ML20056E088
| ML20056E088 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/02/1993 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E089 | List: |
| References | |
| NUDOCS 9308190319 | |
| Download: ML20056E088 (4) | |
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NUCLEAR REGULATORY COMMISSION e
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y WASHINGTON, D. C. 20555
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t ENTERGY OPERATIONS INC.
j DOCKET NO. 50-313 f
ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. DPR-51:
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1.
The Nuclear Regulatory Comission (the Umission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the-licer.see), dated March 19, 1993, 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; l
B.
The facility will operate in conformity with the application, the i
prov'.sions of the Act, and the rules and regulations of the -
Comission; j
C.
There is reasonable assurance:
(i) that the activities authorized
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by this amendment can be conducted without endangering the health-and safety of the public, and (ii) that such activities will be 3
conducted in compliance with the Commission's regulations; i
2 D.
The issuance of this l atase amendment will not be inimical ta the-j common defense and secu) 'y or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable r"quirements have l
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 amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 167, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
& Harry Rood, Actin r
Project Directorate IV-1 Division of Reactor Projects - III/IV/V.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 2, 1993 i
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Y ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace 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.
REMOVE PAGE INSERT PAGE 78 78
- 3 4.3 TESTING FOLLOWING OPENING OF SYSTEM Anolicability Applies to test requirements for Reactor Coolant System integrity.
Obiective To assure Reactor Coolant System integrity prio: to return to criticality following normal opening, modification, or repair.
Soecification 4.3.1 When Reactor Coolant System repairs or modifications have been made, those repairs or modifications shall be inspected and tested to meet all applicable code requirements prior to the reactor being made critical.
4.3.2 Following any opening of the Reactor Coolant System, it shall be-leak tested at not less than 2155 psig, prior to the reactor being made critical, in accordance with the ASME Boiler and Pressure Vessel Code,Section XI; IWA-5000.
4.3.3 The limitations of Specification 3.1.2 shall apply.
Bases Repairs or modifications made to the Reactor Coolant System are inspectable and testable under applicable codes, such as B 31.7, and ASME Boiler and Pressure Vessel Code,Section XI.
For normal opening, the integrity of the Reactor Coolant System in terms of strength, is unchanged. The ASME Boiler and Pressure Vessel Code,Section XI; IWA-5000 requires a system leak test at nominal operating pressure (2155 psig) following system opening. At the end of refueling outages, this test also satisfies the requirements of IWB-2500, Table IWB-2500-1; Category B-P items B15-10, B15-20, B15-30, B15-40, B15-50, B15-60, and B15-70 for all Class I pressure retaining components.
RFFERENCES
( ) FSAR, Section 4
(
ASME Boiler and P. essure Vessel Code,Section XI i
78 Amendment No.167