ML20056B288
| ML20056B288 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/23/1990 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056B289 | List: |
| References | |
| NUDOCS 9008280078 | |
| Download: ML20056B288 (10) | |
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UNITED STATES
, g NUCLEAR REGULATORY COMMISSION g"
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w VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 YERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPEP.ATING LICENSE Amendment No.125 License No. DPR-28 1.
The Nuclear Pegulatory Commission (the Commission or the NPC) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear PowerCorporation(thelicensee)datedApril8,1990complieswith 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; 3.
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 ainendment 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 Specifica-tions 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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendrent No.125, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9008280078 900823 PDR ADOCK 05000271 p
2 3.
This license amendment is effective within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY C0t4 MISSION h
b Victor Nerses, Acting Director Project Directorate 1-3
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Division of Reactor Projects I/11 Office of Nuclear Reactor Regulation
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Attachment:
Changes to the Technical Specific 6tions i
Date of Issuance: August' 23',.1990 l
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ATTACHMENT TO LICENSE AMENOMENT NO.125 FACILITY OPERATING LICENSE NO. DPR-28
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DOCVET N0. 50-271 I
Replace the following pages of the Apperdix A Technical Specifications with I
+he attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
-Remove Insert 174 174 174a 174a 175 175 175a 176a 178a 178a 180 180 l
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1
VYNPS 3.10 LIMITING CONDITIONS FOR OPERATION
_4.10 SURVEILLANCE REQfRREMENTS b.
The undervoltage automatic starting circuit of each diesel generator shall be tested once a month.
c.
Once per operating cycle, the actual conditions under which the diesel generators are required to start automatically will be simulated and a test conducted to demonstrate that they will start within 13 seconds and accept the emergency load and start each load within the specified starting time. The results shall be logged.
2.
Battery Systems 2.
Battery Systems The following battery systems shall be a.
Every week the specific gravity, operable:
temperature, level, and voltage of the pilot cell and overall battery voltage a.
The four Neutron Monitoring and Process shall be measured and logged.
Radiation Batteries, associated chargers, and 24 VDC Distribution Panels.
b.
Every three months the voltage, temperature, level, and specific gravity of each cell, and overall battery b.
The two main station battery systems voltage shall be measured and logged.
consisting of:
c.
Once per operating cycle each ECCS 1.
Battery Al, Battery Charger A or battery, Alternate Shutdown AS-2 Spare Charger AB and Bus DC-1.
battery, and Main Station battery shall be subjected to a Service (Load Profile) 2.
Battery B1, Battery Charger B or discharge test. The specific gravity Spare Charger AB and Bus DC-2.
and voltage of each cell shall be measured after the recharge at the end c.
Two Switchyard Batteries each with one of the discharge test and logged.
associated charger and its associated DC distribution panel.
Amendment No. 58 ~ 125 174
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i VYMPS l
3.10 LIMITING COISITIONS FOR OPERATION 4.10 SURVEILIANCE REQUIREIENTS i
d.
Both ECCS Instrunectation batteries, d.
Once every five years, each ECCS, UPS, i'
associated chargers, and distribution AS-2, and Main Station Battery shall be panels.
subjected to a Perfo m are (capacitj)
Discharge Test. This test will be performed in lieu of the Service Test requirements of 4.10.A.2.c above.
e.
Each 480 V Uninterruptible Power System i
e.
The Alternate Shutdown AS-2 battery, one shall be checked daily.
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of the two associated chargers, and DC Distribution panel DC-2AS.
f.
Both UPS batteries, associated f.
480 V Motor Control Centers 89A and 89B Uninterruptible Power Supplies and shall be checked daily.
MCC 89A and B.
I g.
Once per operating cycle, the actual conditions under which the 480 V Uninterruptible Power Systems are required will be simulated and a test
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conducted to demonstrate equipment performance.
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VYNPS i
i 3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEITT.Aur'E REQUIREMENTS 3.
Emergency Buses 3.
E-rnenew m----
i The emergency 4160 volt Buses 3 and 4, and The emergency 4160 volt buses and 480 volt 480 volt Buses 8 and 9 shall be energized and buses shall be checked daily.
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j 4.
Off-Site Power 4.
Off-Site Pnwar a.
At least one off-site transmission line The status of the off-site power sources and at least one start-up transformer in shall be checked daily.
l service.
t b.
One of the following additionst sources of delayed access power:
t The acia stepup transformer and unit auxiliary transformer available and capable of supplying power to the emergency 4160 volt buses or, The 4160 volt tie line to Vernon Eydro-Electric Station capable of supplying power to either of the two emergency 4160 volt buses.
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i Amendment No. 24. I!! 125 175 1
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VYNPS 1
3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS l
i d.
From and after the date that the AS-2 125 Volt battery system is made or found to be inoperable for any reason, contiamed reactor operation is l
permissible provided Diesel Generator DC1,1A control pcWer is transferred to Station Battery 31 and a fire watch is established to inspect the cable vault a minimum of every two hours.
e.
From and after the date that one of the
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1 two 24 Volt Neutron Monitoring and Process Radiation Monitoring battery l
systems is found or made to be inoperable for any reason, continued reactor operation is permissible I
providing the minimum chamael requirements of Sections 3.1 and 3.2 for the Neutron Monitoring and Process Radiation Monitoring systems are met.
f.
From and after the date that cae of the two 125 volt Switchyard battery systems is found or made to be inoperable for any reason, continued reactor operation is permissible provided that the other 125 volt Switchyard battery system is operable.
a 96 176a 4
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VYNPS f
A battery charger is supplied for each battery. In addition, the two 125 volt station batteries have a spare charger available. Since one spare 125 volt station charger is available, one station battery charger can be allowed out of service for maintenance and repairs.
Power for.the Reactor Protection System is supplied by 120 V ac motor generators with an alternate supply from NCC-88. Two red==d==t, Class IE, seismically qualified power protection panels are connected in series with each ac power source. These panela 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.
B.
Adequate power is available to operate the emergency safeguards equipment fr9e either startup transformer f
or for minimum engineered safety features from either of the emergency diesel ~ generators. Therefore, reactor operation is permitted for up to seven days with both delayed-access off-site power sources lost.
Each of the diesel generator units is capable of supplying 100 percent of the minimum emergency loads required under postulated design basis accident conditions. Each unit is physically and electrically j
independent of the other and of any off-site power source.. Therefore, one diesel generator can be allowed out of service for a period of seven days without jeopardizing the safety of the station.
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VYNPS 4.10 (Continued) t Both diesel generators have air compressors and air receiver tanks for starting. It is expected that the air i
compressors will run only infrequently. During the monthly check of the units, each receiver will be drawn down j
below the point at which the compressor automatically starts to check operation and the ability of the compressors to recharge the receivers.
t Following the tests of the units and at least weekly, the fuel volume rersaining will be checked. At the end of the monthly load test of the diesel generators, the r'uel oil transfer pump will be operated to refill the day tank and to check the operatica of the pump. h day tank level indicator and alarm switches will be checked at this time.
h test of the diesels and Uninterruptible Power Systems during each refueling interval will be more comprehensive in that it will functionally test the system; i.e., it will check starting and closure of breakers and sequencing of loads. h units will be started by simulation of a loss of coolant accident. In addition, a loss of normal power condition will be imposed to simulate a loss of offsite power. h timing sequence will be checked to assure proper loading in the time required. Periodic tests between refueling inte;vuls check the 5
i capability of the diesels to start in the required time and to deliver the expected emergency load requirements. Periodic testing of the various components plus a functional test at a refueling interval are aufficient to maintain adequate reliability.
B.
Although the Main Station, ECCS, AS-2, and UPS batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure.
Tt~ type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
I h Performance Discharge test provides adequate indication and assurance that the batteries have the specified
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ampere hour capacity. h rate of discharge during this test shall be in accordat.ce with the manufacturer's discharge characteristic curves for the associated batteries. The results of these tests will be logged and compared with the manufacturer's reca==andation of acceptability.
h Service Discharge test provides a test of the batteries ability to satisfy the design requirements (battery j
duty cycle) of the associated DC system. This test will be performed using simulated or actual loads at the rates and for the durations specified in the design load profile.
C.
Iogging the diesel fuel supply weekly and after each operation assures that the minimum fuel supply requirements will be maintained. During the monthly test for quality of the diesel fuel oil, a viscosity test and water and j
sediment test will be performed as described in AS'IM D975-68. The quality of the diesel fuel oil will be l
acceptable if the results of the tests are within the limiting requirements for diesel fuel oils shown on Table 1 of ASTM D975-68.
Amendment No. N 125 180 s
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