ML20217F285
| ML20217F285 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/24/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217F290 | List: |
| References | |
| NUDOCS 9803310335 | |
| Download: ML20217F285 (11) | |
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UNITED STATE 8 g
j NUCLEAR REGULATORY COMMISSION p
WASHINGTON, D.C. 30006-40tH
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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.155 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 October 10,1997, as supplemented by letter dated October 31,1997, 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 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 j
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 satisfed.
9003310335 900324 PDR ADOCK 05000271 P
PDR 4
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2.
Accordingly, the license is amended by changes to the Technical Specdications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility
' Operating License No. DPR-20 is hereby amended to read as follows:
(B)
Technical Specificafjons The Technical Specdications con'tained in Appendix A, as revised through Amendment No.155, are hereby ir+eted in the bcense. 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 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION s/0
/WW Cecil O Thomas, Diredor Project Directorate 1-3 Division of Reactor Projects - t/il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 24, 1998 f
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ATTACHMENT TO LICENSE AMENDMENT NO.155 FACILIT( 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 10and 214 214 217 217 217a 220 220 221 221 221a 222 222 223 223 I
VYNPS 3.10. LIMITING CONDITIONS FOR 4.10 SURVEILLANCE REQUIREMENTS OPERATION 3.
Emeroency Buses 3.
Emeroency Buses
.The emergency 4160 volt The emergency 4160 volt
~ Buses 3 and 4, and buses and 480 volt 480 volt Buses 8 and 9 buses shall be checked shall be energized and
- daily, operable.
4, Off-Site Power 4.
Off-Site Power Two qualified off-site a.
The status of the l
power sources off-site power consisting of the sources shall be immediate access source checked daily, and the delayed access source shall be b.
Once per operating energized and operable.
cycle, the delayed access source shall be established within one hour.
5.
Peactor Protection 5.
Resetor Protection System Power Protection System Power Protection 7vo RPS power once per operating protection panels for cycle, the operability each inservice RPS HG of each overvoltage, set or alternate power undervoltage, and source shall be underfrequency
- operable, protective device shall be demonstrated by the performance of an instrument channel calibration test.
Settings shall be verified to be in accordance with Table 4.10.1.
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- Amendment No. 84, 66a, 666.155 214
...p.
. [w-VYNPS 3.10 LIMITING CONDITIONS FOR 4.10. SURVEILLANCE REQUIREMENTS OPEP.ATION f.
From and after the date that one 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.
3.
Off-Site Power 3.
Off-Site Power a,
From and after the a.
When one off-site date one off-site power source is power source is unavailable, the made or found to remaining power be inoperable for source, both any reason, emergency diesel reactor operation generators, may continue for associated seven days emergency buses provided the and all Low remaining off-site Pressure Core and source, both Containment emergency diesel Cooling Systems generators, shall have been or associated shall be verified emergency buses operable within and all Low one hour and once Pressure Core and per eight hours Containment thereafter.
Cooling Systems are operable.
If this requirement cannot be net, an orderly shutdown shall be initiated and the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the conditions of
- Specifications-3.10.B.3.b are applicable.
- Amendment ' No. as,
++4, +46,155 217
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~3,10 LIMITING CONDITIONS FOR:
4.10 SURVEILLANCE REQUIREMENTS OPERATION b.
From and after the b.
When either date that either off-site power off-site power source and one source and one diesel or diesel generator associated buses are made or found are unavailable:
to be inoperable for any reason, 1.
The other continued off-site operation is power source permitted for and all Low 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as long Pressure as the remaining Core and off-site power Containment source,.the Cooling remaining diesel Systems generator, shall have associated been or emergency buses shall be and all Low verified Pressure Core and operable Containment within one Cooling Systems.
hour and are operable, once per eight hours
.If this require-thereafter.
ment cannot be net, an orderly 2.
The shutdown shall be remaining initiated and the diesel reactor shall be generator in cold shutdown shall have within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
been or shall be demonstrated j
to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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1 Amendment-No.155 217a
l VYNPS MEE.1 3.10 AUXILIARY ELECTR*C PO'elER SYSTEMS A.
The objective of this Specification is to assure that adequate power will be available to operate the emergency safeguards equipment.
Adequate power can be provided by any one of the following sources:
an immediate access source through both startup transformers, backfeed through the main transformer, or either of the two diesel generators. The backfeed through the main transformer is a delayed access off-site power source. The delayed access source is made available by opening the generator no load disconnect switch and establishing a feed from the 345 kV switchyard through the noin generator step up transformer and unit auxiliary transformer to the 4.16 kV buses. The delayed access source is available within an hour of loss of main generator capability to assure that fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded.
Electric power can be supplied from the off-site transmission network to the on-site Emergency Safeguards Electric Power Distribution System by two independent sources, one immediate access and one delayed access, designed and located so as to minimize to the extent practicable the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. An additional off-site source, a 4160 V tie line to Vernon Hydroelectric Station, can supply either 4160 V emergency bus.
It is used to meet station blackout and Appendix R licensing requirements.
Off-site power is supplied to the 345 kV switchyard from the transmission network by three transmission lines. A 400 MVA autotransformer is connected between the 345 kV north bus and the 115 kV bus.
The autotransformer is the normal source for the 115 kV bus and the station startup transformers. The autotransformer also feeds the 115 kV transmission line to Keene.
The immediate access source is supplied from the 345 kV Transmission System through the 345 kV/115 kV autotransformer. It feeds the on-site Electric Power Distribution System through the two 115 kV to 4.16 kV startup transformers and is available within seconds following a design basis accident to assure that core cooling, containment integrity and other vital functions are maintained. An alternate immediate access source through the Keene line may be made available. Its availability is dependent on its preloading which must be limited by system dispatchers prior to it being declared an immediate access source.
A qualified source consists of all breakers, transformers, switches, interrupting devices, cabling and controls required to transmit adequate power from the off-tite transmission network to the on-site Emergency Safeguards Buses 3 and 4.
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 l
on-site ac power sources.
This. Specification assures that at least two off-site and two on-site power sources, and both 460 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/ he power sources.
t i Amendment No. 96, 58, 'i&E,124,.125, 155' 220
VYNPS f_Mj;S :
3.10 (Cont'd)
Station service power is supplied to the station through either the unit auxiliary transformer or the startup transformers.
In order to l
start up the station, the startup transformers are 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 accidents therefore, an alternate source of power is not essential. Normally one startup transformer supplies 4160 volt Buses'1 and 3, and the other supplies l
Buses 2 and 4.
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 MCC-8B.
Two redundant, Class 1E, seismically qualified power protection panels are connected in series with each ac power source. 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 connec;ed to the bus.
B.
Adequate power is available to operate the emergency safeguards l
equipment from the immediate access source or for minimum engineered safety features from either of the emergency diesel generators.
Therefore, reactor operation is permitted for up to seven days with l
the delayed-access off-site power source unavailable.
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 independent of the other and of any off-site power source. Adequate power is also available to operate the emergency safeguards equipment from the immediate access source or from the delayed access source of off-site power. Therefore, one diesel generator can be allowed out of service for a period of seven days without jeopardizing the safety of the station.
l In the event that the immediate access source is unavailable, adequate power is available to operate the emergency safeguards equipment from the emergency diesel generators or from the delayed-access off-site power source. Therefore, reactor operation is permitted for up to 7 days with the immediate access source unavailable.
In the event that both emergency diesel generators are lost, adequate power is available to operate the emergency safeguards equipment from the immediate access source or from the delayed-access off-site power source within one hour.
The plant is designed to accept one hundred percent load rejection without adverse' effects to the plant or the transmission system.
Network stability analysis studies indicate that the loss of the Vermont Yankee unit will not cause instability and consequent tripping of the connecting 345 kV and 115 kV lines. Thus, the l
availability of the off-site power sources is assured in the event of a turbine trip.
Amendment No. 96, 58, 61, 155 221
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VYNPS j&gIf.: 3.10 (Cont'd)
In the event that one off-site power source and one emergency diesel generator are unavailable, adequate power is available to operate
-both emergency safeguards buses from the operable off-site power.
source and to operate 100% of the minimum emergency safeguards loads from the operable diesel generator. In additioni the station blackout alternate ac source of power is capable.of supplying power to the bus with the inoperable diesel generator. Therefore, continued operation is permitted for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with one off-site power source and one emergency diesel generator unavailable.
Either of the two station batteries has enough capacity to energize the vital buses'and supply d-c power to the other emergency equipment for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without being recharged.
In addition, two
-24 volt ECCS Instrumentation batteries supply power to instruments that provide automatic initiation of the ECCS and some reactor pressure and level indication in the Control Room.
Due to the high reliability of battery systems, one of the two batteries may be out of service for up to three days. This minimizes the probability of unwarranted shutdewn by providing adequate time for reasonable repairs. A station battery, ECCS Instrumentation battery, or an Uninterruptible Power System battery is considered inoperable if more than one cell is out of service. A cell will be considered out of service if its float voltage is below 2.13 volts and the specific gravity is below 1.190 at 778F.
The Battery Room is ventilated to prevent accumulation of hydrogen gas.
With a complete loss of the ventilation system, the accumulation of hydrogen would not exceed 4 percent concentration in 16 days. Therefore, on loss of Battery Room ventilation, the use of portable ventilation equipment and daily sampling provide assurance that potentially hazardous quantities of hydrogen gas will.not accumulate.
C.
The minimum diesel fuel supply of 25,000 gallons will supply one diesel generator for a minimum of seven days of operation satisfying the load requirements for the operation of the safeguards equipment.
Additional fuel can be obtained and delivered to the site from nearby sources within the seven-day period.
. Amendment No.': 155 221a
VYNPS Eh5Islt 4.10 AUXILIARY ELECTRICAL POWER SYSTEMS A.
The monthly tests of the diesel generators are conducted to check for equipment failures and deterioration. The test of the undervoltage automatic starting circuits will prove that each diesel will receive a start signal if a loss of voltage should occur on its emergency bus. The loading of each diesel generator is conducted to demonstrate proper operation at less than the continuous rating and at. equilibrium operating conditions. Generator experience at other generator stations indicates that the testing frequency is adequate to assure a high reliability of operation should the system be required.
Both diesel generators have air compressors and air receivers tanks for starting.
It is expected that the air compressors will run only infrequently. During the monthly check of the units, each receiver will be drawn down below the point at which the compressor automatically starts to check operation and the ability of the compressors to recharge the receivers.
Following the tests of the units and at least weekly, the fuel volume remaining'will be checked. At the end of the monthly load test of the diesel generators, the fuel oil transfer pump will be operated to refill the day tank. The day tank level indicator and alarm switches will be checked at this time.
Fuel oil transfer pump operability testing is in accordance with Specification 4.6.E.
The test of the diesels and Uninterruptible Power Systems'during each refueling interval will be more comprehensive in that it will functionally test the systems i.e.,
it will check starting and closure of breakers and sequencing of loads. The 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 off-site power. The timing sequence will be checked to assure proper loading in the time required. Periodic tests between refueling intervals check the 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 sufficient to maintain adequate reliability.
The purpose of establishing the delayed access source once per operating cycle is to demonstrate that the delayed access source can be established within the required time of one hour and to demonstrate proper operation of the generator no load disconnect switch. The test demonstrates that power can be transferred to the delayed access source in a timely fashion. The test is not intended to simulate an actual loss of the immediate access source, failure of both diesel generators and consequent loss of power to the station buses.
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. The 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.
The performance discharge test provides adequate indication and assurance that the batteries have the specified ampere hour capacity. The rate of discharge during this test shall be in accordance with the manufacturer's discharge characteristic curves Amendment No. M, 4M, 4M 155 222-
o.
VYNPS ff4plSS:
'4.10 (Cont'd) for the associated batteries. The results of these tests will be logged and compared with the manuf acturer's recomendations of acceptability.
The service discharge test provides a test of the batteries ability to satisfy the design requirements (battery duty cycle) of the associated de system. This test will be performed using simulated or actual loads at the rates and for the durations specified in the design load profile.
Verification of operability of an off-site power source and Low Pressure Core and Containment Cooling Systems within one hour and once per eight hours thereafter as required by 4.10.B.3.b.1 may be performed as an administrative check by examining logs and other information to determine that required equipment is available and not out of service for maintenance or other reasons.
It does not require performing the surveillance needed to demonstrate the operability of the equipment.
C.
Logging 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 sediment test will be performed as described in ASTH D975-68.
The quality of the diesel fuel oil will be acceptable if the results of the tests are within the limiting requirements for diesel fuel oils shown on Table 1 of ASTM D975-68.
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-Amendment No. 155 223
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