ML20066D643
| ML20066D643 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/05/1982 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20066D641 | List: |
| References | |
| NUDOCS 8211110467 | |
| Download: ML20066D643 (28) | |
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4 ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS (TVA BFNP TS 180)
BROWNS FERRY NUCLEAR PLANT i
UNITS 1, 2, AND 3 4
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UNIT 1 MI 1
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I TABLE 4.1.A REACTOR FR0ftCTION SYSTEN (SG/JG INSTamertAT105 FUNCTIONAL TESTS NINDER( FWICTIONAL TEST FREQUERCIES FOR SAFETT INSTE. AND CONTROL CIRCUITS Crees (2)
Functional Test Mista s Frequency (3)
Made Switch ta Shutdows A
Place Nede Switch in Shus wa Eack Refseling Detage i
h 1 Scram A
Trip Chamael and Alarm Every 3 Neaths IRN Eigh Flus C
Trip Chamael and Alarm (4)
Gace Per Week During Refueliny and Refere Each Startup Imeparative C
Trip Chamael and Alaru (4)
Dare Per Week During Refuelta t
and Before Each Startup APRN 4
Eigh Flus (15Z scram)
C Trip output talays (4)
Before Iack Startup and Useki h a Raquired ta he Operable Righ Flum B
Trip Output Relays (4)
Once/ Week i
Imoperative 2
Trip Outpet Ralsys (4)
Dece/Usek i
Dewascale E
Trip Output Relays (4)
Once/Veek Flev sina n
(6)
(6)
Eisk meset.c Pressure A
Trip th=1 and Alarm Once/Noath (1)
Eigh Drywell Preeevre A
Trip Cheemel and Alare
, once/ Neath (1)
Baseter taw Meter tavel (3)
A Trip Chamael and Alarm cace/ Neath (1)
Migh Water Level in Screa Discharge Tank A
Trip Chamael and Alarm Oncehtonth Turbine Condenser low Vacuun A
Trip Chamael and Alarm Once/ Neath (1)
Main Steau Line Righ Radiatios 3
Trip Channel and Alarm (4)
Once/ 3 Months (7)
TABt.F. 4.1.A (Continued)
Croup (2)
Functional Ten,(
Minteue Freevency (D Mata Steam Line Isolation Yalve closure A
Trip Chansel and Alaru Once/3 Months (7)
Turbine Control valve Fast Closure i
A TrtP Chamael and Alara Once/Moath (1) or Turbine Trip i
Turbine First Stage Pressure Permissive A
Trip Channel and Alaru Every 3-Noeths Turbine Stop Valve closure A
Trip Channel and Alors Once/Moeth (1) u l
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NOTES FOR TABLE 4.1.A 1.
Initially the minimum frequency for the indicated tests shall he once per month.
2.
A description of the three groups is included in the Bases of this specification.
3.
Functional tests are not required when the systems are not required to be operable or are operating (i.e., aircady tripped). If tegen are missed, they shall be performed prior to returning the systems to an operable status.
4.
This instrumentation is exempted from the instrument channel test definition. This instrument channel functional test will consist of injecting a sinulated electrical signal into the measurement channels.
5.
The water level in the reactor vessel will be perturbed and the corres-pending level indicator changes will be monitored. This perturbation test will be performed every month after completion of the monthly f'inctional test program.
6.
The 'unctional test of the flow bien network is performed in accordance with Table 4.2.C.
7.
The functional test frequency decreased to once/1 months to reduce challenges to relief valves per NUREG 0737, Teem II.K.3.16.
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I TARLE 4.2.4 SORVIILIANCE REQUIREMEJrTS FOR PRIMAJtY CONTAINMElif AND REACTOR BUILLING ISotATION INSTRUMENTATIOW runction Functional Test Calibration Frwquency Inst.rument Check Instrument channel -
( 13 (5) once/ day asactor low unter tavel (LIS-3-203A-D, SW 2-3)
Isotsument osannel -
(13 once/3 montre none Reactor High Pressure Instrument Channel -
(1) once/3 month once/ day Beactor 14w water Level (LIS-3-56A-D, SW 81)
Instrument channel -
(13 (5)
N/A Bigh Drywell Pressure (PS-64-56A-D)
Instrument Channel -
Once/3 months (27) g g, o,cofee, sigh Radiation Main steam Line Tunnel Instrument Channel -
once/3 months (27) oneen conths none to tm Pressure Main steaa Line Instrument channet -
once/3 months (27) oncan montas once/ day Righ Plow Maan Steam Line '
instrument enannel -
once/3 months (27) once/operatani eycle none Main Steam Line Tunnel sigh Temperatur.
Instrument channel -
(1) (14) (22) once/3 senths Beactor suilding ventilation once/ day (6)
Righ Radiation - Beactor tone e
MoTCS rot TASLES 6.2.A THROUCH 4.2.H (Con t inue d) 14 Upe'cale trip to functionally tested during functional test time as required by section 4.7.3.1.s and 4.7.C.1.c.
- 15. The flow bias comparator will be tested by putting one flow unit in
" Test" (producing 1/2 scram) and adjusting t;ie test input to obtain comparator red block. The flow bias upscale vill be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.
16 Perforned during operating cycle. Fortions of the logic to r.hecked mere f requently during functier.nl teste of the functions that p'roduce a red block.
12.
This calibration consiste of re'oving the function f ree service and m
perfern4ng an electronic calibration of the channel.
18.
Functional test is limited to the condition where secondary containment integrity le not required se specified in sections 3.7.C.2 and 3.7.C.).
19.
Functional test is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.1.c.
20.
Calibration of the comparator requires the inputs f rom both recirculation loops to be interrupted. thereby removing the flaw bias signal to the AFAM and PJM and scramming the reactnr. This calibration can only be performed durtag an outage.
21.
Logic tuet is limited to the time where actual operation of the equipment le permissible.
22.
One channet of either the reactee.one or refueling mone Reactor su11 ding Ventilation Radiation Monitoring System may be administratively bypassed for a period cot to exceed 'a hours for functional testing and calibration.
- 23. The Reactor Cleanup Systen Space Temperature monitors are RTD's that ferd a temperature euttch in the control room. The temperature evitch may be tested monthly by using a simulated signal. The RTL itself is a highly reliable instrument and less frequent testing to necessary.
24 This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).
25.
During each refueling outage, all acoustic monitoring channels shall l
be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.
26.
This instrunent check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refuelink outages).
I 27.
The functional test frequency decreased to once/3 months to reduce challenges to relief valves per NUREC-0737. Item II.K.3.16.
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i YASI.E 4.1. A REACTOE PROTECTION SYSTEN (SCIAN) INSTRUMENTATION FUNCTIONAL TESTS NMDCM FUNCTIONAL TEST FREQUSCIES FOR SAFETT INST 1. AND CONTROL CIRCUITS Craus (21 Functional Test Miniana Frequency (3)
Mode Switch la Shutdown A
Flace Mode Switch in Shutdown Each Refueltag Outage Manual Screa A
Trip Channel and Alarm Every 3 Months IRN High Flux C
Trip Channel and Alaru (4)
Once For Week During Refueliny and Before Each Startup Inopera tive C
Trip Channel and Alarm (4)
Occa Fer Week During Refuelta and Before Each Startup AFRM M
Righ Fluz (151 scram)
C Trip Output Relays (4)
Refere Each Startup and Week 1 When Required to be Operable Righ Flus B
Trip Output Relays (4)
Once/ Week Imoperative 2
Trip Outpet Relays (4)
Once/ Week Downscale 3
Trip Output Relays (4)
Once/ Week Flow Bias 3
(6)
(6) 1 l
Migh teactor Fressure A
Trip Channel and Alarm Once/ Month (1)
Righ Drywell Freasure A
Trip Channel and Alaru Once/ Month (1)
Reactor low Water level (Si A
Trip Chamael and Alarm
'Once/ Month (1)
High Water 14 vel in Screa Diecharge Tank A
Trip Channel and Alare Once/ Month Turbine Coodcasar low Vacuum A
Trip Channel and Alara Once/Nonth (1)
Nain Steam Line Righ Radiation R
Trip Channel and Alarm (4)
Once/ 3 Months (7) i
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TABLE 4.1.A (Continued)
Group (2)
Tunctional Tegg Minteum Trequency (3) l Main Steam Line Isolation Yalve closure A
Trip Channel and Alaru Once/3 Months (7) i Turbine Control valve Fast Closure A
Trip Channel and Alaru Once/Noath (1) or Turbine Trip Turbine First Stage Pressure Fermissive A
Trip ChEnnel and Alara Every 3 Months Turbine Stop Valve Closure A
Trip Channel and Alars Once/ Month (1) i s
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NOTF.S FOR TARLE 4.1. A
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1.
Initially the minimum frequency for the indicated tests shall be once per month.
2.
A description of the three groups is included in the Bases of this specification.
3.
Functional tests are not required when the systems are not required to he operable or are operating (i.e., already tripped). If tests are missed, they shall be performed prior to returning the systems to an operable status.
4.
This instrumentation is exempted from the instrument channel test definition. This instrument channel functional test will consist of injecting a sinulated electrical signal into the measurement channels.
5.
The water level in the res ; tor vessel will be perturbed and the corres-ponding level indicator changes will be monitored. This perturbation tent will be performed every month af ter completion of the monthly f'inctional test program.
6.
The unctional test of the flow bias network is performed in accordance with Table 4.2.C.
7.
The functional test frequency decreased to once/3 months to reduce challenges to relief valves. per NUREG 0737, Item II.K.3.16.
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i TABLE 4.7.A 50RVEILIAlfCE REQUIRE.MSNTS FOa PRIMARY CONTA.INME!TT AND It1 ACTOR 80!LLING IS01ATION INSTRUMENTATION runction Functional Test Calibration Frequency Instrument Check Instrument Channel -
(1)
(5) once/ day Reacter low Water 14wel (LIS 20 3 A-D, Stf 2-3)
Instrummat Oannel -
(1) once/3 months Reactor High Precoure none L strument channel -
(1) once/3 month Reactor Low Water level once/ day (LIS-3-56A-D, Sw 01)
Instrument osannel -
(1)
(51 N/A 81g 81 Drywell Pressure (PS 5 6 A-D)
Instrument channel -
once/3 months (27)
Sigh Radia tion Main Steam (5) oneefeay Line 1%Anel Instrument Channel -
Once/3 months (27)
CD Low Pressure Main Steam oneefs monene none Line Instrument Osannel -
once/3 months (27) oncen months High Flow Main Steam Line once/ day instrument Cnannet -
once/3 months (27)
Main Steam Line Tunnel Bagh once/operatin, e gje none Temperat.ru Instrunwnt Cnannel -
(1) tit) (22)
Reactor Sullding Ventilation once/3 montt.s once/ day (B)
B1gh Radia t1on
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Mote $ roR TASLt$ 4.2.A THRoUC11 4.2.H (Continued) 14 Ups'cale trip te functionally tested during functional test time es required by sec tion 4. 7. 8.1.s and 4. 7.C.1.c.
- 13. The flow bias comparator will be testd Sy putting one flow unit in
- Te a t ** (producing 1/2 scram) and adjusting the test input to obtain comparator rod block. The flow bias upscale will be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.
le.
Performed during operating cycle. Fortions of the logic le checked more f requently during functior.a1 teste of the functions that produce a rod block.
- 17. This calibrat tan consiste of removing the funetton f rom service and perforMng en electronic calibration of the channel.
18.
Functional teet is limited to the conditic,n where secondary containment integrity te not required as specified in sectione 3.7.C.2 and 3.7.C.3.
19.
Functional test is limited to the time where the SCT3 is required to meet the requirements of section 4.7.C.1.c.
20.
Calibration of the comparator requires the inputs from both rectrevlation loops to be interrupted. thereby reersving the flow bias signal to the APRM and 21 and scramming the reactor. This calibration can only be performed dort.ig an outage.
21.
Logic tuet to limited to the time where actual operation of the equipment le permissible.
22.
One channet of etther the reacter zone ur refueling tone Reactor Building Ventilation Radiation Monitoring System may be administrative 1y bypassed for a pertod not to exceed N havre for funettonal testing and calibration.
23.
The Reactor Cleanup System Space Temperature ronitors are RTD's that feed a temperature outsch in the control room.
The temperature evitch e.ny be tested conthly by using a etaiulated signal. The RTD itself to a highly reliable ins t ru..ent and less frequent testing is necessary.
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24.
This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueline, outages).
25.
During each refueling outage all acoustic monitoring channels shall be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.
26.
This instrunent check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).
27.
The functional tent frequency decreased to onec/1 months to reduce challenges to rolle f valves per HURIT.-07'37. Item II.K.3.16.
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UNIT 3 e
TABLE 4.1. A AEACTOR PROTECTION SYSTEM (SCRAM) INSTRUND(TATION FtH8CTIONAL TESTS n!NIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTR. AND COtfTROL CIRCUITS Group (23 runctional Test Minimum rreraency (Il main steam Line alp Radiation a
Trip channel and Alare get once/ 3 months (7)
Main steam Line Isolation valve Closure A
Trip Channel and Alarm Once/3 Months (7)
Turbine control valve rast closure or Trip Channel and Alarm Once/ Month (1)
Turbine Trip Turbine First stage Pressure Permissive A
Trip channel and Alara Every 3 Months Turbine stop valve Closure A
Trip Channel and Alass Once/ Month (1) i 0
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tNR'ES FOR TABLE 4.1.A Initially the minimum frequency for 'the indicated tests shall
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be once per month.
2.
A description of the three groups le included in the Bases of this specification.
3.
Functional tests are not required when the systems are not required to be operable or are operating (i. e., already tripped).
If tests are missed, they shall be performed prior to returning the systems to an operable status.
4 This instrumentation is exempted from the instrument channel-test definition. This instrument channel functional test will consist of injecting a simulated electrical signal into the measurement channels.
5.
The water level in the reactor vessel will be perturbed and the corresponding level indicator changes will be monitored.
This perturbation test will be performed every month after completion of the monthly functional test ex ogram.
6.
The functional test of the. flow bias network is performed in accordance with Table 4.2.C.
7.
Functional test frequency decreased to once/ 3 months to reduce the challenges to relief valves per NUREC 0737, Item II.K.3.16.
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l TAaLE 4.2.h 50RVamamCE REQUIREIEENTS FOR PRIMERY COIffAIIDEEME AES REACTOR SOILDING ISOIATION IMSTREMIEastATION Function Functional Test Calibration Fregosacy Isotrument Check Instrument Chamael -
(1)
(5) menctor Imv IInter Invol amoe/ day i
(LIS-3-203A-D, as 2-3) t Instremat C2hannel -
(1) ence/3 months acee asector E.igh Pressere Instrument Ctanael -
(1) once/3 month ance/ day teactor Imer hter Imvel (LIS-3-S6A-o, su 01)
Instrument th (1)
(S) pfa Righ Drywell Pressure (Ps-64-56A-Op Zoetrument Chamael.
Once/3 months (27) gS) fd.y Righ Radiation semia steam Line Temaal zastrument Channel -
once/3 months (27) ence/3 monthe acee i
Low Pzweeure Main Steam Line Instrument onannel '
once/3 months (27) ence/3 months ence/$ay Righ F1mer Ita1A Steam Line Instrument Channel -
once/3 months (27) ence/ operating cycle acae main ste,am Line Tennel algh a
1 Temperature Instrueent channel -
(1) tie) (22) ence/3 montas once/ day (8)
Reactor an11 ding ventilation Eigh Radiation - Reactor Sone l
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No7ES FOR TABLES 6.2.A THROUCil 4.2.H (Continued) 14 Upecele trip is functionally tested during functionet test time se required by section 4.7.3.1.s and 4.7.C.1.c.
- 15. The flew bles comparator will be tested br putting one flow unit in "Teet" (producing 1/2 ocram) and adjusting th. test input to obtain cooperator rod block. The flow bias upscale will be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.
16.
Performed during operating cycle. Fortions of the logic le c. hec,ked more f requently durins functional teste of the functions that produce a rod block.
17.
T41s calibrat tan consiste of removing the function f rom service and performing an electronic calibration of the channel.
18.
Functional test is limited to the condition where secondary containment integrity is not required se specified in sections 3.7.C.2 and 3.7.C.3.
19.
Functional test is limited to the time where the SCTS is required to meet the requiremente of section 4.7.C.1.c.
20.
Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flow bLas signal to the AFAN and RLM a,d scramming the reactor. This calibration can only be performed durt.ig an outage.
- 21. Logic test to 11mited to the time where actual operation of the equipment le pe rmiselbte.
22.
One channet of either the reactor sone or refueling zone Reactor Building Ventilation Radiation Honitoring System may be administratively bypassed for a period est to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.
- 23. The Reactor Cleanup System Space Temperature monitors are gTD's that feed a temperature switch in the control room. The temperature switch may be tested monthly by using a atmulated signal. The RfD itself is a highly reliable instrument and less frequent testing te necessary.
24.
This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).
25.
Durina each refueling outage, all acoustic monatoring channels shall he calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor, i
26.
This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outanes).
27 Functional test frequency decreased to once/3 months to reduce the challenges to relief valves per NUREG-0737, item II.K.3.16.
4 107
O ENCLOSURE 2 i
DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 180) 4
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Justification and Safety Analysis Item II.K.3 16 of NUREG-0737 calls for a comprehensive study to determine feasible means to reduce ti.e challenges to relief valves. One suggestion stated in item II.K.3 16 was to reduce the testing frequency of the main steam isolation valves. Item II.K.3 16 also states that "those chenges which are shown to reduce relief valve challenges without compromising the performance of the relief valves or other systems should be implemented."
These proposed technical specification revisions are a result of a feasibility study which indicates that testing frequency may be reduced without Lapacting overall system reliability. This will in turn produce a marked decrease in inadvertent reactor isolation events and scrams associated with testing. Besides reducing challenges to the relier valves by a significant and quantifiable factor, it follows that the general reduction in initiator events will have commensurate benefit in reducing challenges to other reactor protection and safeguard features.
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I*ITn0 DUCTION This report documents a study performed in response to NUREG-0737, item II.I.3 16 9hich requires an evaluation of the feasibility of reducing challenges to the relief valves. This study specifically addresses iten 3. 1. 81. 81 of the B'fR Owners' Group Evaluation of NUREG-0737, iten II.K.3 16, " Reduce 14SIV Testin.e, Frequency," as it applies to Brouns Ferry Nuclear Plant (letter from D. B. Uaters (BUROG) to D. G. Eisenhut (NRC) dated $1 arch 31, 1931). Reducing the ifSIV testing frequency will directly reduce the challent,es to the relief valves and, in return, reduce the likelihood of a stuck-open relief valve.
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DISCUSSION This study is to determine the feasibility of reducing the testing frequency of the main steam line isolation valves and associated instrumentation to reduce the challenges of the relief valves while still maintaining overall nystem reliability. During a typical 12-nonth operating cycle on each unit, there are approxinately 100 functional tests and 14 inte.qrated calibrations performed on instrumentation associated 91th the main steam line isolation logic.
Fron the Drowns Ferry nuclear Plant Unit Scram List, there have 5een approximately 41 inadvertent scrans or isolations in the history of Browns Ferry associated uith the I!SIVs and associated logic. Of these 33 have occurred while performing a surveillance instruction (SI).
Therefore, 80.5 percent of the forced scrans associated uith the MSIV logic have occurred as a result of an SI.
Conservatively assuming there have been 12 fu11.12-month cycles in the history of Browns Ferry units 1, 2, and 3, there has been an average of 2.75 forced scrams /isolations each. cycle as a result of a main 4
stean line instrunentation SI. This results in a probability of 0.0275/SI that an individual SI 9111 result in a scram. By reducing the number of functional tests performed during a cycle by over two-thirds, the nunber of unnecessary scrans coul.d be reduced to less than one scram each cycle. It follows directly that unnecessary J
challenges to relief valves and other safety systens ' rill be proportionally reduced. Table 1 contnirm proposad revisionn in the testing frequency for the functional tests on several main steam line instruments which uill result in the 1&ier scran probabilitv.
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. The existing testing frequency for instrunentation listed in table 1 was initially established by using the methodology described in the technical specification 4.1 bases. A conservative testing faequency of once each month 'ias established pendina, furthe" analyses.
Similarly, for the main stean line rad!ation monitor an initta1 testing frequency of once each week was set.
It is appropriate to show that by reducing the frequency of the functional tests listed in table 1, the overall safety of the systems will not he reduced. The Browns Ferry LER list for units 1, 2, and 3 indicates there have been ten LERs on minor setpoint deviations e.nd only two LERs of any significance discovered during scheduled sis.
The tuo najor Lens were results of fails Jensors. Note that no change in calibration frequency is being proposed.
To determine a new functional testing frequency using the technical specification 4.1 bases, the total number of operating hours and the total number of identi. cal components are needed. Table 2 contains the information on each surveillance instruction required, the M value calculated, and the recomnended testing interval found from figure 4.1-1 of the technical specifications using the M value and the nunbea of undetnoted failures. It is shoun that an interval of greater than 6 months is justified. Therefore, a required testing frequency of once each th"ee nonths is being proposed to maintain conservatism.
r
. In summary, from plant records there have been 33 forced scrans associated 'sith the specific functional ta.sts listed in table 1 trhile the sis detected only two equipment failurcs. This in itself would waarant a reduction in testing frequency. By reducin.g the MSly isolation testing frequency from onen each nonth to once aach 3 monthn for nain steam line isolation valve closure, main stnam line l'ow pressure, nain steam line 5tch flow, and nain steam line h.igh temperature, and fron once each week to once each 3 months fo" main stean line high andiation, it still remains unde" the recomnended frequency of six nonths as stated earlier and thus remains conservative. Therefore, the reduction of testing frequency will not aeduce the margin of safety in detecting failed equipnent belo the reconnended limit hut will inc" ease'the overall nargin of safety by reducine, the challenges to the relief valves and other syntems. Thin proposed testing frequency trill also increase the unit capacity factor as a result of fewer resulting scrams. Ancillary benefits from hur.an factors considerations included reduction in test activities by technicians and operators, minimization of abnornal system alignment durin?, testing, and reduced paperwork.
O
4 4.
COi!CLt!SIOil.9 The conclusion of this study is that the challenges to the relief valves can be reduced br reducing the testing frequency of the riain steam line instrumentation without reducing system reliability.
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TABif I
!!ain Steam Line Instrucientation e
Technical Specifintion SI No.
- Title, Functional Test Frequency Change Current Proposed 4.1.A-10 Main Steam Line Radiation !!onitor once/ week once/3 months Table 4.1.A 4.1.A-11 Main Steam Line Isolation Valve Closure once/ month once/3 months Table 4.1.A 4.2.A-6 Low Pressure 11ain Steam Line once/ month once/3 months Table 4.2.A 4.2.A-7 High Flow Main Steam Line once/ month once/3 months Table 4.2.A 4.2.A-8 Main Steam Line Tunnel liigh Temperature once/ month once/3 months Table 4.2.A
4
=
- n TADLE 2 ft = nT T = 105120 hours Number of s
Surveillance Identical Number of Instructinn Components (n)*
Failu*en Interv1188 II.1.A-10 12 0
1.26x106 6 rnonths i 6-
'6 months it.1.A-11 2fl 2
2.52x10 li.2.A-6 12 0
1.26x106 6 months 6
6 months li.2.A-7 48 O
5 05x10 li.2.A-8 IIB 0
'5.05x106 6 nonths
- Total number of conponents for all 3 units.
"' Interval from figure 11.1-1 of Brouns Ferry !!uclear Plant technical specifications.
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REFERENCES
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Brounc Perry Technical Specifications P.
Browna Ferry Scran List 3
Dro' ens Ferry LER List 18 Jacobs, I.:1., "Ifeliability of Enc,ineered Safety Features ss a Function of Testin:r, Faequency,a !!uclein % Ce ty, Vol. 9, :o. II, July-Aus,ust 1968, pp. 303-312
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