ML15113A105
| ML15113A105 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/27/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A106 | List: |
| References | |
| DPR-38-A-130, DPR-47-A-130, DPR-55-A-127 NUDOCS 8409070304 | |
| Download: ML15113A105 (10) | |
Text
UNITED STATES V
o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 130 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 February 10, 1983, 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 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; 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.
- 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. 130 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8409070304 840827 PDR ADOCK 05000269, K
P PDR
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John F. Stolz, Chief Operating Reactors Branrch No. 4
<,pvision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1984
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. 130 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 February 10, 1983, 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 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; 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.
- 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 130 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 REGYLATORY COMMISSION John F. Stolz, Chief Op 'rating Reactors Branch No. 4
-vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1984
oUNITED 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. 127 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 February 10, 1983, 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 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; 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.
- 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. 127 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 John F. Stolz, Chief Operating Reactors Brinch No. 4
'division of Licensing.
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1984
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 130 TO DPR-38 AMENDMENT NO. 130 TO DPR-47 AMENDMENT NO. 127 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 4.5-2 4.5-2 4.5-7 4.5-7 4.9-1 4.9-1
Reactor Coolant System, verification shall be made that the check and iso lation valves in the core flooding tank discharge lines operate properly.
- b. The test will be considered satisfactory if control board indication of core flood tank level verifies that all valves have opened.
4.5.1.2 Component Tests 4.5.1.2.1 Pumps The high pressure and low pressure injection pumps shall be started and op erated to verify proper operation in accordance with the requirements of Specification 4.0.4. Acceptable performance will be indicated if the pump starts, operates for 15 minutes, and the discharge pressure and flow are within +/- 10 percent of a point on the pump head curve.
(Figures 4.5.1-1 and 4.5.1-2) 4.5.1.2.2 Valves - Power Operated
- a. Valves LP-17, -18, shall only be tested every cold shutdown unless previously tested during the current quarter.
- b. During each refueling outage, low pressure injection pump discharge (engineered safety features) valves, low pressure injection discharge throttling valves, and low pressure injection discharge header crossover valves shall be cycled manually to verify the manual operability of these power-operated valves.
4.5.1.2.3 Check Valves Periodic individual leakage testing (a) of valves CF-12, CF-14, LP-47 and LP-48 shall be accomplished prior to power operation after every time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is performed.
Whenever integrity of these valves cannot be demonstrated, the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.
For the allowable leakage rates and limiting conditions for operation, see Technical Specification 3.1.6.10 Bases The Emergency Core Cooling Systems are the principle reactor safety featues in the event of loss of coolant accident. The removal of heat from the core provided by these systems is designed to limit core damage.
(a)
To satisfy ALARA requirements, leakge may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
Amendment Nos. 130, 130, 127 4.5-2
(2) Verification of the engineered safety features function of the Low Pressure Service Water System which supplies coolant to the reactor building coolers shall be made to demonstrate operability of the coolers.
(b) The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal properly, the appropriate pump breakers have completed their travel, fans are running at half speed, LPSW flow through each cooler exceeds 1400 GPM and air flow through each fan exceeds 40,000 CFM.
4.5.2.2 Component Tests 4.5.2.2.1 Pumps The reactor building spray pumps shall be started and operated to verify proper operation in accordance with the requirements of Specification 4.0.4.
Acceptable performance will be indicated if the pump starts, operates for 15 minutes, and the measured discharge pressure and flow results in a point above the pump head curve.
(Figure 4.5.2-1).
Bases The Reactor Building Coolant System and Reactor Building Spray System are
.designed to remove heat in the containment atmosphere to control the rate of depressurization in the containment.
The peak transient pressure in the con tainment is not affected by the two heat removal systems.
Hence, the basis for the spray pump flow acceptance test is the flow rate required during re circulation (1,000 gpm).
The delivery capability of one reactor building spray pump at a time can be tested by opening the valve in the line from the borated water storage tank, opening the corresponding valve in the test line, ahd starting the corres ponding pump.
Pump discharge pressure and flow indication demonstrate per formance.
With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection valves can each be opened and closed by operator action. With the reactor building spray inlet valves closed, low pressure air or fog can be blown through the test connections of the reactor building spray nozzles to demonstrate that the flow paths are open.
The equipment, piping, valves, and instrumentation of the Reactor Building Cooling System are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary concrete shield. Personnel can enter the Reactor Building during power operations to inspect and maintain this equipment. The service water piping and valves out side the Reactor Building are inspectable at all times. Operational tests and inspections will be performed prior to initial startup.
4.5-7 Amendment No& 130, 130, 127
4.9 EMERGENCY FEEDWATER PUMP AND VALVE PERIODIC TESTING Applicability Applies to the periodic testing of the turbine-driven and motor-driven emergency feedwater pumps and associated valves.
Objective To verify that the emergency feedwater pumps and associated valves are operable.
Specification 4.9.1 Pump Test The turbine-driven and motor-driven feedwater pumps shall be operated on recirculation to the upper surge tank for a minimum of one hour in accordance with the requirements of Specification 4.0.4.
4.9.2 Valve Test Automatic valves in the emergency feedwater flow path will be determined to be operable in accordance with the requirements of Specification 4.0.4.
4.9.3 System Flow Test Prior to Unit operation above 25% Full Power following any modifications or repairs to the emergency feedwater system which could degrade the flow path and at least once per refueling cycle, the emergency feedwater system shall be given either a manual or an automatic initiation signal.
4.9.4 Acceptance Criteria These tests shall be considered satisfactory if control board indication and visual observation of the equipment demonstrates that all components have operated properly. In addition, during operation of the System Flow Test (Item 4.9.3 above), flow to the steam generators shall be verified by control room indication.
Bases The monthly testing frequency is sufficient to verify that the emergency feed water pumps are operable. Verification of correct operation is made both from the control room instrumentation and direct visual observation of the pumps.
The parameters which are observed are detailed in the applicable edition of the ASME Boiler and Pressure Vessel Code,Section XI.
The System Flow Test verifies correct total system operation following modifications or repairs.
REFERENCES (1) FSAR, Section 10.2.2 (2) FSAR, Section 14.1.2.8.3 4.9-1 Amendment Nos. 130, 130, 127