ML20202B451
| ML20202B451 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (NPF-06-A-200, NPF-6-A-200) |
| Issue date: | 01/26/1999 |
| From: | Nolan M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20202B454 | List: |
| References | |
| NUDOCS 9901290085 | |
| Download: ML20202B451 (5) | |
Text
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rerg dh UNITED STATES O
E NUCLEAR REGULATORY COMMISSION E
'E WASHINGTON, D.C. 20066-0001
\\...../
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. NPF-6 1.
The Nuclear Regulatory Cornmission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 29,1998, 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, 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 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 Commission's regulations and all applicable requirements have been satisfied.
9901290085 990126 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 Parag aph 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 Appendix A, as revised through Amendment No. 200, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The I! cense amendment is effective as of its date of issuance and shall be implemented prior to the facility's restart from refueling outage 2R13.
FOR THE NUCLEAR REGULATORY COMMISSION M#
M. Christopher Nolan, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
January 26, 1999
ATTACHMENT TO LICENSE AMENDMENT NO. 200 FACILITY OPERATING LICENSE NO. NPF4 DOCKET NO. 50-368 Revise 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. The corresponding overleaf pages are also provided to maintain document completeness.
[
REMOVE PAGES INSERT PAGES 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 l
l I
a f
{.. -
i l
I 1
i TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATI M SYSTEM INSTRUMENTATION TRIP VALUES Am.noNABLE FUNCTIONAL UNIT TRIP VALUE VALUES j
4.
MAIN STEAM AND FEEDNATER ISOLATION (MSIS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable I
i b.
Steaun Generator Pressure - Low k 712 psia (2) k 699.6 pela (2) l
'l [
5.
CONTAINMENT COOLING (CCAS) f i
a.
Manual (Trip Buttons)
Not Applicable Not applicable l
j b.
Contaisument Pressure - Nigh 5 18.3 psia 5 10.490 psia i
c.
Pressurizer Pnasure - Low k 1717.4 psia (1) 1 1686.3 pela (1) i l
6.
RECIRCULATION (RAS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable t
b.
Refueling Water Tank - Low 54,400 1 2,370 gallons between 51,050 and 50,600 l
(equivalent to 6.0 1 0.5%
gallons (equivalent to indicated level) between 5.1119 and 6.8894 l
indicated lewl) 7.
LOSS or PONER a.
4.16 kv anergency Bus Underoltage (4) 2300 i 699 volts (Loss of Voltage) with a 0.64 i 0.34 second time delay b.
460 volt meergency Bus Undervoltage 423 1 2.0 volts 423 1 4.0 volts (Degraded Voltage) with an 8.0 1 0.5 with an 8.0 1 0.8 second time delay second time delay j
t i
ARKANSAS - UNIT 2 3/4 3-17 Amendment No. 34,447,448,449,4es,200
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES 8.
Manual (Trip Buttons)
Not Applicable Not Applicable t
b.
Steam Generator (A&B) Level-Low 2 23% (3) 2 22.111% (3) c.
Steam Generator AP-High (SG-A > SG-B) s 90 psi s 99.344 psi f
d.
Steam Generator AP-High (SG-B > SG-A) s 90 psi s 99.344 psi I
Steam Generator (A&B) Pressure - Low 2 712 psia (2) 2 699.6 paia (2) e.
f (1)
Value may be decreased manually, to a minimum of 2 100 psia, during a planned reduction in pressurizer pressure, provided the margin between the pressurizer pressure and this value is maintained at s 200 psip the setpoint shall be increased automatically as pressurizer pressure is increased until the trip set-point is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically reseved before pressuriter pressure exceeds 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 s 200 psis the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(3)
% of the distance between steam generator upper and lower level instrument nozzles.
(4)
The trip value for this function is listed in the surveillance test procedures. The trip value will ensure that adequate protection is provided when all the applicable calibration tolerances, channel uncertainties, l
and time delays are taken into account.
i ARKANSAS - UNIT 2 3/4 3-18 Amendment No. 9,34,46,449,446,200
.