ML20206T537
| ML20206T537 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/26/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20206T541 | List: |
| References | |
| DPR-51-A-101 NUDOCS 8610070018 | |
| Download: ML20206T537 (5) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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ARKANSAS POWER AND LIGHT COMPANY DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the-licensee) dated May 21, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set 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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
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of the Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, t
and paragraph 2.c.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
i 0610070018 860726 0500gl3 PDR ADOCK
. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
g John F. Stolz, Direc@ r PWR Project Directorate #6 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 26, 1986 1
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l ATTACHMENT TO LICENSE AMENDMENT NO.101 l
l FACILITY OPERATING LICENSE N0. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 40 40 41a 41a
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3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the turbine cycle components for removal of reactor decay heat.
Objective
..To specify minimum conditions of the turb ne cyc e.equ pment necessary to i
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i assure the capability _ to remove decay heat from the reactor core.
Specifications l
3.4.1 The reactor shall not be heated, above 280'F unless the following conditions are met:
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 i
available in Tank T418.
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:
" low steam generator pressure" initiate shall be operable a.
when the main steam pressure exceeds 750 psig.
w b.
" loss of 4 RC pumps" initiate shall be operable when neutron k
flux exceeds 10% power.
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" main feedwater pumps tripped" initiate shall be operable c.
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 be reset for the duration of the test, to allow the required pressure for the test to be attained.
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Amendment No. 56,96,94 101 40
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pressure" initiate are the only shutdown bypasses to be manually initiated during cooldown.
If reset is not done manually, they will automatically Main feedwater pump trip bypass is automatically removed above 10%
reset.
power.
In the event of loss of main feedwater, feedwater is supplied by the dmergency feedwater pumps, one which is powered from an operable emergency bus and one.which is powered from an operable steam supply system.
Both EFW pumps take suction from tank T418.
Decay heat is removed from a steam generator by steam relief through the turbine bypass, atmospheric dump valves, or safety valves.
Fourteen of the steam safety valves will relieve the necessary amount of steam for rated reactor power.
The minimum amount of water in tank T418 would be adequate for about 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation.
This is based on the estimate of the average emergency flow to a steam generator being 390 gpm.
This operation time with the volume of water specified would not be reached, since the decay heat removal system could be brought into operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or less.
A portion of tank T41B is protected from tornado missiles.
The protected volume is sufficient to provide a thirty minute supply of water.
This thirty minute period is sufficient to allow manual operator action, if required, to transfer suction of the emergency feedwater pumps to service water.
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Amendment No. 9I,101 41a r
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