ML19322B380
| ML19322B380 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/26/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B374 | List: |
| References | |
| NUDOCS 7912020228 | |
| Download: ML19322B380 (2) | |
Text
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UNITa3 STATES NUCLt i REGULATORY COMMIS$10N f
nasHINGToN. O..C. 20558 d
DUKE POWER COFLDANY DOCKET NO. 50-270 OCONEE NUCLEAR. STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. DPR-47 The Nuclear Regulatory Commission (the Comission) has found that:
1.
The application for amendment by Duke Powe.r Comphy (the li,censee)
A.
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 I; 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.
Accordingly, the license is amended by a change to the Technical i
2.
Specifications as indicated in the attac:. ment to this license amendment.
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2-3.
This license amendment is effective as of the date of'its issua POR THE NUCLEAR REGUIATORY COSNISSION Robert A. Purples Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the
,,,, Technical Specifications.
Date of Issuance: March 26, 1976 e
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ATTAC14!ENT TO LICENSE MENDMENTS_
TO FACILITY LICENSE Nor DPR-38
- ENDMENT NO.21 4
TO FACILITY LICENSE NO. DPR-47_
- ENDMENT NO.21 TO FACILITY LICENSE NO. DPR-SS_
AMENDMENT NO.18 50-269, 50-270, AND 50-287_-
DOCKET NOS.
l Revise' Appendix A as follows:
Remove page 4.2-3 and insert relised page 4.2-3.
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4.2.10 Fa Unit 1 Cyclef ptrati n, tho survsillenco (
suiss will ba removcd frea tha reactor vcssil and tha provisiens of Sptcificatica 4.2.9 will b3 rcvisod prist ts Cyclo 4 cp ratitn.
4.2.11 During the first two refueling periods, two reactor coolant systen piping elbows shall be ultrasor.ically inspected along their longitudinal velds (4 inches beyond each side) for clad bonding' and for cracks in both the clad and base r:etal. The elbows to be, inspected are identiff'ed in B&W Report 1364 dated December 1970.
A Beses i
The surveillance program has been developed to co= ply with Section XI nf the ASME Eoiler and Pressure Vessel Code. Inservice Inspection of Guelect Reactor Ccolant Systems, 1970, including 1970 vinter addenda, edi:Icn.
The program places =ajor emphasis on the stea of highest stress concentrations end on areas where fast neutron irradiation.c.ight be sufficient to change material properties.
The reactor vessel speci en surveillance pro 3 ram for Unit I and Uni-t 2 is
~ bared on equivslent exposure ti=es of 1.3. 19.6, 30.9 and 30.5 years.
The contents 'cf the dif ferer.t type or cap:nics are defir.cd
.J:v.
A Type, B'Tyse c
Weld Material BAZ Haterial HAZ Material Baseline :!sterfsl Baseline P.aterisi For IJnit 3, the Reactor Vessel Surveillance Program is based on a:;uivslent exposure tir.cs of J.S. 13.3, 26.7, sad 30.0 years.
The speci=cas have becn selected and fabricated as specified in ASD:-E:ISS-72.
Early inspection of Reactor Coolant System piping elbows is considered desirable in order to reccafir the integrity of the carbon steel base cetal when explosively clad with sensitited srcialess steel.
If r.o degradation is ebserved during the two annual. inspections, surveillcnce requirements vill revert to Section XI of the ASME Boiler and Pressure Vassel Code.
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Amendment Nos. 21, 21, 13 si2si7s i
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