high level in the scram discharge volume is provided to assure that there is still sufficient free volume in the discharge system to receive the control rod drives discharge.
Following a scram, bypassing is permitted to allow draining of the discharge volume and resetting of the reactor protection system relays.
Since all control rods are completely inserted following a scram and since the bypass of this particular scram initiates a control rod block, it is permissible to bypass this scram function.
The scram trip associated with the shutdown position of the mode switch can be reset after 10 seconds.
The condenser low vacuum, low-low vacuum and the main steam line isolation valve position signals are bypassed in the startup and refuel positions of the reactor mode switch when the reactor pressure is less than 600 psig.
These are bypassed to allow warmup of the main steam lines and a heat sink during startup.
235 Amendment No. ~
123