ML15112B021
| ML15112B021 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/24/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B022 | List: |
| References | |
| DPR-38-A-099, DPR-47-A-099, DPR-55-A-096 NUDOCS 8107300298 | |
| Download: ML15112B021 (12) | |
Text
NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.
50- 269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 6, 1981, 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 pro visions 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 satis fied.
- 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-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8107300298 810724 PDR ADOCK 05000269 p
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Chte erating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 24, 1981
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50- 270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.99 License No. DPR-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 6, 1981, 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 pro visions 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 complidnce 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 satis fied.
- 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-47 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
F. Stolz, Chief 0 erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 24, 1981
REG&
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.96 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated July 6, 1981, 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 pro visions 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 incompliance 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 satis fied.
- 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-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J hn F. Stolz, Chie erating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 24, 1981
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 99 TO DPR-38 AMENDMENT NO. gg TO DPR-47 AMENDMENT NO. 96 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are-identified by amendment numbers and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 3.7-3 3.7-3 3.7-4 3.7-4*
3.7-7 3.7-7 3.7-8 3.7-8 3.7-9 3.7-9
- No change on this page; included for document completeness.
- 1. 230KV Switching Station 125VDC Power System
- 2. Keowee Hydro Station 125VDC Power System
- 3. Each unit's 125VDC Instrumentation and Control Power System (f) For periods not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each unit's 125VDC system may be separated from its backup unit via the isolatiig and transfer diodes.
3.7.3 In the event that the conditions of Specification 3.7.1 are not met within the time specified in Specification 3.7.2, except as noted below in Specification 3.7.4, 3.7.5, 3.7.6, and 3.7.7 the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If these requirements are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed 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 />.
3.7.4 In the event that all conditions in Specification 3.7.1 are met ex cept that one of the two Keowee hydro units is expected to be un available for longer than the test or maintenance period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor may be heated about 200 0F if previously shutdown or be permitted to remain critical or be.. restarted provided the following restrictions are observed.
(a) Prior to heating the reactor above 200 0F or prior to the re start of a shutdown reactor or within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the loss of one Keowee hydro unit, the 4160 volt standby buses shall be energized by a Lee gas turbine through the 100 kV circuit.
The Lee gas turbine and 100 kV transmission circuit shall be electrically separate from the system grid and offsite non safety-related loads.
(b) The remaining Keowee hydro unit shall be connected to the under ground feeder circuit and this path shall be verified operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and weekly thereafter.
(c) The remaining Keowee hydro unit shall be available to the overhead transmission circuit but generation to the system grid shall be prohibited except for periods of test.
(d) Operation in this mode is restricted to periods not to exceed 45 days and the provisions of this specification may be utilized without prior NRC approval only once in three years for each Keowee hydro unit. Office of Inspection and Enforcement, Region II, will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.7.5 In the event that all conditions of Specification.3.7.1 are met ex cept that all 230 kV transmission lines are lost, the reactor shall be permitted to remain critical or be restarted provided the following restrictions are observed:
3.7-3 Amendment Nos. 99. 99 & 96
g (s)
Prior to the restart of a chutdown reactor-or vithin I hour of losing all 230 kV trancmission lines for an operating rec tor, the 4160 volt standby buses shall be energized by one of the Lee gas turbines through the 100 kV transmission circuit.
The Lee gas turbine and the 100 kV transmicsion circuit chill be c=pletely separate from the rystem grid and offite non-s o
f
-et related loads.,
(b) The reactor coolant T chall be above 5250F. retctor coolant pumg power =ay be g used to ele'Vate the tenperature from 500 F to 5250 in the case of restart.
If Tays decreases below 5000F, restart is not permitted by this specification.
(c). If all 230 UV transmission lines are lost, restore at least one of the inoperable 230 kV offsite sources to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. With only one offsite source restored, restore at least two 230 kV offsite circuits to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and-in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
(d) After loss of all 230 kV transmission lines, this information shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Office of Inspiction and Enforcement, Region II. If the outage is expected to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a vritten report shall be submitted detailing the cir cuxstances of the outage and the estimated tie to return the 130 UV transmission lines to operating condition.
3.7. 6 In the c 't that all conditions of Specificatic:
3.7.L are act, end lan~
- cZs or maintenance are required, which will rake both Keowee unit --
vfilable, the 4160 volt standby buses shall first be ener g-zc: 'y Lee gas turbine through the 100 kV transmission circuit crnd
- ~. be separate from the system grid and offsite non-safety-related cocad.
The reactor shall then be permitted to remain critical for pericic rot to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with both Keowee units unavailable.
Prior to hot restart of a reactor from a tripped condition, the causes and the effects of the shutdoun shall be established and analyzed. A restart wil1 be-permitted if the cause of such trips are the result of error. or of minor equipment =alfunctions.
A restart will not be permitted if the, trip is a result of cystem transients or valid pro tection rvstem action.
3.7.7 In the event that'all conditions of Specification 3.7.1 are met except that both Keowee hydro units become unavailable for unplanned reasons, the reactor shall be permitted to remain critical for periods not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the 4160 volt standby buses are energized withn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by the Lee gas turbinethrough the 100 kVN transmission circuit and it shall be separate from the system grid andall offsite norl-safety-related loads.
3.7-4
The standby bus can receive power from the hydro station through the underground feeder circuit or from a combustion turbine generator at the Lee Steam Station over an isolated 100 kV transmission line. The 230 kV switchyard can receive power from the on-site Keowee hydro station or from several. off-site sources via transmission lines which connect the Oconee Station with the Duke Power system
'power distribution network.
Redundancy of DC System A.
125 VDC Instrumentation and Control Power System The 125 VDC Instrumentation and Control (I&C) Power System consists of two batteries, three battery chargers, and two I&C distribution centers per unit. All reactor. protection and engineered safety features loads on this system can be powered from either the Unit I and Unit 2 or Unit 2 and Unit 3 or Unit 3 and Unit 1 125 VDC I&C distribution centers. The 125 VDC I&C distribution centers are normally supplied from their associated battery and charger. For one unit, in the event that only one of its batteries and associated chargers are operable, both I&C distribution centers will be tied together allowing operation of the DC loads from the unit's operable battery and charger. As shown above,.one I&C battery (e.g., ICA) can supply both I&C distribution centers (e.g., IDCA and IDCB) and their associated panelboard loads. Also, one of the three battery chargers for each. unit can supply all connected ESF and reactor protection loads.
In order to find and correct a DC ground on the 125 VDC Instrumentation and Control system each unit's DC system must be separated from the other two units. This is due' to the interconnected design of the system. With the backup function disabled the units would be in a degraded mode but would in fact have all of its own DC system available if needed. Each unit's batteries either.CA or CB is capable of carrying all the 125 VDC Instru mentation and Control loads on that unit.
B..125 VDC' Switching Station Power System There are two essentially independent subsystems each complete with an AC/DC power supply (battery charger), 'a battery bank, :a.battery charger bus, motor control center (distribution panel).
Except for the support racks for the batteries, all safety-related equipment and the relay house in which it is located are seismic Category I design. The support racks for the batteries will be upgraded to seismic Category I as soon as possible. Each sub-system provides the necessary DC power to:
- a.
Continuously monitor operations of the protective relaying,
- b.
Isolate Oconee (including Keowee) from all external 230 kV grid faults,
- c.
Connect on-site power to Oconee from a Keowee hydro unit, or
- d.
Restore off-site power to Oconee from non-faulted portions of the external 230 kV grid.
Provisions are included to manually connect a standby battery charger to either battery/charger bus.
3.7-7 Amendment Nos. 99, 99 & 96
C.
125 VDC Keowee Station Power System There are essentially two independent physically separated seismic Category I subsystems, each complete with an AC/DC power supply (charger) a battery bank, a battery/charger bus and a.DC distribution center. Each subsystem provides the necessary power to automatically or manually start, control and protect one of the hydro units.
An open or short in any one battery, charger of DC distribution center, cannot cause loss of both hydro units.
The 230 kV sources, while expected to have excellent availability, are not under the direct control of the Oconee station and, based on past experience cannot be assumed to be available at all times.
However, the operation of the-onsite hydro station is under the direct control of the Oconee Station and requires no offsite power to startup. Therefore, an onsite backup source of auxiliary power is pro vided in the form of twin hydro-electric turbine generators powered through a common penstock by water taken from Lake Keowee. The use of a common penstock is justified on the basis of past hydro plant experience of the Duke Power Com pany (since.1919) which indicates that the cumulative need to dewater the pen stock can be expected to be limited to about one day a year, principally for inspection, plus perhaps four days every tenth year.
Operation with one Keowee Hydro unit out of service for periods less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is permitted. The operability of the remaining Keowee hydro unit is verified within one hour by starting the unit and energizing the standby buses through the.underground feeder circuit. This action is repeated once every eight hours thereafter until the Keowee hydro unit is restored to service and will provide additional assurance of the operability of the remaining unit.
Provisions have been established for those conditions in which long term pre ventative maintenance of a Keowee Hydro unit is necessary. The primary long term maintenance items are expected to be hydro turbine runner and discharge ring welding repairs which are estimated to be necessary every six to eight years. Also, generator thrust and guide bearing replacements will be necessary.
Other items which manifest as failures are expected to be extremely rare and could possibly be performed during the permitted maintenance periods. Time periods of up to 45 days for each Keowee Hydro unit are permitted every three.
years. During these outages the remaining Keowee Hydro unit will be verified to be operable within one hour and weekly thereafter by starting the unit and energizing the underground feeder circuit. The remaining Keowee hydro unit will also be available through the overhead transmission path and will not be used for system peaking. Additionally, the standby buses will be energized continuously by one of the Lee gas turbines through the 100 kV transmission circuits.
This transmission circuit would be electrically separated from the systemngrid and all off-site non-safety-related loads.. This arrangement provides a high degree of reliability for the emergency power systems.
Operation with both Keowee Hydro units out of service is permitted for planned or unplanned outages for periods of 72 or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> respectively. Planned out ages are necessary for.the inspection of common underwater areas such as the penstock and to enable the removal of one Keowee unit from service. This would be a controlled evolution in which the availability and condition of the off site grid,. startup transformers and weather would be evaluated and a Lee gas 3.7-8
turbine would be placed in operation on the isolated 100 kV transmission line prior to commencement of the outage.
A time period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for unplanned outages of both Keowee units is ac ceptable since a Lee gas turbine will be started within one hour and will energize the standby buses through the dedicated 100 kV transmission line.
This period of time is reasonable to determine and rectify the situation which caused the loss of both Keowee units.
In the event that none of the sources of off-site power are available and it is considered important to continue to maintain an Oconee reactor critical or return it to criticality from a hot shutdown condition, one of the Lee gas tur bines can be made available as an additional backup source of power, thus assuring continued availability as an auxiliary power to perform an orderly shutdown of a unit should a. problem develop requiring shutdown of both hydro units.
3.7-9