ML20214W650
| ML20214W650 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/04/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Vermont Yankee |
| Shared Package | |
| ML20214W652 | List: |
| References | |
| DPR-28-A-097 NUDOCS 8612100356 | |
| Download: ML20214W650 (4) | |
Text
.
'o UNITED STATES P
NUCLEAR REGULATORY COMMISSION o
h WASHINGTON, D. C. 20666
%...../
VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET N0. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No.
DPR-28 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power
~
Corporation (thelicensee)datedOctober 28, 1986 as supplemented November 3, 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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the ppblic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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-28 is hereby amended to read as follows:
l 8612100356 861204 PDR ADOCK 05000271 P
(2) Technical Specifications The Technical Specifications, contained in Appendix A, as revised through Amendment No. 97, 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 wY f hH v
/
Daniel R. Huller, Project Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1986 f
4
ATTACHMENT TO LICENSE AMENDMENT N0.97 FACILITY OPERATING LICENSE i;0. DPR-28 DOCKET NO. 50-271 l
Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Page 86 9
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l VYNPS 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT l
Item Frequency i
c.
Pump and Motor-Operated once/ month j
Valve Operability except
)
Recirculat. ion Pump discharge valves.
2.
From and after the date that one of the Core Spray 2.
When it is determined that one Core Spray Subsystems is made or found to be inoperable for Subsystem is inoperable, the operable Core Spray any reason, reactor operation is permissible only Subsystem, both LFCI Subsystems (except the during the succeeding seven days unless such Recirculation System discharge valves} and the subsystem is sooner made operable, provided that diesel generators required for operatica of such during such seven days, all active components of components if no external source of power were i
the other Core Spray Subsystem, the LPCI available, shall be demonstrated to be operable f
Subsystems, and the diesel generators required for immediately. The operable Core Spray S daysten j
operation of such components if no external source shall be demonstrated to be operable daily j
of power were available, shall be operable.
thereafter.
)
1 3.
From and after the date that one of the LPCI pumps 3.
When it is determined that one of the LPCI pumps is made or found to be inoperable for any reason, is inoperable, the remaining active components of I
reactor operation is permissible only during the the LPCI (except the Recirculation System j
succeeding seven days unless such pump is sooner discharge valves) and the Containment Cooling made operable, provided that during such seven Subsystems, both Core Spray Subsystems, and the days, the remaining active components of the LPCI diesel generators required for operation of such Containment Cooling Subsystem and all active components if no external source of power were i
components of both Core Spray Subsystems and the available, shall be demonstrated to be operable i
diesel generators required for operation of such immediately and the operable LPCI pumps daily I
components if no external source of power were thereafter, available, shall be operable.
During the inspection / repair of the impeller wear For the purpose of performing inspection / repair of rings on each LPCI pump during the 1986-1987 the impeller wear rings on each LPCI pump during operating cycle, the remaining active components the 1986-1987 operating cycle, reactor operation of the LPCI Subsystem (except Recirculation System is permissible only during the succeeding 14 days discharge valves), the Containment Cooling 1
from the time each pump is made inoperable unless Subeystems, both Core Spray Subsystems, and the such pump is sooner made operable. Additionally, diesel generators required for operation of such
)
during the out-of-service time, the remaining components if no external source of power were active components of the LPCI Containment Cooling available, shall continue to be demonstrated Subsystem and all active components of both Core operable on a monthly basis as specified in Spray Subsystems and the diesel generators Technical Specifications 4.5.A.1 and 4.10.A.1.
required for operation of such components if no l
external source of power were available, shall be operable.
271 1
'Amentment wn. 17 N'97