ML20198Q865
| ML20198Q865 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/28/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198Q869 | List: |
| References | |
| NUDOCS 9901080006 | |
| Download: ML20198Q865 (5) | |
Text
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@ thq UNITED STATES j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20666 4001 I
\\..... pf VERMONT YANKEE NUCLEAR POWER CORPORATION i
DOCKET NO. 50-271 i
VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE D
Amendment No.163 License No. DPR-28
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- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by the Vermont Yankee Nuclear Power Corporation 1
(the licensee) dated May 8,1998, as supplemented on July 10,1998, and October 2, 1998, 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.
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9901000006 981228 l
PDR ADOCK 05000271 l
P PDR I
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. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.163, 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 its date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 0
Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects -l/il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 28, 1998 k
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e ATTACHMENT TO LICENSE AMENDMENT NO.163 FACILITY OPERATING LICENSE NO DPR 28 DOCKET NO 50-271 Replace the following pages of Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 146 146 g
147 147 1
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VYNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION 3.7 STATION CONTAINMENT SYSTEMS 4.7 STATION CONTAINMENT SYSTEMS Applicability:
Applicability:
Applies to the operating status Applies to the primary and of the primary and secondary secondary containment system containment systems.
integrity.
Objective:
Objective:
To assure the integrity of the To verify the integrity of the primary and secondary primary and secondary containment systems.
containments.
Specification:
Specification:
A.
Whenever primary 1.
The suppression chamber containment is required, water level and the volume and temperature shall be temperature of the water checked once per shift.
in the suppression A visaal inspection of chamber shall be the suppression chamber maintained within the interior including water following limits:
line regions and the interior painted a.
Maximum Water surfaces above the water Temperature during line shall be made at normal operation -
each refueling outage.
l 90*F.
Whenever there is indication of relief b.
Maximum Water valve operation which Temperature during adds heat to the any test operation suppression pool, the which adds heat to pool temperature shall the suppression be continually monitored pool - 100'F; and also observed and however, it shall logged every 5 minutes not remain above until the heat addition 90*F for more than is terminated. Whenever 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
there is indication of relief valve operation c.
If Torus Water with the temperature of Temperature exceeds the suppression pool 110'F, initiate an reaching 160'F or more immediate scram of and the primary coolant the reactor.
Power
~ operation shall not
_ system pressure greater than 200 psig, an be resumed until external visual the pool examination of the
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I tenperature is suppression chamber reduced below 90*F.
shall be conducted I
before resuming power d.
During reactor operation.
isolation conditions, the reactor pressure vessel shall be depressurized to less than 200 psig l
Amendment No. 44, 60, es, 163 146 i
VYNPS 3.7 ' LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION at normal cooldown rates if the torus water temperature
-exceeds 120'F.
-e.
. Minimum Water Volume -
68,000 cubic feet f.
Maximum Water Volume -
70,000 cubic feet g
l2.
The primary containment integrity shall be integrity shall be maintained at all times demonstrated as required when the reactor is by the Primary critical or when the Containment Leak Rate reactor water Testing Program temperature is above' (PCLRTP).
212'F and-fuel is in the reactor vessel except while performing low power physics tests at atmospheric pressure at power levels not to exceed 5 Mw(t).
3.
If a portion of a system 3.
(Blank) that is considered to be an extension of primary containment is to be opened, isolate the-affected penetration flow path by use of at least one closed and deactivated automatic valve, closed manual valve or blind flange.
4.
Whenever primary 4.
The leakage from any one containment is required, main steam line the leakage from any one isolation valve shall main steam line not exceed 11.5 scf/hr isolation valve shall-not at 24 psig (Pt).
Repair exceed 15.5'sef/hr and retest shall be
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at ' 4 4 psig - (P.).
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conducted to insure compliance.
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' Amendment No. 44, esa,163 147
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