ML15112A846
| ML15112A846 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/06/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A847 | List: |
| References | |
| NUDOCS 7903160046 | |
| Download: ML15112A846 (10) | |
Text
UNITED STATES 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. 70 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 June 9, 1978, 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.
7903160096
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- 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. 70 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 6, 1979
4A UNITED STATES NUCLEAR REGULATORY COMMISION WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO.,50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING.LICENSE Amendment No. 70 License No.
- 1. The Nuclear Regulatory Commissioi,(the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated June 9, 1978, 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.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.R 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. 70 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1979
UNITEDSTATES 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. 67 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 June 9, 1978, complies with the standards and require ents 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.
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. 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. 67 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1979
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 70 TO DPR-38 AMENDMENT NO. 70 TO DPR-47 AMENDMENT NO. 67 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 3.9-1 3.9-1 3.9-2 3.9-2 3.9-2a 3.9-3 3.9-3 Changes on the revised pages are indicated by marqinal lines.
3.9 RELEASE OP LIUID RADIOACTIVE WASTE Applicability Applies to the controlled release of aUl liquid waste dischaged from the station which say contain radioactive Materials.
Obiective To establish conditions for the release of Liquid veste containing radio active materials and to assure that all such releases are within the concan tration limits specified in 10 CYR Part 20.
In addition, to assure that the releases of radioactive material in Uquid wastes (above background) to Unrestricted areas meet the as low as reasonably achievable concept the following liquid release objectives shall apply:
- a.
The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, shall be lass than 5 curies per unit;
- b.
The annual average concentration of radioactive materials in liquid waste, upon release from the Restricted Area, excluding tritium and dissolved noble gases, shall not exceed 2 x 10-8 uCi/ul;
- c.
The annual average concentration of tritium in liquid waste, upon release from the Restricted Area, shall not exceed 5 x 10-6 pci/ml;
- 4. The annual average concentration of dissolved gases in liquid wats, upon release from the Restricted Area, shall not exceed 2 x 10-6 pCi/ml; Specifications 3.9.1 If the experienced release of radioactive materials in liquid wastes, when averaged over a calendar quarter, is such that these quantities if continued at the same release rate for a year would exceed twice the annual objectives the licensee will:
- a.
Make an investigation to identify the causes for such release rates;
- b. Define and initiate a program of action to reduce such release rates to the design levels; and
- c. Describe these actions in a report to MRCfDOR within 30 days after incurring the reporting obligation.
3.9.2 The release rate of radioactive liquid effluents, excluding tritium and dissolved noble gases, shall not exceed 10 curies during any calendar quarter without specific approval of the Comission.
Similarly, the quarterly average concentration of tritium released from the Restricted Area shall not exceed 1 x 1o-5 UCi/ml.
Amendments Nos. 70, 70 & 67 3.9-1
3.9.3 The rate of release of radioactive materialsin iod waste the station shall be controlled such that the instantanebous concentrations5 of radioactivity in liquid waste upon release from the Restricted Area, does not exceed the values listed in.
0CTR20, Appendix B, Table II, Column 2.
3.9.4 The equipment installed in the liquid radioactive waste system shall be maintained and operated to process liquids as necessary priort their discharge in order to limit the activity, excluding tritium and dissolved noble gases, released during any calendar quarter to 1.25 curies or less per unit.
3.9.5 As far as practicabler the releases of liquid waste shall be co ordinated with the operation of the Keowee hydro unit.
3.9.6 Liquid waste discharged from the liquid waste disposal system shall be continuously monitored during release.
The liquid effluent control monitor reading shall be compared with the expected reading of each discharge batch.
The monitor shall be tested daily or prior to releases and calibrated at refueling intervals.
The calibration procedure shall consist of exposing the detector to a referenced calibration source in a controlled, reproducible geometry.
The sources and geometry shall be referenced to the original monitor calibration which provides the applicable cali bration curves.
3.9.7 The effluent control monitor shall be set to alarm and automatically close the waste discharge valve such that the limits specified in 10CFR20 are met.
In the event that the effluent control monitor is inoperable or cannot be calibrated to perform this function, redundant valve line up check of the effluent pathway and redundant sample analyseshwill be performed prior to each liquid effluent release to assure that prescribed release limits are not exceeded.
3.9.8 In addition to the continuous monitoring requiraements, liquid radio active waste sampling and activity analysis shall be performed in accordance with Table 4.1.3. Records shall be maintained and reports of the sampling ad analysis shall be submitted in accordance with Section 6.6 of these Technical Specifications.
Bases It is expected that the releases of radioactive materials and liquid wastes will be kept within the design objective levels and will not exceed the concentration limits specified in
- OCtR2o.
These levels provide the reasonable assurance that the resulting annual exposure to the whole body or any in dividual body organ will not exceed 5 milirem per year.
At the same time, the licensee isi 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 Amendments Nos. 70, 70 & 67 3.9-2
ateporariYresult in releases higher than design Objective levels but still within the concentration limits spcfe n1C 1
opt i
g epcndithats when using this operational flexibility under unusual pea i
ctions the li es, shall exert every effort to keep the levels of radiatv terialS nd iudwse slw reasonably achievable and that annual releases will not exceed a =all fraction of the annua limits specified in releases from the three Oconee units have been developed The anticipated aun l releases on of variables including fuel failures, primary sysn nt cut a prim nt ci~
lekgadte performance of the sariste tratetosytem.
The actual magnitude of these parameters is as follows:
- a.
maximum expected reactor cooan corso rdc ocnrtions.2 b
- Reac o olant fission Product concentration correspondin o02 percent fuel cladding defects-.
c.* Steam generator p~iary-tosecoudary leakage rate of 20 gPd S25,160nganspe ared by the waste disposal system in a 30
- d. 255.160 gallons Per Yerprcs day hold-up.
rocessed by the reactor-coolant bleed treat e
1,060,800 gallons per year pro e blr sent system.-
n faCt4rof 104 for all radionuclides except triting for A decontaminationaste evaporators and a decontamination factor of the coolant bleed and waste evpr otritium which had an assumed 10 for the demineralizers except for trt mwwich hadzan sue decontaination factor of 1 for evaporationadeiyneradeaontamination factor
- g.
!oreoval by demineralizatiou for Cs. Mo, and Y eotilfainfco o 10 ws ed for the evaporation of iodine.
s3 as
- h.
The decay time of ra coo biodnystem was 30 days.
The application of the above estimates results inthe radionuclide discharge concentrations and rates shown in Table 111-12 of het il evirone Rn3e Statement Related to Operation Of Oconee Nuclear Stto ntse 1, e
2,iade3.
These concentrations are based on an annual average flow inth eoeRir of 1,100 cfs.
operatig pcel identify all equipment installed in the liquid waste Operating Procedures will idnt1 a
slequimetailed procedur" for handling and treatment systems and will pcf ealdpoe.r o
operating and maintaisiy this equipment.
The aspe lo as rasonablyahievable liquid release objectives expressed in this specification are based onl the 14RCgudlnsfApi1,17, derived from Appendix I of 10 CFR 50.
3.9-3 Amendments Nos. 70, 70 & 67