ML17055B686
| ML17055B686 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/12/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055B688 | List: |
| References | |
| NUDOCS 8605200473 | |
| Download: ML17055B686 (8) | |
Text
gp,S REoy
~
~gw
~
~,
0
~y 4<a
~+0
+)t**+
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 LICENSF.
Amendment No.82 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 January 28, 1986, 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 hy 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:
Sb05200473 Bb0512 PDR ADOCK 05000220 P
~
~
l
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE 47 INSERT 47
I
(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.82
, 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 REAU TORO COMMISSION Joh A. Zwolinski, Director BWR roject Directorate ¹1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 12, 1986.
(I
LIMITINGCONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.1.3 EMERGENCY COOLING SYSTEM A~At blitt Applies to the operating status of the emergency cooling system.
~0b ective:
To assure the capability of the emergency cooling system to cool the reactor coolant in the event the normal reactor heat sink is not available.
J55 lll tl a.
During power operating conditions and whenever the reactor coolant temperature is greater than 212'F except for hydrostatic testing with the reactor not critical, both emergency cooling systems shall be operable except as specified in 3.1.3.b and c.
b.
During the remainder of Cycle 8-with one emergency cooling system inoperable, Specification 3.1.3a shall.-be considered fulfilled, provided the additional surveillance required in 4.1.3.f is performed.
c.
During Cycle 9 and subsequent cycles, if one emergency cooling system becomes inoperable, Specification 3.1.3.a shall be considered fulfilled, provided that the inoperable system is returned to an operable condition within 7 days and the additional surveillance required in 4.1.3.f is performed.
4.1.3 EMERGENCY COOLING SYSTEM blitt:
Applies to periodic testing requirements for the emergency cooling system.
~0b'ective:
To assure the capability of the emergency cooling system for cooling of the reactor coolant.
~tati tl The emergency cooling system surveillance shall be performed as indicated below:
a.
At least once ever tive ears The system heat removal capability shall be determined.
b.
At least once dail The shell side water level and makeup tank water level shall be checked.
c.
At least once er month The makeup tank level control valve shall be manually opened and closed.
Amendment No. 7$, 82 47