ML20092M416
| ML20092M416 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/22/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092M419 | List: |
| References | |
| NPF-06-A-165 NUDOCS 9510020182 | |
| Download: ML20092M416 (5) | |
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i UNITED STATES i
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066 0001 49.....,o
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2
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AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.165
~i License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 4,1995, as supplemented by letter dated 3
August 25, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the
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Commission's rules and regulations set forth in 10 CFR Chapter I; 2
B.
The facility will operate in conformity with the application, the j
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 license 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.
9510020182 950922 ADOCK050003j8 PDR P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.165, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/
George Kalma ior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
' Changes to the Technical Specifications Date of Issuance: September 22, 1995
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ATTACHMENT TO LICENSE AMENDMENT NO. 16s FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE INSERT PAGE 3/4 4-26 3/4 4-26 i
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L REACTOR COOLANT SYSTEN l
3/4.4.10 ETRUCTURAL INTEGRITY l
e AsMr CODE etARS 1. 2 AND 3 COMPONENTE LfMfTfMC CONDITION FOR OPKsATION i
3.4.10.1 The structural integrity of ASNE Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
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APPLICABILITY: ALL N00E8 t
l AEllE:
With the' structural integrity of any ASNE Code Class 1 a.
component (s) not conforming to the above requirements, restore l
the structural integrity of the affected component (s) to withia its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more then 50*F above the minimum temperature required by NDT considerations.
i b.
With the structural integrity of any A8NE Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200'F.
With the structural integrity of any A8NE Code Class 3 c.
component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.
EURVEfLLANCE REOUTREMENTE 4.4.10.1 In addition to the requirements of specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1. August 1975.
3 ARKAN8AS - UNIT 2 3/4 4-26 Amendment No. 134 MAY 5 1007
REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CIkSS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY: ALL MODES ACTION:
With the structural integrity of any ASME Code Class 1 a.
component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*r above the minimum temperature required by NDT considerations.
b.
With the structural integrity of any ASME Code class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.
With the structural integrity of any ASME Code Class 3 c.
component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the af fected component from service.
SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.*
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- For reactor coolant pump 2P32A, the ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway may be extended through the 2R12 refueling outage.
ARKANSAS - UNIT 2 3/4 4-26 Amendment No. -144,165
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