ML19322B375
| ML19322B375 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/26/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B374 | List: |
| References | |
| NUDOCS 7912020224 | |
| Download: ML19322B375 (4) | |
Text
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UNITE 3 STATES NUCLEAR REGULATORY COMMISSION W A9HINoToN. D. C. 20555 W
DUKE POWER COMPANY _
DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. DPR-38 The Nuclear Regulatory Commission (the Commission) has found that:
1.
A.
The application for amendment by Duke Power Company (the licensee) dated March 16, 1976, 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 1; The facility will operate in conformity with the application, B.
the provisions of the Act, and the rules and regulations of the Commission;
'Ihere is reasonable assurance (i) that the activities authorized C.
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; The issuance of this amendment will not be inimical to the common D.
defense and security or to the health and safety of the public; and An environmental statement or negative declaration need not be E.
prepared in connection with the issuance of this amendment.
i Accordingly,' the license is amended by a change to the Technical 1
2.
Specifications as indicated in the attachment to th_is license amendment.
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2-3.
This 18. cense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0lNISSION
__. - - g Q
Robert A. Purples Chi f Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1976 6
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ATTACHMENT TO LICENSE AMEND >ENTS AMENDMENT NO. 21 TO FACILITY LICENSE NO.* DPR-38 AMENDMENT NO. 21 TO FACILITY LICENSE NO. DPR-47 AMENDMENT NO.18 TO FACILITY LICENSE NO. DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-787 Revise Appendix A as follows:
Remove page 4.2-3 and insert revised page 4.2-3.
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For Unit 1 Cycle 3 operation, tha survaillcr.ca c i
4.2.10 4.2.9 will be, revised prior to Cycle 4 op6 ration.
During the first two refueling periods, two reactor coolant system piping elbows shall be ultrasonically inspect 4.2.11 ld The bonding and for cracks in both the clad and base metal.
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elbows to be inspected are identified in S&W Report dated December 1970.
Btses The surveillance program has been developed to comply with Section XI of f Nuclect the ASME Eoiler and Pressure Vessel Code, Inservice Inspection o Reactor Coolant Systems, 1970, inclucing 1970 winter addenda, edition.
tions The program places major emphasis' on t'he area of. h caterial properties.
1 and Unit 2 is The reactor vessel specimen surveillance program for Unit 1.3, 19.6, 30.6 and 39 The bared on equivalent exposure tices of contunts of the different type of capsulas are defir.ed ci.r.
B Type A Type RAZ }bterial Veld Fbterial Baseline "aterial.
RAZ Material Baselipe Material For Unit 3, the Reactor Vessel Survcillance Progrna is base.d on equivalen exposure cines of J.8,13.3, 26.7, and 30.0 years.
selected and fabricated as specified in ASTM-E-1SS-72.
Early Jnspection of Reactor Coolant' Systen piping el If no cetal when explosively clad with sensiti:cd stainless stec1.
degradation 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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4.2-3 Amendment Nos. 21, 21, 18 W
3/26/76,
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