ML15113A144
| ML15113A144 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/11/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A145 | List: |
| References | |
| DPR-38-A-135, DPR-47-A-135, DPR-55-A-132 NUDOCS 8502250742 | |
| Download: ML15113A144 (9) | |
Text
0-AR,&C UNITED STATES 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. 135 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 August 8, 1984, 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 Commiss4on',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 li-cense
-amendment, and paragraph 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.1 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8502250742 85026 PDR ADOCK0 PDR
-2
- 3. This license amendment is effective as of the date-of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION jJoh
. Stolz, Chief Op ating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 11, 1985
RE A
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. 135 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 August 8, 1984, 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 requtrements have been sati'sfifed.
- 2. Accordingly, the license IAs :amended,by changes to the TecTncal Specifications as Indicated In the 'attachment to-this license amendment, and paragraph :3..B of Facility O0perating 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.135 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 Jo n F. Stolz, Chief 0 erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 11, 1985
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.132 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 August 8, 1984, 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 reaulations 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 3.8 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.132 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 i.ts issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
.Stolz, Chief 0 erating Reactors Branch #4 isivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 11, 1985
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.13 5 TO DPR-38 AMENDMENT NO.135 TO DPR-47 AMENDMENT NO.132 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the followino page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment numbers and contains a vertical line indicating the area of change.
Remove Page Insert Page 4.4-3 4.4-3 4.4-4 4.4-4*
- Overleaf page provided for document completeness.
4.4.1.5 Containment Air Lock Testing 4.4.1.5.1 Scope of Testing The Personnel Air Lock and Emergency Air Lock shall be tested as required by the following:
4.4.1.5.2 Frequency of Test (a) The Personnel Air Lock and Emergency Air Lock shall be tested semiannually at an internal pressure of not less than 59 psig.
(b) Air locks opened during periods when containment integrity is not required shall be tested at the end of such periods by a full hatch leak test at not less than 59 psig. If the full hatch test has been performed within the previous 3 days, the leak test can be performed between the double seal of the outer door at not less than 59 psig.
(c) When containment integrity is required, either a full hatch leak test or a leak test of the outer door double seal will be performed within 3 days of initial opening, and during periods of frequent use, at least once every 3 days. Each leak test will be performed at not less than 59 psig.
4.4.1.5.3 Acceptance Criteria The acceptance criteria for the air lock leakage test is as stated in Specification 4.4.1.2.3.
Amendment Nos. 135, 135 & 132 4.4-3
Bases The Reactor Building is designed for an internal pressure of 59 psig and a steam-air mixture temperature of 28601. This corresponds -to a post-accident containment atmosphere mass of 5.1277 x 105 ibm. Prior to initial operation, the containment was strength tested at 115 percent of design pressure and leak rate tested at the design pressure. The containment was also leak tested prior to initial operation at approximately 50 percent of the design pressure.
These tests verified that the leak rate from Reactor Building pressurization satisfies the relationships given in the specification.
The performance of Oa periodic integrated leak rate test during unit life provides a current assessment of, potential leakage from the containment, in case of an accident. In order to provide a realistic appraisal of the integrity of the containment under accident conditions, this periodic test is to be per formed without preliminary leak detection surveys or leak repairs, and contain ment isolation valves are to be closed in the normal manner.
The test pressure of 29.5 psig for the periodic integrated leak rate test is sufficiently high to provide an accurate measurement of the leak rate and it duplicates the pre operational leak rate test at 29.5 psig.
The frequency of the periodic integrated leak rate test is normally keyed to the refueling schedule for the reactor, because these tests can best be performed during refueling shutdowns.
The specified frequency of periodic integrated leak rate tests is based on three major considerations.
First is the low probability of leaks in the liner, because of conformance of the complete containment to a 0.25 percent leakage rate at 59 psig during preoperational testing and the absence of any significant stresses in the liner during reactor operation.
Second is the more frequent testing, at design pressure, of those portions of the contain ment envelope that are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.125 percent) of leakage that is specified as acceptable from penetrations and isolation valves.
Third is the tendon stress surveillance program which provides assurance that an important part of the structural integrity of the containment is maintained.
Leakage to the penetration room, which is permitted to be up to 50 percent of the total allowable containment-leakage, is discharged ;through high efficiency particulate: air (KEPA) and charcoal filters to the -unit !vent.
The ffiters are conservatively said -to be 90.percent efficient for iodine removal.
More frequent testing of various penetrations is :specified as these locations are more susceptible to leakage than the Reactor Building liner due to the mechanical closure involved.
Testing of these penetrations is performed with air or 2i:rogen. The basis for specifying a maximum Leak rate of 0.125 tpercent from penetrations and isolation valves is that one-half-of the actual integrated leak rate is-- expected from those sources.
Valve operability tests are speci fied to assure proper closure or opening of the Reactor Building isolation valves to provide for isolation of functioning of Engineered Safety Features systems.
Amendments Nos.
104, 104, & 101 4.4-4-