ML20031A671
| ML20031A671 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/09/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031A672 | List: |
| References | |
| NUDOCS 8109250067 | |
| Download: ML20031A671 (4) | |
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'%,,,, ',' J ARKAtlSAS PCWER AND LIGHT CC"PANY i
DOCKET fl0. 50-368 ARKANSAS NUCLEAR ONE. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 27 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The app'lications for amendment by Arkansas Pov.er and Light Compar./
(the licensee)' dated February 20 and March 5,1981, as supplemented, by letter dated August 12, 1981 comply with the standards and re-quirements 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 applications, the provisions of the Act, and the rules and regulations of the Commission; i
l 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 i
in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the cccmon 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.
2.
Accordingly, Facility Operating License No. NPF-6 is amended by changes to the Technical Specifications as indicated in the attachment to this license
_ amendment, and Paragraph 2.C.(2) is hereby amended to read as follows:
(1) Technical Specifications The Technical Specifications contained in Appendices A and B, as re-vised through Amendment No.
are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This licence amendment shall be effective within 7 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief Operating Reactors Branch #3 Divisicn of Licensing Attachrent:
Changes to the Technical Specifications Date of Issuance:
September 9, 1981
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.l-ATTACHMErlT TO LICENSE AMEtJDMEriT 110. 27 FACILITY GPERATIriG LICEtJSE t;0. f!PF-6 DOCKET NO. 50-368 Replace the following page cf the Apendix "A" Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The correspcoding overleaf page is also reovided to maintain document completeness.
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TABLE 2.2-1 9
SEACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS c
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VA!.UES
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1.
_ Manual Reactor Trip Not Applicable-Not Applicable Linear Power Level - High a.
Four Reactor Coolant Pumps
's 110% of RATED THERMAL POWER 1 110.712% of RATED TilERMAL POWiI Operating b.
.Three Reactor Coolant Pumps Operating c.
Two Reactor Coolant Pumps Operatino - Same Loop ro d.
Two Reactor Coolant Pumps i
Operating - Opposite Loops 3
Logarithmic' Power Level -
3.
High (1)
< 0.75% of RATED THERMAL' POWER
'1 0.819% of RATED TitEdMAt PR R 4.
Pressurizer Pressure - High
< 2362 psia
< 2370.387 psia
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5.
Pressurizer Pressure - Low L 1766 Psia (2?
t 1712.757 psia (2) 6.
Containment Pressure - liigh 1 18.4 psia 1 19.024 psia
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7.
Steam Generator Pressure - Low
> 751 psia (3) t 729.613 psia (3)
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Steam Generator Level - Low
> 46./% (4)
- 45.811" (4) 4 X
- These values lef t blank pending NRC approval of safety analyses for operation wit: less tn.u.
four reactor coolant pumps operating.
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TABLE 2.2-1 (Continued )
REACT 0F PROTECTIVE ItiSTRUMEt4TATI0t1 TRIP SETP0 INT LIMITS NM FUtiCTIONAL 8JNIT TRIP SETP0ltiT ALLOUABLE VALUES 5
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Locai Power Density - High 1 20.3 kw/ft (5) 1 20.3 kw/ii (5) e c-10.
DNBR - Low
> 1.24 (5)(6)
__1.24 (5 )(6) 11.
Steam Generator Level - High
__ 93.7 % (4 )
_ 94.589% (4) y TABLE NOTATION (1) Trip may be manually bypassed above 10-4% of RATED THERiiAL POWER; bypass shall be automatically 4
removed whn TilERMAL POWER is 1 10 of RATED TilERMAL POWER.
(2) Value may be decreased manually, to a minimum value of 100 psia, during a planned reduction in pressurizer pressure, provided the margin oetween the pressurizer pressure and this value is maintained at 1200 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.
Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is > 500 psia.
(3) Value may be decreased manually during a planned reduction in steam generator pressure provided the rhargin between the steam generator pressure and this' value is maintained at 1 00 psi; the setpoint 2
shall be increased automatically as steam generator pressure is increased until the t -ip setpoint is reached.
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(4) % of the distance between steam generator upper and lower level instrument nozzles.
a.
M (5) As stored within the Ccre Protection Calculator (CPC).
Calculation of the trip setpoint includes measure-5 ment, calgt.lational and processor uncertainties, and dynamic allowances.
Trip may be manually bypassyd -
2 below 10~ % of RATED TilERMAL POWER; bypass shall be automatically removed when TilERMAL POWER is > 10- # 'l-P of RATED THERMAL POWER.
(6) The minimum allowable value of the addressable constant BERR1 in each OPERABLE channel is 1.0f,5.
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