ML20102B188
| ML20102B188 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/21/1992 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20102B190 | List: |
| References | |
| NUDOCS 9207280237 | |
| Download: ML20102B188 (5) | |
Text
_-
@ Rf00 O
- O"
- [e UNITED STATES
.i NUCLEAR REGULATORY COMMISSION 3
[
WASHINGTON. D.C. 20555
%, *.
- v /
VERMONT YANKEE NUCLEAR POWER CORPORATIO.t{
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 License No. DPR-28 1.
The Nuclear Regulatory Coinmission (the Commission or the NRC) has found s
that:
A.
The application for amendment filed by the Vetmont Yankee Nuclear Power Corporation (the licensee) dated December 27, 1991, complies a
with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regnlations 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 set forth
~
in 10 CFR Chapter I; 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 attachmeist to this license amendment, and paragraph 3.B of Facility Operati!g ticense No. DPR-28 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.134, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technien1 Specifications.
9207280237 920721 PDR ADOCK 050W271 P
v.
r 2-3.
This license amendment i'., effective as of its date of issuance, FOR THE NGLEAR REGULATORY C0i1MISS10N i
h Victor Nerses, Acting Director 7
Project Directorate 1-1 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
July 21,-1992 4
g f l
l
ATTACHMENT TO LICENSE AMENDMENT NO.134 3;
EACillTY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and
- contain vertical lines indicating the area of change.
Remove Insert 132 132 133 133
~
J VYNPS 4.7 SURVEll1ANCE REQUIREMENTS 3.7 LIMITING CONDrr!ON FOR OPER ATION b.
Addiduel tests shaU be perfomed during the b.
'Ihc reactor water temperature is below 212*F and first operating cycle under an adequate number of the teactor coolant system is vented.
different environmental wind condidons to enable vdid extrapolation of the test results.
No activity is being performed which can reduce c.
the shutdown margin below that specified in Secondary contaimnent capability to maintain a c.
SpecifL = tina 3.3.A.
0.15 ir.ch of water vacuum under calm wind d.
The fuel cask or irrwtiarrei fuel is not being moved (2 <"T< 5 mph) conditions witn a filter train flow rate of not more than 1,500 cfm, shall be in the Reactor Buddmg.
demonstrated at least quarterly and at each refueling outage prior to refueling.
2.
Core spray and LPCI pump lower compartment door openings shall be closed =t all times except during passage 2.
The core spray and LPCI lower compartment openings or when reacsor coolant semperature is less than 212*F.
shall be cha:ked closed daily.
D.
Primary Containment Isolation Valves D.
Prinnry Conrainment Isoladoes Valves 1.
Surveillance of the prinuuy containment isoladon 1.
During reactor power operadng condidens all isoladon valves listed in TaNe 4.7.2 and all instrument line flow valves shall be performed as follows:
check valves sbil be operable except as specified in
'lle operable isoladon valves dia are gx)wer a.
Specificadon 3.7.D.2.
operated and automatically initiated shall te tested for automade initiadon and de closure l
dmes s,necified in Table 4.7.2 at least once per operadng cycle.
l b.
Operability testing of the primary cor.tainment isoladon valves shall be performed in accordance with Specification 4.6.E.
132 Anradment No.ng. 134
.(1
}
r-'s:
V U)
- i ~
I 3.7 LIMITING CONDITIONS FOR OPERATION 4.7 SURVEI'. LANCE REQ 8tIREMENTS i
I c..
At test.t. once per quarter, with the p
reactor power.less than 75-percent of rated, trip all main stean isolation valves'(one et a time) and verify closure time..
i -
twice per week, the main
.l d.
At least1 steam line isolation valves shall j
be, exercised by partial closure and subsequent reopening.
2.
In the event any isolation valve 2.
Whenever an ' isolation valve listed in i
'specified in Table 4.7.2 becomes 4.7.2 is inoperable, the position of_at inoperable, reactor power. operation may least one other valve in'each line continue:provided at least one valve in having.an; inoperable valve shall be o
each line having an inoperable valve la logged daily.
in the mode corresponding to the isolated condition.
3.
If' Specification 3.7.D.1 and 3.7.D.2 cannot be met, an.' orderly shutdown shall be initiated and the reactor shall be in
-the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
t i
.AmendmentNo.%d,kg. 128* 134 133-
.W-p
_p
- ,I '.
,,,w
,