ML17058B021
| ML17058B021 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/23/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058B022 | List: |
| References | |
| NUDOCS 9208040233 | |
| Download: ML17058B021 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE.
4 Amendment No.
13O 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 October 22,
- 1991, as supplemented November 19,
- 1991, 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:
9208040233 920723 PDR ADOCK 05000220 P
1 ff
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
1 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 218 221 236 Insert Pa es 218 221 236
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 130, 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 Date of Issuance:
July 23, 1992 Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Table 3.6.2g (cont'd)
INSTRUMHNTATION THAT INITIATES CONTROL ROD VITHDRAVALBIAXX 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 Set Point Reactor Mode Svitch Position in Vhich Function Must Be 0 erable Q
Q Q
4J w
al g
0 ca (4) Recirculation Flov a.
Comparator Off Normal
<6.8X b.
Flov Unit Inoperative c.
Flov Unit Upscale (5) Refuel Platform and Hoists 2 (f)
<103.7X (6) Mode Svitch in Shutdovn Amendment No. W 130 218
Table 4.6.2g (cont'd)
INSTRUMENTATION THAT INITIATES CONTROL ROD VITHDRAVALBLOCK Surveillance Re uirement Parameter Sensor Check Instrument Channel Test Instrument Channel Calibration (3)
- a. Inoperative
- b. Upscale (Biased by Recirculation Plov)
None None Once per month Once per month None Once per 3 months
- c. Dovnscale (4) Recirculation Flov None Once per month Once per 3 months a.
Comparator Off Normal None Once per month Once per 3 months
- b. Plov Unit Inoperative
- c. Plov Unit Upscale None None Once per month Once per month Once per 3 months Once per 3 months Amendment No.~,
130 221
BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION The set points on the generator load rejection and turbine stop valve closure scram trips are set to anticipate and minimize the consequences of turbine trip vith failure of the turbine bypass system as described in the bases for Specification 2.1.2.
Since the severity of the transients is dependent on the reactor operating pover level, bypassing of the scrams belov the specified pover level is permissible.
Although the operator vill set the setpoints at the values indicated in Tables 3.6.2.a-l, the actual values of the various set points can differ appreciably from the value the operator is attempting to set.
The deviations include inherent instrument error, operator setting error and drift of the set point.
These errors are compensated for i the transient analyses by conservatism in the controlling parameter assumptions as discussed in the bases for Specification 2.1.2.
The deviations associated vith the set points for the safety systems used to mitigate accidents have negligible effect on the initiation of these systems.
These safety systems have initiation times vhich are orders of magnitude greater than the difference in time betveen reaching the nominal set point and the vorst set point due to error.
The maximum allovable set point deviations are listed belov:
Neutron Flux APRH Scram,
+2.3X of rated neutron flux (analytical limit is 120X of rated flux)
APRH Rod Block, g2.3X of rated neutron flux (analytical limit is 110X of rated flux)
IRH, g2.5Z of rated neutron flux Recirculation Flov Upscale, z1.6X of rated recirculation flov (analytical limit is 107.1X of rated flov)
Recirculation Flov Comparator,
+2.09X of rated recirculation flov (analytical limit is 10X flov differential)
Reactor Pressure, zl5.8 psig Containment Pressure
+0.053 psig Reactor Mater Level, g2.6 inches of vater Hain Steam Line Isolation Valve Position,
+2.5X of stem position Scram Discharge
- Volume,
+0 and -1 gallon Condenser Lov Vacuum, +0.5 inches of mercury Amendment No. +, H, 236