ML20115B259
| ML20115B259 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/05/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115B261 | List: |
| References | |
| NPF-06-A-137 NUDOCS 9210150368 | |
| Download: ML20115B259 (9) | |
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' UNITED STATES f'
7g; NUCLEAR REGULATORY COMMISSION i g-j-WASHINGT ON, D. C. 205551 y}
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 5
ARKANSAS NUCLEAR ONE. UNIT NO._2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.' 137.
License No. NPF-6 1.
The Niiclear Regulatory Commission (tt.e Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensees dated July 9, 1992, as-supplemented by letter dated September 14,1992.= complies with the standards and requirements of the.Atomit Energy Act of 1954, as amended (the Act), and.the Commission's rules and regulations set forth in 10 CFR Chapter I; L
B..-
The facility will operate'in conformity with'the application, the.
provisions of the Act, and the rales 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 condrted 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.
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9210150368 921005 PDR ADOCK 05000368 P.
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as inucated in th) attachment to this license amendment, and Paragraph 2.C,(2) of Facility Operating License No. NPF-6 is hereby amended to read as foll)ws-2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.137, 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 Yf ins, y Jr.hn T. La Director oroject Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Reculation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 5, 1992
Q ATTACHMENT TO LICENSE AMENDMENT NO. 137
[A[JLITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-J52 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 2-5 2-5 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 l
i
IAB E 2.2-1 EffCTOR PR27.LG.TIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT IRIP SLTPOINJ ALLOWASLE VALUES 1.
Manual Reactor Trip Not Applicabic Not Applicable 2.
Linear Power Level - liigh a.
Four P netor Coolent Pumps 110*, of RATED TiiERMAI. POWER 5 110.712% of RATED TifERMAL POWER l
Operating l
b.
Three Reactor Loolant Pumps l
Operating c.
Two Reactor Coolant Pumps Operating - Same Loor d.
Two Reactor Coolant Purps Operating - Opposite Loops I
[
3.
Iogarithmic Power Lesel -
l liigh (1) 50.75% of FATED T:fERMiL POWER 5 0.819% of RATED Tl!ERMAL POWER I
4.
Pressurizer Pressure - High 1 2'162 psia 5 2370.887 psia 5.
Pressurizer Pressure - Low 2 1766 psia (2) 2 1712.757 psia (2) l 6.
Containment Pressure - liigh 5 18.3 pria 5 18.490 psia 7.
Steam Generator Pressure - Low 2 751 psia (3) 2 729.613 psia (3) 8.
Eterm Generator Level - Low 2 23% (4) 2 22.111 (4)
- These values lef t blank pending NRC approval of safety analyses for operation with less than four reactor coolant pumps operating.
^
ARKANSAS - UNIT 2 2-5 Amendment No. 1. 14. M, 137 l
s.
TABLE 2.2-1 (Continued) j REACT 0i PROTECTIVE INSTR 1HENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNir IRIP SETPOINT ALLOWABtE VALUES 9.
Local Power Density - High
$21.0 kw/ft (5) 121.0 kw/f t (5) 10 DNBR - Low
>1.25 (5)
>1.25 (5) 11.
Steam Generator Level - High p 3.7% (4) 194.589% (4)
TABLE NOTATION (1) Trip may be ranually bypassed above 10 4% of RATED THERMAL POWER; bypass shall be autocatically removed when THERMAL *0WER i5 1 10-4 of RATED THERMAL POWER.
Value may be decreased manually, to a minimum value of 100 psia, during a plarned reduction in (2) pressurizer pressure, provided the margin between the pressurizer pressure and this value is maintained 200 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until at $
the trip setpoint is reached.
Trip eay be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is > 560 psia.
f
('3) Value may be decreased manually during a planned reduction in steam generatcr pressure provided the between the steam generator pressure and this value is maintained at < 200 psi; the setpoint N
marg i
shal e be increased automtically as steam generator pressure is increased until the trip setpoint is reached.
(4) % of the distance between cteam generator upper and lower level instrument nozzles.
l (5) As stored within the Core Protection Calculator (CPC).
Calculation of the trip setpoint includes measurement, calculational and prc_essor uncertainties, and Jynamic allowances.
Trip may be manually bypassed below 10 4% of RATED THERMAL POWER; byriss shall be automatically removed when THERMAL POWER is > 10 4% of RATED THERMAL POWER.
ARKANSAS - UNIT 2 2-6 Amendment No. 24, 26, 27, (s. 79 p
y p
l p
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TABLE 3.3-4 ENGINEERED
- SAFETY FEATtjRE ACTUA~ ION SYSTEM INSTRUMENTATION TRIP VALUES i
ALLOWABLE IllP SETPOINT VALJCS l
FUNCTIONf&, U.LNIT 1.
SAFETY INJECTION (SIAS)
Not Applicable Not Applicable
, Manual (Trip Buttons) a.
l l
b.
Containment Pressure - liigh 5 18.3 psia
$ 18.490 psis 1
l l
c.
Pressurizer Pressure -Low 21766 psia (1) 2171'.757 psia (1) 2.
Not Applicable Not Applicable Manual (Trip Buttons) a.
l b.
Containment Pressure -- High-High
$ 23.3 psia
$ 23.490 psia l
l 3.
CONTAINMENT ISOLATION (CIAS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable High 5 18.3 psia
$ 18.490 psia l
b.
Containment Pressure ARKANSAS ' UNIT 2 3/4 3-16 Amendment No. ZA, 137
=.
f:
TABLE 3.3-3 (Continued)
~
TABLE NOTATION ACTION 10 -
With the number of OP5RABLE Channals one less than the-Total Number of Channelt, eceration may proceed provided the inocerable crannel is placed in the bypassed condition and the Minimum Channels OPERABLE recuirement is demon--
strated within I hour; one additional enannel may be bypassed or placed in the tripped condition for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing par Specification 4.3.2.1.1.
'JNIT 2 3/4 3-15 4
~
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TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRI" lALUES ALLOWAELE FUNCTIONA1 UNIT TRIP VALUE
_ VALUES 4
MAIN STREAM AND FEEDWATER ISOLATION (MSIS) a.
Manual (Trip Buttons)
Not Applicable Nat Applicable b.
Steam Generator Pressure - Low 751 psia (2) 2 729.613 psia (2)-
5.
CONTAINMENT COOLING (CCAS) a.
Manual (Trip Buttons)
Not Applicable Not applicable b.
Containment Pressure - High f 18.3 psia 5 18.490 psia c.
Pressurizar Pressure - Los 2 1766 psia (1) 21712.757 psia (1) 6.
RECIRCULATION (RAS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Refueling Water Tank - Let 54,400 2,370 gallons between 51,050 and 58,600 (equivalent to 6.0 1 0.5%
gallons (equivalent to indicated level) between 5.111% and 6.889%
iriicated level) 7.
LOSS OF POWER a.
'4.16 kv Emergency Bus Undervoltage (Loss of Voltage) 3120 volts (4) 3120 volts (4) b.
460 volt Emergency Bus Undervoltage 423 i 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 ARKANSAS - UNIT 2 3/4 3-17.
Amendment No. 24,137
TABtr 3.3-4 (Continued)
E C
ENGINEERED SAFETY FEATURE AC.iii!GN SYSTEM INSTRUMENTATION TRIP VALUES i
5 3;
ALLOWABLE FUNCTIONAL UNIT Tr. P VALUE VALUES h!
3.
Manual (trip Buttons)
Not Applicab te Not Applicable b.
Steam Generator (A&B) Level-Low 1 23 (3)
> 22.111 (3) c.
Steam Generator eP-High (SG-A > SG-8) 1 90 psi 1 99.344 psi d.
Steam Generator SP-High (SG-B > SG-A) 1 90 pri 1 99.344 esi e.
Steam Generator ( A&B) Pressure - Lew
> 751 psia (2)
> 729.613 psia (2) t' (1) Value may be decreased manually, to i minimum of > 100 psia, during a planned reduction in pressurizer pressure, provided the margin between the pressurizer pressure and this value is maintained at i 200 pst; T'
the'setpoint shall be increased automatically as pressurizer pressure is increased until the trip set-6; 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 'he steam generator pressure and this value is maintained at 1 200 psi, the setpoint shall be incraased autonatically as steas generator pressure is increased until the trip setpoint is reached.
g s
[3) % of the distance between steam generator upper and lower level instrament nozzles.
5 A
(4)
Inverse time relay set value, not a trip value.
The zer-voltage trip will occur in 0.75 1 0.075 seconds.
z
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