ML16138A625
| ML16138A625 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/15/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A626 | List: |
| References | |
| NUDOCS 8806210321 | |
| Download: ML16138A625 (8) | |
Text
0REG 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. 167 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 January 21, 1986, as revised March 3, 1987, 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 1; 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 attachments to this license amendment, and Paragraph 3.8. of Facility Operating License No. DPR-38 is hereby amended to read as follows:
8806210321 880615 PDR ADOCK 05000269 P _
FPDR
-2 3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 167, 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 Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -I/II
Attachment:
Technical Specification Changes Date of Issuance:
June 15, 1988
- SEE PREVIOUS PAGE FOR CONCURRENCE OFFICIAL RECORD COPY PDII-3/DRP-I/II*
PDII-3/DRP-I/II*
OGC-WF*
PD I P-I/II MRood HPastis:
DM hews 4/21/88 4/26/88 4/27/88
/1q/88
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. 167 License No. DPR-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 January 21, 1986, as revised March 3, 1988, 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 1; 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 attachments to this license amendment, and Paragraph 3.B. of Facility Operating License No. DPR-47 is hereby amended to read as follows:
-2 3.B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment Mo. 167, 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 Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/I
Attachment:
Technical Specification Changes Date of Issuance: June 15, 1988
- SEE PREVIOUS PAGE FOR CONCURRENCE OFFICIAL RECORD COPY PDII-3/DRP-I/II*
PDII-3/DRP-I/II*
OGC-WF*
P DRP-I/II MRood HPastis:
0 thews 04/21/88 04/26/88 04/27/88
/11/88
P,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. 164 License No. OPR-55 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 January 21, 1986, as revised March 3, 1988, 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 set forth in 10 CFR Chapter 1; 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 attachments to this license amendment, and Paragraph 3.B. of Facility Operating License No. DPR-55 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.164, 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 Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/I
Attachment:
Technical Specification Changes Date of Issuance: June 15, 1988
- SEE PREVIOUS PAGE FOR CONCURRENCE OFFICIAL RECORD COPY PDII-3/DRP-I/II*
PDII-3/DRP-I/II*
OGC-WF*
P
-3 DRP-I/II MRood HPastis:
DMatthews 04/21/88 04/26/88 04/27/88
/,q/88
ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 164 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 a vertical line indicating the areas of change.
Remove Page Insert Page 3.9-3 3.9-3
where A = pond inventory limit for single radionuclide "j" (curies)
C = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j" (curies)
- b.
After a primary to secondary leak is detected, the initial batch of used Powdex resin shall not be transferred to the CTP.
No batch of used powdex resin shall be transferred to the CTP unless the sum of the ratios of the activity of the radionuclides identified in the preceeding batch from any powdex cell in the same unit is less than 0.1% of the limit identified in 3.9.4.a.
j-Aj
< 1.0 X 10 j Aj where Qj = radionuclide activity in the batch Aj = pond inventory limit for radionuclide "j"
- c.
The total radionuclide inventory of all batches of used powdex resin transferred to the Chemical Treatment Ponds over the previous 13 weeks, shall not exceed 0.4% of the pond radionuclide inventory limit.
If this limit is exceeded, a report shall be submitted within 30 days to the Regional NRC Office describing the reason or reasons for exceeding the limit and plans for future operation. Decay of radionuclides may be taken into account in determining inventory levels.
Qj1 Qj2 +Qj3 --------
j
.004 x Aj
- Where, Qj = Total inventory of radionuclide j in a batch n = Number of batches transferred to the Chemical Treatment Ponds during the previous 13 - week period.
3.9.5 Liquid Holdup Tanks
- a.
The quantity of radioactive material contained in each out side temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
- b.
The quantity of radioactive material contained in each of the outside temporary tanks shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive materials are being added to the tank.
3.9-3 Amendment No. 167 (Unit 1)
Amendment No. 167 (Unit 2)
Amendment No. 164 (Unit 3)