ML20059K694
| ML20059K694 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/13/1990 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059K696 | List: |
| References | |
| NUDOCS 9009240183 | |
| Download: ML20059K694 (12) | |
Text
,
_ - - ~
h
[
k UNITED STATES i
NUCLEAR REGULATORY COMMISSION v
we sHiNoToN, D. C. 20665 j
s....../
i ENTERGY OPERATIONS, INC.
l DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.135 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
~
.A.
The application for amendment by Arkansas Power and Light Company dated August 9,1989, as supplemented on March 30 and June 15, EnergyActof1954,asamended(theAct)quirementsoftheAtomic 1990, complies with the standards and re
, 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:
(1)thattheactivitiesauthorized
-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.
9009240103 900913 gDR ADOCK 05000313' PNV t
~ _
i 2-l 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attacfatnt to this license asiendment, and Paragraph 2.C.(2) of Facility Operating License No.
DPR-51 is bereby amnced to read as follows:
l 2.
Technical Specifications The Technical Specifications contained in Aspendix A, as revised through Amendment No.135, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
t 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
}llu-AnS.Scy Theodore R. Quay, Acting Director Project Directorate IV-1 Division of Reactor Projects - III.
IV, Y and Special Projects Office of Nuclear Reactor Pegulation
Attachment:
Changes to the Technical Specifications l.
Date of Issuance: September 13, 1990 4
+
l l
l-1 l
l
i ATTACHNENT TO LICENSE AMENDMENT NO.135 FACILITY 00pATINGLICENSENO.DPR-51 DOCKET NO. 50 313 Revise the following pages of the Apoencix 'A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number ano contain vertical lines indicating the area of change.
REMGYE PAGES INSERT PAGES 42b 43b 43b 45d1 45d1 459 45g 72a 72a 726 72b 72b1 72d 72d i
i l
l l
l l
3.5.1.13 The Seismic Monitoring Instrumentation shall be operable with a minimum measurement range from 0.01 to 1.0 g (2-25.4 HZ for Triaxial Response Spectrum Recorders).
i t
I I
r i
k I
r
. Amendment No. 135 42b 1
~
The Degraded Voltage Monitoring relay settings are based on the short term starting voltage protection as well as long term running voltage protection.
The 4.16 KV undervoltage relay setpoints are based on the allowable starting voltage plus maximum system voltage drops to the motor terminals, which allows approximately 78% of motor rated voltage at the motor terminals.
The 460V undervoltage relay setpoint is based on long term motor voltage requirements plus the maximum feeder voltage drop l
allowance resulting in a 92% setting of motor rated voltage.
1 The OPERABILITY of the accident n.onitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor 1
and assess these variables during and following an accident.
This i
capability is consistent with the recommendation of Regulatory Guide 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess.
Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "THI-2 Lessons learn'ad Task Force Status Report and Short-Term Recommendations."
]
The OPERABILITY of the chlo u.ie detection system ensures that sufficient capability is available to promptly detect and initiate protectiva action in the event of an accidents 1 chlorine release.
This capability is required to protect control room personnel and is consistent with the
]
recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release,"
February 1975.
The subcooled margin monitors (SMM), and core-exit thermocouples are a result of the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737.
The function of the ICC instrumentation is to increase the ability of the plant operators to diagnose the approach to and recovery from ICC.
Additionally, they aid in tracking reactor coolant l
inventory.
These instruments are included in the Technical Specifications at the_ request of NRC Generic Letter 83-37 and are not required by the accident analysis, nor to bring the plant to cold shutdown conditions.
The OPERABILITY of the Seismic Monitoring Instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a
- cismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10CFR Part 100.
The instrumentation is consistent with the recommendations of Safety Guide 12,
" Instrumentation for Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4, " Seismic Instrumentation."
REFERENCE l
FSAR, Section 7.1 FSAR, Section 2.7.6 g
Amendme'nt No. 60, 69, 9Z,1W,135 43b L
l
o Table 3.5.1-1 (cont'd)
N OTHER SAFETY RELATE 0 SYSTEMS (cont'd) 1 2
3 4
5 No. of Operator action EF channels Min.
- Min, if conditions of No. of for sys-operable degree of column 3 or 4 ti Functional Unit channels tem trip channels redundancy cannot be met
- 13. In core Thermocouples 6/ core quadrant N/A 2/ core quadrant 0
Note 22 M
(cor e wit thermocouples)
- 14. Seismic Monitoring Instrumentation a.
Triaxial Time-History Accelerographs 1.
ACS-8001, Unit 1 1
N/A 1
0 Note 27 Containment Base (Slab, Elev. 335'*)
S 2.
ACS-8002, Unit 1 Top of 1
N/A 1
0 Note 27 Containnent, Elev. 531'6" b.
Triaxial Peak Accelerographs 1.
2XR-8347, Unit 2 Containment 1
N/A 1
0 Note 27 Base Slab, Elev. 336'6" 2.
2XR-8348, Unit 2 Primary Shield 1
N/A 1
0 Note 27 0/5 Reactor Cavity, Elev. 366'3" 3.
2XR-8349, Unit 2 Top of 1
N/A 1
0 Note 27 Containment, Elev. 531'6" t
c.
Triaxial Response-Spectrum Recorders 1.
2XR-8350, Unit 2 Containment 1
N/A 1
'd Note 27 Base Slab, Elev. 335'6" (0/5 Containment)
- With Unit I control room indication /or alarm
~.
Table 3.5.1-1 (cont'd)
N 23.
With the number of operable Electronic (SCR) Trip relays one less than the +,otal number of Electronic 'l 5
(SCR) Trip relays-in a channel, restore the inoperable Electronic (SCR) Trip relay to operable status e'
in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the SCRs associated with the inoperable Electronic (SCR) Trip relay in trip'in 5
the next hour. With two or more Electronic (SCR) Trip relays inoperable, place all Electronic (SCR)
Trip relays associated with that channel in trip in the next hour.
This requirement does not apply z
?
to '.he Electronic Trip channels associated with Group 8 Regulating Power Supply.
- 24. With the nund>er of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER l OPERATION may proceed provided the following conditions are satisfied:
U a.
Within I hour:
1.
Place the inoperable channel in the tripped condition, or 2.
Remove power supplied to the control rod trip device associated with the inoperable channel.
b.
One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing and the inoperable channel above may be bypassed for up to 30 minutes in any 24-hour period when necessary to test the trip breaker associated with the logic of the channel being tested. The inoperable channel above shall not be bypassed to test the logic of a channel of the trip system aE associated with the inoperable channel.
25.
With one of the Control Rod Drive Trip Breaker diverse trip features (undervoltage or shunt trip I
attachment) inoperable, restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.
26.
Interrupts motor power to 'the Safety Groups of control rods only.
l 27.
With one or more seismic me.iitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.12.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
s
~
y m',
,_s m
m m
,m_________.______e
f".
~
Tabla 4.1-1 (Cont. )
Channel Description' Check Test Calibrate Remarks
- 36. Boric Acid Addition Tank W3 a.
Level Channel NA NA R
b.
Temperature Channel M-NA R
2
?
- 37. Degraded Voltage Monitoring W
R R
m*
'38. Sodium Hydroxide Tank NA NA R
w*
Level Indicator E
- 39. Incore Neutron Detectors M(1)
NA NA (1) Check Functioning m
- 40. Emergency Plant Radiation M(1)
NA R
(1) Battery Check i
Instruments
- 41. Reactor Trip Upon M
PC R
Turbine Trip Circuitry i
h
- 42. Seismic Monitoring Instruments y
a.
Triaxial Time-History Accelerographs 1.
ACS-8001, Unit 1 M(1)
SA R
(1) Except Seismic Trigger yy Containment Base Slab, Elev, 335' (with Unit I control room indication) 7 2.
ACS-8002, Unit 1 M(1)
SA R
Top of Containment t
Elev. S31'6" 1
6
+
~
y e
~~
e..
,-e e
v.
,v----e.
y4.,w-e..
v *.- -. -,
-r
,,..+--
.--e.
m --
o a
.?.
~ Table 4.1-1 (Cont.)
Channel Description Check Test Calibrate Remarks E
b.
Triaxial Peak Accelerographs
~o 1.
2XR-8437, Unit 2 NA NA R
Os Containment Base Slab, jg Elev. 336'6" h5 2.
2XR-8348, Unit 2 NA NA R
in Primary Shield 0/S Reactor
-((
Cavity,'Elev. 366'3"
's 3.
2XR-8349, Unit 2 Top NA NA R
q of Containment, Elev. 531'6" n'
c.
Triaxial Response-Spectrum M
Recorders er 1.
2XR-8350, Unit 2 NA R
R Containment Base Slab, Elev. 335'6" (0/5 Containment)
- 43. ESAS Manual Trip Functions a.
Switches & Logic NA.
R NA b.
Logic NA M
- 44. Reactor Manual Trip NA P
NA
- 45. Reactor Building Semp Level NA NA R
- 46. EFW Flow indication M
NA R
w
--,o e m
.n.e w
w
'wn-
-,.e e
se, v
r4--
m,
+
~g
,w-w
--ow~,
- - - ~ _,
.o
. Table 4.1-1 (Cont.)
.k Channel Description-Check Test Calibrate-Remarks Eg
- 47. RCS Subcooling Margin D
NA R
g Monitor zo-
- 48. Electromatic Relief Valve D
NA R
Flow Monitor m
m
'w
- 49. Electromatic Relief Block 0
NA R
-[
Valve Position Indicator s
'm
- 50. Pressurizer Safety Valve D
NA.
R Flow Monitor
- 51. Pressurizer Water Leva:1 D
NA R
C Indicator w
- 52. Control Room Chlorine Detector D M
R 5
- 53. EFW Initiation a.
Manual NA M
NA b.
SG Low level, SGA or B 5
M R
c.
Low Pressure SGS or B S
M R
l d.
Loss of both MFW Pumps S
M R
and PWR > 10%
i
[..
l l
l
~
..g;. 4 Table 4.1-1 (Cont.)
E Channel Description Check Test Calibrate Remarks E
d.
SG A High Range Level S
M R
High-high E
e.
SG B High Range Level S
M R
20 High-high s'
- 57. Containment High Range D
M R
Radiation Monitors E
- 58. Containment Pressure-Hinh M
NA R
El
~
. 59. Containment Water Level-Wide M
NA R
p Range 4
- 60. Low Tem,erature Overpressure NA R
R g;
Protection Alarm Logic w
- 61. Core-exit Thermocouples M
NA R
$f 62 Electronic (SCR) Trip Relays NA-M NA NOTE:
S - Each Shift T/W - Twice per Week R - Once every 18 months W - Weekly Q-Quarterly PC - Prior to going Critical if not M - Monthly P-
. Prior to gach done within previous 31 days D - Daily startup if not done NA - Not Applicable previous week SA - Twice per Year' s
B/M - Every 2 months I
J