ML15112B006
| ML15112B006 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 03/31/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B007 | List: |
| References | |
| DPR-38-A-095, DPR-47-A-095, DPR-55-A-092, TAC 54862, TAC 54863 NUDOCS 8104090161 | |
| Download: ML15112B006 (9) | |
Text
UNITED STATES 0
NUCLEAR REGULATORY-COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The filing by Duke Power Company (the licensee) dated flay 19, 1980, as supplemented December 17, 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 filing, 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 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. 95 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
810 4OS0/lole
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oh F. St Chief rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1981
UNITED STATES 16, NUCLEAR REGULATOR Y.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. 95 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The filing by Duke.Power Company.(the licensee) dated flay 19, 1980, as supplemented December 17, 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 B. The facility will operate in conformity with the filing, the pro visions of the Act, and the rules and regulations of the Cormission; 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 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. 95 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 J hn F. Stol z, Chie) 0Oerating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1981
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.
92 License No. DPR-55
- 1. The,Nuclear Regulatory Commission (the Commission) has found that:
A. The filing by Duke Power Company (the licensee) dated flay 19, 1980, as supplemented December 17, 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 filing, 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 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. 92 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 Oate of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,onF.
Stolz, Chief 0
rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1981
ATTACHMEqT TO LICENSE AMENDMENTS AMENDMENT NO. 95 TO DPR-38 AMENDMENT NO. 9b TO DPR-47 AMENDMENT NO. 92 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 3.10-3 3.10-3 3.10-4 3.10-4
3.10.8 The reactor building shall not be purged unless the following conditions are met:
- a. Reactor building purge shall be through the high efficiency parti culate filters and charcoal filters until the activity concentration is below the occupational limit inside the reactor building, at which time bypass may be initiated.
- b. If reactor building is purged, the purge shall be through the high efficiency particulate filters whenever irradiated fuel is being handled or any objects are being handled over irradiated fuel in the reactor building.
3.10.9 Used oil, contaminated by radioactivity, may be incinerated in. the Station auxiliary boiler provided it meets the following limits:
- a. Oil shall not be disposed of by incineration.if any 55-gallons contain radioactivity in excess of the quantities given in 10 CFR Part 20, Appendix C;
- b. The rate of incineration shall be limited such that the concentration in the stack does not exceed 0.5 times the quantity given in 10 CFR Part 20, Appendix B, Table 2, Col. 1;
- c. Contaminated oil shall be burned no more than six hours in any calendar quarter.
3.10.10 In addition to the above continuous sampling and monitoring requirements, gaseous radioactive waste sampling and activity analysis shall be pcr formed in accordance with Table 4.1-3. Records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section 6.6 of these specifications.
Bases It is expected that the releases of radioactive materials and gaseous wastes will be kept within the design objective levels and will not exceed on an instantaneous basis the dose rate limits specified in 10CFR20..
These levels provide reasonable assurance that the resulting annual exposure from noble gases to the whole body or any organ of an individual will not exceed 10 mRem per year. At the same time, the licensee is permitted the flexibility of operation compatible with considerations of health and safety to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10CFR20.
It is expected that using this operational flexibility under unusual operating conditions, the licensee shall exert every effort to keep levels of radioactive materials and gaseous wastes as low as practicable and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10CFR20. These efforts shall include consideration of meteorological con ditions during releases.
The anticipated annual releases from the three Oconee reactor units have been developed taking into account a combination of system variables including fuel failure, primary system leakage, and the performance of radio-isotope removal mechanisms. The values assumed for these variables include the following:
Amendments Nos. 95
, 95,
& 92 3.10-3
- a. Reactor coolant fission product concentration corresponding to 0.25 percent fuel cladding defects;
- b. Steam generator primary-to-secondary leakage rate of 20 gpd;
- c. Reactor coolant leakage to the containment building of 120 gpd and 12 containment vents per year;
- d. Primary coolant stripped 12 times per year;
- e. Decay time of the waste gas processing system -
30 days;
- f. Decontamination factor of 1,000 for iodine in the evaporator;
- g. Charcoal filter decontamination factor of 10 for iodine removal in the purge exhaust system.
The application of the above estimates results in the radio-gas.discharge rates shown in Table 111-13 of the "Final Environmental Statement Related to Operation of Oconee Nuclear Station Units 1, 2, and 3".
The noble gas release rates stated in the objectives are based on a X/Q value from the annual meteorological data. The dispersion factor used, 3.6 x 10-6 sec/m 3, is conservative and the release rate is controlled to a small fraction of 10CFR20 requirements at. the exclusion area boundary (.02 of 10CFR20 =
less than 10 mRem per year).
The 1-131 and particulate release rates stated in the objectives limits the concentration at the exclusion area boundary to much.less than 1 percent of the MPC listed in 10CFR20. The release rate also controls the expected iodine dose due to the milk pathway (using concentration factor in the milk pathway of 700) at the nearest cow and the nearest dairy (taken as five miles west, X/Q = 1.22 x 10-7 sec/m 3 ) to less than five millirem per year. This meets the intent of proposed Appendix I to 10CFR50. A survey will be conducted once per year to a>'are that nCd ;;ilk producing cows are within a five mile radius of the plant.
The maximum one-hour release rate limits the dose rate at the exclusion area boundary to less than 2 mRem per hour even during.periods of unfaiorable meteorology (using conservative meteorological conditions, i.e., two hour X/Q of 1. 16 x 10
- sec/m 3 accident meteorology).
The maximum activity in a gaseous waste tank is specified as 17,200 curies/E based on a postulated tank rupture that allows all of the contents to escape to the atmosphere. This specification limits the maximum off-site dose to well below the limits of 10CFR100.
The lowest practicable gaseous release objectives expressed in this specifi cation are based on the guidelines contained in the proposed Appendix I of 10CFR50. Since these guidelines have not yet bden adopted, the release objectives'of this specification will be reviewed at the time Appendix I becomes a regulation to assure that this specification is based upon the guidelines contained therein.
Amendments Nos. 95, 95, & 92 3.l04