ML16138A587
| ML16138A587 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/30/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A588 | List: |
| References | |
| NUDOCS 8705060226 | |
| Download: ML16138A587 (11) | |
Text
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. 158 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 12, 1986, as revised October 10 and additional information sent'on October 20, 1986, 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 apolication, 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 amended by 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:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 158, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
9705060226 670430 PDR ADOCK 05000269 P
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate 11-3 Division of Reactor Projects -
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Attachment:
Technical Specification Changes Date of Issuance: April 30, 1987 PDI -3DRP-I/II PD
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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.158 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 1 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated February 12, 1986, as revised October 10 and additional information sent on October 20, 1986, 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 amended by 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:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 158, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: April 30, 1987 PDII73 RP-I/II PD
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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. 155 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 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated February 12, 1986, as revised October 10 and additional information sent on October 20, 1986, 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 () 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 amended by 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.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 155, 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 its date of.issuance.
FOR THE NUCLEAR REGULATORY COMMISSION B.J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance:
April 30, 1987 PDIIJ3RP-I/II PD
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 158 TO DPR-38 AMENDMENT NO. 158 TO DPR-47 AMENDMENT NO. 155 TO DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached Dages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page Page 3.16-1 3.16-1 3.16-2 4.4-17 4.4-17 4.4-18 4.4-18 4.4-19
3.16 CONTAINMENT HYDROGEN CONTROL SYSTEMS Applicability Applies to the Containment Hydrogen Recombiner System (including portable hydrogen recombiner unit and the Hydrogen Recombiner System flow path) and the Reactor Building Hydrogen Purge System whenever any Oconee unit is above cold shutdown conditions.
Objective To define the conditions necessary to assure the availability of adequate containment hydrogen control capability.
Specifications 3.16.1 The Containment Hydrogen Control Systems shall be operable as follows:
- a.
A portable hydrogen recombiner unit shall be operable and available for connection to the affected unit.
- b.
If no portable hydrogen recombiner unit is operable and available for connection to the affected unit, a portable hydrogen recombiner unit shall be restored to an operable status within 7 days.
- c.
If the conditions in 3.16.1.b caninot be satisfied, the Reactor Building Hydrogen Purge System 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 operating status within 30 days or submit a report to the NRC within the next 30 days describing the circumstances resulting in inoperable equipment and plans for returning the equipment to service and for any interim surveillance testing of the purge system.
- e.
With a portable hydrogen recombiner unit operable, the 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown in an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 shutdown within an add itional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
OCONEE -
UNITS 1, 2 & 3 3.16-1 Amendment No. 158 (Unit 1)
Amendment No. 158 (Unit 2)
Amendment No. 155 (Unit 3)
- Bases, 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 its lower flammability limit of 4.1 percent by volume. The Containment Hydrogen Recombiner System includes a portable hydrogen recombiner which 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 station and a portion of the Penetration Room Ventilation System. The purge system is operated as necessary (if the Containment Hydrogen Recombiner System is inoperable) to maintain the hydrogen concentration below the control limit.
The Containment Hydrogen Recombiner System is the preferable method of post-accident hydrogen control since it produces no radioactive gaseous release to the atmosphere. Therefore, the Containment Hydrogen Recombiner System will be utilized as the primary method to control the containment hydrogen concentration below 4.1 percent by volume.
Reference FSAR, Section 15.16 OCONEE -
UNITS 1, 2 & 3 3.16-2 Amendment No. 158 (Unit 1)
Amendment No..158 (Unit 2)
Amendment No. 155 TUnit 3)
4.4.3 CONTAINMENT HYDROGEN CONTROL SYSTEMS Applicability Applies to the Containment Hydrogen Control Systems.
Objective To verify that the Containment Hydrogen Control Systems are operable.
Specifications 4.4.3.1 Containment Hydrogen Recombiner System In-place Testing During each refueling outage, an in-place system test shall be performed on a recombiner unit. This test shall consist of:
- a.
Visual inspection of the system.
- b.
Connection of the hydrogen recombiner unit to the Reactor Building.
- c.
Hydrogen recombiner unit operation in the.post-LOCA configuration with flow greater than 50 SCFM. Operation at recombination temperature is not required by this test.
4.4.3.2 Containment Hydrogen Recombiner System Operational Performance Testing
- a.
The testing requirement of this section may be performed without connecting the system to one of the Reactor Buildings.
- b.
The isolation flanges on the Containment Hydrogen Recombiner System permanent piping shall be leak tested on each unit at refueling to ensure adequate isolation.
- c.
At a refueling outage frequency:
- 1.
Calibrate all recombiner instrumentation and control circuits.
- 2.
Operate a recombiner unit at design flow rate +/-10% and allow unit to reach recombination temperature.
4.4.3.3 Reactor Building Hydrogen Purge System Testing
- a.
Prior to declaring this system operable, a system test shall be performed.
- b.
This test shall consist of:
- 1.
Visual inspection of the system.
OCONEE -
UNITS 1, 2 & 3 4.4-17 Amendment No. 158 (Unit 1)
Amendment No. 158 (Unit 2)
Amendment No. 155 (Unit 3)
- 2.
Installation of new carbon and HEPA filters and in-place filter leakage test per ANSI-N510-1975 (minimum DOP efficiency 99%, minimum halogenated hydrocarbon removal 99%).
- 3.
Connection of the system to a Reactor Building.
- 4.
Flow measurement using flow instruments in the portable purging station.
- 5.
Verification that the pressure drop across the combined HEPA filters and charcoal absorber banks is less than six inches of water at the system design flow rate (+/-10%).
- 6.
Verification of the operability of the heater at rated power when tested in accordance with ANSI N510-1975.
Bases The control panel mounted near the recombiner enables the operator to control and monitor system parameters for all functions of the recombiner system except containment isolation valve operation. The control and monitor func tions include: process temperature indications, temperature control, flow indication, start/stop switch, low temperature timer and various annunciators.
Therefore, the operational performance testing ensures operability.
The penetrations to and from the hydrogen recombiner are shared with the gaseous radiation monitoring pump. Since this pump is normally in operation and since there is no system isolation valve on the supply branch to the recombiner, the blind flanges are the only means of system isolation.
Therefore, these flange joints should be leak tested periodically to ensure adequate isolation.
The hydrogen recombiner unit performance test should be conducted with full flow and with the heaters energized. The capability of the recombiner to achieve the required recombination temperature and flow rate is considered an adequate test of recombination efficiency. Gas inlet and outlet sampling is not required.
The pre-operational testing requirements for the Reactor Building Hydrogen Purge System are applicable only when the system is required'to be operable as required by Technical Specification 3.16.1.c. Requirements for interim surveillance testing of the Reactor Building Hydrogen Purge System during any period of its required operability will be reported to the NRC as described in Technical Specification 3.16.1.d.
New carbon and HEPA filters are installed during pre-operational testing.
HEPA filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The.charcoal adsorbers are installed to reduce the potential release of radioiodine.
Bypass leakage for the charcoal adsorbers and particulate removal efficiency for HEPA filters are determined by halogenated hydrocarbon and DOP, respectively.
OCONEE -
UNITS 1, 2 & 3 4.4-18 Amendment No. 158 (Unit 1)
Amendment No. 158 (Unit 2)
Amendment No. 155 (Unit 3)