ML15112A977
| ML15112A977 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/10/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A978 | List: |
| References | |
| NUDOCS 8101090184 | |
| Download: ML15112A977 (11) | |
Text
o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET-NWO.
5O0226
-OCONEE NUCLEAR STATION, UNIT NO. 1 ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 June 24, 1980, as supplemented October 14, 1980, 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 (1) 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 anonded by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.1 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.
89 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
810100
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1980 IA I
oUNITED 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. 89 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 June 24, 1980, as supplemented October 14, 1980, 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 suchlactivities 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 51lof the Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is anonded by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.1 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. 89 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 Roert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 3055 DUKE POWER COMPANY DOCKET NO. 50-287 OCOfE -NUCLEARSIATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 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 June 24, 1980, as supplemented October 14, 1980, 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 anonded by changes to the Technical Specifications as indicated in the attachment to this license amondnent and paragraph 3.8 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. 86 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This -licenvse-amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch 14 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1980 p I
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT'NO. 89 TO DPR-38 AMENDMENT NO. 89 TO DPR-47 AMENDMENT NO. 86 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages ii ii 1-2 1-2 3.0-1 3.1-1 3.1-1
Section 1.5.4 Ietueent Channel Calbraton 1-3 1.5.5 Beat Balance Check 1-4 1.5.6 Beat Balance Calibration 1-4 1.6 POWER DISTRIBUTION 1-4 1.7 CONTAINMENT INTEGRITY 1-4
- 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1-1 2.1 SAFETY LIMITS, REACTOR CORE 2.1-1 2.2 SAFETY LIMITS, REACTOR COOLANT SYSTEM PRESSURE 2.2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS PROTECTIVE 2.3-1 INSTRUMENTATION 3
.INa3,1 3.0 LIMITING CONDITION FOR OPERATION 3,0-1 3.1 REACTOR COOLANT STYES11 3.1.1 Operational Comonente 3.1-1 3.1.2 Pressurization, Beatup, and Cooldown Limitatione 3.1-3 3.1.3 Minimum Conditions for Criticality 3.1-8 3.1.4 Reactor Coolant System Activity 3.1-10 3.1.5 Chemistry 3.1-12 3.1.6 Leakage 3.1-14 3.1.7 Moderator Temerature Coefficient of Reactivity 3.1-17 3.1.8 Single Loop Restrictions 3.1-19 3.1.9 Low Power Physics Testing Restrictionb 3.1-20 3.1.10 Control Rod Operation 3.1-21 3.2 HIGH PRESSURE INJECTION AND CHEMICAL ADDITION SYSTEMS 3.2-1 3.3 EMERGENCY CORE COOLING., REACTOR BUILDING COOLING, REACTOR 3.3-1 BUILDING SPRAY AND LOW. PRESSURI SERVICE WATER SYSTEMS Amendments Nos. 89, 89,
& 86
1.2.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.
1.2.8 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going 'critical.
1.3 OPERABLE A system, subsystem, train, component or device shall be considered OPERABLE when it is capable of performing its intended safety functions. Implicit in this definition shall be the assumption that all essential auxiliary equip ment required in order to assure performance of the safety function is capable of performing its related support function(s).
Auxiliary equipment includes but is not limited to normal or emergency electrical power sources, cooling and seal water, instrumentation andcontrols, etc. If either the normal or emergency power to system, subsystem, train, component or device is not available it is considered OPERABLE for the purpose of satisfying the require ments of its applicable Limiting Condition for Operation, provided:
(a) the alternate power source is available, and (b) the redundant system is operable.
1.4 PROTECTIVE INSTRUMENTATION LOGIC 1.4.1 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control and/or protection.
An instrument channel may be either analog or digital in nature.
1.4.2 Reactor Protective System The reactor protective system is shown in Figures 7-1 and 7-6 of the FSAR.
It is that combination of protective channels and associated circuitry which forms the automatic system that protects the reactor by control rod trip.
It includes the four protective channels, their associated instrument channel inputs, manual trip switch, all rod drive protective trip breakers and activating relays or coils.
1.4.3 Protective Channel A protective channel as shown in Figure 7-1 of the FSAR (one of three or one of four independent channels, complete with sensors, sensor power supply units, amplifiers and bistable modules provided for every reactor protective safety parameter) is a combination of instrument channels forming a single digital output to the protective system's coincidence logic. It includes a shutdown bypass circuit, a protective channel bypass circuit and reactor trip module and provision for insertion of.a dummy bistable.
Amendments Nos.
89, 89, &
86 1-2
3 LIMITING CONDITIONS FOR OPERATION 3.0 LIMITING CONDITION FOR OPERATION Specification In the event a Limiting Codition for Operation (LCO) and/or associated Action requirements cannot be satisfied because ot circumstances in excess of those addressed in the specification, the affected unit shall be placed in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in at least Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless corrective measures are completed that permit operation under the permissible Action statements for the specified time interval as measured from initial discovery or until the reactor is placed in a mode in which the specification is not applicable. Exceptions to these requirements shall be stated in the individual specifications.
Bases This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements of existing LCOs and whose occurrence would violate the intent of the specification. For example, Specification 3.3.1 requires that two independent trains of the High Pressure Injection (HPI) System be operable and provides explicit Action requirements if one train of the HPI System is inoperable. Under the terms of Specification 3.0, if more than one train of the HPI System is inoperable, the affected unit is required to be in at least Hot Shut down within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in at least Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It is assumed that the unit is brought to the required mode within the required times by promptly initiating and carrying out the appropriate Action statement.
Amendments Nos. 89, 89, & 86 3.0-1
3.1 REACTOR COOLANT SYSTM Applicability Applies to the operating status of the reactor coolant system.
Objective To specify those limiting conditions for operations of the reactor coolant system components which must be met, to ensure safe reactor operation.
Specification 3.1.1 Operational Comnonents
- a. Reactor Coolant Pumps
- 1. Whenever the reactor is critical, single pump operation shall be pro hibited, single-loop operation shall be restricted to testing, and other pump combinations permissible for given power levels shall be as shown in Table 2.3-1.
- 2. Except for test purposes and limited by Specification 2.3, power operation with one idle reactor coolant pump in each Loop shall be restricted to 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.
If the reactor is not returned to an acceptable RC pump operating combination at the end of the 25-hour period, the reactor shall be in a hot shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. The boron concentration in the reactor coolant system shall not be reduced unless at least one reactor coolant pump or one low pressure injection pump is circulating reactor coolant.
- 1. One steam generator shall be operable whenever the reactor coolanc.
average temperature is above 2500
- c. Pressurizer Safety Valves
- 1.
pAll ressurizer code safety valves shall.be operable whenever the reactor is critical.
- 2.
At least one pressurizer code safety valve shall be operable whenever all reactor.coolant system,openings are closed, except for hydrostatic tests in accordance with the ASMLE Section III Boiler and Pressure Vessel Code.
Amendments Nos.
89, 89,
& 86 3.1-1