ML20077G720

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Reactor Vessel Level Monitoring Sys & Hot Leg Level Measurement Sys
ML20077G720
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 06/18/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20077G713 List:
References
NUDOCS 9107020200
Download: ML20077G720 (16)
v • d • e


Text

. _ .

i

. ANO-1 TECllHICAL SPECIFICATIOD l'ROPOSED CilANGED PAGES k

'l 9

.b 9107020200 910618 PUR P ADOCK 05000313 PDR

_ - - - - - - - - - - - - - _ . - ~ - - . - . - - - - .-

The Degraded Voltage Monitoring relay settings are based on the short term starting voltage protection as well as long term running voltago protection. The 4.16 KV undervoltage relay potpoints are based on the allowable starting voltage plus maximum system voltaan drops t a the motor terminals, which allows approximately 78% of motor rated voltage at tho mot or terminals. The 460V undervoltage relay sotpoint is based on long term motor voltage requirements plus the maximum feedor voltage drop allowance resulting in a 92% setting of motor rated voltage.

The OPERASILITY of the accident monitoring instrumentation ensures that sufficient informat.fon is available on selected plant parameters to monitor and acness these variables during mid following an accident. This capability is consistent with the recommendation of Regulatory Guido 1.97,

" Instrumentation for I.ight-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accjdent," December 1975 and NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short-Torm Recommendations."

Tito OPERABILITY of the chlorine detection system ensures that suf ficient capability is available to promptly detect and initiate protective action in the ovent of an accidental chlorine rolense. This capability is required to protect control ro.)m personnel and is consistent with the recommendations of Regulatory Guido 1.95. " Protection of Nuclear Power Plent Control Roes. Operators against an AccjJental Chlorfue Release,"

February 1975.

The subcooled margin monitors (SHM), core-exit thercoccuples (CET), Reactor vessel Level Monitoring System (RVLMS) and llot Leg Level Hensurement Systen.

(llLLMS) 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 recovely from 100. Additionally, this instrumentation aids in tracking react..r coolant 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 Reactor Vossal Level Monitor is provided as a means of Indicating level in the reactor vencel during accident conditions. The channel operability of the RVLMS is defined as a minimum of three sensors in the upper plenum region and two sensors in the dome region orntablo. When Roactor Coolant pumps are running, all except the dome sensors are interlocked to read " invalid" due to flow induced variables that may offset the sensor outputs. Tho channel operability of thn llLLMS is defined as a minimum of one wide range and any two of the narrow range transmitters in the sano channel operable. If the t equipment is inaccessible due to health and industrial safety concerns (for example, high radiation area, low oxygen content of the containment atmosphore) or dun to physical location cf the fault (for exemple, probe failure in thn teactor vessel), then operation may continue until the next scheduled refueling outage and a report filed.

i 1

)

\

\

l  ;

l Amendment No. ff, ff, 9J, JJf, J)), 43b j l

l - -

'Thn Ol'I:RAlill,1TY of t he Seismic Honitoring Instrurnontat ion ensur en that r.uf ficient capability is available to promptly determinn the mngnitudo of a snismic event nnd ovnlunto t he response of those fontures f wportant to safety. This enpability is required to permi roiapir lson o f t hn rnensu r ort rerponse to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10CTR Part 100. 1ho instrurnentation is consistent with the recommendnt ions of Safety Guide 12

" Inst rument ation for I:nrthquakn," published Hncch 19, 1971, and NURTG-0800 Section 3.7.4, "Soismic Instrun.cntation."

EEf1RLSCL FSAR Section 7.1 l'SAR, Section 2.7.6 Arnendment No. 43c

j Jable 313.1-1 (cont'dl  ;

i

)

OTHER SAFETY RELATED SYSTEMS (cont'd) 1 2 3 4 5  :

i No. of Operator action  !

channels Min. Min . if conditions of j No. of for sys- operable degree of column 3 or 4 i Functional Unit channels tre trip channels redundancy cannot be met

13. In core Thermocouples 6/ core quadrant N/A 2/ core quadrant 0 Note 22
(core-exit thermocouples)

. 14. Seismic Monitoring Instrumentatio, t I a. Triaxial Time-History

Accelerographs l i: t
1. ACS-8001, Unit 1 1 N/A 1 0 Note 27  !

i Containment Base (Slab, Elev. 335'*) l

)

i

2. ACS-8002, Unit 1 Top of 1 N/A 1 0 Note 27 [

j Containment, Elev. 511'6"  ;

i I Triaxial Peak Accelerographs  !

b.

l 1. 2XR-8347, Unit 2 Containment 1 N/A 1 0 Note 27 I 1 Base Slab, Elev. 336' 6"

2. 2XR-8348, Unit 2 Primary Shield 1 N/A 1 0 Note 27 l O/S Reactor Cavity, Elev. 336' 6"
3. 2XE-8349, Unit 2 Top of 1 N/A 1 0 Note 27 Containment , Elev. 531'6" l

i

  • With Unit I control room indication /or alarm i  !

J i l i C  !

l Amendment No. JJ6. 135, 45d1 I

i l  !

I Table 3.5.1-1 (cont'd) .

OTHER SAFETY RETATED SYSTEMS (cont'd) 1 2 3 4 5 No. of Operator action (
channels Min. Min. if conditions of

! No. of for sys- operable degree of column 3 or 4 I Functional Unit shennels tem trio channels redundancy cant.ot te met a

c. Triaxial Respouse-Spectrum Recorders i
1. 2XR-8350, Unit 2 Containment 1 N/A 1 0 Note 27  ;

Base Slab, Elev. 335' 6" l

(0/S Containment) i

> 15. Reactor Vessel Level Monitoring System 2 N/A 2 0 Note 28, 29' i 16. Hot Leg Level Measurement System (HLLMS) 2 F/A 2 0 Note 28, 29 t

, +

r

} l 4 i 4  ;

i

! i I

i i

t  !

! t I

i i 4

i l Amendment No. 45d2 [

I

I T_ahle 3.5.1-1 (cont'd) l

28. With the number of OPERABLE channels one less taan the minimum number of channels required to be OPERABLE:
a. If repairs are feasible, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWS within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b. If repair is not feasible without shutting down, operation may continue and a special report pursuant to specification 6.12.5 shall be submitted to the NRC within 30 days following the failure; describing the action taken, the cause of the inoperability, and the plc.ns and schedules for restoring the channel to OPERABLE status during the next scheduled refueling outage.
29. With the number of OPERABLE channels two less than the minimum channels required to be OPERABLE:
a. If repairs are feasible, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.

i

b. If repair is not feasible without shutting down, operation may continue and a special report I pursuant to specification 6.12.5 shall be submitted to the NRC within 30 days following the failure; describing the action taken, the cause of the inoperability, and the plans and schedules  ;

for restoring the channels to OPERABLE status during the next scheduled refueling outage.  ;

t f

I

[

[

i e

l i

l i

i t

t Amendment No. 117 45h

- ' - - - - ^ - - - - - -

i l

Jable 4.1-3 (cont'd.)  !

Channel Descrintien Check Test Calibrate Re-arks  !

t i

d. SG A High Range Level S M R j High-high  !:

I

e. SG B High Range Level S M R  !

High-high  !

57. Containment High P.inge D M R Radiation Monit rs i
58. Containment Tressure-High M NA R i i

I

59. Containment Water Level-Wide M NA R Range  ;

i

] 60. Low Temperature Overpressure NA R R i Protection Alarm Logic i i

t

! 61. Core-exit Thermocouples M NA R 62 Electronic (SCR) Trip Relays NA M NA ,

1 s

63. EVLMS M NA R f 1 i
64. HLLMS M NA R I

h0TE:

S - Each Shift T/W - Twice per Week R - Once every 18 months W - Weekly Q- Quarterly PC - Prior to going Critical if not l M - Monthly P- Prior to each done within previous 31 days [

D - Daily startup if not done NA - Not Applicable '

previous week SA - Twice per year ,

B/M - Every 2 months i

j

) I .

! ' . Amendrent No. 7J, PA, 75, JJ6, JJ7, 135, 72d

} I 2

i

I, k

r I

h. Inoperabic Fire Detection Instrumentation, Specification 3.5.5.2.

i

1. Inoperablo Fire Suppression Systems. Specifications 3.17.2, 3.18.2, and 3.19.2.

J. Degraded Aux 111ary Electrical Systems,-Specification 3.7.2.H.

k. Inoperablo Reactor Vessel Levol Monitoring Systems. Table 3.5.1-1
1. Inoperable Hot Leg 1,evel Measurement Systems, Tabic 3.5.1-1 b

l Amendment No. JJE, 146b l i

1 l

?,

1 i

i l

i 1

l 1

1 1

1 l'

I I I

i lj l

ANO-2 TECilNICAL SPECIFICATION l PROPOSED CllANGE PAGES l

'l 1

l k

i. >

f i .

5 ll 9

'f 4 -I i I i t a

i i

J -

1 a

d i

3

(

i i

N 1 i

k 4

J r

i i .

l -

1

!.-_.___.___..- - - . . _ . . . . , _ - - _ . . . _ - - , ~ . . , - . _ _ . . _ . - , _ . - , , , . _ , - , , - - , , , - . , - . , , . - . . , - . - - , - . . . . , . . . - , _ _ . . . _ . - -

_ _ _ _ _ _ _ . _ ~ . _ . _ _ . _ . . _ _ _ _ _ _ . . _ . . _ _ _ _ _ _ _ . _. _ __.. _ _

4 INSTRUH.ENTATI_off l

POST-ACCIDENT INSTRUMENTATION LililURQ CONIllIlQN FOR Ol'ERAUQN ,

3.3.3.6 '!he post-accident monitoring instrumentation channels shown in ,

Table 3.3-10 shall be OPERABLE. ,

AITLICABILITY MODES 1. 2 and 3.

ACTION :

a. As shown in Table 3.3-10.
b. The provisions of Specification 3.0.4 are not applicable.

E'RYEILLARGE_XLQUIREMENIS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPF9ABLE by performance of the CilANNEL CilECK and CllANNEl.

CALIBRATION operations at the frequencies shown in Table 4.3-10.

i l

l l

l h

i ARKANSAS - UNIT 2 3/4 3-39 Amendment No.

f i

TABLE 3.3-10 1 POST-ACCIDENT MONITnRING INSTRU m 7ATION l

! MINIMUM l CHANNELS

]

l INSTRUMENT OPERABLE ACTION l 1

] 1. Containment Pressure (Normal Design Range) 2 1 l l

! 2. Containment Pressure (High Range) 2 2  :

4 j 1

3. Pressurizer Pressure 2 1  ;

4 Pressurizer Water Level 2 1  ;

l

5. Stesa Generator Pressure 2/ steam generator 1
6. Steam Generator Water Level 2/ steam generator 1
7. Refueling Water Tank Water Level 2 1 [

t t

8. Containment Water Level - Wide Range 2 2 l
9. Emergency Feedwater Flow Rate 1/ steam generator i I i
10. Reactor Coolant System Subcooling i Margin Monittr 1 1 f
11. Pressurizer Safety Valve Acoustic j l Position Indication 1/ Valve 1 l l
12. Pressurizer Safety Valve Tail Pipe [

i Temperature 1/ Valve 1 l

)

! r l

i ARKANSAS UNIT - 2 3/4 3-40 Amendment No. 7,23,29,63,117, f

. t I

[

, + , - f _ , , - - -

- y - _ _

i 1

d TABLE 3.3-10 (cont'd)

POST-ACCIDENT MONITORING INSTRUMENTATION ,

I MINIMUM CHANNELS INSTRUMENT OPERAPLE ACTION  ;

I

12. In Core Thermocouples (Core-Exit Thermocouples) 2/ core quadrant 1 i

14 Reactor Vessel Level Monitoring System (RVLMS) 2 3, 4 l t

i i

Action 1: With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SliUTDOWN -

l within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.  ;

r I

) Action 2: With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days, or be in 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 />.  !

If only one channel is inoperable and containment entry is required to restore the inoperable channel,  !

the channel need not be restored until the following refueling outage.  !

I

! Action 3: With the number of OPERABLE channels one less than the minimum number of channels required to be  ;

OPERABLE: ,

. a. If repairs are feasible, restore the inoperable channel to OPERABLE status within 7 days or be in

, at least HOT SHUTD0hN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.  !

I b. If repair is not feasible without shutting down, operations may continue and o special report  ;

i pursuant to specification 6.9.2 shall be submitted to the NRC within 30 days following the

failure; describing the action taken, th. cause of the inoperability, and the plans and schedule i t

for restoring the channel to OPERABLE status during the next scheduled refueling outage. i t

! Action 4: With the number of OPERABLE channels two less than the minimum channels required to be OPERABLE:

a. . If repairs are feasible, restore at least one inoperabic channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 3

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 />.

l b. If repair is not feasible without shutting down, operation may continue and a special report i pursuant to specification 6.9.2 shall be submitted to the NRC within 30 days following the j , failure; describing the action taken, the cause of the inoperability, and the plans and schedule  ;

for restoring the channels to OPERABLE status during the next scheduled refueling outage.

^

j

. i ARKANSAS - UNIT 2 3/4 3-40a Amendment No. F1,

i I i j TABLE 4.3-10 (con't) i

! POST-ACCIDENT MONITORING INSTRIENTATION St'RVEILLAN2 EEOUIRE*'ENTS -

I I  !

j CHANhTL CHANNEL

INSTRUMENT CHECK CALIERATION I
13. Ir. Core Thermocouples (Core-Exit Thermocouples) M R 1 .

I 14. Reactor Vessel Level Monitoring System (RVLMS) M R i 1

i l,

0 i

i i t ,

r

} I 3  :

i I

i r

I i

i I

s I

4 i

T i

s 1 ARKAN3AS - UNIT 2 3/4 3-41a Amendment No. M ,

I v -- ,--2 --

ADMINISIRAT1YILCONTKQLS

1. Radiological Environmental Monitoring Sample Analysis, .

Specification 3.12.1. )

] m. Unplanned offeito Rolonan during one hour peritxl of 1) more than I curio of radioactivo material in liquid effluents, 2) morn I

than 150 curies of noble gas in gaseoun of fluent n, or 3) more than 0.05 curfen of radioiodine in gaseous offluents. Thin i report shall be submitted within 30 days of the occurrence of I thn event ard shal? include the followirg information.

l

1. Descript ion of the occurrenco.
2. Identify the cause(s) of exceeding the limit (s).
3. Explain corrective action (s) taken to mitigate occurronen.
4. Do' inn action (s) taken to provent recurrence. l

. 5. Summary of the consequence (s) of occurrence,

n. Inoperabic Reactor Vessel Lavol Monitoring System (RYLMS),

Specification 3.3.3.6, Tablo 3.3-10 item 14.

SEMI-ANNUAL. RAD 10 ACTIVE EFFLUENT RELEASE REPORI*

6.9.3 Routina radioactive effluent release reports covering the operating -

of the unit during the previous 6 months of operations shall be submitted within 60 days af ter Jenuary 1 and July 1 of each year.

  • A single submittal may be mado for a multiplo unit station. a r.c submittal should combine those sections that are common to all units at t the atation; however, for units with separato radwasto system, the I submittal shall specify the releason of radioactive matorial from each unit.

r l

ARKANSAS - UNIT 2 6-19a Amendment No. ff, 74,

w. , -- , , 7. , . , ,.m~.<,,...-,...-o,--,r.-c~ . . . - . ----,.--v--.

. yy,-.---.-.,.,.. . ~ - - - , ,-, ,- ,.~- ,, -..-- ., ._ __-4

1H11RUMENTAIJOS MSES -

3/i d M , POST-ACCIDENT INSTRUMENTATIQN Tho OPERABil.1TY of the post-accident in.trumentation ensures that sufficient information is available on selected plant parameters to monitor and assess ther.n variables following an accident. This capability is consistent with the recommendations of Regulatory Guido 1.97,

" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions Durit.g and Following an Accident," December 1975 and NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short Term Recommendatlons."

The Reactor Vessel I. cycl Monitor is provided as a means of indicating level in thn reactor vessel during accident conditions, A minimum of two operablo level sensors in the upper plenum region and *>ne operable level sensor in the dome region are required for RV1.MS channel operability.

When Reactor Coolant Pumps are running, all except the domo sensors are interlocked to road "invalfd" due to flow induced variables that may offset the sensor outputs. If the equipment is inaccessible due to health and industrial safety concerns (for examplo, high radiation area, low oxygen content of the containment atmosphero) or due to physical location of the fault (for example, probo failure in the reactor vessel), toer. operation may continue until the next scheduled refueling outage and a report filed.

3/4.3.3.7 CHLORINE DET];CTION SYSTEMS The OPERABILITY of the chlorino detection system ensures that sufficient capability is available to promptly detect and initiata protectivo action in the event cf an accidental chlorino release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guido 1.95 " Protection of Nuclent Power Plant Control Room Operators Against an Accidental Chlorino Releaso," February 1975.

3/4.3.3.8 FIRE DEIECTION INSTRUMENTATION OPERAbiblTY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locato fires in their early stages. Prompt detection of fires will reduce the potential for damaga to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, except for detectors located in the containment during MODES 1 and 2, the establishment of frequent fire patrols in the affected areas as required to provido detection capability until the intperable instrumentation is restored to OPERABILITY.

ARKANSAS - UNIT 2 P 3/4 3-3 Amendment No. 12, 17, ff,

1EEIKV11MIAIl0N EASEL. _

2/A 2 3.9 RAD 10ACILYLGA5110VS JHINLlill&11RV11LtillIl0N The radionctive gnscous effluent instrumentation in provided to monitor and control, na r.pplicable, the releases of radionet (ve materials in gaseous effluents during nctuni or potential relennes of gnscous effluents. The nintm/ trip setpoints for these inntruments shall he calculat ed in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CI'R Part 20.

For the rn licactive gaseous ef fluent inst rumentation surveillance requirements, the CilANNE!, PUNCT10NAl TEST demonst rates that control room alarm annunciation occurs if any of the following condit ions exist :

ARKANSAS - UNIT 2 B 3/4 3-3n Amendment No.

_ _ _ - _ . _ _ - _ _ _ _ _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20077G720&oldid=2764781"