ML20197B721
| ML20197B721 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/05/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20197B725 | List: |
| References | |
| NUDOCS 9803110378 | |
| Download: ML20197B721 (5) | |
Text
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t p eno UNITED STATES i
a NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 3000HeD1 VERMONT YANKEE NUCI FAR POWER CORPORATION i
DOCKET NO. 50-271 4
VERMONT YANKEE NUCL FAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.153 License No. DPR-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated November 20,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations; 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 aniendment 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.
6 9803110378 980305 PDR ADOCK 05000271 P
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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 Append;x A, as revised through Amendment No.153, are hereby incorporated in thi 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 and shell be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION U*
M4Pr Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specification Date of lasuance: March 5, 1998
ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of Appendix ^ Tech:=lcal Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Jasmi 212 212 220 220
4
. e WNPS 3.10 LIMITING CONDITIONS FOR 4.10 SURVEILLANCE REQUIREMENTS OPERATION within 13 seconds and accept the emergency loads and start each load within the specified starting time.
The results shall be logged, c.
Each diesel fuel' oil transfer pump shall be tested in accordance with Specification 4.6.E.
2.
Patterv Systems 2.
Battery Systems lhe following battery a.
Every week the systems shall be specific gravity, operable:
temperature, level, and voltage a.
The four Neutron of the pilot cell Monitoring and and overall Process Radiation battery voltage Batteries, shall be measured associated and logged.
chargers, and 24 VDC b.
Every three months Distribut on the voltage, l
- Panels, temperature, level, and b.
The two main specific gravity station battery of each cell, and systems consisting-overall battery of:
voltage shall be measured and 1.
Battery A1, logged.
Battery Charger A and Bus DC-1.
2.
Battery B1, Battery Charger B and Bus DC-2.
- Amendment No. 64, 446, t&P 153 212
VYNPS BASES:
3.10 AUXTLIARY ELECTRIC POWER SYSTEMS A.
The objective of this Specificaticn is to assure that adequate power will be available to operate the emergency safeguards equipment, i
Adequate power can be provided by any one of the following sources either of the startup transformers, backfeed through the main transformer, the 4160 volt line from the Vernon Hydroelectric Station or either of the two diesel generators. The backfeed chrough the main transformer and 4160 volt Vernon line are both delayed access off-site power sources.
Backfeeding through the main transformer can be accomplished by disconnecting the main generator from the main transformer and energizing the auxiliary transformer from the 345 kV switchyard through the main transformer. The time required to perform this disconnection is approximately six hours.
The 4160 volt line from the Vernon Hydroelectric Station can be connected to either of the two emergency buses within seconds by simple manual switching operation in the Main Control Room.
Two 480 V Uninterruptible Power Systems supply power to the LPCIS valves via designated Motor Control Centers.
The 480 V Uninterruptible Power Systems are redundant and independent of any on-site power sources.
This Specification assures that at least two off-site and two on-site power sources, and both 480 V Uninterruptible Power Systems will be available before the reactor is taken beyond "just critical" testing.
In addition to assuring power source availability, all of the associated switchgear must be operable as specified to assure that the emergency cooling equipment can be operated, if required, from the power sources.
Station service power is supplied to the station through either the unit auxiliary transformer or the startup transformers.
In order to start up the station, at least one startup transformer is required to supply the station auxiliary load.
After the unit is synchronized to the system, the unit auxiliary transformer carries the station auxiliary load, except for the station cooling tower loads which are always supplied by one of the startup transformers.
The station cooling tower loads are not required to perform an engineered safety feature function in the event of an accident; therefore, an alternate source of power is not essential. Normally one startup transformer supplies 4160 volt Buses 1 and 3, and the other supplies Buses 2 and 4; however, the two startup transformers are designed with adequate capacity such that, should one become'or be made inoperable, temporary connections can be made to supply the total station load (less the cooling towers) from the other startup transformer.
A battery charger is supplied for each battery.
In addition, the j
two 125 volt station batteries have a spare charger available.
Power for the Reactor Protection System is supplied by 120 V ac motor generators with an alternate supply from MCC-SB.
Two redundant, Class 1E, seismically qualified pcwer protection panels are connected in series with each ac power seurce.
These panels provide overvoltage, undervoltage, and underfrequency protection for the system.
Setpoints are chosen to be consistent with the input power requirements of the equipment connected to the bus.
Amendment No. G4, GG, 444, 444, tes.153 220
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