ML20079E387
| ML20079E387 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/26/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079E389 | List: |
| References | |
| NUDOCS 9110070147 | |
| Download: ML20079E387 (5) | |
Text
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'g UNITED STATES 3c,
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'. e NUCLEAR REGULATORY COMMISSION t
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ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.iS2 License No. DPR-51
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
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l A.-
The application for-amendment by Entergy Operations, Inc. (the licensee) dated February 20, 1991, as_ supplemented by letter-dated-August 6, 1991, complies with the standards and requirements of the Atomic Energy A4.t of 1954, as amended (the Act), and the Commission's rules and regulations.et forth in 10 CFR Chapter I; B.
The facility will' operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
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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; j
D.
The issuance of this license amendinent will not be inimical to the common defense and security or to_the health and safety of the public; 1
and t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51
.of the Commission's regulations and all applicable requirements have teen satisfied.
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F 9110070147 910926 i
-POR ADOCK 05000313 PDR P
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' 2.
Accordingly, the license is aniended 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.
lechnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.152, are hereby incorporated in the license.
The licensee shall operate the facility in accoroance with the Technical Specifications.
3.
The license amendment is effective 30 days from its date of issJance.
FOR THE NUCLEAR REGULATORY COMMISSION
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^y Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 26, 1991
ATTACHMENT TO LICENSE AMENDMENT NO.152 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment numbet and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 72 72 73a 73a
Table 4.1-1 (Cont.1 g
m E
Channel Descriotion Check lett Calibrate Remarks o"
5
- 30. Decay Heat Removal S(1)(2)
M(1)
R (1)
Includes RCS Pressure Analog Channel System I solation Valve (3)
(2)
Includes CFT Isolation Valve Position z
P Automatic Closure and (3) At least once every refueling shutdown, with Reactor Coolant System Pressure a
Interlock System greater than or equal to 200 psig, but 4
less than 300 psig, verify automatic E
isolation of the decay heat removal system from the Reactor Coolant System on high m
Reactor Coolant System pressure.
'm
- 31. Turbine Overspeed Trip NA R
HA Mechanism u",
N
- 32. Diesel Generatoc M
Q NA Protective Relaying Starting Interlocks y
and Circuitry
- 33. Of f-site Power Undervo' age W
R(1)
R(1)
(1) Shall be tested during refueling shutdown to demonstrate selective ar-d Protective Relaying Interlocks and. Circuitry load shedding interlocks function during manual or automatic trans-fer of Unit 1 auxiliary load to Startup Transformer No. 2.
- 34. Borated Water Storage W
NA R
Tank Level Indicator
- 35. Reactor Trip Upon Loss M
PC R
of Main Feedwater Circuitry I
j l
l 1
Table 4.1-2 (Cont.)
Minimum Equioment Test Frecuency lism Ital frecuency
- 11. Decay Heat Removal Functioning Each Refueling System Isolation Shutdown Valve Automatic Closure and Isolation System 12.
Flow Limiting Ann-Verify, at normal One year, two years, ulus on Main operating conditions, three years, and Feeovater Line at that a gap of at least every five years Reactor Building 0.025 inches exists thereafter measured Penetration between the pipe and from date of initial the annulus, test.
- 13. Main Steam Isola-
- a. Exercise through a Quarterly tion Valves approximately 10%
travel
- b. Cycle
- b. Every 18 months
- 14. Main Feedwater
- a. Exercise through
- a. Quarterly Isolation Valves approximately 5%
travel
- b. Cycle
- b. Every 18 months
- 15. Reactor Internals Demonstrate operability Each refueling shutdown.
Vent Valves by:
- a. Conducting a remote visual inspection of visually accessible surfaces of the valve body and disc sealing faces and evaluating any observed surface irregularitie,.
- b. Verifying that the valve is not stuck in an open position, and
- c. Verifying through manual actuation that the valve is fully open with a force of s 400 lbs (applied vertically upward).
Amendment No. A, 2J, 2E, Order-dated-4/20/81, 91,152 73a
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