ML16138A806
| ML16138A806 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/07/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16138A807 | List: |
| References | |
| NUDOCS 9602120293 | |
| Download: ML16138A806 (9) | |
Text
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 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 February 6, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 I; 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 hereby amended by page 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:
9602120293 960207 PDR ADOCK 05000269 P
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 214, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
'Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/Il Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
February 7, 1996
,ptREG(,
UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 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 February 6, 1996, complies with the standards and requirements of. the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 I; 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 hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 214, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: February 7, 1996
r1 ftREGo,.0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DPR-55
- 1.
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 February 6, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 I; 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 hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.211, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/Il Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
February 7, 1996
0 0
ATTACHMENT TO LICENSE AMENDMENT NO. 214 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 214 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO.211 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 3.16-1 3.16-1 3.16-2 3.16-2
3.16.3 Components in the Containment Hydrogen Control Systems' flow path shall be operable on each Oconee unit with the following exceptions.
- a.
If the flow path is inoperable it shall be restored to operable status within 7 days.
- b.
If an inoperable flow path is not restored to operable status within 7 days, then the affected unit shall be at hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and at cold shutdow within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (1)
The Containment Hydrogen Control Systems are required at approximately 460 hours0.00532 days <br />0.128 hours <br />7.60582e-4 weeks <br />1.7503e-4 months <br /> (19.2 days) following a LOCA to limit hydrogen concentration to 4.1 percent by volume.
The Containment Hydrogen Recombiner System is utilized as the primary method to maintain the post-accident containment atmosphere hydrogen concentration below is lower flanimality limit of 4.1 percent by volume. The Containment Hydrogen Recombiner System includes a portable hydrogen recombinor wlih will be moved to the affected unit following a LOCA, anchored to its foundation, and connected to piping penetrations. Also included is a portable control panel.
which will be locally mounted near the recombiner, anchored to its foundation and connected to its motor control center and the recombiner.
The Reactor Building Hydrogen Purge System is composed of a portable purging staton and a portion of the Penetradan Room Ventilation System. The purge system is operated as necessary (if the Containment Hydrogen Recombinor Syinum is inoperable) to maintain the hydrogen concentration below the control limit.
The Comainment Hydrogen Recombiner System is the preferable method of post-accida hydrogen control since It produces no radioactive gaseous release to the atmosphere. Therefore, the Containment Hydrogen Reermbiner System will be utilied as the primary method to control the conainent hydrogen concentration below 4.1 percent by volume.
PSAR, Section 15.16 Oconee 1, 2 and 3 Amendment No. 214 (Unit 1) 3.16-2 Amendment No. 214 (Unit 2)
Amendment No. 211 (Unit 3) 1 A one-time allowable outage time of fourteen (14) days is granted for installation of a modification to provide drainage for moisture which may accumulate in the Containment Hydrogen Recombiner System piping,
g 3.16 CONTAINMENT HYDROGEN CONTROL SYSTEMS Annliablit Applies to the Containment Hydrogen Recombiner System (including portable hydrogen recombih unit and the Hydrogen Recombiner System flow path) and the Reactor Building Hydrogen Purge System whenever any Oconee unit is above cold shutdown conditions.
To dine the conditions necessary to assure the availability of adequate containment hydrogen control capability.
3.16.1 The Contalnment Hydrogen Control Systems shall be operable as follows:
- a. A portable hydrogen recombiner unit shall be operable and available for connecdon to the affected unit.
- b. If no portable hydrogen recombiner unit is operable and available for connectiob to the affected unit, a portable hydrogen recombiner ut sala be restored to an operable status within 7 days.
- c. If the conditions in 3.16.1.b can not be satisfied, the Reactor Buiding Hydrogen Purg Systen shall be verified operable within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- d. With the Reactor Building Hydrogen Purge System operable, restore a hydrogen recombiner unit to operati status within 30 days or submit a report to the NRC within the next 30 days describing the circumances reauftn in i
able equipment aid plans for returning tho equipment to service ad for any interim surveillance testing of the purge system.
- e. With a portable hydrogen recombiner unit operable, tbe Reactor Building Hydrogen Purge system is not required to be operable.
3.16.2 If the conditions under Technical Specification 3.16.1.c are not met, the Oconee Units shall be in hot shutdown within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. and in cold shtdown in an additionai Oconee 1, 2 and 3 3.16-1 Amendment No. 214 (Unit 1)
Amendment No. 214 (Unit 2)
Amendment No. 211 (Unit 3)