ML20154N954
| ML20154N954 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/27/1988 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20154N945 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GL-83-37, NUDOCS 8806030148 | |
| Download: ML20154N954 (5) | |
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PROPOSED TECHNICAL SPECIFICATIONS CHANGES G806030148 880527 PDR ADOCK 05000313 (P
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The Degraded Voltago 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 bssed on long term motor voltage requirements plus the maximum feedwater voltage drop allowance resulting in a 92% setting of motor rated voltage.
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent witn 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, "TMI-2 Lessons Learned Task Force Status Report and Short-term r.
mmendationj."
ae OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental 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 i
the ability of the plant operators to diagnose the approach to and recovery from ICC.
Additionally, they aid in tracking reactor coolant invcatory.
These instruments are included in the Technical Specifications at the i
request of NRC Generic Letter 83-37 and are not required by the accident analysis, nor to bring the plant to cold shutdown conditions.
REFERENCE FSAR, Section 7.1 l
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Amendment No. 60, 89, 91 43b
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F-2 Table 3.5.1-1 (cont'd) 1 k,_
OTHER SAFETi RELATED SYSTEMS (cont'd) 1 2
3 4
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No. of.
Operator action'.
channels Min.
Min.
if condit. ions of No. of for sys ~ operable Functional Unit channels tem trip channels-.
' degree of-column 3 or 4 redundancy cannot be met-
- 13. In core Thermocouples 6/ core quadrant N/A 2/ core quadrant 0
Note 22 (core-exit thermocouples) umS
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$g Table 3.5.1-1 (cont'd)
@g Notes:
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22.
With the number of operable channels less than two (2) per core quadrant restore the inoperable channel to operable status siithin 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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Table 4.1-1 (Cont.)
8" Channel Description Check Test Calibrate Remarks k
A d.
SG A high range level S
M R
high-high 2
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SG B high range level S
M R
high-high 57.
Containment High Range D
M R
Radiation Monitors
- 58. Containment Pressure-High M
NA R
- 59. Containment Water Level-Wide M
NA R
Range
- 60. Low Temperature Overpressure NA R
R
-a Ef Protection Alarm Logic j
- 61. Core-exit Thermocouples M
NA R
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NOTE:
1 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 each done within previous 31 days 1
0 - Daily startup if not done NA - Not Applicable previous week B/M - Every 2 months i
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