ML16138A611
| ML16138A611 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/07/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A612 | List: |
| References | |
| NUDOCS 8712160286 | |
| Download: ML16138A611 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated August 13, 1986, as supplemented May 14, 1987, 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 set forth in 10 CFR Chapter 1; D. The issuance of this license 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 Technial Specifications as indicated in the attachments 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. 164, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
87121 96286 871207 PDR ADOCK 05000269
! PDR
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan N. Jabbour, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance:
December 7, 1987 PDII-DRP-I/II P
-3/DRP-I/II OGC-Bethesda PDII-3/DRP-I/II u an*/rad H
is 1.Acting Director 11/ q/87 11/1)-/87 11/ Wi/87 116-/
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- jkRECOu, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated August 13, 1986, as supplemented May 14, 1987, 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 set forth in 10 CFR Chapter 1; D. The issuance of this license 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 Technial Specifications as indicated in the attachments 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. 164, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan N. Jabbour, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: December 7, 1987 PD I/RP-I/II PD
/DRP-I/II OGC-Bethesda PDII-3/DRP-I/II MDun a rad HP s
Actiy1X 16
/
11/ 1L187 1111q87 14ok/87
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 161 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated August 13, 1986, as supplemented May 14, 1987, 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 safetyiof the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D. The issuance of this license 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 Technial Specifications as indicated in the attachments to this license amendment, and Paragraph 3.8 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. 161, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan N. Jabbour, Acting Director Project Directorate 11-3 Division of Reactor Projects - I/II
Attachment:
Technical Specification Changes Date of Issuance: December 7, 1987 PDII-4 RP-I/II PI 3/DRP-I/II 0GC-Bethesda PDII-t
/DRP /I MDbi'n/rad P tis A
Acting Di/ee/-87 ii/5 /87 li/ P4,8 7 1 1/iS /87 11/6z,/87
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 164 TO DPR-38 AMENDMENT NO. 164 TO DPR-47 AMENDMENT NO. 161 TO DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised page are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page Page 2.2-1 2.2-1 2.3-3 2.3-3 2.3-5 2.3-5 2.3-7 2.3-7
2.2 SAFETY LIMITS -
REACTOR COOLANT SYSTEM PRESSURE Applicability Applies to the limit on reactor coolant system pressure.
Obj ective To maintain the integrity of the reactor coolant system and to prevent the release of significant amounts of fission product activity.
Specification 2.2.1 The reactor coolant system pressure shall not exceed 2750 psig when there are fuel assemblies in the reactor vessel.
2.2.2 The setpoint of the pressurizer code safety valves shall be in accordance with ASME, Boiler and Pressurizer Vessel Code,Section III, Article 9, Summer 1967.
Bases The reactor coolant system (1) serves as a barrier to prevent radionuclides in the reactor coolant from reaching the atmosphere.
In the event of a fuel cladding failure, the reactor coolant system is a barrier against the release of fission products. Establishing a system pressure limit helps to assure the integrity of the reactor coolant system. The maximum transient pressure allowable in the reactor coolant system p Msure vessel under the ASME code,Section III, is 110% of design pressure.
The maximum transient pressure allowable in the reactor coolant system piping, valves, and fittings under USAS Section B31.7-is 110% of design pressure. Thus, the safety limit of 2750 psig (110% of the 2500 psig design pressure) has been established. ()
The settings, the reactor high( essure trip (2355 psig) and the pressurizer safety valves (2500 psig) have been established to assure never reaching the reactor coolant system pressure safety limit. The initial hydrostatic test was conducted at 3125 psig (125% of design pressure) to verify the integrity of the reactor coolant system. Additional assurance that the Reactor Coolant pressure does not exceed the safety limit is provided by setting the pressurizer electromatic relief valve at 2450 psig.
REFERENCES (1) FSAR, Section 5 (2) FSAR, Section 5.2.3.10.1 (3) FSAR, Section 5.2.2.3, Table 5.4-7 (4) FSAR, Section 5.4.6, Table 5.1-1 2.2-1 Amendment No. 164 (Unit 1)
Amendment No. 164 (Unit 2)
Amendment No. 161 (Unit 3)
Reactor Coolant System Pressure During a startup accident from low power or a slow rod withdrawal from high power, the reactor coolant system (RCS) high pressure setpoint is reached before-the nuclear overpower trip setpoint. The high RCS pressure trip set point (2355 psig) ensures that the prqsure remains below the safety limit (2750 psig) for any design transient.
The low pressure (1800 psig) and variable low pressure (11.14 Tout -
4706) trip setpoints shown in Figure 2.3-1 ensure that the minimum DNBR is greater than or equal to the min mum allowable DNBR for those accidents that result in a reduction in pressure. '
The limits shown in Figure 2.3-1 bound the pressure-temperature curves calculated for 4, 3, and 2 pump operation.
Accounting for calibration and instrumentation errors, the safety analyses used a variable low RCS pressure trip setpoint of (11.14 T 4756).
out Coolant Outlet Temperature The high reactor coolant outlet temperature trip setpoint (618 0F) shown in Figure 2.3-1 has been established to prevent excessive core coolant temper atures. Accounting for calibration and instrumentation errors, the safety analyses used a trip setpoint of 620oF.
Reactor Building Pressure The high reactor building pressure trip setpoint (4 psig) provides positive assurance that a reactor trip will occur in the unlikely event of a loss-of coolant accident, even in the absence of a low reactor coolant system pressure trip.
Shutdown Bypass In order to startup the reactor and to be able to perform control rod drive tests and zero power.physics tests (see Technical Specification 3.1.9), there Ris provision for bypassing certain segments of the reactor protective system (RPS).
The RPS segments which can be bypassed are given in Table.2.3-1. Two conditions are imposed when the RPS is bypassed:
- 1.
By administrative control the nuclear overpower trip setpoint is reduced to a value of < 5.0%4 of rated power.
- 2.
The high reactor coolant system pressure trip setpoint is automatically lowered to 1720 psig.
The high RCS pressure trip setpoint is reduced to prevent normal operation with part of the RPS bypassed. The reactor must betripped before the bypass is initiated since the high pressure trip setpoint is lower than the normal low pressure trip setpoint (1800 psig).
The overpower trip setpoint of < 5.0% prevents any significant reactor power from being produced when performing physics tests.
If no reactor coolant pumps are operating, sufficteqt natural circulation would be available to remove 5.0% of rated power.~5 Amendment No. 164 (Unit 1)
Amendment No. 164 (Unit 2) 2.3-3 Amendment No. 161 (Unit 3)
2400 P = 2355 PSIG T
618oF 2300 2200 ACCEPTABLE OPERATION 2100 UNACCEPTABLE OPERATION 0
2000 1900 P = 1800 PSIG 1800
-T
= 584F 540 560 580 600 620 640 Reactor Outlet Temperature.F PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNITS 1, 2, AND 3 u
OCONEE NUCLEAR STATION Figure 2.3-1 Amendment No. 164 (Utit 1)
Amendment No. 164 (Unit 2)
Amendment No. 161 (Unit 3) 2.3-5
TABLE 2.3-1 Reactor Protective System Trip. Setting Limits Shutdown RPS Trip RPS Trip Setpoint Bypass
- 1.
Nuclear Overpower 105.5% Rated Power 5.0%
Rated Power
- 2.
Flux/Flow/Imbalance 1.07 Bypassed
- 3.
Pump Monitors
- a.
> 0% Rated Power loss Bypassed of two pumps in one reactor coolant loop
- b.
> 55% Rated Power loss of two pumps
- c.
> 0% Rated Power loss of one or two pumps during two pump operation
- 4.
High Reactor Coolant 2355 psig 1720(2)
System Pressure
- 5.
Low Reactor Coolant 1800 psig Bypassed System Pressure
- 6.
Variable LoW Reactor P (ps g-(11.14 To Bypassed Coolant System Pressure 4706) 3out
.7.
High Reactor Coolant 618 0 F 618 0 F Temperature
- 8.
High Reactor Building 4 psig 4 psig Pressure (1) Administratively controlled reduction set only during reactor shutdown.
(2) Automatically set when other segments of the RPS are bypassed.
(3) Tout is in degrees Fahrenheit (OF).
Amendment No.
164 (Unit 1)
Amendment No. 164 (Unit 2) 2.3-7 Amendment No. 161 (Unit 3)