ML15113A169
| ML15113A169 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/24/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A170 | List: |
| References | |
| DPR-38-A-140, DPR-47-A-140, DPR-55-A-137 NUDOCS 8507260079 | |
| Download: ML15113A169 (10) | |
Text
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. 140 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 April 30, 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 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 Nb. DPR-38 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. 140 are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.
85072674950624 PDR ADOCK 05000269 PDR
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Stolz, Chief p ating Reactors Branc #4 D' is ion of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 24, 1985
-t~j REOU 0
0 oUNITED STATES Co 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.i/ 140 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 April 30, 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 1; 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.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140 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 o
F lz, Chief Op rating Reactors R nch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 24, 1985
~pfk REGU 1 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.> 137 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 April 30, 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 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. 137 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 REGU ATORY COMMISSION Jo F. Stolz, Chief 0 erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 24, 1985
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 140 TO DPR-38 AMENDMENT NO. 140 TO DPR-47 AMENDMENT NO. 137 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 3.10-3 3.10-3 3.10-4 3.10-4 4.1-12 4.1-12
3.10.4 Waste Gas Holdup Tanks
- a.
The quantity of radioactivity contained in each waste gas hold up tank shall be limited to < 3.8E+05 curies noble gases (considered as Xe-133).
- b.
Daily, when radioactive materials are being added to a waste gas holdup tank, the quantity of radioactive material contained in the tank being filled shall be determined.
- c.
If the quantity of radioactive material in any waste gas hold up tank exceeds the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank 'contents to within the above limit.
3.10.5 Used Oil Incineration Used oil, contaminated by radioactivity, may be incinerated in the Station auxiliary boiler provided releases do not exceed one-tenth of one percent (0.1%) of the limits in Technical Specification 3.10.2.b.2.
3.10.6 Explosive Gas Mixture
- a.
The concentration limit of hydrogen in the Waste Gas Holdup Tanks is 3% by volume.
- b.
If the concentration of hydrogen in the Waste Gas Holdup Tanks exceeds 3% by volume, but is less than or equal to 4%
by volume, then within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the concentration of hydrogen to within the limit.
- c.
If the concentration of hydrogen in the Waste Gas Holdup Tanks exceeds 4% by volume, then promptly suspend all additions of waste gases to the tank,'and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, reduce the concentration of hydrogen to within the limit.
3.10.7 The provisions of Technical Specifications 3.0 do not apply.
Bases Specification 3.10.1 is provided to assure that the dose rate at anytime at the exclusion area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactivity material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an Amendments Nos. 140, 140, & 137 3103
individual at or beyond the exclusion area boundary to < 500 mrem/year to the total body or to < 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid rate above background to an infant via the milk animal-milk-infant pathway to < 1500 mrem/year for the nearest milk animal to the plant.
Specification 3.10.3 is provided to implement the requirements of Appendix I, 10 CFR Part 50. The specification provides the required operating flexibility and at the same time implements the guides set forth in Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."
Surveillance requirements are implemented to meet the requirements of Appendix I. Calculational procedures based on models and data show that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods for calculating the doses due to the actual re lease rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
Equations in the ODCM are provided for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the develop ment of these calculations are:
- 1) individual inhalation of airborne radio nuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the release of radioactive ma terials in gaseous effluents will be kept "as low as is reasonably achievable."
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50.
Restricting the quantity of radioactivity contained in each waste gas holdup tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.
Specification 3.10.6 is provided to ensure that the concentration of potenti ally explosive gas mixtures contained in the Waste Gas Holdup Tanks is main tained below the flammability limits of hydrogen. (Administrative controls are used to prevent the hydrogen concentrations from reaching the flammability limit.)
These controls include sampling each tank 5 times a week while in ser vice, and/or once in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank; injection of dilu tants to reduce the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive materials will be con trolled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10CFR Part 50.
- 3. 10-4 Amendments Nos. 140 140, & 137
C+,
C TABLE 4.1-3 Continued Minimum Sampling Frequency And Analysis Program Lower I.imit of Detection(s)
Stem Check Frequency of Lab Analysis for Waste 8a.
Waste Gas Decay
- a.
Principal Gamma Emitters
- a.
Grab Sample prior to re-
- a.
<10 4
pCi/cc (gases)
Tank lease of each batch
<10o10 pCi/cc (particulates he and iodines)
- b.
- b.
Grab sample prior to re-
- b.
<10- pCi/cc lease of each batch 8b.
Reactor Building
- a.
Principal Gamma Emitters
- a.
Grab Sample each purge
- a.
<10 pCi/cc (gases) te
<10-to pCi/cc (particulates b
Tritand iodines)
- b.
- b.
Grab Sample each purge
- b.
<106 pCi/cc
- 9.
Keowee Hydro Dam Measure Leakage Flow Rate Annually Dilution Flow
- 10.
Delete
- 11.
Backwash Receiving Tanks Principle Gamma Emitters in-Grab Sample prior to cluding dissolved noble gases release of each batch
- 12.
- 3 Chemical Treatment Pond
- a.
Principal Gamma Emitters(6)
- a.
Monthly from (10)
- a.
Ce-144 and Ho-99 <5xl0 pCi/ml Effluent composite sample Other Gamma Nuclides
<5xl0 7 pCi/ml Dissolved Gases
<10 5 pCi/ml 1-131 <10 6 pCi/ml
- b.
Radiochemical Analysis
- b.
Quarterly from
- b.
<5x]Os PCi/ml for Sr's Sr-89, Sr-90, Fe-55 composite sample(b.
<50 6
pCC/mI for Fe-55
- c.
- c.
Monthly from (10)
- c.
<10-pCi/mi composite sample
- d.
Gross Alpha Activity
- d.
Monthly from (10)
- d.
<10-7 pCi/ml composite sample
- 13.
Waste Gas Holdup Tank Hydrogen Concentration 5 times/week on each tank while in service and/or once in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank