ML20116N231
| ML20116N231 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116N236 | List: |
| References | |
| NUDOCS 8505070074 | |
| Download: ML20116N231 (7) | |
Text
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q UNITED STATES S
NUCLEAR REGULATORY COMMISSION O
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment NoS5 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated December 21, 1984, 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 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
8505070074 850430 PDR ADOCK 05000368 P
. 2.
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. NPF-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, 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 the date of its issuance.
FOR THE NUCLEA GULATORY COMMISSION
//
4
/' James R. Miller, Chief y' Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 30,1985 l
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ATTACHMENT TO LICENSE AMENDMENT N0. 65 FACILTIY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overlead pages are also provided to maintain document completeness.
Remove Pages Insert Pages 2-5 2-5 3/4 3-18 3/4 3-18
- - -.. - -,... - -., ~ _ _.. - -..,.,, -, _ - _ _. - -,.,,.. _.,., - - _ - _ _,,. - - - - - -.-.._._,
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS
=.
2 Y'
FUNCTIONAL UNIT E
TRIP SETPOINT ALLOWABLE VALUES Q
1.
Manual Reactor Trip Not Applicable Not Applicable ro 2.
Linear Power Level - High a.
Four Reactor Coolant Pumps i 110% of RATED THERMAL POWER 1 110.712% of RATED THERMAL POWER Operating b.
Three Reactor Coolant Pumps Operating c.
Two Reactor Coolant Pumps Operating - Same Loop d.
Two Reactor Coolant Pumps 7
Operating - Opposite Loops 3.
Logarithmic Power Level -
High (1) 1-0.75% of RATED THERMAL POWER 1 0.819% of RATED THERMAL POWER 4.
Pressurizer Pressure - High 1 2362 psia 1 2370.887 psia
{
5.
Pressurizer Pressure - Low
> 1766 psia (2)
> 1712.757 psia (2) 6.
Containment Pressure - High 1 18.4 psia 1 19.024 psia 7.
Steam Generator Pressure - Low
> 751 psia (3)
>.729.613 psia (3) 8.
Steam Generator Level - Low
> 23% (4)
> 22.111 (4) l 2
- These values left blank pending NRC approval of safety analyses for operation with less th coolant pumps operating.
an four reactor i
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TABLE 2.2-1 (Continued) i REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS E
3ll FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 9.
Local Power Density - High 1 0.3 kw/ft (5) 2 1 0.3 kw/ft (5) 2
- 10. DNBR - Low
> 1.24 (5)(6)
> l.24 (5)(6)
[
11.
Steam Cenerator Level - High 1 93.7% (4) 1 94.589% (4)
TABLE NOTATION (1 ) Trip may be manually bypassed above 10~4% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is 1 10'4 of RATED THERMAL POWER.
(2) Value may be decreased manually, to a minimum value of 100 psia, during a planned reduction in i
pressurizer pressure, provided the margin between the pressurizer pressure and this value is maintained at 1200 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until
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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 margiri between the steam generator pressure and this value is maintained at 1 200 psi; the setpoint j
shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(4) % of the distance between steam generator upper and lower level instrument nozzles.
o.
P.
(5) As stored within the Core Protection Calculator (CPC). Calculation of the trip setpoint includes measure-
?,
ment, calgulational and processor uncertainties, and dynamic allowances.
below 10' % of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 1 2
P of RATED THERMAL POWER.
~
(6) The minimtsn allowable value of the addressable constant BERR1 in each OPERABLE channel is 1.065.
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TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRtMENTATION TRIP VALUES W
ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES E
4.
MAIN STEAM AND FEEDWATER ISOLATION (MSIS)
G a.
Manual (Trip Buttons)
Not Applicable Not Applicable m
b.
Steam Generator Pressure - Low g 751 psia (2) g 729.613 psia (2) 5.
CONTAllMENT COOLING (CCAS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Containment Pressure - High 1 18.4 psia 1
1 9.024 psia 1 1766 psia (1) g 1712.757 psia (1) h c.
Pressurize-Pressure - Low t
6.
RECIRCULATION (RAS)
[
a.
Manual (Trip Buttons)
Not Applicable Not Applicable O
b.
Refueling Water Tank - Low 54.400 1 2,370 gallons between 51,050 and 58,600 (equivalent to 6.0 + 0.5%
indicated level) gallons {eguivalentto between
.311% and 6.889%
g indicated level) k 7.
LOSS OF POWER 2
a.
4.16 kv Emergency Bus Undervoltage f.
(Loss of Voltage) 3120 volts (4) 3120 volts (4) b.
40 volt Emergency Bus Undervoltage 423 + 2.0 volts 423 + 4.0 volts 2
(Degraded Voltage) with an 8.0 1 0.5 with an 8.0 1 0.8 second time delay second time delay
TABLE 3.3-4 (Continued)
E9 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES 5
ALLOWABLE FUNCTIONAL UNIT TRIP VALUE.
VALUES c
g 8.
EMERGENCY FEEDWATER (EFAS) m a.
Manual (trip Buttons)
Not Applicable Not Applicable b.
Steam Generator (A&B) Level-Low
> 23% (3)
> 22.111% (3) c.
Steam Generator AP-High (SG-A > SG-B) 1 90 psi 1 99.344 psi d.
Steam Generator AP-High (SG-B > SG-A) 1 0 psi 9
1 9.344 psi 9
e.
Steam Generator (A&B) Pressure - Low
> 751 psia (2)
> 729.613 psia (2) t' (1 ) Value may be decreased manually, to a minimum of > 100 psia, during a planned reduction in pressurizer pressure, provided the margin between the pressurTzer pressure and this value is maintained at 1 200 psi; Y
the setpoint shall be increased automatically as pressurizer pressure is increased until the trip set-g point is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is > 500 psia.
(2) Value may be decreased manually during a planned reduction in steam generator pressure, provided the margin between the steam generator pressure and this value is maintained at 1200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
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(3) % of the distance between steam generator upper and lower level instrument nozzles.
3 (4)
Inverse time relay set value, not a trip value. The zero voltage trip will occur in 0.75 + 0.075 seconds.
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