ML19322B312
| ML19322B312 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/25/1976 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B297 | List: |
| References | |
| NUDOCS 7912020161 | |
| Download: ML19322B312 (4) | |
Text
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UNITED STATES
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NUCLEAR RECULATORY COMMISSION 4
E WASHING TON, D. C. 20555 e *-
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n 1g '.... yd DUKE POWER COMPANY DOCKET'No. 50-287 OCONEE NUCLEAR' STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. DPR-55 w
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated May 7, 1976, complies with the standards
.and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comsission'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 activitie. 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 applic.able requirements I
have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to'this license 2.
i amendment.
i This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY C01D11SSION
".nedu+"t.L A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical c
Specifications Date of Issuance:
June 25, 1976 f
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ATTACHMENT TO LICENSE AMENPMENTS 26 TO DPR-38 AMENDMENT NO.
AMENDMENT NO. 26 TO DPR-47 AMENDMENT NO. 23 TO DPR-55_
50-269, 50-270 AND 50-287 DOCVITS NOS.
n Revise Appendix A as follows:
Remove page 4.2-3 and insert 4.2-3 revised page.
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ForUnit5, Cycle 3 operation,thecurveillancecepuleswill 4.2410 be removed from the reactor vessel and the provisions of Specification 4.2.9 will be revised prior to Cycle 4 operation.
For Unit 2, Cycle 2 operation, the surveillance capsules will be removed from the reactor vessel and the provisions of Specifica-tion 4.2.9 will be revised prior to Cycle 3 operation. For Unit 3, Cycle 1 operation, the surveillance capsules will be removed from the reactor vessel for a portion of the cycle and the pro-visions of Specification 4.2.9 will be revised prior to Cycle 2 operation.
4.2.11 During the first two refueling periods, two reactor coolant system piping cibows shall be ultrasonically inspected along their longitudinal wc]ds (4 inches beyond each side) for clad bonding and for cracks in both the clad and base metal. The elbows to be inspected are identified in B&W Report 1364 dated December 1970.
Bases The surveillance program has been developed to comply with Section XI of the ASME Boiler and Pressure Vessel Code. Inservice Inapection of Nuclear Reactor w.
Coolant Systems, 1970, including 1970 winter addenda, edition.
The program places emjor emphasis on the area of highest stress concentrations and on areas where fast neutron irradi_ tion might be sufficient properties.
to change material The reactor vessel specimen surveillance program for Unic 1 and Unit 2 is based on equivalent exposure times of 1.8, 19.8, 30.6 and 39.6 years.
The contents of the dif ferenc type of capsules are defined below.
A Type B Type Weld haterial HAZ Material HAZ Material Baseline Material Baseline Material l
For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent 1
cxposure times of 1.8, 13.3, 26.7, and 30.0 years.
The specimens have been celected and fabricated as specified in ASTM-E-185-72.
Early inspection of Reactor coolant System piping elbows is considered desirable in order to reconfirm the integrity of the carbon steel base metal when explosively clad with sensitized stainless steel.
If no de, gradation is cbserved during the two annual inspections, surveillance requirements will revert to Section XI of the ASME Boiler and Pressure Vessel Code.
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BMMWa-4.2-3 Amendments No, 26, 26 6 23 m