ML15113A141
| ML15113A141 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain, Oconee  |
| Issue date: | 02/06/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A142 | List: |
| References | |
| DPR-38-A-134, DPR-47-A-134, DPR-55-A-131 NUDOCS 8502140355 | |
| Download: ML15113A141 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 00 E
WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 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 November 9, 1984, 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.
- 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8502140355 650206 PDR ADOCK 05000269 P
2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hn F. Stolz, Chief p ating Reactors Bra h #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 6, 1985
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REGoU o0 UNITED STATES 0
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. 134 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 November 9, 1984, 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.
- 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-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.134 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 REGULATORY COMMISSION Jo F. Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 6, 1985
9, UNITED STATES 04 NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 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 November 9, 1984, 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.
- 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.131 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 REGULATORY COMMISSION Joh F. Stolz, Chief Op rating Reactors Branch #4 D ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 6, 1985
0 S
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.134 TO DPR-38 AMENDMENT NO. 1 34 TO DPR-47 AMENDMENT NO. 1 31 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment numbers and contains vertical lines indicating the area of change.
Remove Page Insert Page 4.18-2 4.18-2
by starting with the piston at the as found setting and extending the piston rod in the tension mode direction. All snubbers con nected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers. Snubber operability will be veri fied in accordance with the following schedule:*
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period 0
18 months +/- 25%
1 12 months +/- 25%
2 6 months +/- 25%
3,4 4 months +/- 25%
5,6,7 2 months +/- 25%
>8 1 month +/- 25%
Note: (1) The required inspection interval shall not be lenkgthened more than two steps per inspection.
(2) Snubbers may be categorized in two groups, "accessible" or "inaccessible," based on their accessiblity during reactor operation. These two groups may be inspected independently according to the aboye schedule.
(3) Hydraulic and mechanical snubber inspection schedules are independent.
4.18.2 The seal service life of hydraulic snubbers shall be monitored to ensure that the seals do not exceed their expected service life by more than 10% between surveillance inspections. The maximum expected service life for the various seals, seal materials, and applications shall be estimated based on engineering information, and the seals shall be replaced so that the maximum expected service life is not exceeded by more than 10% during a period when the snubber is re quired to be OPERABLE. The seal replacements shall be documented and the documentation shall be retained in accordance with Specifi cation 6.5.1.m.
4.18.3 At least once per refueling outage, a representative sample, a minimum of 10% of the total of hydraulic snubbers in use in the plant, shall be functionally tested either in place or in a bench test. For each hydraulic snubber that does not meet the functional test acceptance criteria of Specification 4.18.4, an additional minimum of 10% of the hydraulic snubbers shall be functionally tested until none are found inoperative or all have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of hydraulic snubbers. The representative sample shall be selected randomly from the total population of safety-related hydraulic snubbers.
- A one-time extension is granted for the Unit 2 inaccessible hydraulic snubbers inspection such that it be performed during the 1985 Unit 2 refueling outage, provided that such outage begins no later than March 15, 1985.
Amendment Nos. 134, 134, & 131 4.182