ML16293A754
| ML16293A754 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/21/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A721 | List: |
| References | |
| NUDOCS 9109060095 | |
| Download: ML16293A754 (10) | |
Text
REG RE0 0
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. 189 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 February 11, 1991, 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 I; 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 hereby amended by page 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:
9 109060095 910121 PDR ADOCK 05000269 PDR
_)
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 189, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
August 21, 1991
\\,~P REGuZ 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. 189 License No. DRR-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 February 11, 1991, 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 I; 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 hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 189, 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 its date of issuance.
FOR T NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 21, 1991
C REG&jZ 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. 186 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 February 11, 1991, 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 I; 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 hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 186, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 21, 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 189 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 189 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 186 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding over leaf page is also provided to maintain document completeness.
Remove Pages Insert Pages 5.2.1 5.2.1 5.2.2*
5.2.2*
- Overleaf page
5.2 CONTAINMENT Specification The containment for this unit consists of three systems which are the reactor building, reactor building isolation system, and penetration room ventilation system.
5.2.1 Reactor Building The reactor building completely encloses the reactor and its associated reactor coolant system. It is a fully continuous re inforced concrete structure in the shape of a cylinder with a shallow domed roof and flat foundation slab. The cylindrical portion is prestressed by a post tensioning system consisting of horizontal and vertical tendons. The dome has a three-way post tensioning system. The structure can withstand the loss of 3 horizontal and 3 vertical tendons in the cylinder wall or adjacent tendons in the dome without loss of function. The foundation slab is conventionally reinforced with high strength reinforcing steel. The entire structure is lined with 1/4" welded steel plate to provide vapor tightness.
The internal volume of the reactor building is approximately 1.836 x 106 cu. ft. The approximate inside dimensions are:
diameter-116'; height--208 1/2'.
The approximate thickness of the concrete forming the building are:
cylindrical wall--3 3/4'; dome--3 1/4';
and the foundation slab--8 1/2'.
The concrete containment structure provides adequate biological shielding for both normal operation and accident situations.
Design pressure and temperature are 59 paig and 2860F, respectively.
The reactor building is designed for an external atmospheric pressure of 3.0 psi greater than the internal pressure.
This is greater than the differential pressure of 2.5 paig that could be developed if the building is sealed with an internal temperature of 120oF with a barometric pressure of 29.0 inches of Hg and the building is subsequently cooled to an internal temperature of 80aF with a concurrent rise in barometric pressure to 31.0 inches of Hg. Since the building is designed for this pressure differ ential, vacuum breakers are not required.
Penetration assemblies are seal welded to the reactor building liner. Access openings, electrical penetrations, and fuel trans fer tube covers are equipped with double seals. Reactor building purge penetrations and reactor building atmosphere sampling penetrations are equipped with double valves having resilient seating surfaces. (1)
Amendment No. 189 (Unit 1 5.2-1 Amendment No. 189 (Unit 2)
Amendment No. 186 (Unit 3)
The principal design basis for the structure is that it lit capable of withstanding the internal pressure resulting from a loss of coolant accident, as defined in FSAR Section 15 with no loss of integrity. In this event the total energy contained in the water of the reactor coolant system is assumed to be released into the reactor building through a break in the reactor coolant piping.
Subsequent pressure behavior is determined by the building volume, engineered safety features, and the combined influence of energy sources and heat sinks.
5.2.2 Reactor Building Isolation System Leakage through all fluid penetrations not serving accident consequence-limiting systems is to be minimized by a double barrier so that no single, credible failure or malfunction of an active component can result in loss-of-isolation or intolerable leakage.
The installed double barriers take the form of closed piping systems, both inside and outside the reactor building and various types of isolation valves.
(2) 5.2.3 Penetration Room Ventilation System This system is designed to collect, control, and minimize the release of radioactive materials from-the reactor building to the environment in post-accident conditions. It may also operate intermittently during normal conditions as required to maintain satisfactory temperature in the penetrations rooms. When the system is in operation, a slight negative pressure will be main tained in the penetration room to assure inleakage. (3)
RE RENCES (1) FSAR Sections 6.2.1, and 6.2.3 (2) FSAR Section 6.2.3 (3) FSAR Section 6.5.1.1 Amendments Nos.
139, 139 136 5.2-2
The principal design basis for the strycture is th cp of withstanding the internal pressure resu t com a loi on coolant accident, as defined in FSAR Sectjon. 15.ith no lo1s of integrity. In this event the tnotd1inene rgy-on ndt of the reactor coolant system is assumed to be re eased into the reactor building through a break in the reactor coolant piping.
Subsequent pressure behavior is determied by b
uildin
- volume, engineered safety features, and the combined influence of energy.
sources and heat sinks.
5.2.2 Reactor Building Isolation System Leakage through all fluid penetrations not serving accident consequence-limiting systems is to be minimize, by a double barrier so that no single, credible failure or malfunction of an active component can result in loss-of-isolation or intolerablc leakage.
The installed double barriers take the.'form of closed piping systems, both inside and outside-.the reactor building and various types of isolation valves.
(2) 5.2.3 Penetration Room Ventilation System This system is designed to collect, control, and minimize the release of radioactive materials from the reactor building to the environment in post-accident conditions. It may also operate intermittently during normal conditions as required to maintain satisfactory temperature in the penetrations rooms.
When the system is in operation, a slight negative pressure will be main tained in the penetration room to assure inleakage. (3)
RE REN C S (1) FSAR Sections 6.2.1, and 6.2.3 (2) FSAR Section 6.2.3 (3)
FSAR Section 6.5.1.1 Amendments Nos.
- 139, 139, & 135 5.2-2