ML18025B374

Tech Spec 3.2 & Tables 3.2.F & 4.2.F for Instrumentation Surveillance

ML18025B374
Person / Time
Site:	Browns Ferry
Issue date:	03/03/1981
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025B373	List: ML18025B372 ML18025B374
References
NUDOCS 8103110440
Download: ML18025B374 (21)

Text

UNIT 1

PROPOSED CHANGES

TABL~ 3.2.F Surveillance Instrumentation Minimum g of Operable Instrument Channels Instrument g H M 37 H2M 39 Instrument Drywell ff Concentration Type Indication and Ra e

O.l <<20fr Notes lgM 38 Suppression Chamber lg Concentration 0.1 - 2$

PdI-64-137 Pdz-64-138 Drywall to Suppression Chamber Differential pressure Indicator 0 to 2 paid (1) (2)

(5) 2 (1 per header)

LM-85-85A, B, C,

D Ultrasonic Water Level Monitor on the Reactor Scram Di ~charge Header Alarm at 1.25

.25 in.

+

or instrument malfunction (6) (7)

(1)

Fron and

~ftcr the date that one of those paral >>ter ~ ia reduc>>d to on>> indication, continu>>d op>>ration ia permissible during the aucc>>>>ding thirty days unless such instrumentation ia sooner made operable.

(2)

From and after th>> date chat one of these parameters is not indi-cated in the control room, cont'nucd operation is pernissibi.c durins the succeeding seven days unlcsa such instrumentation ia sooner l>>ade operable.

(3) If the requirements of notes (1) and (2) cannot be met, either the requirements of 3.5.H shall be complied vith or an orderly ahutdovn shal.l bc initiated and thc reactor shs)l be in a Cold Condition vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4)

These surveillance instruments are considered to.be redundant to each other<

(5) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in six (6) hours, an orderly shutdown shall be initiated 'and the reactor sha11 be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(6)

The continuous monitoring system shall be operable during reactor operation except as specified below.

The ultrasonic water level monitor consists of four transducer

channels, tvo per reactor scram discharge header.

Xf the number of operable channels becomes less than one per header, within eight, hours perform a manual check for vater in the SDV and institute procedures for a 1

h k of the SDV each shift and following each scram until should the system is o.ier;bxe.

When not fully operable, the system s ou be used to the extent practical in addition to the manual checks.

If the system is not operable within seven days, the frequency'of the manual check should be increased to once every four hours.

If the system is not operable within 30 days, the plant shall be shut down.

(7)

Immediate operator action vill be taken upon receipt of alarm.

80

TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUEt~CY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequenc Instrument Check

1) Reactor Hater Level

2) Reactor Pressure

3) Drywell Pressure

4) Drywell Temperature

5) Suppression Chamber Air Temperature

6) Suppression Chamber Hater Temperature

7) Suppression Chamber Hater Level

0) Control Rod Position

9) Neutron Monitoring

10) Drywell Pressure (PS-64-67) ll) Drywell Pressure (PS-64-58B)

12) Drywell Temperature (TR-64-52)

13) Timer (IS-64-67) 14)

CAD Tank Level Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift NA

~ NA NA NA Once/day

15) Containment Atmosphere Monitors 16)

Drywall to Suppression Chamber Differential Pressure Once/6 Once /6 months months Once/day Each Shift 17)

Ultrasonic hater Level Monitor in the Reactor Scram Discharge lleader Once /6 months (24)

NOTES FOR TABLES 4.2.A THROUCII 4.2.H Continued 14.

Upscale trip le functionally tested during functional test time as required by section 4.7.B.l.a and 4.7.C.l.c.

16.

The flow,bias comparator will be tested by putting one flow unit in "Test" (producing 1/2 scram) and adgusting 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 pr'educe a rod block during the operating cycle.

Performed during operating cycle.

Portions of the logic is checked more frequently during functional tests of the functions that produce a rod block.

17.

This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.

Functional test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3,7.C.3.

19.

Functional test Ls limited to the time where the SCTS is required to meet the re quirements of section

4. 7.C. l.c.

20.

Calibration of the comparator. requires the inputs-from both r'ecirculation loops to bc interrupted, thereby removing the flow bias signal to the APRM and RBH and scramming the reactor.

This calibration can only be performed during an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

2 ~

One channel of either the reactor zone or refueling zone Reactor Building Ventilation Radiation Honitoring System may be administratively bypassed for a period not 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 Spnce Temperarurc monitors are RTD's that feed a temperature switch in the control room.

The temperature switch may be tested monthly by using a simulated signal.

The RTD itself is a highly reliable instrument snd less frequent testing is necessary.

24.

In addition, once per operating cycle and during startup after plant outages where maintenance may have taken place near the water level monitoring

system, the channel shall be calibrated and functionally tested by introducing water into the scram discharge header using the manual VT system as a standard.

110

3 ~ 2 BASCS For each parameter monitored, as Listed in TabLe 3.2.F, there are tvo cha'nnels of Instrumentation except as noted.

By comparing readings betveen the tvo channels, a near continuous surveillance of instrumenc performance is available.

Any deviation in readings uill initiate an early recalibra-tion, chereby maintaining the quality of the 'instrument readings.

Instrumentation is provided for isolating the control room and initiating a pressurizing system chat processes outside aiz'efore supplying it to the control room.

An accident signal that isolates prirary containmenc vill also automatically isolate the control room and initiate the emergency presour irat ion system.

In addition, there are z'adiation monitors in the

. normal vcnr.ilation system that vill isolate the control room and initiate the emergency pressurization system.

- Activity required to cause automatic actuacion is about one mRem/hr.

Because of the conozanc surveillance and control exez'cised by TVA over the Tennessee'Valley, flood levels of large mangicudes can be predicted in advance of their actual occurrence.

In all cases, full advantage vill be taken of advance vazning to take appropriate action uhenevar reservoir levels above normal pooL are predicted;

hovever, the plant flood protection ia always I'n place and does not depend in, sny uay on advanced varning.

Therefore, during flood conditions, the plant vill be permitted to operate until vatcr begins zo run across the top of the pumping station at elevat'on

565, Seismically qualified, redundant level suitches each povez'ed from a separate division of pouer are provided at thc pumping station to give main

~ control room indication of this condition."

Ac that time an orderly shutdovn of the plant uill be initiated, al.though surges even to a depth of several feet over the pumping station deck vill roc causa the loss of che main con-denser circulating vater pumps.

The operability of the meteorological instrumencacion ensuzes that sufficient mereozological daca is available for estimating potenrial radiation dose to che public as a result of routine oz'ccidental release of radioaccive materials to the acmosphere.

This capability is required to evaluace rhe need for iniciating protective measures to protect the health and safety of the public.

The operability of the seismic instrumentation ensures that sufficient capabilicy is available co promptly determine the magnitude of a seismic evenr.

and evaluate che response of those features important to safety.

This capabilicy is requized Lo permit comparison of the measured response co that used in t'e design basis for Brovns Ferry lfuclear P'ant.

The instrumentac,ion provided is consistent vith spec'fic portions of the recommendations'f Regulatory Guide l. l2 "Instrumentation for Earthquakes."

The ultrasonic water level system on the re'actor scram discharge header detects the presence of a preset level of water in the header.

and initiates an alarm when that level is reached.

The monitoring system includes four cransducers,,

two of which are mounted on each of the two scram discharge header banks.

Each cranszlucer is connected co an ultrasonic signal processor which provides output to an annunciator in the control room in the event of lzilch water level or inscrzmzent failure.

. 115

= UNIT 2 PROPOSED CHANGES

TABID 3.2.F Surveillance Instrumentation Hinimum g oi'perable Instrument

-Channels Instrument 0 lgld 94 H~M 104 Instrument Drywell and Torus Hydrogen Concentration Type Indication and Ra e

O.l - 20f, Notes 2 (1 per header)

LH-85-85A, B, C,

D Ultrascnic Mater Level Yionitor on the Reactor Scram Di ~charge Header Alarm at 1.25.25 in.

+

or instrument malfunction (6) (7)

Fdz-64-137 Pdl-64-138 Drywall to Suppression Chamber Differential pressure Indicator 0 to 2 paid

'(1) (2)

(5)

MOTKS FOR TABLE 3.2.F 0

?ro~ and after the dace that one of these para~ster

~

Ls reddced to one indication, continued operation Lo pcraissibic durinE the succeeding thirty days unlese such instrumentation is sooner cade operable.

(2)

Fron and after the date that one of these parameters is not indi-cated in the control roon, continued operation is permissible during the succeeding seven days unless such Lnstru"Icn a on Ls sconer remade operable.

(3) If the requirements of notes (1) and (2) cannot be cet, either the requirements of 3.5.H shall be ceaplied vi h or an orderly shutdovn shall bc init'ated and the reactor shall be in a Cold Condition Mithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4)

These surveillance instruments arc considered to.be redundant to each other.

(5)'f the requirements of notes (1) and (2) cannot be met, and if one of the indicat'ons cannot be restored in six (6) hours, an orderly shutdovn shall be initiated 'and the reactor shall be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(6)

The continuous monitoring system shall be operable during reactor operation except as specified belov.

The ultrasonic water level monitor consists of four transducer

channels, tvo per reactor scram discharge

header, Tf the number of operable channels becomes less than one per header, within eight'ours perform a manual check for water in the SDV and institure procedures for a manual check of the SDV each shift and folloving each scram until the system is o.ierabLe.

When not fully operable, the system should be used to the extent practical in addition to the manual checks.

If the system is not operable within seven

days, the frequency'of the manual check should be increased to once every four hours.

If the system is not operable within 30 days, the plant shall be shut down.

Immediate operator action vill be taken'pon receipt of alarm.

80

TABLE 4.2.F IlINIblUbi TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check

1) Reactor l7ater Level

2) Reactor Pressure

3) Drywell Pressure

4) Drywell Temperature

5) Suppre sion Chamber. Air Temperature

6) Suppression Chamber tVater Temperature

7) Suppression Chamb r Mater Level

8) Control Rod Position

9) Neutron Honitoring

10) Dr~iel1. Pressure (PS-64-67) ll) Drywel1 Pressure (PS-64-58B)

12) Drywell Temperature (TR-64-52)

13) Timer (IS-64-67) 14)

CAD Tank Level Once/6 months Once/6 months Once/6 months Once/6 months.

Once/6 months Once/6 months Once/6 months

. NA (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months L'ach Shift Each Shift Each Shift Each Shift t

Each Shift Each Shift Each Shift Each Shift Each Shift NA HA NA Once/day

.15) Containment Atmosphere ftonitors 16)

Drywall to Suppression Chamber Differential Pressure Once/6 Once

/6 months months Once/day Each Shift 17)

Ultrasonic Nater Level Monitor in the I'cactor Scram Discharge lleader Once (6 months (24)

NOTES FOR TABLES 4.2.A THROUGH 4.2.H Continued 14.

Upscale trip ie functionally tested during functional test time as required by section 4.7.B.l.a and 4.7.C.l.c.

15 ~

The flow bias comparstor vill be tested by putting one flov unit in "Test" (producing 1/2 scram) and adgusting the test input to obtain comparator rod block.

The flov bias upscale vill be verified by observing a local upscale trip light during operation and verified that it vill produce a rod block during the operating cycle.

16.

Performed during operating cycle.

Portions of the logic is checked more frequently during functional testa of the functions that produce a rod block.

17.

This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.

Functional test is limited to the condition vherc secondary containment integrity is not required'as specified in sections 3.7.C.2 and 3.7.C.3.

19.

Functional test is limited to the time vhere the SGTS is required to meet the requirements of section 4.7.C.l.c.

I 20.

Calibration of the "comp'arator requires the inputs from both recirculation loops to bc interrupted, thereby removing the flov bias signal to the APRN and RBN and scramming the reactor.

This calibration can only be performed during an outage.

21.

Logic test is limited to thc time vhcre actual operation of the equipment is permissible.

22.

One channel of either thc reactor xone or refueling xone Reactor Building Ventilation Radiation Honitoring System may be administratively bypassed for a period not 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 RTD's that feed a temperature svitch in the control room.

The temperature svitch may be tested monthly by using a

s imulated signal.

Thc RTD itself is a highly reliable instrument and less frequent testing is necessary.

24.

In addition, once per operating cycle and during startup after plant outages where maintenance may have taken place near the water level monitoring

system, the channel shall be calibrated and functionally tested by introducing water into the scram discharge header using the manual UT system as a standard.

110

3.2 BASCS For each parameter monitored, as listed in Table 3.2.F, there are tvo

<<ha'dnels of instrumentation except as noted.

Dy comparing readings betveen the tvo channels, a near continuous surveillance o'f instrument performance is available.

Any deviation in readings vill initiate an early recalibra-tion, thereby maintaining the quality of the.'instrument readings.

Instrumentation is provided for isolating the control room and initiating a pressurizing system that processes outside air before supplying it to Cha control room.

An accident signal that isolates primary containment vill also automatically isolate the control room and initiate the emergency pressurization system.

In addition, there are radiation monitors in the normal ventilation system that vill isolate the control room and initiaCe the emergency preieurization system.

Activity required to cause auComatic actuation ie about one mRem/hr.

Because of the constant surveillance and control exercised by TVA over the Tenncasce Valley, flood levels of large mangitudea can be predicted in advance of their actual occurrence.

'ln all cases, full advantage vill be taken of advance varning to take appropriate action vhenevar reservoir levels above nornul pool are predicted;

hovever, the plant lood protection fa-always. in place and. does noC depend in, any" way on advanced'arning.

Therefore, during flood conditions, the pLant vill be permitted to operate until vatcr begins to run across the top of the pumping station at elevat'on 565.

Seismically qualified, redundant level svitches each powered from a separate division of pover are provided at thc pumping station to giv main control room indication of this condition.

At that time an orderly shutdovn of the plant vill be initiated, al.though surges even to a depth of several feet over the pumping station deck villrot cause the loss of the main con-denser. circulating vater pumps.

The operability ot'he meteorological instrumentation ensures that sufficient meteorological data is available for estmating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate he need for initiating protective measures to protect the health and safety of the public.

The operability of che seismic instrumentation ensures that sufficient

. capability is available co promptly determine the magnitude of a seismic event and evaluate the response of Chose features Mpnrtant to safety.

This capability is required to permit comparison of thc measured response to that used in the design basis for Brovns Ferry tfuclear Plant.

The instrumentation provided is consistent vith spec'fic portions of the recommendations'f Regulatory Guide 1.12 ulnstrumentotion for Earthquakes."

V The ultrasonic water level system on the re'actor scram discharge header drtects the presence of a preset level of water in the header and initiates an alarm when that level is reached.

The monitoring system includes four transducers, two of which are mounted on each of the two scram discharge header banks.

Hach tron. duccr is connected to an ultrasonic signal processor which provides output to an annunciator in the control room in the event of jii h water level or instrument failure.

115

UNIT 3 PROPOSED CHANGES

TAB[8 3i2.F Surveillance Instrumentation Minimum g of Operable Instrument Channels Instrument 0 lQH 94 N2H 76 104 Instrument Drywell and Torus Nydrogen Concentration Type Indication O.l - 20[(

Notes 2 (1 per header)

LM-85-85A, B, C,

D Ultrasonic Liater Level Monitor on the Reactor Scram Di~,"harge Neader Alarm at 1.25

.25 in.

+

or instrument malfunction (6) (7) 2 PdI-64-137 PdI-64-138 Drywall to Suppression Chamber Differentia1 pressure

~

Indicator 0 to 2 paid (1) (2) (5)

~S FOR TABLE 3 2 P (1)

Prom and after the date that. one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

(2)

From and after the date that one of these parameters is not indicated in the contxol room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable (3) If the requirements of notes (1) and (2) cannot be met, either the requirements of 3 5.8 shall be complied with or an orderly shutdown shall be initiated and the reactor shall be in a Cold Condition within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

(0)

These surveillance instruments axe considered to be redundant to each other.

(5) If the requirements of notes (1) and (2) cannot be met, and jf one of the indications cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be jn a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(6)

The continuous monitoring system shall be operable during reactor operation except as specified below.

The ultrasonic water level monitor consists of four transducer. channels, two per reactor scram discharge header.

If the number of operable channels becomes lass than one per header, within eight hours perform a manual check for water in the SDV and institute procedures for a manual check of the SDV each shift and following each scram until tl<<..y" tum is o>or:.I>ie.

Mhcn not fully operab]c, the system should I>(> u::( ~ d to the extent practical in addition to, tho manual chocks.

If tho system is not operable within seven

days, the frequency of the manual check should be increased to once every four hours.

If the system i" not operable within 30 days, the plant shall be shut down.

(7)

Im>>>ediate operator action will be taken upon receipt of alarm.

TABLE 4.2.F NI~!UH TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE I11STRUllENTA"'ION Instrument Channel

1) Reactor Hater Level

2) Reactor Pressure

3) Drywell Pressure Calibration Frequency Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Gnce/6 months

'nce/6 months (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 Once

/6 months months

4) Drywell Temperature

5) Suppre"sion Chamber. Air Temperature

6) Suppres io>> Chamber Hater Temperature

7) Suppression Chamber Hater Level

8) Control Rod Position

9) Neutron 1!onitoring

10) Drywell Pressure

{PS-64-67) ll) Drywell Pre sure (PS-64-58B)

12) Drywall Temperature (TR-64-52) 13)

Timer.

(IS-64-67) 14)

CAD Tank Level

15) Containment Atmosphere Monitors l6)

DryMell to Suppression Chamber Differential Pressure Instrumen=

Check Lach Shift Each Shift Each Snift Each Shift Hach Shift Each Shift Each Shift Each Shift Hach Snift NA NA Once/day Once/day Hach Shift 17)

Ultrasonic <;.ater Level Monitor in the Reactor Scram Discharge Ileader Once./6 months (24)

BOOTES FOR TABLES 4.2.A T1IROUCll 4.2.ll Continued 14.

Upscale trip is functionally tested during functional test time as required by section 4.7.B.l.a and 4.7.C.l.c.

15.

The flow bias comparstor will be tested by putting one flow unit in "Test" {producing 1/2 scram) and adjusting che test input to obtain camparacar rod block.

The flow bias upscale will be verified by abeerving a local upscale trip light during aperation end verified that ic will produce a rod block during the operating cycle.

16.

Performed during operating cycle.

Portions af the logic is checked more frequently during functional testa of the functions that produce a rod block.

17.

This calibracian consists of removing the function fram service and performing an electronic calibration of the channel.

18.

Functional ceec is limiced to che condition where secondary containment integrity is noc required'es specified in sections 3.7.C.2 and 3.7.C.3.

19

~

Functional case is limited to the time where the SCTS ie required to meet the requirements of section 4.7.C.l.c.

20.

Calibration af the camparator requires the inputs fram both recirculation loops co be interrupted, thereby removing the flow bias signal to the APRM and RBM and scramming the reactor.

This calibration can only be performed during an outage.

21.

Logic test ie limited to the time where actual operation of the equipment is permissible.

22.

Onc channel of either the reactor zone or refueling zone Reactor Building Ventilation Radiation Monitoring System may be administratively bypassed for a period noc 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.

Thc Rrnccar Cleanup Sysccm Spncc Temperature aenicars are RTD's that feed e cwnpcracure switch in the control room.

The temperature switch may be tested monthly by using a simulated signal.

The RTD itself is a highly reliable instrument end 1css froquenc testing is necessary.

24.

Zn addition, once pcr operating cycle and during startup after plant outrages whore maintenance may have taken place near the water level monitoring

system, the channel shall bc calibrated nnd functionally tested by introducing water into the scram discharge header using the manual UT system as a standard.

107

The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a siesmic 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 Browns Ferry Nuclear Plant.

The instrumentation provided is consistent with specific portions of the recommendations of Regulatory Guide 1.12 "Instrumentation for Earthquakes.

The. ultrasonic water level system on the rc'actor scram discharge header dr toots thc presence of a prcsct level of water in thc header and initiates an alarm when that level is reached.

The monitorinp system includes four transducers, two of which are mounted on each of the two scram discharge header banks.

Hach transducer is connected to an ultrasonic signal processor which provides output to an annunciator in thc control room in the event of pigh water level or instrument failure.