ML19322B384
| ML19322B384 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/26/1976 |
| From: | Purple S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B374 | List: |
| References | |
| NUDOCS 7912020232 | |
| Download: ML19322B384 (2) | |
Text
.
UNITEo STATSS NUCL..A REGULATORY COMMISSION l
1N ASHINGTON. O. c. 2055s I
t d
DUKE POWER COMPANY _
i DOCKET NO. 50-287_
OCONEE NUCLEAR STATION, UNIT 3f AMENDMENT TO FACILITY OPERATING LICENSE _
Amendment No. 18 License No. DPR-55 The Nuclear Regulatory Commission (the Commission) has found
)
1.
The application for amendment by Duke Power Comp A.
dated March 16, 1976, d the of the Atomic Energy Act of 1954, as amended I;
The fac,ility will operate in conformity with the application, i
of the provisions of the Act, and the rules and regulat ons B.
the Coxnission; There is reasonable assurance (i? that the C,
ill be and safety of the public, and (ii) that such activi The issuance of this amendment will not be in D.
An environmental statement or negative declaration need not b prepared in connection with the issuance of this amendment.
E.
Accordingly, the license is amended by a ch d
2.
1 i
L 7812020 M N
2-This license amendment is effective as of the date of its issuance.
3.
FOR TE NUCI. EAR REGULATORY COMISSION Robert A. Purple, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications March 26, 1976 Date of Issuance:
a O
e i
l e
9 0
~.
[
O t
ATTACH >ENT TO LICENSE AMENDMENTS TO FACILITY LICENSE Nor DPR-38_
AFENDMENT NO.21 TO FACILITY LICENSE NO. DPR-47 AMENDMENT NO.21 TO FACILITY LICENSE NO. DPR-55 AMENDMENT NO.18 50-269, 50-270, AND 50-287_
DOCKET NOS.
Revise Appendix A as follows:
Remove page 4.2-3 and insert revised page 4.2-3.
~
~
^
I o
h" '
~
T- -
h h IPM 3,..c
....... _ m i.~....
'4.2.10 i
F:r Unit 1 Cycli 3 operction, the survaillcnca epsulas will be removed fr:m tha reacter vassal an'd tha previsions of Specification 4.2.9 will b9 r;visad prier to Cycle 4 operation.
4.2.11 During the first two refueling periods, two reactor coolant system piping elbows shall be ultrasonically inspected along their longitudinal velds (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 S&W Emport 1364 dated December 1970.
Bases
.a The surveillance program has been developed to co= ply with Section XI of
~
the ASME Eoiler and Pressurc Vessel Code, Inservice Inspection of Nuclect Reactor Coolant Systems, 1970, including 1970 vinter addenda, edition.
The progras places =ajer cephasis on the area of highest stress concentrations and on areas there fast neutron irradiation tight be sufficient to chnnge material properties.
The reactor vessel speci=en surveillance program for. Unit 1 and Unit 2 is bared on equivalent exposure ti=cs of 1.3, 19.6, 30.6 and 30.5 years.
The contunts of the differcr.c type of capruics are defir.es c/.:v.
A Type, B'Tyse Weld >bterial MAZ Haterial RAZ Material Esscline "sterial Baselipe Material For Unit,3, the P.gactor Vessel Surveillance Prspram is based on equivalent exposure tir.cs of J.S.
13.3, 26.7, and 30.0 years.
The specimens have been selected and fabricated as specified in ASTM-ELIS3-72.
Early inspection of Reactor Coolant System piping elbevs is considered desirable in order to reconfir: the integrity of the car ~ron steel base cctal when explosively clad with sensiti:cd stc' ialess steel.
If t.o degradation is ebserved during the two annual inspecticus, surveillcnce requirements will revert to Section XI of the ASME Boiler, and Pressure Vessel Code.
l
\\
O 4.2-3 Amena. ment Nos. 21, 21, 18 g
3/26/76 m m 1
e-F
,e
...;. w --..pg., -----or.
L