ML20247A620
| ML20247A620 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/31/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247A626 | List: |
| References | |
| NUDOCS 8909120162 | |
| Download: ML20247A620 (4) | |
Text
. _ _ _ _ _ _ _ _ _
Mf
'q, UNITED STATES 8
,o NUCLEAR REGULATORY COMMISSION c
- p 9 l-WASHINGTON, D. C. 20555 A*'
' %, *,, 5,$
I f
ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by Arkansas Power and Light Company (the licensee) dated June 13, 1989, 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; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and tne rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amer.dment 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 Comission's regulations and all applicable requirements have been satisfied.
s90912016g 'g'gjyhis PDR ADCC ppc P
2.
Accordingly, the license is amended by chances 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.125, 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
< 4 r-Frederick J. Hebdon, Director Project Directorate IV Division of Reactor Projects - III, 1
IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 31, 1989 l
.. ji.
i..
1 ATTACHMENT TO LICENSE AMENDMENT NO.125 o.
FACILITY OPERATING LICENSE NO.'DPR-51 DOCKET NO. 50-313.
a Revise'the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
. REMOVE PAGE INSERT PAGE-40' 40 k
I am.__m._.-_.__..-_-._m.-____m_..__
3.4 STEAM AND POWER CONVERSION SYSTEM App icability Applies to the turbine cycle components for removal of reactor w ay heat.
Objective To specify minimum conditions of the turbine cycle equipment necessary to assure the capability to remove decay heat from the reactor core.
, Specifications 3.4.1 The reactor shall not be heated above 280 F unless the following conditions are ret:
1.
Capability to remove decay heat by use of two steam generators.
- 2.
Fourteen of the steam system safety valves are operable.
3.
A minimum of 11.1 feet (107,000 gallons) of water is available in Tank T41B.
- 4.
Both EFW pumps and their flow paths are operable.
5.
Both main steam block valves and both main feedwater isolation valves are ' operable.
3.4.2 Initiate functions of the EFIC system which are bypassed at cold shutdown conditions shall have the following minimum operability conditions:
a.
" low steam generator pressure" initiate shall be operable when the main steam pressure exceeds 750 psig.
b.
" loss of 4 RC pumps" initiate shall be operable when neutron flux exceeds 10% power.
c.
" main feedwater pumps tripped" initiate shall be operable when neutron flux exceeds 10% power.
- Except that during hydrotests, with the reactor subcritical, fourteen of the steam system safety valves may be gagged and two (one on each header),
may 3e reset for the duration of the test, to allow the required pressure for the test to be attained.
- Except that a test with available steam pressure of the steam driven EFW pump shall demonstrate its functionality until completion of surveillance testing at hot shutdown conditions as required by Surveillance Requirement 4.8.1.
I Amendment No. 50, 90, SI, 101, 125 40
!