ML20106C903
| ML20106C903 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/28/1992 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20106C901 | List: |
| References | |
| NUDOCS 9210060416 | |
| Download: ML20106C903 (12) | |
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j 3.5.1.13 The Seismic Monitot ing Instrumnntation shall im opninble with n minimum measurement range of 0.01 - 1.0 g for Trinxini Timo -
llistory Accnlerographs, 0.05 --1.0 g for Trinxial Penk Accolorographs, and 2-75.4 Ilz for Trinx. int Response Spectrum Recorder a.
3.5.1.14 Tim Main Steam I,ine Endlation Monitoring instrue.cntation shall
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bn operable with a minimum mensurement range frem 10
to 10' mR/hr, whennver the rencton in above tbo cold shutdown condl'lon.
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Table 3.5.1-1 (cont'd) i f
- OTHER SAFETY RELATED SYSTEMS (Con-:'d) 1 2
3 4
5
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4 1
I No. of Operator action
[
channels Min.
Min.
if conditions of
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No. of for sys-operable degree of column 3 or 4 i
Epnctional Unit channels ter trin channels adundancy car.not be met
- I c.
Triaxial Response-Spectrum Recorders l
L I
1.
2XR-8350, E-2 Cr-tainment 1
N/A 1
0 Note 27 i
Base'Siab, t i.'335' 6" i
'(0/S Containment) l j.
15.
Reactor Vessel Level Monitoring System 2
N/A 2
0 Note 28, 29 j:
i 16.
Hot Leg Level Measurement System (HLLMS) 2 N/A 2
0 Note 2S, 29' r
17.
Main Steam Line 1 / steam line N/A 1/ steam liae O
Note 30 Radiation Monitors s
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A
IJble 4.1-1 (Cont'd) 4 Channel Descriotion Check Test Calibraig Bamarks 20.
Reactor Building Spray System NA M(1)
NA-(1)
Including RB spray pump, 3
. System Logic Channels spray valves, and chem.
add. valve logic channels.
21.
Reactor Building Spray System Analog Channels a.
Reactor Building Pressure
(
Channels NA M
R 22.
Pressurizer Temperature Channels S
.iA R
I 23.
Control Rod Absolute Position S(1)
NA R
(1) Compare with Relative Position Indicator.
I 24.
Control Rod Relative Position S(1)
NA R
(1) Check with Absolute Position Indicator
'l 25.
Core Flooding Tanks a.
Pressure Channels S
NA R
b.
Level Channels S
.NA R
26.
Pressurizer Level Channels S
NA R
27.
Makeup Tank Level Channels D
NA R
L 28.
Radiation Monitoring Systems (1) Check functioning or self-checking- ;
other than containment high feature on each detector.
range monitors (item 57) t a.
Process Monitoring System S
Q R
b.
Area' Monitoring System.
S M(1)
R l
.c.
Main Steam Line Radiation Monitors S
M R
I Amendment.No. 95, 126 71-y g
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Table 4.1-1 (Cont.)
Channe1' Description Check Test Calibrate Remarks
- 29. High and'LowiPressure
- N.;
NA R
Injectic
'y,tems-Flow Channels
- 30. Decay heat removal S(1)(2)
M(1)(3) R (1)
Includes RCS Pressure Analog Channel system isolation valve-(2)
Includes CFT Isolation Valve Position 6
automatic closure and (3) At least once every refueling shutdown, interlock system with Reactor Coolant ' System Pressure-greater --han or equal to 200 psig, but less t's 300 psig,' verify automatic isolation of the decay heat removal system from the Reactor Coolant System t
on high Reactor Coolant System pressure.
- 31. Turbine overspeedtrip NA R
NA (1) The provisions of Specification' 4.0.4 l
4 mechanism are not applicable.
-j
- 32. Diesel generator M
Q NA protective relaying' starting interlocks anc circuitry
- 33. Off-site power. undervoltage W
R(1)
R(1)
(1) Shall be testei during refueling
'f and' protective relaying-shutdown to /amonstrate selective
!'I interlocks and circuitry load shedding' interlocks function during manual or automatic trans-fer of Unit I auxiliary load to t
l Startup Transformer No. 2.
]
l
- 34. Borated water storage W
NA R
[
tank. level-indicator 3
i
-35. Reactor trip upon loss M
PC R
7 of main feedwater circuitry l
Amendment No.~A, 17, 59, f9, (7, 91i 152 72 161 1
4 h.
- Inopernbin Fire Detection Instrumentation-1.
Jnoperabic Fire Suppression Systems
.}.
Degraded Auxillary Electrical Systems, Specification 3.7.2 ll.
k.
Inoperablo Reactor Vessel 14cvol Monitoring Syst ems, Tabin 3.5.1-1 1.
Inoperable llot Leg 1,ovel Measurement Systems, Table 3.5.1-1 m.
Inoperablo Main Steam Line Radiation Monitors, Specification 3.5.1, Tablo 3.5.1-1.
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ANO-2 TECllNICAL SPECIFICATION PROPOSED PAGE CilANGES F
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e TSI Applicable 368-02-00 '-
TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICAPLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERAFLE MODES SETPOINT RANGE ACTION i
1.
AREA MONITORS a.
Spent Fuel Pool Area Monitor i
Note 1 5 1.5x10 R/hr 10 ' - 10 R/hr 13 2
b.
Containment High 7
Range 2
1, 2, 3 & 4 Not Applicable 1 - 10 R/hr 16 2.
PROCESS MONITORS a.
Containment
- i. Gaseous Activity a) Purge & Exhaust 1 solation 1
5&6 5 2 x background 10 - 10' cpm 16 b) RCS Leakage Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10' cpm 14 ii. Particulate Activity a) RCS Leakage Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10' cpm 14 b.
Control Rrom Ventilation Intake Duct Monitor 1
ALL MODES 5 2 x background 10 - 10' cpm 17 c.
Main Steam Line 1/ Steam 1, 2, 3, & 4 -
Not Applicable 10 10' mR/hr 19 Radiation Monitors Line Note 1
'n'ith fuel in the spent fuel pool or building ARKANSAS. UNIT 2 3/4 3-25 Amendment No. 63, 1)S
IADLE 3.3-6 (ContluneJ11 IABLE NOTATION
-ACTION 13 -.
With the number of channels OPERABLE less than required by the Minimum Channnis OPERABLE requirement, perform area-surveys of the monitored -area with portable monitoring instrumentation at least once por 2^ hours.
ACTION 14 --
With the number of channels OPERABLE less than required by-tho Minimum Channels OPERABLE requirement, comply with thn ACTION requirements of Specification 3.4.6.1.
ACTION 16 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, complote'the following:
- a. If performing CORE ALTERATIONS or moving irradiated fuel within the reactor building, secure the containment purgo-system or suspend CORE ALTERATIONS and movement of irradiated fuel within tha reactor buliding,
- b. If a containment PURGE is in progress, secure the containment purge system, c.
If continuously ventilating, verify the SPING monitor:
operable or perform the ACTIONS of 3.',.3.9, or secure -the containment. purgo. system.
ACTION 17 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within I hour initiato and maintain operation of the control room emergency ventilation system in the recirculation modo of operation.
ACTION 18 -
With the number of channels OPERABLE one less than required by tho Minimum Channels OPERABLE requirement, (1) either restore the inoperable channel to OPERABLE status within 7 days or (2) prepare and submLit a Special Report to the Commission pursuant to Specification 6'9.2 within 30. days following the event, outlining the action taken, the cause of the luoperability, and the plans and schedule for restoring =the system to OPERABLE status. With both channels inopn able. initiate alternato methods of monitoring the containment radiation-level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in addition to the actions described above.
ACTION'19 -
_ With the number of OPERABLE Channels Inss than required by the Minimum Channels-OPERABLE requirements, initiate the proplanned alternatn method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,-and:
- 1) either restore the inoperable Channel (s)-to OPERABLE status within 7 days of the event, or
- 2) preparn and submit a Special Report to' the Commission -
pursuant to Specification 6.9.2 within 14 days following-the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 6), J$$1
TABLE 4.3-3 l'
RADIATION MONITORING INSTRUE NTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REOUIRED
-1.
AREA. MONITORS a.
Spent Fuel Pool Area
' Monitor S
R M
Note 1 b.
Containment High Range S
R Note 4 M
1, 2, 3, & 4 2.
PROCESS MONITORS a.
Containment
- i. ' Gaseous Activity a). Purge & Exhaust Isolation Note 2 R
Note 3-566 b) 'RCS Leakage Detection S
R M
1,2,3,64 11.
Particulate Activity a) RCS Leakage
' Detection S
R M
1, 2, 3, & 4 b.
Control Room Ventilation Intake Duct Monitor S
R M
ALL MODES c.
Main. Steam Line Radiation -
S R
M 1, 2, 3, & 4 Monitors Note 1 - With fuel'in:the spent fuel pool or building.
Note 2 - Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initiating containment purge operations and at least once per 12 bours during containment purge operations.
Note 3 - Within 31 days prior to initiating containment. purge operations and at least once'per 31 days during containment purge operations.
Note 4 - Acceptable criteria' for calibration lare provided 'in Table II.F.1-3 of NUREG-0737.
ARKANSAS - UNIT 2 3/4 '3-27 Amendment No. 53, JER
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M M MTEAI1YI RONIRQLS 1.-
Radiological Environmental Monitoring Sample Analysis, Specifjcation 3.12.1.
m.
Unplanned Offsite Release during one hour period of 1) more than I curle of-radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioicijne in gaseous effluents. This report shall be submitted within 30 days of the occurrence of the event and shall include the following information:
1.
Descriptjon of the occurrence.
2.
Identify the cause(s) of exceeding the limit (s). -
3.
Explain corrective action (s) taken to mitigate occurrence.
4.
Define action (s) taken to prevent recurrence.
5.
Summary of the consequence (s) of occurrence, n.
Inoperable Reactor Vessel Level Monitoring System (RVLMS),
Specification-3.3.3.6, Table 3.3-10 Item 14.
o.
Inoperable Main Steam Line Radiation Monitors, Specification 3.3, Table 3.3-6.
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- l 6.9.3 Routine radioactive ef fluent release reports covering the_ operating of the unit during. the previous 6 months of operations shall be submitted-within 60 -days af ter January 1 and July 1 of each year.
- A sing'le subraittal may be made for a multiple unit station. The submittal should combine'those sections that are common to all units at the station; however, for units with separate radwaste system, the submittal shall specify the releases of radioactive material from each unit.
_ UNIT 2 6-19a Amendment No.' $J, Pf,J23-
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