ML15112B002
| ML15112B002 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/30/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B003 | List: |
| References | |
| DPR-38-A-094, DPR-47-A-094, DPR-55-A-091 NUDOCS 8104090017 | |
| Download: ML15112B002 (9) | |
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. 94 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power'.Company (the licensee) dated July 15, 1980, 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 pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonableassurance (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 regulatiohs; 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 reoulations and all applicable requirements have been satis fied.
- 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.94, are hereby incorporated in the license. The licensee shall operate the facility in.accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J n Stolz, Chief pe ting Reactors Branch #4 sion of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 30, 1981
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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. 94 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 July 15, 1980, 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 pro visions 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Faility Operating License No. DPR-47 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. 94,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 REGUL TORY COMMISSION oh F. Stolz, Chief Op ating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 30, 1981
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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. 91 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 July 15, 1980, 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 pro visions 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 satis fied.
- 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. 91,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REG LATORY COMMISSION oh Stolz, Chief p ating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 30, 1981
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 94 TO DPR-38 AMENDMENT NO. 94 TO DPR-47 AMENDMENT NO. 91 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 4.17-3 4.17-3 4.17-4*
4.17-4*
- Overleaf page; no changes.
than 10 months nor more than one fuel cycle after the previous inspection.
The increase in inspection frequency shall apply until a subsequent inspec tion meets the conditions specified in 4.17.4.a and the interval can be extended to a maximum of 40 months.
- c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.17-1 during the'shutdown subsequent to any of the following conditions:
- 1. A seismic occurrence greater.than the Operating Basis Earthquake,
- 2. A loss-of-coolant accident requiring actuation of the engineered safe guards, or 3.. A main steam line or feedwater line break.
- d.
After primary to secondary leakage in excess of the limits of Specification 3.1.6, an inspection of the affected steam generator will be performed in accordance with the following criteria:
- 1. If the leaking tube is in a Group as defined in Section 4.17.3.b, all of the tubes in this Group in this steam generator will be inspected. If the results of this inspection fall into the C-3 category, additional inspections will be performed in the same Group in the other steam generator.
- 2. If the leaking tube.is not in a Group as defined in 4.17.4.d.1, then an inspection.will be performed on the affected steam generator in accordance with Table 4.17-1 with an initial inspection sample size of 6% of the tubes in the affected steam generator.
4.17.5 Definitions As used in this specification:
- a.
Imperfection means an exception to the dimensions, finish or contour of a tube.
from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- b.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either the inside or outside of a tube.
- c.
Degraded Tube means a tube containing imperfections >20% of the nominal wall thickness caused by degradation.
- d.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
- e.
Defect means an imperfection of such severity that it exceeds the plugging Timit. A tube containin'g a defect is defective.
- f.
Plugging Limit means the imperfection depth beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection; It is equal to 40% of the nominal tube wall thickness.
- g.
Unserviceable describes the condition of a tube if it leaks or contains Amendments Nos.
94, 94, & 91 4.17-3
a defect Large ugh to -affect its structural i grity in the vent of an operating Basis Earthquake, a loas-of-coolant accident, or a Btu= line or feedvater line break as specified in Specification 4.17.4.
- h.
Tube Inspection means an Inspection of the steam generator tube from thg point of entry completely to the point of exit.
4.17.6 Reports
- a.
The number of tubes plugged in each steam generator shall be reported to the Director, Office of Inspection and Enforcement, Region II, within 30 days following the completion of the plugging procedure.
- b.
The results of the steam generator tube inservice inspection shall be reported to the XRC within 3 months following completion of the inspec tion.
This report shall include:
- 1.
Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of a degraded tube.
- 3.
- dentification of tubes plugged.
C.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the NRC shall be reported pursuant to Specification 6.6.2.1.a prior to resumption of plant operation. The ritten followup of this report shall provide a description of inves tizazicns conducted to determine cause of the tube degradation and correc civ!e measures taken to prevent recurrence.
Eases The program of periodic inservice inspection of steam generators provides the means to monitor the integrity of the tubing and to maintain surveillance in the event there is evidence of mechanical damage or progressive deterioration.
due to design, manufacturing errors, or operating conditions. Inservice inspec tIon of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures may be taken.
Removal from service will be required for any tube with service-induced me:al loss in excess of 40% of the tube nominal vall thickness or with a through wall crack. Additional corrective actions may be required to ttabilize a circum
- erentially cracked t'ube.
The initial sample of tubes inspected in a stea= generator includes cubes from three groups.
First, lane tubes are inspected to assure their in:egrity.
- Second, all other inservice tubes with degradation, inspected in previous.inspections, are inspected to assure tube integri+/-v and determine degradation growth, if any.
hird, a random sample of 3% of the total number of tubes in both steam gen erators is insbected. The results of the lat:er inspection dictate the extent of further exaninations.
Amendments Nos. 80, 80 & 77 4.17-4