ML17056B243
| ML17056B243 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/11/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B242 | List: |
| References | |
| NUDOCS 9101220161 | |
| Download: ML17056B243 (12) | |
Text
~p,8 AECy
~C P
+
0 oO IVl
+a
++*+~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
121 License No.
DPR-63 1.
The Nuclear Regulatory COIImIission (the Comission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated Februay 26,
- 1990, as superseded October 26, 1990 and supplemented November 30, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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:
9iOi220ihi qiOiii PDR ADOCK 05000220 p
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 121, 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 COtC~iISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1991 Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 121 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 4
25 Insert Pa es 4
25 25a
l
1.12 Reactor Buildin Inte rit Reactor Building Integrity means that the reactor building is closed and the following conditions are met.
a.
At least one door at each access opening is closed.
b.
The standby gas treatment system is operable.
c.
All Reactor Building ventilation system automatic isolation valves are operable or ai e secured i
closed posi)ion.
e e or ai e secured in the 1.13 Core Alteration A core alteration is the addition, removal, relocation, or other manual movement of fuel or controls in the reactor core.
Control rod movement with the control rod drive hydraulic system is not considered to be a core alteration.
1.14 Rated Flux Rated flux is the neutron flux that corresponds to a steady-state power level of 1850 therma) megawatts.
The use of the term 100 percent also refers to the 1850 thermal megawatt power level.
1.15 Surveillance Surveillance means that process whereby systems and components which are essential to p]ant nuclear safety during all modes of operation or which are necessary to prevent or mitigate the consequences of incidents are
- checked, tested, calibrated and/or inspected, as warranted, to verify peA'ormance and availability at optimum intervals.
Amendment No. XX 121
/%
I
3.0 LIHITING CONDITIONS FOR OPERATION 3.0.1 OPERABILITY RE UIREHENTS Hhen a system, subsystem,
- train, component or device is determined to be inoperable solely because its.
emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered operable for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is operable; and (2) al,l of its redundant system(s)-,
subsystem(s),
train(s),
component(s) and device(s) are operable, or likewise satisfy the requirements of this specification.
Unless both conditions
( 1) and (2) are satisfied the unit shall be placed in a condition stated in the individual specification.
In the event a Limiting Condition for Operation and/or associated surveillance requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in a condition consistent with the individual specification unless corrective measures are completed that permit operation under the permissible surveillance requirements for the specifi'ed time interval as measured from initial discovery or until the reactor is placed in an operational condition in which the specification is not applicable.
4.0 SURVEILLANCE RE UIREHENTS 4.0.1 SURVEILLANCE INTERVALS Each Surveillance Requirement shall be performed within the specified survei.llance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
BASES Specification 4.0.
1 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibilityto accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with a 24 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.1 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
Amendment No.
KKXX 121 25
3.1.0 FUEL CLADDING A)
GENERAL APPLICABILITY s stem Applies to the power level regulation, control rod system liquid poison sy t y
, and core spray system.
LCO's for the minimum allowable circuits corresponding to the LS oison sys em, emergency cooling settings are included in the Reactor Protection System LCO (3.6.2).
B)
GENERAL OBJECTIVE I
LIHITING CONDITIONS FOR OPERATION To define the lowest functional capability or performance level of the systems and associated components which will assure the integrity of the fuel cladding as a
barrier against the release of radioactivity.
SURVEILLANCE REQUIREHENTS To define the tests or inspections required to assure the functional capability or performance level of the required systems or components.
Amendment No. 121 25a