ML20073J010
| ML20073J010 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/26/1994 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML19304C590 | List: |
| References | |
| NUDOCS 9410060175 | |
| Download: ML20073J010 (309) | |
Text
{{#Wiki_filter:Docket N3. 50-277 Ucense No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 ATTACHMENT 3A MARKUP OF CHANGES AND NEW PAGES FOR TS 3.1 (Unit 2) Ust of Pages Affected: 35 Page replaced 36 Page replaced 36a Page deleted 37 Table 3.1.1 38 Table 3.1.1 # 39 Table 3.1.1 (Notes) 41 Table 4.1.1 42 Table 4.1.1 43 Table 4.1.1 (Notes) 44 Table 4.1.2 45 Table 4.1.2 46 Table 4.1.2 (Notes) 5 94o926 podOOj8f[K05000277
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l PBAPS-SURVEILLANCE REQUIREMENTS ' Y LIMITING CONDITIONS'FOR OPERATION f 4.1 REACTOR PROTECTION SYSTEM 3,1 REACTOR' PROTECTION SYSTEM Applicability: pplicability:. Applies to the surveillance '
-Applies to the instrumentation and. of the instrumentation and associated devices which initiate associated devices which :
initiate reactor scram. (areactorscram. Objective l Objective . , To specify the' type and To' assure the operability frequency of surveillance
.of the_ reactor protecti.on
- to be applied to the system. protection instrumentation.
[ Specification: Specification: j A. Instrumentation systems ~ fi. When there is fuel in the vessel shall be functionally :
, the setpoint, minimum number
'. tested and calibrated '
" of trip systems, and minimum as indicated in Tables number of instrument channels 4.1.1 and 4.1.2 ;
that must be operable for respectively. each position of the reactor > mcde switch shall be as given L in Table 3.1.1. - ' I . B. DELETED !
. B. _The designed system response times from the opening of the k r sensor contact up to and )
including the.. opening of;the gg @ trip actuator contacts shall - not exceed 50 milliseconds. - Otherwise, the affected trip system shall be placed in the tripped condition, or-the. action listed in Table ' r _ 1pued Afe# Pap 36 i(3.1.1 functionfor the shall specific trip be taken. i P i 35 Amendment No. 63, 70, 71, 76, 192 e h
PBAPS r UNIT 2 UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Reactor Protection System (RPS) 4.1 Reactor Protection System A. The RPS instrumentation for each trip function A. Each RPS instrument channel shall be in Table 3.1.1 shall be Operable; and, there demonstrated Operable by performance of a shall be two Operable or tripped trip systems channel functional test and channel calibration for each Trip Function. at the Frequencies shown in Tables 4.1.1 and 4.1.2, respectively. The designed system response times from the Response time measurements (from the opening of the sensor contact up to and opening of the sensor contact up to and including the opening of the trip actuator including the opening of the trip actuator contacts shall not exceed 50 milliseconds, contacts) are not part of the normal instrument test. The RPS response time of each reactor Applicability: trip function shall be demonstrated to be within its limits once per operating cycle. According to Table 3.1.1. Conditions and Reauired Actions: (1)(2) 1 With one or more channel (s) required by Table 3.1.1 inoperable in one or more trip functions, place the inoperable channel or associated trip system in trip within 12 hours.
- 2. With one or more trip functions with one or more channels required by Table 3.1.1 inoperable in both trip systems, place channel in one trip system in trip or place one trip system in trip within 6 hours.
- 3. With one or more automatic trip functions or two or more manual trip functions (Mode Switch in Shutdown, Manual Scram and RPS Channel
' Test Switches) with RPS trip capability not maintained, restore RPS trip capability within one hour.
- 4. If the required actions and associated completion time of Action 1 or 2 or 3 are not met, take the action required by Table 3.1.1 for the Taip Function.
, (1) When a (.hannelis placed in an inoperable status solely for performance of required Surveitiances,initiction of these Actions may be delayed for up to 6 hours provided the associated trip function maintains RPS trip capability. (2) An inoperable channel or trip system need not ce placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the required time, the Action requis ed by Table 3.1.1 for that trip function shall be taken immediately. f . . 2840030300
- ^
PEAPS (,,
/ ~' LIMITING CCNDITIONS FOR OPERATICN SURVIILLANCI RIOUIREMENTS -- r 7
( C. When it is determined that a channel has failed in the unsafe condition, the other RPS channels that r.cnitor the same variable shal'1 be -
}
functionally tested -
. in=ediately before the trip system containing the failure {
t4 \ -s { N is tripped. The trip syscom centaining the unsafe failure . may be placed in the untripped condition during the pericd in which su-veillance testing is being perior=ed on the c::her RPS channels. The. trip system may he'in the untripped pcsitien for nc =cre that eight hours per functional trip pericd for *M s testing. ( .
.iD D. Reacecr protecticn Svsten ' , gC. ..
~...i . Reacecr Pcwer succiv Prceectien System Pcwer Scrolv ' li")
1**Reacec: Protection System 1 **The icilewing EPS pcwer pcwer Supply: supply (MG se ) protective devices shall b'e functionally tested at least once every One trip train
- per RPS MG set six ncnths and calibrated may he in the bypassed or ence each refueling cc: age.
inoperative condition for a . ; i ceried cf 72 hours. If this
~
cendition cannot be satisfied, , , Acceptable l c if bcth trip trains are Device Setting y inoperative, the RPS bus shall - 113 + 2 Volts I I be transf erred to th'e alternate Undervoltage overveltage 131 g 2 Volts ! source er de-energi=ed within 30-minutes. Underfrequency Underfrequency 57 E: i .2 E: Ti=e Del'av. 6 sec .+ 1 sec !. C
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36 - Amendmant No. 75, 99/101 , June 21, 1984 .
c e r8M3 Unit 2 ' I,IMITING CONDITIONS POR OPERATION
. - ~ . . . -
SURVETT.I.ANCE REQUIREMEN;s l l' .; 200
' Cno trip traino of the'RPS _ _ _ _ _ _ _
.2** The folicwing RPS alternate .__ , , - -~~ _ \
alternate pcwer supply may !
. , 1 be'in the bypassed or power supply protective i
' 7j -incperative cenditica fc.r, devices shall Me functienall u1~l 4 a period of 72 hcurs. I'f this . tested'at least once every r ; conditica cannet be satisfied,. , months and ca11 braced once ! cr if both trip t' rains are each r,efueling cutage.
. . ,' inoperative, the RPS bus shall .
. ' : .he tranaf erred to the RPS MG
- ' set or de-energized within .
Acceptabl.
'.30 minutes. .
u-
. Device settine i 4
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' ' Underveltage 113 + 2 vo
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.Overyc1tage 131 7 2 Vc;
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Underfrequency 57 E: + .'
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. Undervolta e
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'A ' rip train censists cf cne breaker, one underveltage relay , cne y,- . (MG set only), and the associated Icgic.overveltage relay, cne und Effaccicve-upen-insnMen of-the-protective tr.ip-devices % A
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e PBAPS-p UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS 3.1 Reactor Protection System (continued) 4.1 Reactor Protection System (continued) B. N/A B. Deleted r p h - C. N/A C. Deleted D. Reactor Protection System D. Reactor Protection System Power Supply Power Supp!v i- D.1 Reactor Protection System Power Supply: D.1 The following RPS power supply (MG set) protective devices shall be functionally One trip train
- per RPS MG set may be in tested at least once every six months and the bypassed or inoperative condition for a calibrated once each refueling outage.
period of 72 hours. If this condition cannot be satisfied, or if both trip trains are Acceptable inoperative, the RPS bus shall be Device Settina transferred to the alternate source or de-energized within 30 minutes Undervoltage 11312 Volts Overvoltage 13112 Volts i Underfrequency 57 Hz i .2 Hz Underfrequency Time Delay 6 see i 1 see D.2 One trip train
- of the RPS alternate power D.2 The following RPS alternate power supply supply may be in the bypassed or protective devices shall be functionally inoperative condition for a period of 72 tested at least once every six months and hours. If this condition cannot be satisfied, calibrated once each refueling outage.
or if both trip trains are inoperative, the , RPS bus shall be transferred to the RPS Acceptable MG set or de-energized within 30 minutes. Device Settina Undervoltage 11312 Volts Overvoltage 13112 Volts Underfrequency 57 Hz i .2 Hz Undervoltage Time Delay Max. 4 secs.
# A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic, f
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{ 2-(j. PBAPS- b ' Unit 2' Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes In which Number of
, of Operable Function Must Be Instrument Instrument Trip Level Setting Operable Channels Action Channels Trip Function Provided by (1) per Tri Refuel Startup Run Design Items System -
0 - (7) 1 1 Mode Switch In x x x 1 Mode Switch A Shutdown (4 Sections) 2 1 Manual Scram x x x 2 Instrument A Channels 3 3 IRM liigh Flux s120/125 of Full x x (5) 8 Instrument A Scale Channels i O' 4 3 IRM Inoperative x x (5) 8 Instrument A Channels . 5 2 APRM liigh Flux (0.66W+71%-0.66aW) x 6 Instrument A or B (Clamp 0 120%) Channels , (12) (13) 6 2 APRM (11) x x x 6 Instrument A or B Inoperative Channels 22.5 Indicated (10) 6 Instrument A or B k 7 2 APRM Downscale on Scale Channels g 8 2 isPRM liigh Flux s15% Power x x 6 Instrument A
@ Channels
" in Startup V.
? 9 2 liigh Reactor $1055 psig x(9) x x 4 Instrument A Pressure Channels g 4 Instrument 2 liigh Drywell $2 psig x(8) x(0) x A 10
'd gy Pressure Channels
- 2 Reactor low 20 in. Indicated x x x 4 Instrument A l 11
'y." Water Level Level Channels YN
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_ . . . , _ _ . . . ~ _ . . . . , - - . . . . . . .-.....,,-m._ , . . _ ~ . _ , , . . . . .
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O >- . ue tgacion pa;TECTION SY31Ent-(Star.') INSTiUnlENTATIDH REQUICEMENT Nu on
- Modse in which Number of
. u Minlosem No. g ,&" of Operelate funct ion uual be Instrument co o Instrument Trip Level Operable
- Chennels *Actlen rt Channele Irlp Funcitan Settine Prowlded , .(l) o y [' Item
. per.Trl System l) ,
fiefuel Sterlup Run by Deelen
- 0) .
12 2 tiloh Water 8.evel 150 Gallone M(2) M^ M 4 Instrument A In serem Discheroe Channelo - y. i.,s i,ument vol..me
'l3 3 Turbine Condenser 123 in. lie. X 4 Instrument A er C
. Low Vacuum Vacuuse - Channels .
4 2 Noin steen Line fl5 M Hermal N N .M 4 Instrument A . ellch medlet ten Full Power Channele
$" Sachereund %
15 [ h Meln Steen Line fl01 Velve M(8) nqtrument A !b . Isolellon Velve Closure ' ' * - Channels .
-g Closure
- ta En I ,
18 2 1serhine Control 5004Pe850 pelg N(4) 4 I ns t ru ment A or D Velve Feet Closure Control Gil Pree- Channele { sure Seewoon rest - Closure Solenold . and Disc pump [ Velve
/ b 17 4 1:erbine Stop *l0E Velve M(4) A Instrument A or D Velve Classere Closesre ,
Channele
-- o . -. ,__._ .
, __-3 le 2 R Ps c h ,,,, a x x x 4 IAJ A TJ GJiLu % A' '
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NOTES FOR TABLE 3.1.1 W--- M " " ~
- 1. -(*Ihere shall be two operable or tripped trip systems for eacB .-~ - -
'% l. function _.fTf the mIMIEchinumber of operable sensor channels 4 ,[h for a trip system cannot be met, the affected trip system u @' shall' be placed in the safe (tripped) condition, or the ouNi 7 f sppropriate actions listed below shall .be taken.f
- _ . . (y (2 *"[/
- p. .
A. Initiate insertion of operable rods and_ complete insertion of all operable rods within[four hoursL[ B. ' Reduce power level to IRM range and place mode switch in the start up position within(8 hours ((Q
'e x L C. Reduce turbine load and close main steam line isolation L valves within M . -(h 6 ,u -
D. Reduce power to less than 30% rated. .ud5% E s.
. 2. Fernissible to bypass, in refuel and shutdown positions of the reactor mode switch.
L 3. Deleted. jW 4 . Bypassed when reactor thermal power is less than 30% of rated Q, - as indicated by turbine first stage pressure,
- n. 5. IRMs.are bypassed when APRMs are onscale and the reactor mode switch is in the run position.
- . 6. The design permirs closure of'any two lines without a scram
'being initiated.
-7. When the reactor is suberitical and the reactor water temperature is.less than 212 degrees F, only the following L
- trip functions need to be operable.
t A. Mode switch in shutdown [ I B. Manual scram 3 -C. . High flux IRM D. Scram discharge instrument volume high level
- 8. Not required to be operable when primary centainment integrity is not' required.
9 . -. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel. {. s.. Amendment No. 33, 708, I2I, 188
~
-39
y - Insert 1 for Page 39: Note 1 for Table 3.1.1 If the required actions and associated completion time of Specification 3.1.A, Actions 1 or 2 or 3 are not met, take the action listed below for the affected trip function as required by Table 3.1.1. 1 e I see
[
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- f. UNIT 2[ %
y 4 ". 1. TADI.E 4,,1.1 REACTOR PHOTECTIOH SYSTEH (SCRAH) , INSTRUMENT FUNCTIONAL TESTS
, HINIHUH FUNCTIONAI. TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS '
- ~
Group (2) Functlona1 Test Hinimum Frequenoy (3) Hode Switch in Shutdown A Place Hode Switch in
~
Each re' fueling outage. Shutdown w~ gQQ Hanual Scram A Trip Channel and Alarm Every 3 months. I RPG Channel Test Switch A Trip channel and Alarm dery ref4e_bng_outake) or af ter channel maintenance.
. IDH
-h Ill g h r i u x
- C Trip Channel and Alarm One per week during -
\ (4) refueling or startup and before each etartup.
Inopera tive C Trip Channel and Alarm (ti) Once per week during O refueling or startup O and before each startup. W
$ APHH
.g
'g liigh Flur
, Inoperative D1 Bl Trip Output Relaya (4) 'Once/ week. het/3 1 m. ,g ro.
Trip Output pelaya (4) Once/ week r-r' D wnocale Flow Dlan D1 Trip Output Relaya (4) _ nce/ week.) <r >
/
}.
HI I'l tilgh Plux in Startup or Refuel Calibrate Flow Dian(4) Signal (4)Once/ month (I_I)d__l-R
\.
C C Trip Output Helays Once per week' uring O ' refueling or startup and before each startup.! O ligh neactor Preasure (6) Trip Channel and Alarm (4) 11 2 Eifery 1 month (1D . Illgh Drywell Prennure (6) !/r 11 2 Trip channel and Alarm (4) Every I month (1)., Itcactor I.nw Water Iervel (5) (6) 11 2 Trip Channel and Alarm (II) <Every 1 month ( 1) '.
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Unit 2 TABI.E 4.1.1 (Cont'd) ; ,, .f x REACTOR Pit (YrECTION SYSTEM (SCRA'H) INSTRUMENT FUNCTIONA1, TEST 8 'T
.o H1HIMUM FUNCTIOllAI. TEST FRE0llENCIES FOR SAFETY INSTilUMENT AND CONTROL CIRCU1TS 3
01 b.
.o b Group (2) Functional Test Minimum Frequency (:
u \ . N F Z lllph Water Level In Scram A Trip Channel and Alarm Every 1 month. g Discharge Instrument, Volume , m - Turbine Condenser Low Vacuum (6) 11 2 Trip Channel and Alarm (4) Every 1 month (1) Hain Steam Line Illgh Radiation D1 Trip Channel and Alarm (4) Once/ week.
- Main steam Line Isolation ! A Trip Channel and Alarm Every 1 month (1).
p;. Valve Closure ! Turbine Control Valve A Trip Channel and Alarm Every 1 month. EllC 011 Pressure = Turbine Fkret Stage Pressure A Trip Channel and Alarm Every 3 months ( 1 ) .f Pernlesive - Turbine Stop Valve Closure- A ', . Trip Channel and Alarm Every 1 month (1).
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UNIT 2
+
J.- ' PIAPS
= .
I; NOTES FOR TAELE k.1.1
- h C V *
- 1. _ Initishy cace every mc=th. The ec=;ilatic=F1:str=ent failm-
- rate data may include data cbtained frc= cther boiling vater reacters ,
fer which the same desis: inst = ment c;erates in .a= envirec=ent s'h to tSat of PPAPS. The fai1=e rate data must te reviewed and appreved . ' 1 (b7_ the IEC prior to any t kege in the c=ce-a-ccath frequenc7f - -
~
- 2. A description of esc 5 cf the grcups is. i=cluded in the 2ases of this
- Specificatic=. .. . t
- 3. Functic:a1 tests are =ct required c= the part of the syste= that is =ct .
. regired to te cperable er are tripped. ,,-
m 4 If tests are =issed c= parts =ct required to te c;erable er are tripped, - then they shall te perfer=ed prier to retu=iss the s7ste= to an c;erable
~
state.s.
' h. This 1:str=e=ta+5c= is e=e=pted frc= the instr =ent e b =- el test
'derd ' tics. This instr =ent eS=- el f=ctic:al test vill censist of i=jecting a s -'=ted d
electrical siscal into the nessure=ent channels. m 5 The vater le rel in the reacter vessel vill te pert =ted a=d the cer es- ! ~
;cading level d-d' ester changes vill te me itered. This pert = hatic:
test v4 te perfc=.ed every =c th after ec=pletic: cf the r=ctic:a1
-test progrs=.
- 6. These c5=- els ec sist of analeg tm 'tters,1:e.ienters and electrcnic trip units. I:str=ent checks shall te perfc=ed cace per f.ay. ,,
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-TABLE 4.1.2 .
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION-MINIMUM CAllBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CH
~
Calibration Minimum Frequency (2). Instrument Channel Group-(t) Comparison to APRM on. Maximum frequency once C IRM High Flux' per week. Controlled Shutdown . APRM High Flux Twice per week. ..
.B1 Heat Balance :
- Output Signal With Standard Pressure Every eighteen months.
Flow Bias Signal B1 l l Source TIP System Traverse Every 6 weeks. 81 l.PRM Signal Standard Pressure Source Once per operating B2 liigh Reactor Pressure cycle. ; Standard Pressure Source Once per operating B2 High Drywell Pressure cycle. Pressure Standard Once per operating 82
- Reactor low Water Level cycle.
{ A Water Column Every refueling outage. h High Water Level in Scram 9 Discharge Instrument Volume Standard Vacuum Source Once per operating B2 z Turbine Condenser Low Vacuum cycle. A Note (5) Note (5)' , 5 Main Steam Line Isolation Valve c Closure ;; Standard Current Source (3) Every 3 months. B1 ' g- Main Steam Line High Radiation Every 6 months.
' E A Standard Pressure Source j
Turbine first State Pressure Permissive , Y .j _,._...____.,_....,_.m--.._. . . _ .
. . - . . . . . . . . . . . , ~ . . . , ,
fr (- ,
.i f f ^ \.
g y , Unit 2 i- { TABLE 4.1.2 ' (Cont'd. )
~
3
.@ REACTOR PR&rECTION SYSTEM (SCRAH) IySTRUMENT CALIRRATION 1
E HINIHUH CALIDRATION FREQUENCIES FOR BEACTOR PROTECTION INSTRUMENT CllANNELS . o ,
- e .
O e
. Instrument Channel Group-(1) Calthration (4) Hinimum Frequency (2) e H
%) .
Turbine Control Valve Fast A . Standard Pressure Source Once per operating Closurc 011 Pressure Trip cycle. u . N M Turbine Stop Valve Closure A Note (5) Note (5) . N
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NOTES FOR' TABLE 4.1.2 . l.-
. A dancripticn.cf thran groups is inclu. dad in the bases of this specification.
p;
.g
. Calibration test is not required en the pa -t of the system
- r. S2. .
that are not re* quired to be operable or are faipped but'is N@S"~~ _ required prior to' return to service.
- 3. ;
The current source provides an instrument channel alignr.ent. Calibration using a radiation source shall be made each refueling outage. i
- - _ . ~
'4. _ . , _ _
Response time is not a part of the routine instrument channel) - st but will be checked once per operating cycle.j g ,
- 5. Physical inspection and actuation of these position switches . ;
will be performed during the refueling outages.
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APRIL 1973 . f
Dscket N3. 50-278 License No. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 ATTACHMENT 3B - MARKUP OF CHANGES AND NEW PAGES FOR TS 3.1 (Unit 3) List of Pages Affected: 35 Page replaced 36 Page replaced 36a Page deleted , 37 Table 3.1.1 l 38 Table 3.1.1 39 Table 3.1.1 (Notes) 41 Table 4.1.1 42 Table 4.1.1 43 Table 4.1.1 (Notes) 44 Table 4.1.2 45 Table 4.1.2 46 Table 4.1.2 (Notes) 1
s= . .
~
l; UniB 3 [ PBAPS, SURVEILLANCE REQUIREMENTS . , LIMITING CONDITIONS FOR OPERATION 4.1 REACTOR PROTECTION SYSTEM 3.1 REACTOR PROTECTION SYSTEM' N
'~
r Applicability:- ANiieability:
^
Appliesto$heinstrumentationand Applies to the surveillance of the instrumentation and associated devices which initiate associated devices which a retctor scram. )& initiati reactor scram. Objective f Objective . To assure the operability To specify the type and of the reactor protection frequency of surveillance : to be applied to the system. protection instrumentation. ; Specification: (Specification: ~
~
A. Instrumentationsystems) k Vfien there 5's~ fuel in the vesse K t_he setoointJminimum numDer shall be functionally j
' + '- ~ of trip systems, and minimum tested and calibrated as indicated in Tables T ." number of instrument channels 4.1.1 and 4.1.2 that must be operable for each position of the reactor respectively mode switch shall be as given in Table 3.1.1.
B. The' designed system response k-
'\
B. DELETED times from the opening of the sensor contact up to and \ ,e including the opening of the N Jd w trip actuator contacts shall @g - exc DJ!illisecondsd t erwi'se, thTTffiEtid tHi;~Q system shall be placed in I\ C-- the tripped condition, or the action listed in Table 3.1.1 for the specific trip (functionJhalLhe_taken 35 >*nt No. (4, 69, 7J,184 b- . OCT 18 m3 9
PBAPS UNIT 3 QMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Beactor Protection System (RPS) 4.1 Reactor Protection System A. The RPS instrumentation for each trip function A. Each RPS instrument channel shall be in Table 3.1.1 shall be Operable; and, there demonstrated Operable by performance of a shall be two Operable or tripped trip systems channel functional test and channel calibration for each Trip Function. at the Frequencies shown in Tables 4.1.1 and 4.1.2, respectively. The designed system response times from the Response time measurements (from the opening of the sensor contact up to and opening of the sensor contact up to and including the opening of the trip actuator including the opening of the trip actuator contacts shall not exceed 50 milliseconds. contacts) are not part of the normalinstrument test. The RPS response time of each reactor Applicability: trip function shall be demonstrated to be within its limits once per operating cycle. According to Table 3.1.1. Conditions and Reauired Actions: (1)(2)
- 1. With one or more channel (s) required by Table 3.1.1 inoperable in one or more trip functions, place the inoperable channel or associated trip system in trip within 12 hours.
- 2. Wth one or more trip functions with one or more channels required by Table 3.1.1 inoperable in both trip systems, place channel in one trip system in trip or place one trip system in trip within 6 hours.
- 3. Wth one or more automatic trip functions or two or more manual trip functions (Mode Switch in Shutdown, Manual Scram and RPS Channel Test Switches) with RPS trip capability not maintained, restore RPS trip capability within one hour.
- 4. If the required actions and associated completion time of Action 1 or 2 or 3 are not met, take the action required by Table 3.1.1 for the Trip Function.
(1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated trip function maintains RPS inp capability. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.1.1 for that trip function shall be taken immediately.
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p . .. 4C 5 LIMITING CONDITIONS FOR OPERATION' - SURVEILLANCE REQUIREMENTS
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. C.f.When it.is.de. term.ined that a channelihas: failed in the 3
' ~
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.unsa'fe .condit'icn, .the other
. > _ RPS channel 5'that' monitor the . same ivariable .shal'1 be .
.. functionally tested- )'
i==ediately'before the trip i n , _3 system containing the failure l V is tripped. .The trip sys tem ' containing the unsafe failure, may be placed in the untripped condition during the pericd- ,
' in which surveillance testing ,
is being performed on the otheri RPS channels. The. trip system
=ay be in the untripped position for no more that eight hours y Iper functional trip periedf this testing y p*-%, - n .. - . -w.. " . ~. . . _ . . . , " . . . . . , ~ ~ ~ -
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> D . Reacter Protecticn System D. Reacecr Protecnicn Svstem '
- g.
Power Su==lv Pcwer Su=cly
- tis- i W i ,
1**Reacter Protection System 1 **The follcwing RPS power Pcwer Supply: supply (MG set) prc:ective devices shall b'e functionally ) tested at least once every ( One trip train
- per.RPS MG set six =enths and calibrated )
may be in the bypassed or .ence each refueling cutage. inoperative conditien for a . g pericd cf 72 hours. If this / condition cannot be satisfied, . Acceptable ;s or if both trip trains are Device settine inoperative, the RPS - L( (j be transferred to th,ebus alternateshall Undervoltage 113 + 2 Volts source or de-energized within overvoltage 131 2 Volts ); 30 minutes. Underfrequency 57 E: t .2 E: ' Unde frequency (
.(A - Ti=e Del'ay 6 sec + 1 sec ! -
w- - _~ -~ a e -{ . i P t y .. - -
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( u( W LTi fJ f x_. ? C. $ c P L o )- . w 7 O ' Amend =ent No. 75, 99 /101 June 21, 1984 .
~7- . cii . . - - . 9" Unit 3 - g LIMITING CONDITIONS POR OPERATION 6' GURVEILI.ANCE REQUIREMENTS 7 . n , z;. 2@e: Cna;st' rip.trhin9)cf1tha RPS 280 - The follcuing RPS nitornate x- -r .alternateipewer; supply may . power supply preeective . /? Y' :be.jin{the bypassed or devices .shan. be functionally -) tested at least once every aix ! $ ; X *'~ inoperative
' a;pefied 'of .72" -condition hours. for If this months and. calibrated once :
/ condition.cannot be. satisfied, each refueling cutage. !
or if both trip trains are - l
! inoperative,.the.RPS bus shall [
be transferred'to the RPS HG Acceptable setJor de-energized within Device. . Seteine
. 30 minutes. _, . !
Undervcitage 113 + 2 vel:sl Overvcitage 131 7 2 Vc1:s\ Underfrequency 57 E: + .2 EI - undervcitage Time Delay Max. 4 secend,
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l .~. . \ l D A trip train censists of one breaker, one underveltage relay, one overvoltage relay, one underfrequency relay, one ti=e delay relay ,,j (MG set only), and the asscciated icgic. - #
-)
Q C* Ef fadi v u -upon-i-nstaMi-thM--cFthe- proteecive-trip-d ev i c e s . s N l i .
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icendent No. IQI,123 3fa (Trtm)C . (YU ur" Ji .Y April 6, 198E (M"hL 3 / ~' u-l
PBAPS UNIT 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS , 3.1 Reactor Protection System (continued) 4.1 Reactor Protection System (continued) . B. N/A B. Deleted , C. N/A C. Deleted D. Reactor Protection System D. Reactor Protection System Power Supply Powe,Supolv The following RPS power supply (MG set) D.1 Reactor Protection System Power Supply: D.1 protective devices shall be functionally One trip train
- per RPS MG set may be in tested at least once every six months and calibrated once each refueling outage.
the bypassed or inoperative condition for a period of 72 hours. if this condition cannot be satisfied, or if both trip trains are Acceptable inoperative, the RPS bus shall be Device Settina , transferred to the alternate source or de-energized within 30 minutes Undervoltage 11312 Volts Overvoltage 131 i 2 Volts Underfrequency 57 Hz i .2 Hz Underfrequency ; Time Delay 6 sec i i see D.2 One trip train
- of the RPS alternate power D.2 The following RPS alternate power supply f
supply may be in the bypassed or protective devices shall be functionally inoperative condition for a period of 72 tested at least once every six months and
! hours. If this condition cannot be satisfied, calibrated once each refueling outage.
or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS Acceptable i MG set or de-energized within 30 minutes. Device Settina l 1 Undervoltage 113 i 2 Volts Overvoltage 131 i 2 Volts Underfrequency 57 Hz i .2 Hz Undervoltage Time Delay Max. 4 secs. i. A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic. l
- i. -
1 i ip - 1 1 t L'
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. L PBAPS l s Unit 3 Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Hinimum No. Modes In which Number of
, of Operable Function Hust Be Instrument Instrument Trip I.evel Setting Operable Channels Action Channels Trip Function Provided by (1)
Refuel Startup Run Design per Tri Items System e () 1 1 Mode Switch In x x x 1 Mode Switch A Shutdown (4' Sections) 2 1 Hanual Scram x x x 2 Instrument A Channels 3 3 IRH liigh Flux 5120/125 of Full x x (5) 8 Instrument A Scale Channels 4 3 IRH Inoperative x x (5) 8 Instrument A d, Channels , 2 APRH liigh Flux (0.66W+71%-0.66aW) x 6 Instrument A or B 5 ' (Clamp @ 120%) Channels ' (12) (13.) 2 APRH (11) x x x 6 Instrument A or B 6 Inoperative Channels 22.5 Indicated (10) 6 Instrument A or B y 7 2 APRM Downscale on Scale Channels g x x 6 Instrument A
.f 8 2 APRH liigh' Flux s15% Power.
Channels f, in Startup liigh Reactor $1055 psig x(9) x x 4 Instrument A
& 9 2 Channels Pressure uw x 4 Instrument A 3.* 10 2 liigh Drywell $2 psig x(8) x(8) ,
Pressure Channels Reactor low 20 in. Indicated x x x 4 Instrument A M 11 2 Channels Water Level Level [d m w p I t
i g M unut O g,, . TcJ;lo 3.4.1 l, t CEr.CTOR PZ3TECTIDH 5YSTES (5CIAH) ..s5TiUMENTOTIDH CEQUIZE;:EZT o 1(g ,, Minimum No. Modee in which Number of -
~
C) p of Operable Functlen Must be Instrument
'8 PP Instrument Trip Level Operable Channele Action ,
c5h Chennale Irlp Functlon Setting . Prevloed .(t). 03 2 per 1rl Refuel Stortup Run by Deelen
" ["D l Item System! I) (7) .
td o
$2 2 Hlgh Water Level 450 Gallone X(2) X X 4 Instrument A a, in Scree Discharge Channele
, Instrument Volume C*'
. 13 2 Turbine conooneer 123 in. Hg. X 4 Instrument A or C Low Vacuum Vacuum Channele ca l
. l4 2 Hein Steam Line el5 M Hormel X X X 4 Instrument A
- HIOh Redletion Full Power Channels
. Bechground ---
15 f8 4 Main Steam Line Isoletion Velve
<10% Velve Closure MI6) (S Instrument Chennale A "
Closure la 2 f.srbine Control 500eP<a50 pelo M(4) 4 Instrument A or D Velve Feet Cleeure Control Oil Pree- Channele l eu . .et...n ,.st j e Closure Solanald t : and Disc Oump v.i.. . i
}l7 4 Turbine Stop elas Velve M(4) 8 Instrument A de,D i volve Closure llosure . Channele 1 - -
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- V '
. . -- or
. - -eri pped tiiip_ systems _for_eacle ;
1. {Thereshall,he_two_operablefunctiond (If the minimum number or operable' sensoz'~Eh _ ffor a trip system cannot be met, the affected trip system {t r gS, shall be placed in the safe (tripped) condition, or the '3 !
, appropriate actions listed below shall be taken. LM \ - ok }
( ~W :,,1 ) A. Initiate insertion of operable rods and complete '%jp insertionofalloperablerodswithin(_ourhour B. Reduce power. level to IRM range and place mode switch in , the start up position within B t hoursA m C. Reduce _ turbine load and close main steam line isolationA p(f -
, k m m ')
valves within p hours) ~ _ _ _ _ _ _ .
- _- m
=.
D. Reduce power to less than 30% rated,V d4W ^*'2'h t
- 2. Permissible to bypass, in refuel and shutdown positions of ,
the reactor mode switch. ,
- 3. Deleted. }
'g; - 4 ~. Bypassed when reactor thermal power is less than 30% of rated ; f as indicated by turbine first stage pressure,
- 5. .IRMs are' bypassed when APRMs are onscale and the reactor mode switch is in the run position. !
- 6. The design permits closure of any two' lines without a scram .
being initiated. - l
- 7. Vnen the reactor is suberitical and the reactor. water ;
temperature is less than 212 degrees F, only the following ; trip functions need to be operable. , A~. Mode switch in shutdown j B. Manual scram C. High flux IRM i D. Scram discharge instrument volume high level
- 8. Not required to be operable when primary contain=ent ;
integrity is not required. l i
- 9. Not required to be operable when the reactor pressure vessel '
-( F ' head is not bolted to the vessel. ;
' ~ - ,
Amendment No. 23, 104, II7, 193 l f PF U 7 ISM t
insert i for Page 39: Note 1 for Table 3.1.1 If the required actions and associated completion time of Specification 3.1.A, Actions 1 or 2 or 3 are not met, take the action listed below for the affected trip function as required by Table 3.1.1. w.e
u gz unnur ucu uy iwanumi.us g , a4 . w
- ** g, ' ;jviwhen modtficat. ions"althorized by'Amendmeth' D67 are comp 1:ted UN1't:3'1 v .3
.1 9 4. < .,
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TABLE 4,1.1 -* - REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS
. HINIMUH 1*tlHCTIONAL TEST FREQtlENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2) . Functional Test -
Minimum Frequency (3)' Hode Switch in Shutdown A* Place Mode Switch in Each re' fueling outage. Shutdown g Manual Scram 'A Trip channel and Ala'rm Every 3 months. RPG Channel Test Switch . A Tri'p channel and Alarm IEverv refueling outa h or-after channel-maintenance.
. IRM .
M' liigh Flux C Trip channel and Alarm (4) One per week during - 3 refueling or startup. '" T and before each startup. Inope ra tive C Trip channel and Alarm (4) Once per week du' ring
, refueling or startup
'and before each startup.
APDM Iligh Flur mov Inoperative D1 Trip Output Rela'ya (4) Once/ week. u A4 Downscalo at Trip output Relays (4) ' Once/we'ek. ~ ill Trip output Relays (4) )nce/ week. Flow Diau lit ca l thrate Flow Ilias Signal (88)once/ month (M-liigh Flux in Startup or Refuel c Trip Output 18elays (4) Once- per week during
, refueling or startup and before each startup.)
liigh Reactor Pressure (6) ,11 2 Trip channel and Alarm (4) Every 1 month y
*lligh Drywell Pressure A Trip Channel and Alarm Kvery 1 month (1).(1)3 I i
eelligh Drywell Pressure (6) 112 Trip channel and Alarm (88) fEvery 1 month (1).; Reactor Low Water lavel (5) (6) 11 2 Trip Channel and Alarin (81) (Every 1 month (1). ii. Amnn,lmnn t fin 67 r, f r, / g o
~ '
j' k ' ' (' j. , '. 1 i i- + { 9 ,., , Unit 3 J' g , . . .
.' TABLE 4.1.1 (Cont'd)' .
4 .
@ REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS . .
MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS" E , ; .
^
k* Oroup (2) Functional Test , [ Minimum Frequency (3) e ('l - .
,,, High Water Level in Scrau A Trip Channel and Alarm p Discharge Instrument Volume
- fEvery-1 month...
k Turbine Condenser Low Vacuum (6) D2 Trip Channel and Alarm (4) Every.1 month (1)'. Main Steau Line High Radiation - B1 Trip Channel and Alarm (4) Once/ week. e Main Steam Line Isolation A Trip Channel and Alarm Every 1 month (1). h . Valve Closure 4 Turbine Control Valve A Trip Channel and Alarm Every 1 month. "
?
EllC 011 Pressure Turbine First Stage Preneure A Trip Channel and Alarm Every 3 months (1).
. Perminalve Turbine Stop Valve Closure A Trip Channel and Alarm Every 1 month (1).
4 - 9 Ota-l3 <
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- 1. . UNIT 3
. PlaFS _s
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!*CTIS FOR TALI.I L.1.1 *
=:d
~--. --.- - _ . - . _- /
- 1. Initially _c. hee eve:7 ::sth. The ec=pilation of i=stru=ent failure rate data =ay include data obtained frc= cther boiling vater reacters fer'which the same design instru=ent operates in.an enviren=ent similar to that of PEAPS. The failure rate data =ust be revieved and approved
~
by the NRC prior to any change in the ence-a-= cath frequency.f
- 2. A descriptien of each of the grcups is included in the Esses cf this - .
Specificatien. 3 Functienal tests e.re not required en the part of the syste= that is not required to be cperable er are tripped. If tests are =issed en parts cet required to be operable er are tripped, then they shall be perfer=ed prior to returning the syste= te en operable status. k ~. This instr =.entatica is exe=pted frc= the instru=ent channel test definition. This instru=ent che.nnel functienal test vill censirt of injecting a si=ulated electrical signal inte the =eesure=ent ch--* e - 5 "Se vaier level in the reacter vessel vill be pertu-bed and the corres-
. p:= ding level indicater ch-- es vill be = nitered. This pertur:c.ti:..
I . .-
- eSt Vi';.1 be perf0r=ed.. CY.ery =00th af t er Cc=ple". i0n c f *.he functi;r.~ .l.
Z_
- test prcgrn=. .
- c. . These channels consist cf annleg tre.ns=itters , indienters a.ni electrrnic trip units. Instru=ent chechs shall be perfer:ed cace per day.
1 1 i
. 1 l
1 r # c f l J - A end=ent .5 7. . no. S.J- Je=ue.ry 3, ic77 l l
[I: (19
)tunit 3 1ABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CilANNELS Group (1) Calibration Minimum Frequency (2)
Instrument Channel Comparison to APRM on Maximum frequency once IRM liigh Flux C Controlled Shutdown per week. APRM liigh Flux B1 IIcat; Balance Twice per week. Dutput Signal Flow Blas Signal B1 With Standard Pressure Every eighteen months. l Source B1 TIP System Traverse Every 6 weeks. LPRM Signal B2 Standard Pressure Source Once per operating h liigh Reactor Pressure cycle. ., B2 Standard Pressure Source Once per operating liigh Drywell Pressure cycle. B2 Pressure Standard Once per operating Reactor low Water Level cycle. A Water Column Every' refueling outage. liigh Water Level in Scram ' Discharge Instrument Volume B2 Standard Vacuum Source Once per operating f Turbine Condenser Low facuum cycle. f, Main Steam Line Isolation Valve A Note (5) Note (5) E i (, Closure Every 3 months. "E - Main Steam Line liigh Radiation B1 Standard Current Source (3) ~o A Standard Pressure Source Every 6 months.
@ "._. Turbine First State Pressure L6 Pemissive lS
[ .(m} . - { l,) ,
^l l Y
. i.
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n g . Unit' 3 , TABLE.4.1.2 (Cont'd.) E ' g REACTOR PROTECTION SYSTEM '(SCRAM) INSTRUMENT CALIBRATION '
. MINIMUM CALIBRATION-FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT y .
Instrument Channel Group (1) Calibration 4) Min'inum Frequency (2) D. N - Turbine Control Valve Fast A, Standard Pressure Source R Closure Oil Pressure Trip Once per operatilng g Turbine Stop Valve. Closure.
. cycle.- '.
m A Note - (5) Note (5) , I ve
**.p,
/Y ,,
a G s, s 4 t a t ie , _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ - . . . - . _ . - _ . _ _ . . _ - _ , . , _ _ - - . . _ - . . _. _. , .m _ _. , ,
~'
.a...f NOTES FOR 1 TABLE .4.1. 2 . , Unit 3
,p .
- 1. A duccription .of thres , groups is inclu.dsd in thd bases of
. this Specification.
i ,3 ' is not required on .the part; of the system ('. f-- ~~'?. ' Calibration test - 1 3, , . that are not required to be operable or are tripped but is required prior to return to service.
- 3. The current source provides an instrument channel align rint.
Calibration using a radiation source shall be made each refueling outage.
- 4. [ Response time is not la part of the' routine instrument channel)
(test but wil1~ b'e checked once per operating cycle.c 'T -
' 5. Physical inspection and actuation of th5se posit 3.on switches will be performed during the refueling outages. j pm l LDMvD., -
e.kJ12 rps r 4 4 D d r~. f
-. i-4 1
I J% % t-. w a -
+
1 i APRIL 1973
Docket No. 50-277 Ucense No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 i ATTACHMENT 4A l MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.A (Unit 2) Ust of Pages Affected: l 57 Page replaced 61 Table 3.2.A 62 Table 3.2.A 63 Table 3.2.A (Notes) 80 Table 4.2.A 87 Notes of Tables 4.2.A through 4.2.F l i l
PSRPS l 1-LIMITING CONDITIO1 FOR OPERATION SURVEILLANCE RE10IREMENT
- y ..
3.2 PROTECTIVE INSTRUMENTATION 4.2 PROTECTIVE NSTRUMENTATION Acolicabilitv: Acclicability-I Applies ~to the plant in- Applies to the surveil-strumentation which initi- lance requirement of the " ates and controls a pro- instrumentation that ini- ! tective function. tiates and controls pro-- _ tective function. l Obiective: Objective: i To assure the operability To specify the type and ' of protective instrumenta- frequency of survoi3 lance tien, to be applied to protec- i tive instrumentation. Scecifications: Scecifications: A. Pfi%irvTontain: hest ~~AT~PhimaCContainmenh .
. Isolation Functions Isolation Functions When primary containment Instrumentation shall be i
. integrity is required, the functionally teated and
;; . limiting conditions of calibrated as indicated in. ,
P operation for the instrd- Table 4.2.A. \ i mentation that initiates i e' D primary containment isola- System logic shall be . tion are civen in-Table functional 1vtestedasin-] l d icated in Table 4.2.A. / 3.2.A.f I. B Core and Containment B. Core and Containment i
;. Cooline Svstems - Cooline Syscens -
Initiat.on & Control _ Initiation & Contr G The limiting conditions Instrumentation shall be for operation for the in- functionally tested, cali- - i
}- brated and checked as in- !
strumentation that initi-atas or controls the core dicated in Table 4,2.3. i and containment _ cooling l systems are given in Table System logic shall be 3.2.B. This instrumenta- functionally tested as in-tion must be operable when dicated in Table 4.2.B. the system (s) it initiates
~
or controls are required - to be operable as speci- j fied in Section 3.5. , I
^
" m V g C MovufLte muo-q 59 w "~ "~"" nm ca APRIL 1973 l
I PBAPS ! UNIT 2
. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
/
- 3.2 Protective Instrumentation 4.2 Protective Instrumentation il
' A. Primary Containment isolation Functions A. Primary Containment isolation Functions ;
The primary containment isolation instrumentation shall be functionally tested and ; instrumentation for each function in Table 3.2.A calibrated as indicated in Table 4.2.A. j shall be Operable; and, there shall be two - Operable or tripped trip systems for each trip
~
System logic shall be functionally tested as ! function. indicated in Table 4.2.A. - Apolicability: Whenever Primary Containment integrity is - ; required.
' Conditions and Reauired Actions:
- (1)(2)-
1
- 1. . With one or more channels required by. Table
- 3.2.A inoperable, place channel in trip within 12 C hours for items 1,4, and S; and, place channel l in trip within 24 hours for items other than 1,4, and 5. l
) i
- 2. With one or more automatic functions with ;
E- primary containment isolation function not [ maintained, restore primary containment ! F . isolation capability within one hour.(3) i
- 3. If the required action and associated completion L time of Action 1 or 2 are not met, take the
. action required by Table 3.2.A for the function. ;
l 6 i i
~ (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation j of these Actions may be delayed for up to 6 hours provided the associated Function maintains primary i
((( E containment isolation capability. i j (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the l
' trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the !
required tirr.e, the Action required by Table 3.2.A for that trip function shall be taken. j y ,
;; (3) .This Action not applicab!e to item 11. Reactor Cleanup System High Temperature.
i
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t I 8 2 3 4 6 S 7 a _
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s . I,8 g- a h- . n g
], d{ {y . JJ3 DFN ) _
08 u cu;;o-ei n
I'ett 3.1,1
.e PBAPS unit 2 .
')
[' ! / s
)
=
s_) 1:31:.trug1TCTIDH YisAT 1:11521E5 PRIMaly COHTAINMENT 150LATIDM
- Of.
u,-
%, U -
o
'-['
La a Minimum He. et operable Instrument ,irlp Level setting Number of Instrument [hennele Prowloed Actlen (2) 0D'
- Instrument Channele per By Doston
'T Trl eten i,4 Item it
\q 4 Inst. Channele B Heln Steam Line
- 200 Dog. F ,
9 2 7* ' Look Det ect ion liigh
- Temperature
\(* 2 Inst.,thennels ,C P Reacter Clsenup e 2001 et meted to 3 system Illsh Flo. Fie.
- 200 Dog. F. I Inst. Channels
'E 18 i Descler Cleanup s,
- System Illph To.perature es b3 4 Inst. Enonnele F
' mescler Pressure
- 800 pelo 32 2 '
freed =eler Flush
' Systa= Interlech)
I m DJ t
.I e
5 1- . 8
?. PEAPS . ^ . Unit 2 ! kC
~
- S ( uwd(c Mn' ST NOTES FOR TABLE 3.2.A
[ Dddb) ,
- 1. WeneveIhidary containment integrity is required by Section 3.7,)
., there shall be two cperable or t; ripped trip _ systems,for eachg
,, (function.J . ,
~
- 2. (If.the first eclumn cannot be met.for one of the trip. systems, that4 trip system shall be. tripped or the appropriate action listed belcu,)
(shall be taken:f . , q ,w% wo ..p-- .,o -. " A. Initiate an orderly shutdewn and have the reactor in Ccid Shutdcwn Condition in 24 hcurs., B. Initiate an orderiv icad redt$cticn and have Main Steam Lines isolated within e:.ght'heurs. ~ _ C. Isolate Reactor Water Cleanup Syste=. 12.) * ~
%[L
-. . A
\ %D '
D. Isciate Shutdown Cccling.
% N s ,
E. Isolate Reacect Water Cleanup Filter De=inerall:ers unless the , following provision is satisifed. The RWCU Filter
- f. x.. Demineralizer may be used (the isclation everridden) te rcute i the reactor water to the =ain condenser er waste surge tank,
- with the high temperature trip ineperable for up to 48 hcurs,
- provided the water inlet temperature is =enitored once per hcur and confirmed to be belcw 180 degrees F.
F. Isolate Feedwater Flush System r _ __._. - ~ ~~~~
- 3. Instrument setpoint correspends.to 538 inches above vessel zero.
- 4. Instrument setpoint correspends to 378 inches above vessel :erc.
'5 . Two required for each steam line.
- 6. These signals also start SEGTS and initiate secondary containment isolation.
- 7. Only required in Run Mede (intericcked with Mcde Switch).
- 8. An illarm will be tripped in the centrol recs to alert the centrcl
-reem operators to an increase in the main steam line tunne' l radiation level. :
l l l t #
*f.
mnenesolp!,Dc,2rf,pf,129 03/03/88 _s3_ l I
~
i l l Insert 1 for Page 63: Note 2 for Table 3.2.A. l if the required actions and associated completion time of l Specification 3.2.A, Actions 1 or 2 are not met, take the { action listed below for the affected Trip Function as ;
. required by Table 3.2.A.
I
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TABLE 4.2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument functional _ Test Calibration Frequency Instrument Check Instrument Channel (5)
- 1) Reactor High Pressure @ Once/3 months None (ShutdownCoolingPermissive) Once/ day (1) (3) Once/ operating cycle
- 2) Reactor low-tow-tow l Water Level (7) Once/ operating cycle- Once/ day
- 3) " Main Steam High Temp. (1) (3) Once/ day
- 4) Main Steam High Flow (7) ,(1)t(3) Once/ operating cycle Once/3 months None
- 5) Main Steam Low Pressure (1) Once/ day
- 6) Reactor Water Cleanup ((1) Once/3 months High Flow None
- 7) Reactor Water Cleanup l(1) Once/3 months High Temp. Once/ operating cycle Once/ day
'8) Reactor Pressure d(3) , (Feedwater Flush Permissive) ___
w i Wk3hed$s - Frequency logic System Functional Test (4) (6) Once/ Operating Cycle
- 1) Main Steam Line Isolation Vvs.
Main Steam Line Drain Vvs. , Reactor Water Sample Vvs. . Once/ Operating Cycle
- 2) RHR - Isolation Vv Control
{
- s Shutdown Cooling Vvs.
Head Spray k 3) Reactor Water Cleanup Isolation Once/ Operating Cycle g Once/ Operating Cycle
- 4) Drywell Isolation Vvs. ,
TIP Withdrawal 8 Atmospheric Control Vvs. Sump Drain Valves d Ed 5) Standby Gas Treatment System Once/ Operating Cycle , Reactor Building isolation g 'A"
- = y t
m
e /- PEAps i NOTES FOR TA3LES h.2.A TE OUGH k.2.F ' # J p~. _.. , %
- 1. 6tial17 c ce every =enth. The ec=pilatic: cf instrument failure ratel data =ay include data obtained frc= cther boiling vater reactors for 1 which the sa=e design instr =ent Operates i= an envirennent si=ilar to that of PEApS. The failure rate data =ust be reviewed and approved by .
Lthe AEC prior to any change in the once-a-secth frequency. [~ '
- 2. Furetional tests, calibra:1ces and i=str=ent checks are cet required when these instr =ents we ::: required to be operable or are tripped.
Functicnal tests ska be perfc=ed before each startup vith a required . frequency not to e=eed c ce per week. Calibraticas sha be perfer=ed within 2h hcurs before each startup er ccatr:11ed shutdov vith a required frequency not to e=eed cace per veek. Instr =ent checks sha he performed at least cece per day during these perieds when the instru-
=ents are required to be operable.
3 This instr =entatica is excepted frc= the emetic a1 test definitica. The functional test vill censist of injecting a si=ulated electrical signal into the =easure=ent channel. These inst::=ent cha- els vill be calibrated using si=ulated electrical signals.
- h. Si=ulated autc=atic actuatica sba11 be perfc =ed ecce each cperating . . . .
7 cycle. 17:ere possible, all legic syste= f=cticcal tests vill te
, perfor=ed using the tes Jacks.
5 Reacecr icy vater level, high d /vell pressure and high radiatic main sten: line tunnel are cet included c Table h.2.A since they are tested c Table h.1.2.
- 6. The legic syste= e=ctic=al tests shall include a calibratie of time
~
delay relays and ti=ers =ecessary for proper recticcing of the trip syste=s.
,7 These channels censis: of s-='eg transmitters , indicaters and electronic Trip units. \
I'" A=end:ent Sc. 30/29 January 3,19T7
Docket N3. 50-278 Ucense No. DPR-56 ; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 4 ATTACHMENT 48 , MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.A (UNIT 3) Ust of Pages Affected:
.57 Page replaced 61 Table 3.2.A 62 Table 3.2.A 63 Table 3.2.A (Notes) 80 Table 4.2.A 87 Notes of Tables 4.2.A through 4.2.F i
. PBAPS- *
- - D l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREIENT -
.r~; - ,
g w A.a 3.2 PROTECTIVE INSTRUMENTATION 4.2 PROTECTIVE INSTRUMENTATION ~ 1 i
,' Aeplicability: -Applicability: 'x, ;
I
'! Applies to the plant in- Applies to the surveil i I strumentation which initi- lance requirement of the k f ates and controls a pro- instrumentation that ini-tective function. tiatesandcontrolspro-\,
tective function. g
. Obiective: Objective:
To' assure the operability To specify the type and i of protective instrumenta- frequency of survoi31ance' tion, to be applied to protec-: tive instrumentation. f I. ./
\ /
Q Seecifications: Scecifications: ,.- A. Primarv Containment A. . Primarv Containment N Isolation Functions -
- Isolation Functions _
\ '
When primary containment Instrumentation shall be ( integrity is required, the functionally te.sted and '1 limiting conditi,ons of calibrated as indicated in 7; - operation for tlie instru- Table'4.2.A.
~
t mentation that initiates System logic shall be
]primarycontainmentisola-tion are given in Table q3 ._2, A
- ~~~~ ' functionally tested as in /
~^ x dicated in Table 4.2 9 B. Core and Containment B. Core and ContainmenD.,
Cooling Systems - Initiation & Control Cooling Systems - \ Initiation & Control The limiting conditions Instrumentation shall be I for operation for the in- functionally tested, cali-f strumentation that initi- brated and checked as in- i ates or controls the core dicated in Table 4,2.B. I, and containment cooling i systems are given in Table System logic shall be j 3.2.B. This instrumenta- functionally tested as in-/ tion must be operable when 4 the system (s) it initiates
, dicated in Table 4. 2.B. ,/
i
. or controls are required ' ' ' _
(to be operable as speci- - -~ ,
% G h 22G.~x f1".d in Section 3.5 (AtoxdL _
m y .m_ e.ccyh_ {, n. GO $W w t}_. 6 Y
~ ~
i APRIL 1973
=
PBAPS UNIT 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS . 3.2 Protective Instru:nentation 4.2 Protective Instrumentation A. Primary Containment isolation Functions A. Primary Containment isolation Functions The primary containment isolation instrumentation shall be functionally tested and instrumentation for each function in Table 3.2.A calibrated as indicated in Table 4.2.A. shall be Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as function. indicated in Table 4.2.A. Apolicability: Whenever Primary Containment Integrity is required. Conditions and Reouired Actions: (1)(2)
- 1. With one or more channels required by Table 3.2.A inoperable, place channel in trip within 12 hours for items 1,4, and 5; and, place channel 1 i'
in trip within 24 hours for items other than 1,4, and 5. t 3
- 2. With one or more automatic functions with primary containment isolation function not maintained, restore primary containment isolation capability within one hour.(3) 5
- 3. If the required action and asacciated completion ;
time of Action 1 or 2 are not met, take the i action required by Table 3.2.A for the function. , 1 l > i l (1) When a channelis placed in an looperable status solely for performance of required Surveillances, initiation I s of these Actions may be delayed for up to 6 hours provided the associated Function maintains primary . containment isolation capability. j (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the
- trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.2.A for that trip function shall be takaa.
e (3) This Action not applicable to item 11, Reactor Cleanup System High Temperature. I i r 'b l i
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- ENSTRUMENTATION THAT INITIATE 5 PRIMARY CONTAlHMENT 150LAfl0H
. 2:
- u. .
Minimum He.
)S.
af Operable Humber of Snetrument Instrument Instrument Trip Level setting Channelo Provided. Action 1 Channele per my Besten (2) Trip System Stem h,
,. J 2 (6) Reacter Law Water > 0* Indicated 4 Inst. Channels A' La f Level Lowel (3)
N 2 l Reactor High Pressure 3 75 pale 2 Inst. Channele 0 (Shutdown Coollne lealetion) 3 2 Reactor Low-Low-Low et er above -180" 4 Inst. Channels a e b Water Level Indlceted level (4)
' 4 High Drywell Pressure 3 2 pelg 4 Inst. Channele A 2 (S)
High Radletion Meln 195 N Hermal meted Full (3) 4 Inst. Channele e l5 2 5 team Line Tunnel Power eschoreund 6 2 Low Preneure Main > , 850 pels (1) 4 Inst. Chennels 8 '7 Steam L i n e' . l,7 2 (5) High Flow Nein < 140% of Rety 4 Inst. Channels 8 Steam Line Iteen Flow I 3 2 Meln Steam Line
- 200 deg. P (S) , 4 Inst. Channele- 8 Tunnel Eshouet Duct High Temperature
. e ,
,N e e t m m I i.
- f. 5 TAD 1U unit a ?
.fl ' (\Ili.._
Tantt 3.7 t A + IE ,! \f Lt s 5 4f . . lH5inuuEHY'. TION TilAT INITIATES Pal"C V .sTI.thuEHT ISOLSTicu 3t s c4 33 Minimum Ho. J p. of Opsrable Humner of Instrueent ?Q Instrument Trip Level Settino Chennele Previded Actlen dNre , Instrument Channels per By Deston -( 2 ) g I r l p._ stem item 1 u. 4 Inst. Channels t kk 9 2 Neln Steen Line
- 1 200 Dec. F *
* , Leek Detectlen itish Temperature
- Reacter Cleanup 4 300% of Reted 2 Inst. Channels C 10 1 System Hleh Flo. Fle. ,
I Inst. Channels E t Reactor Cleanup g 200 Dec. F.
$. I I, System High La N Temperature 4 Inst. Channels F 32 2 Reactor Pressure 1 600 pelg (Feed = ster Flush System Interlech)
N J e e 6 9 1 1 I e
. ?
PSAPS Unit 3 - h-) I' ~ * ~ 7-
^ ^
~
}wul I.o (qt. f NOTES FOR TABLE 3.2.A' /'((^&jc - #~~
_ . . _ . . . . . - - - . . ---.-Y--- . . - -
- 1. fWiienever Primary Containment integrity is required by Section 3.Pj there shall be two operable or tripped trip systems for eafch (function.f tha 2.[IIthe'firstcolumn,cannotbemetforo_neofthetripsystems,tripsystemshallbe'tr w d hall be taken ( ( g g A. Initiate an orderly s'hutdown and have the reactor in Cold Shutdown Condition in 24 hours.
B. Initiate an orderly load reduction and have Main Steam Lines isolated within-(fgTt3 hours.
- v
^ 12 C. Isolate Reactor Water Cleanup System.
N D. IsolateShutdownCooling.\ . T #
^
I. Isolate Reactor Water Cleanup Filter Deminerali:ers unless the ' following provision is satisifed. The RWCU Filter Demineralizer may be used (the isolation everridden) to route the reactor water t6 the main condenser or waste surge tank,
-_ . . , with the high temperature trip inoperable for up to 48 hours, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F.
F. Isolate Feedwater Flush System /- - ~ ~ ~ ~ ~~
- 3. Instrument setpoint corresponds to 538 inches above vessel zero.
- 4. Instrument setpoint corresponds to.378 inches above vessel ero.
- 5. Two required for each steam line.
- 6. These signals also start SBGTS and initiate secondary containment isolation.
- 7. Only required in Run Mode (interlocked'with Mode Switch).
- 8. An alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel radiation level.
A a, E' . l
-Amendment No. M ,%98,JI5, gl.132 03/03/88 l l
l s
.. rA insert 1 for Page 63: Note 2 for Table 3.2.A. If the required actions and associated completion time of Specification 3.2.A, Actions 1 or 2 are not met, take the action listed below for the affected Trip Function as required by Table 3.2.A.
;1 . -pm K
' (JN 3 TABLE 4.2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5) Instrument Functional Test Calibration Frequency Instrument Check
- 1) Reactor High Pressure '(l)') Once/3 months None (Shutdown Cooling Permissive)
I , (1)f(3) Once/ operating cycle Once/ day
- 2) Reactor Low-Low-Low Water level (7)
- 3) Main Steam High Temp. Once/ operating cycle Once/ day
- 4) . Main Steam High Flow (7) (1)!(3)
(1)(3) Once/ operating cycle Once/ day (1) Once/3 months None
- 5) Main Steam Low Pressure Once/ day
- 6) Reactor Water Cleanup (1) Once/3 months High Flow Once/3 months None
- 7) Reactor Water Cleanup (1)
High Temp. Once/ operating cycle Once/ day
- 8) Reactor Pressure V(1)(3)
(Feedwater Flush Permissive) ,- E' Logic System Functional Test (4) (6) (-vOMQ3~4 ,__._.~ . Frequency , Once/ Operating Cycle i
- 1) Main Steam Line Isolation Vvs.
Main Steam Line Drain Vvs. Reactor Water Sample Vvs.
~
Once/ Operating Cycle I
- 2) RHR - Isolation Vv. Control '
t k Shutdown Cooling Vvs. a I
- 3) Reactor Water Cleanup Isolation Once/ Operating Cycle
[ O I E R'
- 4) Drywell Isolation Vvs.
TIP Withdrawal Once/ Operating Cycle w Atmospheric Control Vvs. g ," Sump Drain Valves Once/ Operating Cycle l OM 5) Standby Gas Treatment System g ." Reactor Building Isolation 3 l I e
o : .r ^
- cm P3APS /c Q
( D_d % ). NOTES FOR TABLES h.2.A THROUGH h.2.F .
. . . _ e
- 1. Initially once every conth. The ec=p.ilation of instrument failure rate data may include data obtained frc= other boiling water reactors for i
vhich the same design instrument operates in an environ =ent similar to that of P3APS. The failure rate data must be reviewed and approved by . the AEC prior to any change in the once-a-month frequency.f
~
- 2. Functional tests, calibrations and instrunent checks are not required when these instru=ents are not required to be operable or are tripped.
Functional tests shall be perfor=ed before each startup vith a required frequency not to exceed once per veek. Calibratiens shan be perfor=ed within 24 hours before each startup or controlled shutdown with a required frequency not to exceed once pe'r week. Instrument checks shall be perfor ed at least ence per day during those periods when the instru-ments are required to be operable.
- 3. This instru=entatica is excepted frc= the functional test definition.
The functional test win consist of injecting a simulated electrical signal into the =casurement channel. These instru=ent c% ~~els vill be calibrated using simulated electrical signals. a k. Si=ulated aute=atic actuation shall be perfor=ed once each operating - (L cycle. T(nere possible, an logic syste= functional tests vill be j
. perfor=ed using the test Jacks. '
5 Reactor icv vater level, high dryven pressure and high radiation =ain ! steam line tunnel are not included en Table k.2.A since they are tested en Table k.1.2. , l
- 6. The legic system funct'icnal tests shall include a calibration of time l delay relays and timers necessary for proper functioning of the trip l syste=s.
i 7 The:S ek=~~els consist of analog transmitters, indicators and electronic hip units. m i i I i i 47-A=end=ent No. 30/29 January 3, 1977
l Docket N3. 50-277 l Ucense No. DPR-44 l l PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 1 I I l l l ATTACHMENT 5A l MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.B (Unit 2) i l l List of Pages Affected: 57 (ECCS requirements relocated to Page 57a) 57a New page 64 Table 3.2.B SS Table 3.2.B 66 Table 3.2.B 67 Table 3.2.B 68 Table 3.2.B
-69 - Table 3.2.B 70 Table 3.2.B 71 Table 3.2.B 71a Table 3.2.B 71b . Table 3.2.B 72 Table 3.2.B (Notes) 72a Table 3.2.B (Notes) New page !
81 Table 4.2.B ! 81a- Table 4.2.B 87 Notes of Tables 4.2.A through 4.2.F
,_ LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT
,D.~- 3.2 PROTECTIVE INSTRUMENTATION 4.2 PROTECTIVE INSTRUMENTATION q - m_.--. Aeolicability:
-Acelicability: N l
Applies to the plant in- Applies to the surveil- u( , strumentation which initi- lance requirement of the i ates and controls a pro- instrumentation that ini-tective function. tiates and controls pro- , ' tective function. Obiective: Objective: ; To assure the operability To specify the type and ; of protective instrumenta- frequency of survoi31ance / tien. to be applied to protec- / tive . instrumentation.
/
f.
, (Soecifications : Scecifications: ./
A. frimarv~donf5IfibiEnt- 7. Primarv Containment Isolation Funcrions Isolation Functions l N ' When primary containment Instrumentation shall be \ integrity is required, the functionally tested and j limiting conditions of calibrated as indicated ini' rM operatien for the instru- Table 4.2.A. l
^
mentation that initiates ; System logic shall be l
- primary containrent isola- ,
(> (3.2.A. tion are given in Table functionally tested as in-j dicated in Table 4.2.A. j [ ~
~ Core anTContai:~'U$ehh B. Core and Containme'n D l lB. Cooling Systems - Cooling Systems - 's
! Initiation & Control Initiation & Control The limiting conditions Instrumentation shall be \
for operation for the in- functionally tested, cali-(
/ strumentation that initi- brated and checked as in- !
dicated in Table 4,7..B. I f ates or controls the core and containment cooling I systems are given in Table System logic shall be 3.2.B. This instrumenta- functionally tested as in-tion must be operable when dicated in Table 4. 2.B. the system (s) it initiates . or can'trols are required - to be operable as speci- g- -- fled in Section 3.5. / j
~
-m - m -.,
(mnat i h MLuY pan,^.. Q h >
,. \ Su_ Lla[3.1D, (mun d G w pa g 5 -
" APRIL 1973
PBAPS - UNIT 2 UMITING CONDITIONS FOR OPERATION LIMITING CONDITIONS FOR OPERATION t 3.2 Protective instrumentation (Continued) 4.2 Protective Instrumentation (Continued) t B, Core and Containment Coolina Systems - B. Core and Containment Coolina Systems - Lriitiation and Control Initiation and Control Core and containment cooling system initiation Instrumentation shall be functionally tested, and control instrumentation for each Trip calibrated and checked as indicated in ' Function in Table 3.2.B shall be Operable; and, Table 4.2.B. . there shall be two Operable or tripped trip systems for each Trip Function except as noted System logic shall be functionally tested as in Table 3.2.B. indicated in Table 4.2.B. Applicability: Each Trip Function listed in Table 3.2.B shall be Operable whenever the system (s)it initiates or controls are required to be Operable as specified in Section 3.5. Conditions and Recuired Actions: With one or more channel (s) required by Table 3.2.B inoperable in one or more Trip Functions, take the Action required by Table 3.2.B.
- 57a -
%M j i'
[, E :. .' q$
) .
{(' d,UMI.t*3.2.D , gp g IllSTPuliEllTATIOli TilAT illITI ATES 011 COtITRoi.S Tile Cone AllD Col 4TAllINEllT * .
. C001.IllG SYllTEHS
.a 5 _ -.--- - . - - - - - . . . - - - - - . - - y - . . - - - . . - - - - - - . - - - - - - 3 Itinimum No. . thimber of ins t,ru- .
' of operable It ema rk s Trip Feinc'llon Trip I.evel Hetting nont Channels Pro. = Instrument vidcal by Dealgn . ? channel s Per IE 2.l'Y5t.dL.-bC ___
l e React o r 1.ow-r.ow t-ta s 13. Inifica te d ti lirci G ltCIC InitlhtcollPCILltCIC'l 2 (4(ts) invel Inst. Channela
., stater f.evet il Core Spray 5 1. In conjtInct ion with R e a ct o r 1.ow-T.ou-l.ou- 1-160 In. I nd i c at e<l I,ou nenctor Pressure Hater ine l level ( ) ,I -. nHR In s t ru men t gg} [gg} ' I Channels initiates Corn Spray
,anet I.PCI ti ADS Instrument Channela
- 2. In conjunction with h con firmatory toe level Illgh Drywel.?
Preneure, 120 second Line delay and t.PCI
~
or Core Spray pump Interlock initiates Auto D10wilown (ADS)
- 3. Initiatea starting of Diese t Gentera tore I l- ,
D-
. 6 c.
n t t e
' . 4 e ,
gi
g
! \L N lb \ )
l A *
% :) {}
t'?T i G -
?! &
Q TAats 3.2.s (Couttuuto) TW8TRUMENT& Troll TitW IMITI ATES OR COHTAOLE Tile CopC EllD CONT &tHHIll? .
. 7f COOLlHG SYSTEMS e
- i
; 141al mu s N o. ,
*
- Number of.Instria-
; Of Operable Isetrument Trip Function Trip Level aatting ment Channele Pro Romerke m
w Channels te. - vieled by Design g Trip systant CT le fJ geactor utgh ifator .$e45 in. Indloeted 2 Inst. Chesnele Tr! e llPCI & 3CIC Y3 1.evel level tes laae (Q J(,
\
pesotor' Lou Level 3 113 !"n. above 2 Inst. Chennele Frevente inadvertent . l' linolde ehtoud) vessel sero l2/3 operation of contain-(q) v ID core height) ment oprey during ecoldent condition. 3 contelnaent High I < p < 2 pelg 4 inst. Channele "Frevente inadvertent Pressure operation of contain-ment sprey during ecoldent condition.
' 186 in. Indiosted 2 Inst. Chaenote ADB Permissive g(Ih(lb I Confirmatory Low Level level e
3 High Drywell i 2 pelg 4 Inst. Channele 1. Inittstee core spray Preneura , LPC t s ilFCI
- 2. Initiates eterting of plesel Generatore (Q\[l!}/
o)( -' 3. Inittstee auto alow-down LADS) in conjunction l tj fl. ulth Low-Low-Lop Desotor water level, 120 I
. escond time deley, and
! !.FCI or Core Spray
. pump running.
4 a ..
)
9 9
4 l i i
'g 7
a V..I [') . TAllLE 3. 2.n (Conted) INSTRUMENTATION TilAT INITI ATEb Olt COllTilOI.S Tile CORE AND CONTAlllHENT COOL 1HG SYS1EHS I Hinimum No. - of Operable
-Instrumen t Trip Fpnction Namber of Instru- .
Trip Level Setting ment Channula Pro itemarka Channela Per z. vided by Dealgn
- T J o systemil) 2 Heactor Low 400-500 pa19 Pressure 4 Inst. Channola Permissive for opening Core Spray and LPCI Admission valves.
Coincident with high dry well preauure, starta
' PCI and. Core Spray pumps. ,' 2 9)(ld neactor Inw 200-250 paig 4 Inst. Channota l Pressure
- Perminalve for clouing ^
l Bacirculating Putnp Discharge valve. h* 1, neactor Low 505P575 pa19 Pressure 2 Iriat. Channeta In conjunction with PCI l (l3)(It) '
' signal permita cloBure of HIIn (LPCI) i n jec'tlon valves.
t! v l i Arnendment flo. 68 /67 (s/s/80)
.-, i :
it [' j
' Unit 2
-h
~;"
!' PBAPS TABLE 3.2.B INSTRUMENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT C00 LING' SYSTEMS Illnimum No.
of Operable ' Number of instru-Instrument Trip function Trip level Setting ment Channels Pro- Remarks Cnannels Per vided by Design
,l_r_ip_h , stem k U T Core Spray Pump 6 +/- 1 sec. 4 timers All pumps-loss of offsite 2 (7)(l5) power only Start Timer 13 sec. 4/-7% of setting 2 timers A&C pumps-offsite power available 23 sec. +/-7%-of setting 2 timers Df,D pumps-offsite power available 1 per 480V Emergency 3 +/-0.5 sec. 4 timers All timers - loss of 4kV bus (7) Load Center Timer offsite power only i 2 LPCI Pump Start 2 sec. +/-7% of satting 4 timers LPCI pumps A&B g Timer (Four Pumps) 8 sec. +/-7% of setting 4 timers LPCI pumps C&D ' 2 timers 1 (12)(1G ADS Actuation m./=t </=120 In conjunction with low Timer se:onds Reactor Water level, liigh Drywell Pressure and LPCI or Core Spray Pump runn1ng interlock, initiates ADS.
k 2 2.)(I6 ADS Bypass Timer 0 < /= t </=10 4 timers . In conjunction with low minutes reactor water level, byrmsnes 4 g high drywell pressure
- s initiation of ADS.
n 2 ) RHR (LPCI) Pump Discharge Pressure 50 +/- 10 psig (4 channels Defers ADS actuation pending confirmation of Low Pressure Core Cooling i
- Interlock
'- - system operation (LPCI Pump running interlock).
- g 3 , .w m 105 4/- 10 psig 4 channels Def.rs ADS actuation yw 12 M j g Core Spray Purn pending confirmation of Low p3 "'
2 ((w >) ') Discharge Pressurr-Pressure Core cooling Interloci; system operation (Core Spray Pump running interlock). (*Ef fect ive when morti ficat. ion ansocint nl. wi t 4 .lis encrwiment in completD 't
ik : .
. s. w.._.
' ," [ * ;
i
..lf,
~-
.\ , . .
. EDLt; 3.2.n (Cont'd) '
, INSTRUMENTATION TilAT INITIATE'S OR CONTROLS Tile CORE AND 'CONTAINHENT COOLING SYSTEMS ,
Minimum No. ' ' of Operablo- . Hureber of Instru-Instrument. Trip Function Trip I.evel Sotting "" *""*
- channels Per vided by Design f~ Roma rks Trip System
- 1 (8)(It,) RIIR (LPCI) Trip s System bus' power 11A 2 Inst. Channels Honitors availability.
monitor of power to. logic ..
. systems.
1(2)(l(, Core Spray Trip . HA System bus power 2 Inst. Channels Honitors availability monitor - - of power to logic systems. , 1 (8)[gt.) ADS Trip System bus HA power monitor 3 Inst. Channels - Monitors availability I - of power to logic systems. g 1 (@)(lr,) IIPCI Trip System bus
. power monitor 11A 2 Inst. Channels Monitors availability ' , of power to logic -
systems. I kit, RCIC Trip System bus HA power monitor 2 Inst. Channels ' Honitors availability of power to logic, systems. ' t ? p e I l MI 4 7 /47 netober 10, 1978 ^
rn - fR) ' f q ;; I' N' a , Y R
$a , .
TABT.E 3.2.11 (CONTIHUED) he INSTRtlHENTATION TilAT INITIATESi OR CONTROf.S Tile CORE AND CONTATHHENT COOT.ING SYSTEMS FIElmum Ho. . E Of Operable Humber of instru-Instrument Trip Function U Channels Per Trip f.evel Setting ment channeta Pro-Itema rks Trip System vided by Dealgn 3-4 , 1 Ql) Core Spray Sparger 1 (plus or minus s to Reactor Pressure 1.5) paid - 2 Inst. Channels Alarm to detect core {m vessel d/p spray sparger pipe break, S 2 l ' (to)(K) ' Condensate Storage Greater than or i Tank I.ow t.evel equal to 5' above 2 Inst. Channels Provides Interlock tee ,e . llPCI pump suction 8 ' tank hottom
-- % valves.
2 (1)(nry(eg Suppresalon Chamber I.e s s than or M
.lligh f.evel equal to 5" above 2 Inst. Channels Transfers llPCI pump -
torus midpoint suction to suppression. chamber. 2 (6 Condensate Storage Greater than or Tank I.ow I.evet equal to 5' above 2 Inst. channels Transfer RCIC pump tank bottois auction to suppresaleese chamber. e
$
- 9 e S
- k. '
. I g O b
e D 8 C ,
.m-
- _-- n.e 7 :,, . ,
f ' ~^ ^
.. . ~-:- y
.\: l ~ ',_ , . .. . ;-
c !. _
~~
,l I '
IIISTRUMEt#TATIOtt TilAT INITIATES. OR CONT ' tile {CORE Atif) CollTAltlHENT - ' COOI.IllG SYSTPHS Hinimites .Ho. ' Of Oparable. Insthitsent Trip Function tiumber of Instru-Cliannel a' Per - Trip r. eval Setting ment Channela Pro- Remarks TrltSysteh i y4 vided by Dealgn - I RCIC Turbine liigh Flow 1450" 18 O(2) 2 Inst. Channela
- s. 2 1
RCIC Turbine Illgh 3 1 1 seconda 2 Inst. Channelp-Plow Timo-Delay 8 2[ RCIC Turbine Com-- 1200 deg. F o partment Hall (2) 4' Inst. )
- 116 Inst.
6( RC7C Steam Line 1200 deg. F' Area Temp. (2) 12 Inst. ) 2((19bs) RCIC Steam T.ine 100> p)'50 palg (2) Low Preasur,e . 4 Inst. 1 llPCI Turbine Steam .f225" If2 0 (3) Line Illgh Flow 2 Inst. Channata 1 IIPCI Turbine liigh 31 1 acconda Plow Time Delay 2 Inst. Channela
.o 8 4
e 9g
- a f
%entiment flo. 100/102 .
m, '
~
July 2, 1904 ' f 3.'[iy --
, . l T' mw _ a - __ _____._______.____._________A _____-_s.-- ' - -sw. _ _ -_ r .____ -e - --- w- - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
( l . TADT.E 3.2.D (CollTIHilED) - IliST111115EtiTATIOli TilAT Ili1TI ATES OD COllTil0LS Tilli COnli AllD COllTAIllitENT coo!.111G GYSTEllS flinimtim 110. cf operable . littmher of Instrument Trip Flinction Instralment clihnne t a per Trip T.cVel Setting Channola Remarks Trip System # Provided by Dealgn 4(5) IIPCI Steam I,ine 100>p>50 psig (3) ' 4 Inst. Low Pressure , 2 IIPCI Turbine 1200 deg.F (3) Compartment . 4 Inst.) Temperature ' }
.)
4 \ 11PCI steam I.ine 1200 deg.F (3)- 0 Inst.) 16 Innt.
, Area Temperature
)
) -
2' !!PCI/T111R Valve $200 dog.F (3) Station Area 4 Inat. Temperature 1[' L- J
' LPCI cross-connect IIA Poaltion 1 Innt.. Initiaten anniin-clation uhen valve ia not closed.
1 per 4KV 4.KV Emergency aun 251(451)of nated
- 1. Trips'all loaded nuag;) Ilndervoltage Relay voltage (IIGA) breake rs. '
2.Fant transfer
.permienive. ,,
- 3. Dead bus start of diesel.
I per 4KV 4KV Emergency 11un 951(4 01,-10% ) o f nequential I.onding Unted Voltage Permits sequential. Tins {[I 11elay (SV) - starting of vital. 3 cads
- i Amendment Un. 97 / 99 April 11, 19111
l , Unit 2 l 1' [ .- '& PBAPS . TABLE 3.2.0 (CONTINUE 0) INSTRUMENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. Of Operable Number of Instrument Trip Function Trip Level Setting Instrument Remarks Channels Per Channels - Trip System h h Provided by cTr o J)) Design 2 per i'KV Emergency 60% (15%) of rated 1. Trips emergency Bujp]j Transformer Undervoltage (IAV) voltage- Test at zero volts in 1.8 transfer feed to 4kV emer-(Inverse time- seconds (110%). .m gency bus. voltage) 2. Fast transfer permissive. 2 per 4KV Degraded ,- 98% of rated voltage I. Trips emergency
~ Dus (g voltage (27N) +0.3% of setting transformer feed s ("non-LOCA" relay) T4077 volts + 12 volts) to 4KV 0.9 - 1.1 second internal time delay emergency bus.
60 second i 5% (13 sec.) 2. Fast transfer j time delay , permissive. y 2 per 4KV Degraded 89% of rated voltage I. Trips emergency 3 Bus voltage (27N) 1 0.3% of setting transformer feed Q ("LOCA" relay) (3702 volts i 11 volts) , to 4KV emergency
@ 0.9 - 1.1 second internal time delay bus.
g 9 second i 7% (1 0.6 sec) 2. Fast transfer - time delay permissive. 0 3. Safety injection signal , 3 , required. 1
-- - . ~. ~
-a. _ . . ~
~
- v f .' j .~g . ~ a.
. f ._ ,)y
' TABLE 3.2.B (CONTINUED) Unit 2-INSTRUMENTATION - TilAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT
- COOLING SYSTEMS Minimum-No. Number of of Operable Instrument Instrument Trip Function Trip Level Setting Channels Remarks Channels Per Provided by Trip System @ Design Emergency Trans - 87% (iS%) of 1. Trips emergency 2 per 4 kV former Degraded Rated Voltage. transformer feed Bus
) voltage (Inverse Tests at 2940 to 4kV emer-time - voltage). volts in 30 seconds gency bus, (i10%) 2. Fast transfer e (CV-6) permissive.
e t a g . 8 e h 23
- )c;a
}? 4 e
PBAPS __ _. s
~
NOTES FOR TABLE 3.2.B- N awA.To m (ao c 57q 1 l A - L f
@ 3.-:iWhenever any CSCS subsystem is required by Section 3;5 to be operable, there ~
1sha11 be two operable trip systems.fff-the first column cannot be met for one of the trip systems, that trip. system shall be placed in the tripped condition or the reactor shall be placed in the Cold Shutdown Condition within 24 hours.. I 1
/ !
Close isclation valves.in RCIC subsystem. k 2. I
- I) i
(
- 3. Close isolation valves in HPCI subsystem.
)
- 4. . Instrument set point corresponds to 378 inches above vessel zero. . f
) !
[ 5. . HPCI has only one trip system for these sensors. . g /
) +
- 6. @ith the number of OPERABLE channels less than requ' ired by the Minimum OPERESIT )
Channels per Trip System requirement, place at least one inoperable' channel in l 2
.the- tripped condition within one hedr or declare the RCIC system inoperable
/ j
/ !
- 7. The f ailure of a 480V Emergency Load Center timer could result in the f ailure of #
- a 480V Emergency Load Center to re-energize following the loss of one or both /
fm offsite sources. Therefore.. Technical Specification 3.9.B.7 will apply when a t W M. , ' 480V Emergency Load Center timer is' not operable. ~
.. u % ^ om. J) ;
j I
-~n. -._ l
-k&h d h p~ga 7a d_ d iR] l Nb 0,9,10, l l,12,13,14, I S '
dad,IL. I -l j% l i i l i r
.. i Anendment No. III, II3,173 1l
' i c
APR 2 3 IH3 (
. i
Unit 2 , PBAPS NOTES FOR TABLE 3.2.B
- 1. With one or mere required channel (s) inoperable in one or more Trip Functions, place channel in trip within one hour or the reactor shall be placed in the Cold Shutdown Condition within ,
24 hours.
- 2. Close isolation valves in RCIC subsystem.
- 3. Close isolation valves in HPCI subsystem.
- 4. Instrument setpoint corresponds to 378 inches above vessel zero.
- 5. HPCI has only one trip system for these sensors.
- 6. Deleted l
- 7. The failure of a 480V Emergency Load Center timer could result in the failure of a 480V Emergency Load Center to re-energize following the loss of one or both offsite sources.
Therefore, Technical Specification 3.9.B.7 will apply when a 480V Emergency Load Center timer is not Operable.
- 8. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place inoperable channelin trip; and,
- 2. Within one hour from discovery of loss of feature initiation capability in both trip systems for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (1)).
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated supported features inoperable immediately.
- 9. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, restore channel to Operable status; and, 2.' Within one hour from discovery of loss of initiation capability in both trip systems for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (2)).
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated supported features inoperable immediately.
- 10. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place inoperable channelin trip or align affected (HPCI or RCIC) pump suction to suppression pool; and,
- 2. Within one hour of discovery of loss of initiation capability, declare affected system (HPCI or RCIC) inoperable if associated pump suction is not aligned to suppression pool.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated system inoperable immediately.
(1) Only applicable to the High Drywell Pressure and Reactor Low-Low-Low Water Level functions. (2) Not applicable to Reactor High Water level Function.
Unit 2 PBAPS With one or more required channel (s) inoperable in one or more Trip Functions: 11.
- 1. Within one hour from discovery of loss of ADS initiation capability in both trip systems, declare ADS valves inoperable; and,
- 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable, place inoperable channelin trip; and,
- 3. Within 8 days from discovery of inoperable channelif both HPCI and RCIC are Operat,le, place inoperable channel in trip.
4 If required actions and associated completion times of Action 1 or 2 or 3 are not met, declare ADS inoperable immediately.
- 12. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within one hour from discovery of loss of ADS initiation capability in both trip systems, declare ADS valves inoperable; and,
- 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable, restore channel to Operable status; and,
- 3. Within 8 days from discovery of inoperable channelif both HPCI and RCIC are Operable, restore channel to Operable status.
- 4. If required actions and associated completion times of Action i or 2 or 3 are not met, declare ADS inoperable immediately.
4
- 13. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place channelin trip; and,
- 2. Within one hour from discovery of one or more automatic functions with primary '
^ containment isolation capability not maintained, restore primary isolation capability.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, isolate affected penetration flow path (s) within one hour.
- 14. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place inoperable channelin trip; and,
- 2. Within one hour from discovery of loss of system (HPCI or RCIC) initiation capability, declare affected system (HPCI or RCIC) inoperable.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare affected system (HPCI or RCIC) inoperable immediately.
- 15. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours provided
. associated Trip Function maintains trip capability.
- 16. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours.
l 1
- 72a - 1 l
, . p> yo e,/
. bk:
- t- v ; :s, ,
~ -
...- t o.. .
TAl".t U 4. 2. H ' IllHIHilet TEST K~lill Cist'.llifiKTION FREQllENCY FOR CSCS , Instrument Channel Instrument Fitnctlonal- Test- Calll[ratinn Prectuency Instrument Chuck
- 1) Heactor Water
. Level (7) r S h (3) Once/ operating cycle Once/ day
- 2) Drywell Pressure *
(7) - + h (3) Onco / operating cycle Once/ day
- 3) Reactor Pressure (7) -gh (3) Once/ operating cycle. Once/ day
- 4) 'Itoactor Pressure - <
PC TS/I.PCI intorlock --5 h Onco /3 months None
- 5) Auto Sequencing HA g Tiinarn Once/ operating cycle Hone 8
- 6) ADS - I.PCI or CS i
)
Punip plach. Pressure ,, i Once/3 months Hone
, Interlocks
- 1) Trip System Hun Power flont tors h NA Hone
- 8) Core Spray Sparger d/p yh Once/6 months Once/ day
- 9) Steam T.ine Illgh 5h Flow (IIPCI f. RCIC) Once/3 months ,
None
- 10) Steam Line Illgh IIA Flow Timers (IIPCI Once/ operating cycle Hone and B,CIC)
- l 11) Steam 1.Ine liigh Temp. (llPCI & HCIC) h (3) Once/ operating cycle once/ day '
- 12) Safeguards Area Illgh Temp. Sh once/3 montha Hone Ameaniment flo. EP., 97. JPS. log /112 N (c, eu / a ,. -.L . -
anne 10, l'aus
-m,-- -.
-+ - , . . . , ,-.,..,,,-7
-.n,- ---+,y.--.-,- .-- - , ,- - , ,- y , ,, ,,- 7 ,,.r.. - , - . -, -,- ,n 6 y e ~,
. + ;[ 31 -
Vll. , eQ% e] . [g 'yf
-{ m .
Unit 2l ,
-(yn g [ ,3 putov g o
[_ TABLE 4.2.8-(CONTINUED)
,o -MINIMUM TEST AND CAllBRATION FREQUENCY FOR CSCS'
?
Instrument Channel j f Instrument Functional' Test Calibration Frequency Instrument Check
~
g.g
- 13) HPCI and RCIC Steam Line Low
>h Once/3 months None g .* ,
Pressure h - g 14).HPCI Suction Source Levels h Once/3 months Nonc
~.s ^
- 15) 4KV Emergency Power Once/ operating cycle Once/5' years None System Voltage Relays (HGA.SV) ba 16) ADS Relief Valves Once/ operating cycle Once/ operating cycle None Bellows Pressure Switches
- 17) LPCI/ Cross Connect Once/ refueling cycle N/A N/A Valve Position .
- 18) Condensate Storage Once/3 months Once/ operating cycle Once/ day
~
t Tank Level (RCIC) (7)
~
l 19) 4KV Emergency Fower Once/ month 0nce/elghteen months None Source Degraded Voltage Relays (IAV CV-6,ITE) ,; i i. l .
- . . . . - ..__,.- _- _-_ -...~ ._- . - _ - - - _ _ . - _ _ _ _ _ . _ _ _ _ _ _ _ _ _
. 1 1
l o
\
[ /% . FEApS a t NOTES FOR TA3LES h.2.A TE:.0 UGH h.2.F
- 1. FInitially c ce every = cath. The ce=pilatics of instr =ent failure rate data =ay include data obtained frc= cther boiling vater .reacters for vhich the sa=e design instr =ent operates in an envirc =ent similar to that of PEAPS. The failure rate data =ust be reviewed and appreved b .
the AEC prior to any change in the cace-a- ceth frequency.7
- 2. Functional tests, calibraticas and instr =ent checks are cet required when these instr =er*.s are not required to be operable er are tripped.
Functic:al tests shC. be perfc=ed before each startup vith a required frequency ::: to e=ceed c=ce per veek. Calibratices sh=" be perfc med , within 2h hours 'cetere each. startup er ec=trc11ed shutdeve with a '
- l. required frequency Oct to e=ceed cace per veek. Instr =ent checks shan be performed at least cace per day during those periods vhen the inst =-
se=ts are required to be operable.
- 3. This instr =entatic: is e=cepted frc= the functic al test definitics.
The functional test vill ec sist of 1 Jecting a si=ulated electrical signal into the =essurement eb- e1. These instr =ent we =- els vill te calibrated using si=ulated electrical signals.
+. h.
S4--1ated autc=atic actuatics sW11 be perfc=ed cece each cperating cycle. Where possible, all icgic syste= recticani tests vill te
-7
. perfor=ed using the test jacks.
5 F.eacter icv vater level, high dryvell pressure and high radiatic: =ain sten: line tunnel are cet included c: Table L.2.A since they are tested c Table h.1.2.
- 6. The icgic syste= functie:a1 tests shall include a calihratic ct ti=e
~
delay relays and timers necessar/ for proper functiccing cf the trip systc=s.
,7 These channels ccusis cf =- 'eg trans=itters , indicaters and electronic Trip units.
OI-Amend:en: Uc. 30/2c Ja uar/ 3, 1977
Docket N3. 50-278 License No. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 > ATTACHMENT 5B MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.B (UNIT 3) List of Pages Affected: 57 (ECCS requirements relocated to Page 57a) 57a. New page 64 Table 3.2.B 65 Table 3.2.B 66 Table 3.2.B 67 Table 3.2.B 68 Table 3.2.B 69 Table 3.2.B 70 Table 3.2.B 71 Table 3.2.B 71a- Table 3.2.B 71b Table 3.2.B 72 Table 3.2.B (Notes) 72a Table 3.2.B (Notes) New page 81 Table 4.2.8 81a Table 4.2.B 87 Notes of Tables 4.2.A through 4.2.F 1
PBAPS . w LIMITING CONDITION FOR OPERATION ~ '. SURVEILLANCE REQUIREMENT - 7 g ._ 3.2 PROTECTIVE INSTRUMENTATION ~ 4.2 PROTECTIVE INSTRUMENTATION ~
- t. w
[Aeplicability: Aeolicability i~~~~'- Applies to the plant in-- . Applies to the surveil-strumentation which initi-- lance. requirement of the ates and controls a pro- . instrumentation that ini-i N tective function. tiates and controls pro ,!
..tective function. \
Objective: Objective:
\
\
t To' assure the operability To specify the type and i i of protective instrumenta- frequency of survoi31ance , I tion. to be applied to protec- / tive instrumentation. / SoecificEtions - - - Scecifications: / A. Primarv Containment A. . Primarv Coiitliiissht - Isolation Functions ' Isolation Functions
)
When primary containment Instrumentation shall be
, integrity is required, the functionally te.sted and i limiting condit4cns of calibrated as indicated in g joperation for the instru- Table'4.2.A.
,y. .. imentation that initiates y primary containment isola- System logic shall be (tion are given in Table functionally tested as in-3.2.A.-
-. _dicated in-mTable m..
.._ 4.2.A...
. Core and Containment B. Core and Containment
Cooline Systems - Cooline Systems - Initiation & Control Initiation & Control . N. I The limiting conditions Instrumentation shall be N. l for operation for the in- functionally tested, cali " l strumentation that initi- brated and checked as in- I l ates or controls the core dicated in Table 4,2.B. l and containment cooling k systems are given in Table System logic shall be { 3.2.B. This instrumenta- functionally tested as in- / i tion must be operable when . dicated in Table 4. ' I i the system (s) it initiates '____.- or controls are required to be operable as speci- ./,...~ fled in Section 3.5.._. ' ' et . "X jh m d T~g gg , e,a f ej y ~- -. ..
, m xs-
~ K . ~],
< . Lt.E,.x.E 3. 2. 4 s
_,, thLowcf 7a ,nu.>- FM'
- 7)'
- v .- x_ /
APRIL 1973
PBAPS ! UNIT 3 ! l UMITING CONDITIONS FOR OPERATION LIMITING CONDITIONS FOR OPERATION I I
- 3.2 Protective Instrumentation (Continued) 4.2 Protective Instrumentation (Continued)
B. ' Core and Containment Coolina Systems - B. Core and Containment Coolina Systems - l Initiation and Control Initiation and Control j i e Core and containment cooling system initiation Instrumentation shall be functionally tested, and control instrumentation for each Trip calibrated and checked as indicated in Function in Table 3.2.B shall be Operable; and, Table 4.2.B. ; there shall be two Operable or tripped trip systems for each Trip Function except as noted System logic shall be functionally tested as in Table 3.2.B. indicated in Table 4.2.B. l 1 Apolicability; j Each Trip Function listed in Table 3.2.B shall be j
- Operable whenever the system (s)it initiates or l controls are required to be Operable as i specified in Section 3.5. I f
~ Conditions and Reauired Actions:
With one or more channel (s) required by Table l 3.2.B inoperable in one or more Trip Functions, ! take the Action required by Table 3.2.B. l l 1 1 I I i I i i i l I i
- 57a - l l
f 1 j [l.
.m.t 3.2.D ,
I tiltrPIIMF.llT ATIOt1 TilAT Ill1TI%TES Olt COffTRnT.S Tile CO!tF. A'ID CO!!TAIllitF.*lT CDal.IllG SYliTEMS , I - i. ! Mlist miin t:o. liitmher of Instru-nt Oper.1 tile Bemarka I nst riimen t Trip Feinction Trlp I,cVel Setting' nent Channels Pro-e
' cle,annel n Por ;
vided by Dentgn ,'
- CUo Tr tLi SYut eQn?T )- ~aa=
k ta ll in. Antilca ted 4 IIPCI C itCIC Initlates llPCI L ltCtcl R t 04)(.s) pr'.act o r f.ov-f,ou lovel Inst. Channeln
- Warnt f.nve t -
il Coro spray C 1. In conjunction with R ea cta r t.ou-f,ou-t.nu- 1-160 in. Indicated I,ou iteactor Prenstare I 2 levn1 ( til Itllit In strument j llater tevel nLtta a Coro Spray Shanne a g
^ \ ._ g' ,
4 ADS Instrument '$ . Channels s 2. In conjunctLon with T . con firmatory lou level llLgh Drywell
' Preneure, 120 second time delay and I.PCI .
or Core Spray pismp interlock inLtlates Auto Dloutlown ( ADG) .
- 3. Initlaten starting of DLesel Gesterators,
. at ri e
9 - 1 I e
j'
~
'~ .
- f. l. f-sJ . ..
4 l - -
..j s ,
,f a
e se
% 3 .
-l' '
!'! & TADLE 3.3.5 (CONTIWotal INSTauMENTtTION THtt leIITIATES OR CONTit0Ls THE CORE SHD CONTAlWH5NT ,
** ODOLING SYSTEMS e
.o
~
kielene No.
- Number of Instre-
- Of Operable pomerks Imetrument TrdP reaction Trip tsvol settlag ment Channele pro .
m vided by peelga u channele Per g Trip Systese@ ' RCT/of ra 3v peactor Nigh Heter e45 in. Indicated 2 Inst. Channele Tri e NFCI & SCIC gg) ~ i...ei tesotor Lou Level' evei 3*383 l'n above 3 Inst. Channele tur i.ee Prevents inadvertent [T h I vessel sero (3/3 operation of contain-
) 1 / linalde ehroudt core height) ment spray during
- accident condition.
3 Containment High !4p( 3 pelg 4 Inst. Channele Prevente inadvertent treeeure operation of contain-ment spray during
- ecoldent condition.
106 in. Indloated 3 Inst. Channele ads Permissive Q(g g jp} l Confirmatory I.ow l.sva l level . ,, 8 3 sigh crywell g 3 pelg 4 Inst. Chesnele 1. Initta'es t Coce sprays Pressure , LPCIgHFCI
- 3. Initiates starting.
15 of Dleaal Generatore t \ 3. Initiatee auto slow-down fansi in conjunction-(14)(15) , with Low-tow-Low peactor s water level, 120 second time delay, and I.FCI or Core Spray , pump running. A ce
- Dug b
e ie.
, a
= c - -
t , . . I ' TABLE 3.2.D (Cont'd) INSTittlHENTATIOll TIIAT TilITI ATES Olt CbtrillOI.S TIIE CORE At3D cot 1TAltIHEllT COOLltlG SYS'IEHS Hinimum 110 - cf Operable ilumber of Instru- - Instrucent Trip Function Trip Level Setting ment Channela Pro itemarks Cl nn Per vided by Dealgn 2I(%)(id. Reactor Low a00-500 pa19 4 Inst. Channela Permissive for' opening Prenauro core Spray and LPCI Admission valyca. Coincident with high dry well pressure, atarta LPCI and Core Spray pumps. 2 hi)(.if) neactor Low 200-250 pa19 4 Inst. Channela Perminalve for clouing Pressure Hacirculating Putnp placharge Valve.- ., 1* 1
)( neactor Low. . 50sPs75 pal's 2 Inst. Channela In conjunction with PCI t -) Pressure aignal permita closure of DilR (LPCI) injection valves.
v ' Amendment flo. 68 /67 (5/5/80) ( ..- i'-
Unit 3 j ..! o [I3 PDAPS Q i r TABLE 3.2.0 ! -1 INSTRUMENTAT10N TilAT INITI ATES OR CONTROLS Tile CORE AND CONTAIHMENT COOLING SYSTEMS , Minimum No. cf Operable Humber of Instro-Trip Function Trip Level Setting ment Channels Pro- Remarks Instrument vided by Design Channeis Per ' Trip System h 9 f - Core Spray Pump 6 +/ I sec. 4 timers All pumps-loss of offsite 2 ((fC( -- power only 13 sec. +/-7% of setting .2 timers ALC pumps-offsite power Start Timer availabic 23 sec. +/-7% of setting 2 timers 000 pumps-offsite power i available ti 480V Emergency 3 +/-0.5 sec. 4 timers All timers - loss of 1 per offsite power only 4kVbus(7) load Center Timer 2 sec. +/-7% of setting 4' t,imers LPCI pumps A&B-l ,! 9 LPCI Pump Start LPCI pumps C&D 4 timers 2f[M)(nd T Timer (four Pumps) 8 sec. +/-7% of setting i i 90</=t </=120 2 timers In conjunction witit low ADS Actuation
$ 1 (f 2)(I:0' Timer seconds Reactor Water level, liigh i - Drywell Pressure and LPCI
. or Core Spray Pump running
, interlock, initiates A05.
ADS Bypass Timer a < /=t ( /=10 4 timers in conjunction with low
;r. 2 fl i L) { ii reactor water level, bypasses
,N minutes high drywell pressure Q
'$ initiation of ADS.
8 s
" Is - T Defers ADS actuation RilR (LPCI) Pump 50 +/- 10 psig 4 channels h 2f(1Q [th s pending confirmation'of'
.P t -
Discharge Pressure Low Pressure Core' Cooling Interlock - system operation (LPCI
' y, Pump running interlock). 1 105 +/- 10 'ps ig 4 channels Defers A05 act6ation d' . d O '. l 2 (I Core Spray Pump pending confirmation of low D L M_ Discharqe Pressure Pressure Core cooling j.* Interlock system operation (Corc Spray
_.y Pump running interlock) D l t ,
' ' ^ *~
_ l, ,,. },
- 1 -f i * -
.s . . _ . . . . - . . . . . . _ . . _ , .--
, - - . . . . . . s . _ . . --...a-~
4
.TADI,tt 3. 2. R - (Cent'd)
. INSTRUMENTATION Tilh? ' INITIATES OR CONTROLS Tile CORE AND CONTAINHENT '
' COOLING SYSTEMS ,
1Hinimua No. . Number of Instru-a ent ' Trip Function Trip 'I.evel Setting 1 Channels Pe- ({dedby gn
~
"""#h*'
, Trip Syste (1) t AcTfon); *
+
b ~
. RHR - (LPCI) Trip NA'
' System bus ~ power 2 Inst'. Channels Honitors availability '
monitor , of power to. logic' . . systems. , 1 Core Spray Trlp . HA
~
System bus power , a, 2. Inst. Channels Honitors availability monitor -
- of power to logic systems.
. I b ADS Trip System bus NA power monitor 3 Inst. Channels Honitors availability I -
of power to logic systems. g 1 + llPCI Trip System bus NA 2 Inst. Channels
., power monitor Monitors availability 8
. of power to logic systems.
1 / RCIC Trip System bus HA 2 Inst. Channels power monitor Honitors availability
.of power to logic
_ b. systems. * (Dh l l t 1 l AH 4 7 /47 October 10, 1978 ,. ,i,
lb(g. , t.. j; y i t i j . j
,7 f
, .)
u - ' l TABLE 3.2.Il (CONTINUED)
.?.
INSTRUNENTATION TilAT INITIATES OR-CONTROLS TIIE CORE AND CONTAINNENT .
. COOLING SYSTENS w Rinimum No. .
- E .Of Operable Instrument Trip Function Naimber of Instru-U Channels Per Trip Level.. Setting ment Channels Pro- .
Remarks Tr1p System vided by Design
~
4 . . g 1 ( 1-}) < Core Spray Sparger. 1 (plus or minus s to Reactor Pressure 1.5) paid - 2 Inst. Channels Alarm to detect core { Vessel d/p- ' spray sparger pipe m break. 9 2 (1) + Condensate Storage Greater than or 2 Inst.' Channels
, Tank I.ow Level equal to 5' above Provides interlock tes - ,e llPCI pump suction tank bottom valves.
2 4 Suppression Chamber Less than or 2 Inst.) Channels tilgh I.evel equal to 5 above Transfers llPCI pump torus midpoint auction to - suppression chamber. 2 (6) A Condensate Storage Greater than or Tank Low Level equal to 5' above 2 Inst. Channels Transfer RCIC pump tank bottom suction to suppresslein chamber. (aXia . (zXid s
~
e 9 9 e G ' t t 8 = a __ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ . - _ . _ _ _ _ _ _ _ _ _ ._ _ . _ - _ - _ _ _ _ _ _ . _ _ _ . _ . _ ~ . . . , - - . m.-, . - ~ _ .
MEtB & 2.B -(CollTIllt Iij-
^
i.
' .llSTHUtlENTATIOll TIIA? ; INITIATES OR CONTilOld ..rtlE COltE: AtID CollTAll LENT
- COOLillG SYSTlutS . .
Mi n i murs No. Of . Oparable . Instrument Trip Punction tlumber of:Instru- .
' Channels Per Trip Level Setting ment Channels Pro- Itemarks Trip Syste # vided by'Dealgn l-I h RCIC Turbine liight . .
Flow f 450" 11 O(2) 2 Inst. Channela 2 ' c - 1 RCIC Turbine liigh 3 1.I seconda 2 Inst. Channels t Flow Time Delay
' 2 0 .
Y! RCIC Turbine Com- 1200 deg. F (2) ' partment Hall 4 Inst. ) *
.s 116 Inst.
6 A
- RCIC Steam Line 1200 deg. F'g(2) I'
- Area Temp. 12 Inst. ) '
2 6 RCIC' Steam Line 100) p> 50 palg (2) Low Pressure 4 Inst. I t ilPCI Turbine Steam .f225" Ilp o (3)- Line lijgh Flow 2 Inst. Channela 4, ' 1 IIPCI_ Turbine liigh 311 seconda Flow Time Delay 2 Inst. Channels *
,m 3
ds)(ld . i r i i { # *alentiment flo. 100/102 .:-
\
July 2, 1984
' I," (*.
]
._f
- --,r , n ,. , . . - . - - - - - . - , ~ . - - , . - , , - - . - , . .- -,- r -,~ - - ----- - - --- --_ _ - ------ - - -- - -----.-
P(de'j j WE l 'h
' ^
y y-
.s. . -
; } ..
TADT.E 3.2.11 - (CONTINUED) INSTR 1R1ENTATION TilhT INITIRTES OR COHTROI.S Tile CORE AND CONTAIllHENT
- COOT.ING .S'ISTEMS tlinimum No.
of operable . . Humber of Instrument Instrument ' Trip Funct!on . Trip I.evel. Setting channels Per Channels - Remarks Provided hy Trip System h # Dealgn 4(5) %. HPCI Steam I.ine 100>p>50 psig (3) 4 Inst. I.ow Pressure . 2
- IIPCI Turbino
^ ' * <200 deg.F (3) 4 Inst.)
Compartment 7 - hhIS) i Temperature ' )
-).
4 <J; IIPCI Steam I,lne ) ,
<200 deg.F (3) G Inst.) 16 Inst.
- i. . Area Temperature e i ) ,
4 I ' Y 2 <~ .
)
IIPCI/RifR Valve <200 dog.F (3) 4 Inst.) Station Area Temperature 1 []) I.PCI Cross-Connect Position NA 1 Inst.. Initiittaa annun-clation uhen valve is not closed. 1 per 4KV 4.KV Emergency Bus , 25t(+51)of Rated Hndervoltage Relay voltage 1. Trips all loaded Huaf -- (IIGA) * - breake rs,
- 2. Fast transfer
.perminalve. ,
- 3. Dead bus start of diesel.'
1 per 4KV 4KV Emergency Bus 951(4 01.-101)o f ' Sequential f.oading 11ated voltage - Permits sequential f~ unaf[m'J) nelay (SV) - ' starting of vital 3 cads
- t I e Altl0HflmOHf lIO. 97 [ 9#I NDr5l Il- NN
h f' il' '% kh?b - (a ; TABLE 3.2.B (CONTINUED) INSTRUMENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. Of Operable Number of Instrument Trip Function Trip Level Setting Instrument Remarks Channels Per Channels TripSystemh# r ded by 2 per 4KV Emergency 60% (15%) of rated 1. Trips emergency Bus (f , Transformer vol ta ge.' Test at transfer feed O Undervoltage (IAV) zero volts in 1.8 to 4kV emer-(Inverse time- seconds (110%). gency bus. m voltage) 2. Fast transfer y permissive. 3 2 per 4KV Degraded 98% of rated voltage 1. Trips emergency y voltage (27N) +0.3% of setting transformer feed c-g Bus (fI) ("non-LOCA" relay) T4077 volts + 12 volts) to 4KV
- 0.9 - 1.1 second internal time delay emergency bus.
60 second i 5% (13 sec.) 2. Fast transfer l { a time delay permissive. R 2 per 4KV Degraded 89% of rated voltage 1. Trips emergency 3 voltage (27N) 1 0.3% of setting transformer feed [ Bus (N ((l) ("LOCA" relay) (3702 volts i 11 volts) 0.9 - 1.1 second internal time delay to 4KV' emergency bus, g 9 second i 7% (1 0.6 sec) 2. Fast transfer a; time delay permissive. Q;
- 3. Safety injection
-, signal ' j required. t
*w,,
l 1 .
- = , _ _ . .
i .! ,il H. ~
. [I,9. jdj:1=: -.
-TABLE 3.2.B (CONTINUED) . Unit 3:
- INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT
. COOLING SYSTEMS Minimum.No. Number of of Operable Instrument Trip Function
~
Trip Level Setting Channels Remarks
' Instrument Provided by Channels Per Design Trip System h Emergency Trans- ' 87% (15%) of 1. Trips' emergency l 2 per-4 kV transformer feed
-Bus former Degraded Rated Voltage.
1 Tests at 2940 to 4kV emer-f h. voltage (Inverse gency bus. time - voltage). volts in 30 seconds
, 2. Fast transfer g (CV-6) (110%) ,
permissive. e e er 2. 8 8 O. it hw
- c. $
I I e - - . - . - - - - , -~ -. . . , . . , , , _ . . ~ . . . - . . - -- . - - - , . - . - , - ~
PBAPS
-. - .l -
~
'G. ,
7, . N TES ' F5R T ABLE 3.2.B_ WW 3_
~
,,.j/1; fshall be' two operab'le trip systems.Df-the first column cannot
/
of the trip systems, that trip system shall be placed in the tripped condition or k{/ L the reactor shall be placed in the Cold Shutdown. Condition within 24 hours. . 3 l
~ Close isolation valves in RCIC subsystem. 1
-2. )
_(--
.k '
'3 . Close isolation valves in HPCI subsystem. >
/
~,
4'. Instrument set point corresponds to 378 inches above ' vessel 2ero. / : j' J r-~ V
- 5. HPCI has, only one trip system for these sensors.
/
eber of OPERABLE channels less than required by the Minimum OPERAELE d '
.6. ;
Channels per Trip System requirement, place at least one inoperable channel in inoperable. ,
. the tripped condition within one hour or declare the RCIC system 3.
a} .~~The' f ailure of a 480V. Emergency Load Center timer could result in the f ailure of (..' g,.T f. 7..;a 480V Emergency Load Center to re-energize following the -loss of o u '- offsite sources. , , , T7 l 480V Emergency Load Center timer is not operable. - '
\ .
\ _
..- 7" ~ ~ . - . . - - - -
- m- _ . , . ~.-
t 6 ,. b AC pchgu. a 72g h b k 9, lo, I h I K l 1% I Q 15 Cov$ ll, 'y !' Amendment No. 74, II5, II7, j y~ 176 APR 2 31H1 1 9
-n. - - - . . ,. .. 3.
$ M.;. .. - .
~ - . .~..n,;-...
ym ; --
PBAPS NOTES FOR TABLE 3.2.B t
- L 1. With one or more required channel (s) inoperable in one or more Trip Functions, place channel t in trip within one hour or the reactor shall be placed in the Cold Shutdown Condition within 24 hours.
- 2. Close isolation valves in RCIC subsystem.
- 3. Close isolation va!ves in HPCI subsystem.
i 4. Instrument setpoint corresponds to 378 inches above vessel zero. f
- 5. HPCI has only one trip system for these sensors.
- 6. Deleted i
- 7. The failure of a 480V Emergency Load Center timer could result in the failure of a 480V i Emergency Load Center to re-energize following the loss of one or both offsite sources.
Therefore, Technical Specification 3.9.B.7 will apply when a 480V Emergency Load Center timer is not Operable. L
- 8. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place inoperable channelin trip; and,
- 2. Within one hour from discovery of loss of feature initiation capability in both trip systems
? for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (1)).
- 3. If required actions and associated completion times of Action 1 or 2 are not met, h
declare associated supported features inoperable immediately.
- 9. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, restore channel to Operable status; and,
> 2. Within one hour from discovery of loss of initiation capability in both trip systems for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (2)). $ 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated supported features inoperable immediately.
- 10. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place inoperable channelin trip or align affected (HPCI or RCIC) pump suction to suppression pool; and,
- 2. Within one hour of discovery of loss of initiation capability, declare affected system s- (HDCI or RCIC) inoperable if ascociated pump suction is not aligned to suppression pool.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated system inoperable immediately.
I r V (1) Only applicable to the High Drywell Pressure and Reactor Low-Low-Low Water Level functions. (2) Not applicable to Reactor High Water level Function. k-
+ _
Unit 3 PBAPS
- 11. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within one hour from discovery of loss of ADS initiation capability in both trip systems, declare ADS valves inoperable; and,
- 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable, place inoperable channelin trip; and,
- 3. Within 8 days from discovery of inoperable channelif both HPCI and RCIC are Operable, place inoperable channelin trip.
- 4. If required actions and associated completion times of Action 1 or 2 or 3 are not met, declare ADS inoperable immediately.
- 12. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within one hour from discovery of loss of ADS initiation capability in both trip systems, declare ADS valves inoperable; and,
! 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable, restore channel to Operable status; and,
- 3. Within 8 days from discovery of inoperable channelif both HPCI and RCIC are Operable, restore channelin Operable status.
- 4. If required actions and associated cornpletion times of Action 1 or 2 or 3 are not met, declare ADS inoperable immediately.
? 13. With one or more required channel (s) inoperable in one or more Trip Functions:
- 1. Within 24 hours, place channelin trip; and,
, 2. Within one hour from discovery of one or more automatic functions with primary containment isolation capability not maintained, restore primary isolation capability.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, isolate affected penetration flow path (s) within one hour.
) 14. With one or more required channel (s) inoperable in one or more Trip Functions: i 1. Within 24 hours, place inoperable channelin trip; and,
- 2. Within one hour from discovery of loss of system (HPCI or RCIC) initiation capability, declare affected system (HPCI or RCIC) inoperable.
- 3. If required actions and associated completion times of Action 1 or 2 are not met, declare affected system (HPCI or RCIC) inoperable immediately, i l
- 15. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours provided associated Trip Function maintains trip capability.
i
- 16. When a channelis placed in an inoperade status solely for performance of required Surve!ilances, initiation of required Actions may be delayed for up to 6 hours.
i > l e iQ r.
- 72a -
l
.(
n ; . 4, .
'v t ..; -
TATt-M 4.2.D l ygIDH1H TEST KlincAf.TiiiiKT10N FREQllEHCY FOtt CSCS
]natrument channel Instrument Functional Test- .
Calibration Frequency
- 1) neactor Water Instrument _ Check I.evel. (7) (1) (3) Once/ operating cycle Once/ day
- 2) Drywell Pressure h(3)
(7) Once/ operating cycle Once/ day
- 3) Reactor Pressure ,
-(7) (3) Once/ operating cycle- Once/ day
- 4) neactor Pressure -
PCIS/LPCI Interlock ' Once/3 months None
- 5) Auto Sequencing HA 4 Timern .
Once/ operating cycle None 8
- 6) f ADS - L'PCI or CS Pump Disch. Pressure i
Once/3 months None Interlocks
. I
- 7) Trip Systern Dus r)
Power flonitors / NA Hone
- 8) Core Spray
. Sparger d/p /
[ Once'/6 months Once/ day
- 9) Steam Line liigh Flow (llPCI & RCIC)\ [y (1)) Once/3 months -
None
- 10) Steam Line Illgh IIA Plow Timers (IIPCI Once/ operating cycle Hone and II,CIC)
- 11) Steam Line liigh M
, Temp. (IIPCI & ItCIC) '
(3) Once/ operating cycle Once/ day
- 12) Safeguards Area liigh Temp. j) h .
Once/3 montha Hone On&/3morb Amenilment. flo. ET, 77, /09, 109 /112 ~ ~ ' ,
, June in. 19u5 i i.
- 3 . ,
p;. _ jf}
)^
, av""' -
Unit 3 3ed ' TABLE 4.2.B (CONTINUED) MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional lest Calibration Frequency Instrument Check
- 13) HPCI and RCIC x -
Once/3 months None Steam Line Low ,
-Pressure ,
- 14) HPCI Suction Source Once/3 months None Levels
- 15) 4KV Emergency Power Once/ operating cycle Once/5 years None System Voltage Relays (HGA,SV) f, 16) ADS Relief Valves Once/ operating cycle Once/ operating cycle None .,
Bellows Pressure y e Switches
- 17) LPCI/ Cross Connect once/ refueling cycle N/A N/A Valve Position
- 18) Condensate Storage Once/3 months Once/ operating cycle Once/ day Tank Level (RCIC) (7)
- 19) 4KV Emergency Power Once/ month Once/elghteen months None l
- 3 Source Degraded
" Voltage Relays '
5 (IAV CV-6,ITE) s. 63 "r m e* P t i e
;, c .
l
. i e :-
m
, p,~
PEAPS ^ [ - NOTES FOR TA M h.2.A TEROUGH h.2.F ,
- 1. Init.ially once every month. The cc=p.ilation of instrt:= ant failure rate data =ay include data obtained frc= other boiling vater reactors for which the ss=e design instru=ent operates in an environ =ent simila- to that of PEAPS. The failure rate data natst be reviewed and approved by the AIC prior to any change in the once-a-month frequency.f
- 2. Functional tests, calibrations and instrment checks are not required when these instru=ents are not required to be operable or are tripped.
Functional tests shall be perfor=ed before each startup vith a required frequency not to exceed once per yeek. Calibrations skall be performed i within 2h hours before each startup or centro 11ed shutdown with a required frequency not to' exceed once pe'r week. Instru=ent checks ska be performed at least once per day during those periods when the instru-
=ents are required to be operable.
~
- 3. This instru=entation is excepted frc= the functional test definition.
The functional test vill consist of injecting a si=ulated electrical signal into the =casure=ent channel. These instrment channels vill be l calibrated using si=ulated electrical sig""'s. l
- k. Si=ulated autc=atic actuation skal' be perfor=ed once each operating ..
i l
"2 pN' cycle. Where possible, all logic system functional tests' vill be
.perfor=ed using the test jacks.
l I 5 Reacter lov vater level, high dryvell pressure and high radiation -='- stes= line tu=nel are not included on Table 4.2.A since they are tested en Table 4.1.2.
- 6. . The logie syste= funct'icnal tests shall include a calibration of ti=e delay relays and timers necessary for proper functiccing of the trip syste=s.
- 7. These channels consist of analog transmitters, indicators and electronic Trip units.
1 1 A
- c. nw .
l AI-Amend =ent No. 30/29 January 3, 1977 l l 1 l l
Docket No. 50-277 @ License No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 l of;.yg ATTACHMENT 6A MAHKUP OF CHANGES AND NEW PAGES FOR TS 3.2.C (Unit 2) List of Pages Affected: 58 Page replaced 73 Table 3.2.C (Notes) 74 Table 3.2.C (Notes) 74a Table 3.2.0 (Notes) 83 Table 4.2.C 87 Notes of Tab!es 4.2.A through 4.2.
. b' , ;
~
PBAPS - I i
. .; LIMITING CONDITICNS FOR OPERATION SUFVEILLANCE RECUIREMEFTS h, ,-
p ~~ Ceritre] Wr Rod rc Bicek Actuatien m-m.rm - .. C. .Centrol Rod Bicek Actuatien ~ E.
- 1. The limiting conditiens of . Instrumentatien shall be j' )
operation for the instru- functionally tested, cali- . ; mentatien that initiates brated and checked as indi-control rod blocks are given cated in Tabla 4.2.C. ( in Table 3.2.C. " ('. . System icgic shall be fune- i
- 2. The minimum number of oper- tionally tested as indica- '
- t. able instrument channels ted in Table 4. 2.C.
] ,
specified in Table 3.2.C-for the Rod Bleck Monitor ,y' l may be reduced by one in t ~
/ :
I cne of the. trip systems fer r l maintenance and/or - testing, h . provided that this condi-r,- , ; tien does net last icnger than 24 hours in any thirty /,/ .. ,m - _
~-
day period.
'j b( bgb A Nh g
'... 1
.s_- q 66 ,
__ j x_./ (T.\ m-
=.
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- i
)
1 i i l l I I I J 1 i i l
..-- -58_
Amendment No. 102/104 December 31, l'984 , l l 1
I PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protective instrumentation (Continued) 4.2 Prottetive Instrumentation (Continued) C. Control Rod Block (CRB) Actuation C. Control Rod Block (CRB) Actuation l The Control Rod Block Actuation Instrumentation shall be functionally tested, instrumentation for each function in Table 3.2.C calibrated and checked as indicated in shall be Operable; and, there shall be two Table 4.2.C. f Operable or tripped trip systems for each function except as noted in Table 3.2.C. System logic shall be functionally tested as indicated in Table 4.2.C. Aonlicebility: (1) The Rod Block Monitor (RBM) shall be Operable with setpoints as required by Table 3.2.C and the Core Operating Limits Report (COLR). The APRM,IRM and SRM Control Rod Block (CRB) functions shall be Operable whenever the Reactor Mode Switch is in the Startup or Run positions except as follows: The SRM and IRM functions are not required when the Reactor Mode Switch is in Run. The APRM and RBM functions are not required to be Operable when the Reactor Mode Switch is in Startup execpt for the APRM Upscale (Startup Mode) which is not required to be Operable when the Reactor Mode Switch is in Run. ! The scram discharge instrument volume high level rod block is required to be Operable l whenever the Reactor Mode Switch is in the l Startup or Run positions or in the Refuel j position whenever more than one control rod is 1 l withdrawn. Conditions and Reauired Actions: With one or more channel (s) required by Table 3.2.0 inoperable in one or more trip functions, , l take the Action required by Table 3.2.C. (1) Section 3.3.B.5 is Applicable during operation with a limiting control rod pattern. I
;- n, -
-i
~~
PBAPS- . JUnit 21 ..
-TABLE 3.2.C:
INSTRUMENTATION THAT INITIATES CONTROL ROD BLOCKS' Minimum No. Instrument ' Trip _ Level Setting ' Number of Instrument' Action Channels Provided-
~
of Operable Instrument.- by Design- gq)'
-Channels Per -
Trip System APRM Upscale (Flow Biased) (0.66W+59%-0.66aW) 6 Inst. Channels (10)' 4.(2) (Clamp at.108% max) L4 APRM Upscale -(Startup s12% 6-Inst. Channels. - (10 ) - +--- l l l3 Mode) 4 ' APRM Downscale' 22.5 indicated on scale 6. Inst. Channels (10) *-- , I (7)(11) p : Rod Block Monitor (Power Biased) (RTP 185%), Si, silTSP (65% 'sRTP <85%), S,, sITSP 2 Inst. Channels. %* (30% sRTP <65%), S., sLTSP b 'd i 1 (7)(11) _ Rod Block Monitor >DTSP 2 Inst. Channels - j O Downscale 8 6 IRM Downscale (3) 12.5 indicated on scale 8 Inst. Channels * (10) 6 IRM Detector not in (8) 8 Inst. Channels (10)- Startup Position i IRM Upscale s108 indicated on scale 8 Inst. Channels (10) g 6 SRM Detector not in (4) 4 Inst. Channels (1) k 2 (5) ' Startup. Position-3 SRM Upscale s10' counts /sec. 4 Inst. Channels (1) . 5 2 (5)(6) Scram Discharge s25 gallons 1 Inst. Channel (9) m 1
'i *. ,". ' Instrument Volume liigh level 3hh ..
m.
. . e .
, . . . - - - . _ - - - . . , . ~ _ . - - . _ . , - ~ . . , - . . . _ . . _ . . ~ . . . . - ~ - . - _ - - , - . . . . . . - . . . _ . . . . _ . , - _ . - . . - - - . , , - _ . . , . + . . , . . . . . , . _ . . . _ . . . , . . - - _ - . . ~ - . , - . , . . _ . . ~ . - . - . ~ _ - . . - _ . - - , _ -
PBAPS _- F0TES FOR TABLE 3.2.C NO .. 1. / For the startup and run positions of the Reactor Mode Selector Switch, ( there shall be two operable or tripped trip systems for each functic The SRM and IRM blocks need not be operable in "Run" mode, and the w gE>RBM rod blocks need not be coerable in "Startup" mode.f If the first column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable system-is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped. If the first column cannot be met for both trip systems, the systems shall be tripped.
- 2. W = Loop Recirculation flow in percent of design.
Trip level setting is in ' percent of rated power (3293'MWt). 4W is the difference between two loop and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting is accomplished by correcting the flow input of the flow biased rod block to preserve the original (two loop) relationship between the rod block setpoint and recirculation drive flow. 4W - O for two loop operation, j
- 3. IRM downscale is bypassed when it is on its lowest range.
- 4. This function is bypassed when the count rate is :t 100 cps.
M 5. One of the four SRM inputs may be bypassed.
- 6. This SRM function is bypassed when the IRM range switches are on range 8 or above. -
- 7. The trip is bypassed when the reactor power is s 30%.
- 8. This function is bypassed when the mode switch is placed in Run.
- Amendment No. M, 48,10 75, 123, IEA, ib2 l
l t _
PBAPS NOTES FOR TABLE 3.2.C (Cont.) cAs
'- 9. If the number of operable channels is less than equired by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within mne hour'. his note isX gyptintnr1Trthr"Ruii" mb^d'e7the~StWiip*'Tito~ ~ d the " Refuel" mode ifMs (more_ than one control rod is withdrawnf
- 10. For the Startup (for IRM rod block) and the Run (for APRM rod block) positions of the Reactor Mode Selector Switch and with the number of OPERABLE channels:
- a. One less than . required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
- b. Two or more less than required by the Minimum OPEPABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour.
- 11. The values for HTSP, ITSP, LTSP, and DTSP are specified in the CORE
.0PERATING LIMITS REPORT.
e iZ, N 5 g' (n __
- - m T,d w idoDA '1. 'l> H "h l ) H.
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-74a- Amendment No. SS, 91, 13#,192
- ~___-._______m________ ____ ____ __ __ _ E_
L- ' Insert for Table 3.2.C Notes on Page 74a:
- 12. ' With one or more required Rod Block Monitor channel (s) inoperable;
- a. With one rod block monitor (RBM) channel inoperable, restore RBM b
channel to Operable status within 24 hours.
- b. If the required action and associated completion time in Action a above are not met, place one RBM channel in trip within 1 hour.
c, With 2 RBM channels inoperable, place one RBM channelin trip within 1 hour.
- 13. Section 3.3.B.5 is Applicable during operation with a limiting control rod pattern.
I-
- 14. When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated function maintains control rod block capability. ,
_ : gr
- 15. The scram discharge instrument volume has only one trip system.
l L-
-(~.
L l
. I El
. TABLE 4.2.C MINIMUM TEST AND CALIBRATION' FREQUENCY FOR CONTROL R0D BLOCKS ACTUATION Instrument Channel Instrument functional Test Calibration Instrument Check Once/ day
- 1) APRM - Downscale A (3) Once/3 months
- 2) APRM - Upscale. > (3) Once/3 months .
Once/ day Upscale (3) Startup or Control Shutdown (2)
- 3) IRM IRM - Downscale f (3) Startup or Control Shutdown (2)
- 4) Once/ day
, 5) RBM - Upscale A (3) Once/6 months Once/ day.
- 6) RBM - Downstale A (i (3) Once/6 months '
- 7) SRM - Upscale ( (3) Startup or Control Shutdown (2)
- 8) SRM - Detector Not in (2)(3) N/A (2)
Startup Position
- 9) IRM - Detector Not in (2)(3) N/A (2)
Startup Position
- 10) Scram Discharge Instrument Quarterly Once/ Operating Cycle N/A Volume - High Level 4-Logic System Functional' Test (4) (6) Frequency
- 1) System Logic Check once/ Operating Cycle I l
~
2 ~crL ma/ , kn . I a P i
~
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._. . . _ . _ . . . . - . _ _ . . . _ . . . . _ . _ . _ _ _ _ . - . , , . . - , . _ . -~_. . . _ . - , _ . . _ --...,,m., . ..,m ., .- - - - , - - .
r
, = l i
1 i G PEApS l l
\
NOTES FOR TABLIS h.2.A TE:.0 UGH h.2.F r L- -
- 1. Initially cece every = cath. The ec=pilatic: .
data may include data obtained frc= cther boiling vater reactors forcfinstrumentfailu khich the same design instrument operates in an envirc =ent s1=ilar to
- hat of p3ApS.
ghe AEC prier to a=y change in the cece-t- csth frequency. rThe failure 2. Functional tests , calibratices and instr.:=ent checks are not required when these instr.:=ents are ct required to be operable er are tripped. Functic al tests aba be perfor=ed before each startup vith a required frequency act to e=ceed cece per week. Calibraticas sba he performed . . vithin 24 hours before each sta.rtup or centrolled shu: deva vith a required frequenc'/ =ct to e=ceed cace per veek. Instr.:=ent checks sba he perfor=ed at least cece per day during these periods when the instru-
=ents are required to be operable.
- 3. This instr.:=entatic: is e=cepted frc= the functional test definitic=.
The functional test vill consist of injecting a si=ulated electrical signal into the =casure=ent channel. These inst:.::ent channels vill te calibrated using si=ulated electrical sie d, s.
~. h. S4
; ated autc=atic actuatics shall be perfc:=ed cuee each operating cycle . Were possible, all legic syste= functic:al tests vill te
. perfor=ed using the test jacks. .
'5 Reacter icv vater level, high dryvell pressure and high radiatic: =ain steam line tunnel are act included c: Table h.2.A since they are tested 4
c: Table k.l.2.
- 6. The logic system functional tests shall include a calibraticu cf time
~
delay syste=s. relays and ti=ers necessary for proper functiccing of the trip
, T. These channels censist of =-*'eg tra rrdtters ,1:dicators and electronic Trip t=its.
. ~
i-9 I~ A=endment No. 20/29
.Tacuary 3,1977
Docket N3. 50-278 License No. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 1
. ATTACHMENT 6B MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.C (UNIT 3)
List of Pages Affected: 58 Page replaced 73 Table 3.2.C (Notes) 74 Table 3.2.C (Notes) l 74a Table 3.2.C (Notes) i 83 Table 4.2.C j 87 Notes of Tables 4.2.A through 4.2. l l,
PBAPS . LIMITING CONDITICNS FOR OPERATION SURVEILLANCE RECCIREME27TS ,
,a
_ , . . . - .. _ _ . ~ - , f: Centrol Red Bleck Actuatien C. Centrol ' Red Bicek Actuab ed\ ~
#. s '
1 The limiting conditiens of Instrumentatien shall be operatica for the instru- functionally tested, cali- )
- i mentaticn that initiates brated and checked as indi-centrol red biccks are given cated in Table 4.2.C. )
in Table 3.2.C. ( System icgic shall be func- ) ~ The minimum number of cper-2. able instrument channels ticnally tested as indica-ted in Table 4. 2.C. -
)
suecified in Table 3.2.C
~
fcr the Red Block Mcnitor ' may be reduced by cne in ene of the trip systems fer maintenance and/cr testing, . provided that this condi-tien does not last 1cnger than 24 hours in any thirty
' b\
day pericd. v / d bA.co Q Mk /m ) ~~
~ fQ x.
EO. _ w a.x ! ~ k- Amendment No. 102/104 December 31, 1984
PBAPS UNIT 3 ,
, t
, UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS -
'3.2 Protective Instrumentation (Continued)' 4.2 Protective instrumentation (Continued) [
C. Control Rod Block (CRB) Actuation C. Control Rod Block (CRB) Actuation
. The Control Rod Block Actuation Instrumentation shall be functionally tested. l instrumentation for each function in Table 3.2.C calibrated and checked as indicated in shall be Operable; and, there shall be two Table 4.2.C. t Operable or tripped trip systems for each !
function except as noted in Table 3.2.C. System logic shall be functionally tested as indicated in Table 4.2.C. i Applicability: (1) [ t The Rod Block Monitor (RBM) shall be l Operable with setpoints as required by Table 3.2.C and the Core Operating Umits Report
- (COLR). l The APRM,IRM and SRM Control Rod Block ,
(CRB) functions shall be Operable whenever ; the Reactor Mode Switch is in the Startup or ! Run positions except as follows: l The SRM and IRM functions are not l required when the Reactor Mode Switch is in Run. l The APRM and RBM functions are not > required to be Operable when the Reactor -? Mode Switch is in Startup except for the [ APRM Upscale (Startup Mode) which is not required to be Operable when the Reactor ; Mode Switch is in Run. . The scram discharge instrument volume high level rod b;ock is required to be Operable whenever the Reactor Mode Switch is in the j
- Startup or Run positions or in the Refuel position whenever more than one control rod is - i withdrawn. - ;
Conditions and Reauired Actions: , With one or more channel (s) required by Table ' H 3.2.C inoperable in one or more trip functions, take the Action required by Table 3.2.C. l l (1) Section 3.3.B.5 is Applicable during operation with a limiting control rod pattern. !
~~
4 .
.4. - Fh'$ (j s ,f );
I h) ( PBAPS Unit 3 TABLE 3.2.C INSTRUMENTATION TilAT INITIATES CONTROL R00 BLOCKS Minimum No. Instrument Trip level Setting Number of Instrument Action of Operable Channels Provided In'strument by Design Channels Per J et Trip System - 4 (2) APRM Upscale (Flow Biased) (0.66WtS9%-0.66aW) 6 Inst. Channels 4 (10) (Clamp at 108% max) 4- APRM Upscale (Startup s12% 6 Inst. Channels 4(10) Mode) 4 APRM Downscale 22.5 indicated on scale 6 Inst. Channels > (10) 1 (7)(11) Rod Block Monitor ' (RTP 185%), S., sitTSP (65% sRTP <85%), S , s! TSP
'2 Inst. Channels >Q (Power Blased) 12 (30% sRTP <65%), S., sLTSP 4 1 (7)(11)'(l 3) Rod Block Monitor Downscale
>DTSP 2 Inst. Channels Sh l y
6 IRM Downscale (3) 22.5 indicated on scale 8 Inst. Channels ' (10) 6 IRM Detector not in (8) 8 Inst. Channels (10) Startup Position 6 IRH Upscale s108 indicated on scale 8 Inst. Channels (10) SRM Detector not in (4) 4 Inst. Channels (1) 2 (5) Startup Position SRM Upscale s10' counts /sec. 4 Inst. Channels (1) . 2 (5)(6) Scram Discharge s25 gallons 1 Inst. Channel (9) 1 (;5) 30 Instrument Volume , ,- liigh Level $3 -~- tat w M w
~w ba
__ -,,m.. . . - _ . ,-.- ... . _ - . _ . - _ . . -. - - - - . .. . . . -
. . . . _ . m _. - _ , _ . . .
PBAPS ~~~_s _ NOTES FOR TABLE 3.2.C yhnE M _
~
cy 1. Jor thGartup and run positions of the Reactor Mode Selector Switch, - Mr- there shall be two operable or tripped trip systems for each functio The SRM and IRM blocks need not be operable in "Run" mode, and the APRM ' a RBM rod blocks need not be coerable in "Startuo' mode.fIf the firs column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable i system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped. If the .first column cannot be met for both trip systems, the systems shall be tripped.
- 2. W = Loop Recirculation flow in percent of design.
Trip level setting is in percent of rated power (3293 MWt). AW is the difference between two loop and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting is accomplished by correcting the flow input of the flow biased rod block to preserve the original (two loop) relationship between the rod block setpoint and recirculation drive flow. AW = 0 for two loop operation. l ,
- 3. IRM downscale is bypassed when it is on its lowest range.
- 4. This function is bypassed when the count rate is :t 100 cps. ;
f 8w 5. One of the four SRM inputs may be bypassed. ,
- 6. This SRM function is bypassed when the IRM range switches are on range 8 or above.
- 7. The trip is bypassed when the reactor power is s 30%. >
-8. This. function is bypassed when the mode switch is placed in Run.
l e Amendment No. 33, 4I, 62, 77,
- I"- .
, g150,153, DCT 181993 1
Tnit 3
~
PBAP~S gN 0c, AruAA NOTES FOR TABLE 3.2.C (Cont.) w b"
- 9. If the number of operable channels is less than r quired by the minimum operable channels per trip function requirement,/ place the inoperable channel in the tripped condition within sne houd (This note 1sh
~
r apMTcable in~th~e Run" mod 6~thF"Startup" mode ~ind the " Refuel" mode 3-2-. L more than one control rod is withdrawn _,._.7 L . _ _ . . . .
- 10. For the Startup (for IRM rod block) and the Run (for APRM rod block) positions of the Reactor Mode Selector Switch and with the number of OPERABLE channels:
- a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
- b. Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour.
- 11. The values for HTSP, ITSP, LTSP, and DTSP are specified in the CORE OPERATING LIMITS REPORT.
g..
- g. , m ... - - - q 12 ws m
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- w. _
l l l l I l 4 1
-74a- Amendnent No. B8, 93, If 3,184 1
. . OCT 181993 I
l
E , p
'i nsert for Table 3.2.C Notes on Page 74a:
i l l
- 12. With one or more required Rod Block Monitor channel (s) inoperable: :
. a. With one rod block monitor (RBM) channel inoperable, restore RBM channel to Operable status within 24 hours.
- b. If the required action and associated completion time in Action a above are not met, place one RBM channel in trip within 1 hour.
- c. With 2 RBM channels inoperable, place one RBM channel in trip within 1-hour. ;
l 13.' . Section 3.3.B.5 is Applicable during operation with a limiting control rod pattern. l
- 14. .When a channel is placed in an inoperable status solely for perfo'rmance of ;
required Surveillances, initiation of these Actions may be delayed for up to .
~ 6 hours provided the associated function maintains control rod block capability.
g- , n ,
" 15. The scram discharge instrument volume has only one trip system. j I I b-I p ;
- k. '
p b1 l i t l 1
- ,&= .
%. 4 s
I
,1 ,
.a
}lA Oi i Unit 3?
TABLE 4.2.C MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION
- Instrument Channel Instrument Functional Test Calibration Instrument Check
~
1)(3) Once/3 months' Once/ day 1)' APRM - Downscale
- 2) _APRM - Upscale (3) Once/3 months Once/ day 3). IRM - Upscale 2)(3) Startup or Control Shutdown (2)
- 4) IRM - Downscale 2(3) Startup or Control Shutdown- (2)
- 5) RBM - Upscale 3) .Once/6 months Once/ day Once/6 months- Once/ day
- 6) RBM - Downscale
--( )(3)
- 7) SRM - Upscale- ( (3) Startup or Control Shutdown (2)
- 8) SRM - Detector Not in (2)(3) N/A (2)
Startup Position
- 9) IRM - Detector Not in (2)(3) N/A (2)
Startup Position . .
- 10) Scram Discharge Instrument Quarterly- Once/ Operating Cycle N/A Volume - High Level hi logic System Functional Test,(4) (6) Frequency ,,
l 1) System Logic Check Once/ Operating Cycle l k cm/A _ ,dl
?
M t-h O ty1 E i e i.
C , ,
+ --
~
- m -
PEAPS , . D , NOTES FOR TAME h.2.A TEROUGH h.2.F ,
- 1. Inidany once every renth. .The ce=p.ilation of instru=ent failure rate data =ay include data obtained from other boiling water reactors for which the sa=e design instru=ent operates in an environ =ent similar to that.cf PEAPS. The failure rate data =ust be reviewed and approved by .
the AEC prior to any change in the once-a-nonth frequency.f
- 2. Functional tests, calibrations and instrument checks are not required
, when these instru=ents are not required to be operable or are tripped.
Functional tests shan be perfo:=ed before each startup with a required frequency not to exceed once per veek. Calibrations shall be perfor=ed vithin 24 hours before each startup or controlled shutdown with a required frequency not to' exceed once pe5 veek. Instrument checks ska be performed at least once per day during those periods when the instru-
=ents are required tc be operable.
- 3. This instru=entation is excepted frc= the function =' test derinitien.
The functional test vill consist of injecting a si=ulated electrical signal into the measurement channel. These instru=ent c5 a--els vin be calibrated using si=ulated electrical signals. . -- . k. Si=ulated autc=atic actuation shan be perfo::ed once each operating .. h. cycle. Where possible, all logic system functional tests' vill be
.perfor=ed using the test jacks.
- 5. Reactor lov vater level, high dryven pressure and high radiation main stea= line tunnel are not included on Table 4.2.A since they are tested on Table h.1.2.
- 6. The logic syste= funct'ional tests shan include a calibratien of ti=e delay relays and ti=ers necessary for p:-oper functiccing of the trip syste=s.
T. These chacels censist of a-a'og transmitters, indicators and electrenic T-ip units. T-A=e=d=ent No. 30/29 Ja=uary 3, 1977
Docket N3. 50-277 License No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 l ATTACHMENT 7A MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.D (Unit 2) List of Pages Affected: , 59 Page replaced 75 Table 3.2.D 84 Table 3.2.D 87 Notes of Tables 4.2.A through 4.2.F
l Unit 2 l PBAPS ,
@ SURVEILLANCE REOUIREMENTS
[ LIMITING CONDITIONS FOR OPERATION
.2.D. Radiation Monitorina 4.2.D. Radiation Monitorina'\
Systems-Isolation and Systems-Isolation and' , Initiation Functions ! Initiation Functions 1.' Reactor Buildina Isolation 1. Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System
.The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D. ___
brated and checked as indi-
- 2. Main Control Room System logic shall be The limiting conditions for functionally tested as b operation are given in indicated in Table 4.2.D.
Table 3.2.D.
- 2. Main Control Room E. Drvwell Leak Detection Instrumentation shall be The limiting conditions of functionally tested, operation for the instru- calibrated and checked as mentation that monitors indicated in Table 4.2.D.
OI4 drywell leak detection are Drvvell Leak Detection given in Section 3.6.C, E.
" Coolant Leakage".
Instrumentation shall be
- calibrated and checked as indicated in table 4.2.
W e- - FLD A#' y Q M Q. wm l
# N L CG
'~~~
'Y Amendment No. 102. If0.184
. un a;5 W
PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Erotective instrumentation 4.2 Protective Instrumentation (Continued) (Continued) D. Badiation Monitorina Systerns-Isolation and D. Radiation Monitorina Systems-Isolation and initiation Functions Initiation Functions D.1. Reactor Buildina isolation and Standby Gas D.1. Reactor Buildina Isolation and Standby Gas Treatment System Treatment System The Reactor Building isolation and Standby Instrumentation shall be functionally tested, Gas Treatment System instrumentation for calibrated and checked as indicated in each trip function in Table 3.2.D shall be Table 4.2.D. Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as function. indicated in Table 4.2.D. Applicability: Refuel Area Exhaust Monitors and Reactor Building Area Exhaust Monitors shall be Operable whenever the associated systems are required to be Operable. Main Stack Monitor shall be Operable whenever the containment is purging and primary containment integrity is required. Conditions and Reauired Actions: (1)(2)
- 1. With one or more channels required by Table 3.2.D inoperable in one or more trip functions, place channel in trip within 24 hours.
- 3. With one or more automatic Functions with containment isolation capability not maintained, restore containment isolation capability within one hour.
- 3. If the required actions and associated completion times of Action 1 or 2 are not met, take the Action required by Table 3.2. D.
(1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains isolation capability. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases,if the inoperable channelis not restored to Operable status within ! the required time, the Action required by Table 3.2.D for that trip Function shall be taken. l 1 I 1 l
. ;A y .
' [' .L
+ ~4 4);. g Un t.2' PBAPS.
~
TABLE 3.2.D-RADIATION- MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No. of Operable Instrument No. of Instrument Channels Provided Action Channels'per Trip Trip Function Trip Level Setting by Design Q Upscale, <16 mr/hr 4 Inst. Channels A or B 2- Refuel Area Exhaust Monitor B 2 Reactor' Building Upscale, <16 mr/hr 4 Inst. Channels - ' Exhaust Monitors Upscale, 510' cps 2 Inst. Channels C-1 Main Stack Monitor Upscale, <400 cpm 4 Inst. Channels D Main Control Room 4l 2 m us-Notes for Table'3.2.D
'Whenever the systems are required to be operable, the specified number of instrusent channel If this cannot be met, the indicated shall be operable or placed in the tripped condition.
taction shall be taken. f
, @ Action ,
R Cease operation of the refueling equipment. g A. B. Isolate secondary containment and start the standby gas treatment system. g g C. Cease purging of primary containment, and close vent and purge valves greater than 2 inches t in diameter. D. As described in LCO 3.11.A.5' fl ~
^
3 (3) .Yhe trip function is required to be operable only when the contalnnent is purging ~tYrbugh'lhe~
- - SGTS and containment integrity is required. If both radiation monitors are out of service, -
. action shall be taken as indicated in Note'2, (C) f ~
g
~
- @ The trip function is required to be operable whenever secondary containment is required on '
W either unit.
;T f:)
,l s3
. l,I; 0 -
k 2p ! .it - 2 ;. PBAPS TABLE 4.2.D-MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS , Instrument Functional Instrument-
~
Calibration Check (2) Instrument Channels' Test (1) Once/3 months Once/ day
- 1) Refuel Area Exhaust' Monitors - Upscale Once/3 months once/ day
- 2) Reactor Building Area Once/3 months Once/12 months once/ day -
-3) Main' Stack Monitor as described in-e E 4.8.C.4.a 9
Once/3-months Once/18 months Once/ day
- 4) Main Control Room as described in 4.11.A.5 -
Loaic System Functional Test (4) 'f6) Freauency R Once/ Operating Cycle . E 1) Reactor Building Isolation S Standby Gas Treatment Once/ Operating Cycle 5 2)- z System Actuation o it
.~
4: 2 .* . 4 .~ _.
4 o L T ??sPS NOTES FOR TA3LES k.2.A TEROUGE h.2.F
, l-
- 1. fInitir.11y c=ce every = cath. The ec=pilatics of instr =ent failure rate data =ay i=clude data obtained frc= cther boiling vater .reacters for which the sa=e design instr =ent cperates in an envire==ect s4-9a- to that of PP.AFS. The failure rate data cast be revieved e=d approved by .
(the AIC prier to any chsage is the c=ce-a-aceth frequency. j
- 2. Functic a1 tests, calibraticas and instr =ent checks are not required when these instr.:=ents are cet required to be operable or are tripped.
Functional tests sba" te perfomed before each startup with a required frequency =ct to e=ceed cace ;er veek. Calibraticus sha" he perfc =ed within 2h hours before each. startup or ecstrelled shuedo.in vith a required frequency =ct to e=ceed c=ce per veek. Instr =ent checks sba" be perfomed at least c=ce per day during these periods when the instru-ments are required to be operable.
- 3. This instr =entatics is e=cepted frc= the functic=al test d'efinitica.
The functic a1 test v4.11 censist of injecting a si=.: lated electrical sig=al intc the =essur.=ent cha-ael. These instr =ent ebn- els vill be calibrated using si=clated electrical signals. n.. h. S4m'_ated aute=atic actuatica shall be perfe=ed once each operati:s- . . . . 7 cycle. Where possible, all icgic system functic a1 tests ill be
.perfc = ed using the test jacks.
5 Reacter icv vater level, high dr/vell pressure and high radiatics -n'- stea= line tu==e1 are act i: eluded c Table h.2.A since they are tested c: Table h.1.2.
- 6. The legic syste= r=ctie:a1 tests shall include a calibratic cf ti=e
~
delay relays and ti=ers necessarf for proper f=ctie ing of the trip syst e=s . i
,7 These cha= els censist of =-a'eg transmitters , indicators and electronic !
Trip units. 1 . ' i i
. I i
AY'.5=
~
A=endment ITo . 30/29
.Tacua / 3,1977
i l l Docket N3. 50-278 Ucense No. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 ATTACHMENT 7B MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.D (UNIT 3) Ust of Pages Affected: 59 Page replaced 75 Table 3.2.D 84 Table 3.2.D 87 Notes of Tables 4.2.A through 4.2.F l l I i
)
- Unit 3
- PBAPS
- l SURVEILLANCE REOUIREMENTS
,,,f" ^ 4'IMITING CONDITIONS FOR OPERATION I
/T'2 . D . .Rgdiation Monitorina 4.2.D. Radiation Monitorina '
Systems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions
- 1. Reactor Buildina Isolation 1. Reactor Buildine Isolation and Standby Gas Treatment and Standbv Gas Treatment System System I.
The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali- /
., _ Table._3 L D _ _ _ brated and checked as indi-/
* -- % N cated in Table 4.2.D. /
\[2. Main Control Room N, '
[ System logic shall be
.The limiting conditions f (functionally tested as >
operation are given in g (indicated in Table 4.2.D. Table 3.2.D. - Drvwell Leak Detection N E. Instrumentation shall be N The limiting conditions of functionally tested, ; 1 operation for the instru- calibrated and checked as
! mentation that monitors indicated in Table 4.2.D. ~ '. drywell leak detection are .
W "~ " ' given in Section 3.6.C, E. Drvwell L'eak Detection Coolant Leakage". Instrumentation shall be '
'\ calibrated and checked as indicated in table 4.2.E.
/
- )
, 4 ,..e Iass 64 (fb5U' &
fury t J#rc s l l d, l'.',_..~ l Amendment No. 104, 162. 189 MAY 0 6 GM
PBAPS UNIT 3 UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protective Instrumentation 4.2 Protective Instrumentation (Contnued) (Contnued) D. Radiation Monitorina Systems-Isolation and D. Radiation Monitorina Systems-Isolation and initiation Functions initiation Functions D.1. Reactor Buildina isolation and Standby Gas D.1. Reactor Buildina isolation and Standby Gas Treatment System Treatment System The Reactor Building isolation and Standby Instrumentation shall be functionally tested, Gas Treatment System instrumentation for calibrated and checked as indicated in each trip function in Table 3.2.D shall be Table 4.2.D. Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as function. indicated in Table 4.2.D. Applicability: Refuel Area Exhaust Monitors and Reactor Building Area Exhaust Monitors shall be Operable whenever the associated systems are required to be Operable. ; Main Stack Monitor shall be Operable whenever the containment is purging and primary containment integrity is required. Conditions and Reauired Actions:(1)(2)
- 1. With one or more channels required by Table 3.2.D inoperable in one or more trip functions, place channel in trip within 24 hours.
- 2. With one or more automatic Functions with containment isolation capability not '
maintained, restore containment isolation capability within one hour.
- 3. If the required actions and associated completion times of Action 1 or 2 are not met, take the Action required by Table 3.2.D (1) When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains isolation capability.
(2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur, in these cases,if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.2.D for that trip Function shall be taken. f^ r-Q s; j
.r.4 Q -.' 3 ..
" T Ur._d 3 PBAPS
' TABLE 3.2.D RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOIATE SYSTEMS .
Minimum No. of-Operable Instrument No. of Instrument . Channels per- Channels Provided Action Trip-System' . Trip Function Trip Level Setting by Design
- (0- Q 4 Inst. Channels A or B-2 Refuel Area Exhaust Upscale, <16 mr/hr Monitor Reactor Building Upscale, <16 mr/hr 4 Inst. Channels B 2 '
Exhaust Monitors Main Stack Monitor Upccale, $10' cps 2 Inst. Channels c-1 (3) Upscale, <400 cpu 4 Inst. Channels D l 2 (4 . Main Control Roon
'? '
Notes for Table 3.2.D - . . -
- 1. IWhenever the systems are required to be operable, the specified number of instrument channel]s
'shall be operable or placed in the tripped condition. If this cannot be met, the indicated f taction shall be taken.j -
I. '
$ 2. Action E Cease operation of the refueling equipment.
g A. ' Isolate secondary containment and start the standby gas treatment system. 5 B. Cease purging of primary containment, and close vent and purge valves greater than 2 inches z C. o in diameter. ' l D. As described in I40 3.11.A.5 ! ~ 3 The frip function is requiredTo be operable onlyIfwhen the contiainment is . purging 'tlirodgh~tTe) both radiation monitors are out of service,f O SGTS and containment integrity is required. action shall be taken as indicated in Note 2, JC).f-j ** E The trip function is required to be operable whenever secondary containment is required on + j either unit. ,
. i i,
,.'- p])[, Y ^ a Y
^
t II) _
,.-) -
. -- bilti 3 '
PBAPS
-. TABLE - 4. 2. D MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS i
l. i Instrument' Functional Instrument Instrument Channels Test Calibration Check (2) 1). Refuel Area Exhaust Monitors - Upscale g Once/3 months once/ day
-2) Reactor Building Area W Once/3 months Once/ day-
- 3) Main Stack Monitor Once/3 months once/12 months once/ day '
f as described in 4.8.C.4.a f 4)' Main Control Roon j Once/3 months once/18 months once/ day ,, ( ,p _ y,_., as described in
^5 cy)n/'3 yoJL) 4-Loaic System Functional Test (4) (6) Frecuency-E -
R 5 1) Reactor Building Isolation Once/ Operating Cycle , x I P 2) Standby Gas Treatment Once/ Operating Cycle
~ System Actuation
.I 4 .= ,
M= . . 5"
^Ge I i e ,
e - W ~- s i l @e FEAPS r
- 'd NOTES FOR TAFTE h.2. A THROUGH h.2.F ,
- 1. Initially once every =cnth. The ec=p,11ation of instrument failure rate data =ay include data obtained frc= other boiling vater reacters for which the same design instru=ent operates in an environ =ent si=ilar to that of PEAPS. The failure rate data must be reviewed and approved by the AEC prior to any change in the once-a-month frequency.f
- 2. Functional tests, calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Functional tests shall be perfer=ed before each startup vith a required frequency not to exceed once per yeek. Calibraticas sbil be perfor=ed within 2h hours before each startup cr centrolled shutdown with a required frequency not to exceed ence per veek. Instru=ent checks shall be performed at least once per day during those perieds when the instru-ments are required to be operable.
- 3. This instru=entation is excepted fre= the renetional test definitien.
The functional test vill consist of injecting a si=ulated electrical signal into the =casure=ent channel. These instrument eb- els vill te calibrated using simulated electrical sie, als.
- k. Simulated autc=atic actuatien sb'1 be perfer=ed ence each operating .
cycle. Where possible, all icgic syste= functienal tests vill be Q' "s <
,perfor=ed using the test jacks. '
5 Reactor lov vater level, high dryvell pressure and high radiatic: -a'- steen line tunnel are net included en Table k.2.A since they are tested en Table h.1.2. l
- 6. The logic syste= funct'icnal tests s% include a calibratien of ti=e l delay relays and timers necessa y for prepe: functiening of the trip l Syst, e=s .
T. These channels censist of ea'eg trans=itters, indicaters and electrcnic l Trip units. l l l l l i l I
~ .! l 1
I~ A=end=ent No. 30/29 Janna:7 3,1977 1 1
Docket ND. 50-277 License No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 ATTACHMENT 8A MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.E (Unit 2) MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.F (Unit 2) List of Pages Affected: 59 TS 3.2.D.2 moved to new page 59a 59 TS 3.2.E moved to new page 59a 59a New page 60 TS 3.2.F moved to new page 59a 85 Table 4.2.E i
^
[ Unit 2 PBAPS SURVEILLANCE REOUIREMENTS l'[M'
-! LIMITING CONDITIONS FOR OPERATION Radiation Monitorina 4.2.D. Radiation Monitorina 3.2.D. Systems-Isolation and 1
Systems-Isolation and Initiation Functions Initiation Functions
- 1. Reactor Buildina Isolation 1. Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D.
brated and checked as indi-cated in Table 4.2.D.
- 2. Main Control Room The limiting conditions for functionally tested as operation are given in indicated in Table 4.2.D.
Table 3.2.D.
- 2. Main Control Room
. / E, Drvwell Leak Detection Instrumentation shall be\i I
The limiting conditions of functionally tested, } operation for the instru- calibrated and checked as l mentation that monitors indicatedinTable4.2.D.f d$d drywell leak detection are E. Drvwell Leak Detection
, ~ '
given in Section 3.5.C,
" Coolant Leakage".
Instrumentation shall be calibrated and checked as N indicated in table 4.2.E. M ov atTo w gt.E9a l l l t
. s.
Amendment No. 102, If0,184 "ta 15 S4
PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS 4.2 Protective Instrumentation (Continued) 3.2 Protective Instrumentation (Continued) D. Radiation Monitorina Systems-Isolation and D. Radiation Monitorina Systems-Isolation and initiation Functions initiation Functions (Continued) (Continued) D.2 Main Control Room D.2 Main Control Room The limiting conditions for operation are instrumentation shall be functionally tested, given in Table 3.2.D. calibrated and checked as indicated in Table 4.2.D. E. Drvwell Leak Detection E. Drvwell Leak Detection The limiting conditions of operation for the Instrumentation shall be calibrated and instrumentation that monitors drywell leak checked as indicated in Table 4.2.E. detection are given in Section 3.6.C,
" Coolant Leakage".
F. Surveillance Information Readouts F. Surveillance Information Readouts The limiting conditions for the Instrumentation shall be calibrated and instrumentation that provides surveillance checked as indicated in Table 4.2.F. information readouts are given in Table j 3.2.F-. s } l
- 59a -
l
._ -- ' .. s) i
; h. . ', .
$,a g .
g . fl-a 3 _ TABLE 4.2.E f HINIMUM TEST AND CALIBRnTION FREQUEHCY FOR DRYWELL LEAK DETECTION d - Instrument Channel l M
- Instrument Functional Calibration Instrument Test Frequency Check p .
- R u? . .
- 1) Equipment Drain Sump Flow Integrator ,Q -
Once/3-months Once/ day t
,h 2) Floor Drain Qump Flow Integrator g-)(h
- 3) Drywell A t -n * 'b -
, Monitor i -
_________ _.__ _ _ ' ~- ~ ~ ~ -
. .a _
.r , . ,
PBAPS , Unit 2
~
~ L,I_MITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS g~ > [ Surveillance Information l' F. Surveillance Information ii Reacouts Reacouts ,
~ \
The limiting conditions for , . Instrumentation shall be l the instrumentation.that calibrated and checked as , provides surveillance in- s
., - indicated in Table 4.2.F.
s (formationreadoutsaregiven in: Table 3.2.F.: .- _.n,--- (. K
..- ~ . - - .
G., ,.A1 N 6 ate'R'o N n~sertion and Alternate Red Insertion and-l Recirculation Pumo Trio l . G. ~ Recirculation Pumo Trio
!The'1.imiting conditions for ~ -
. Instrumentation shall be the instrumentation that ,' - functionally tested and
. initiates. an' Alternate Rod o calibrated-as indicated on Insertion scram and trips -
~
. ~ " - Table 4.2.G.
' the reactor recirculation :- System-logic'shall be !
[ {pumpstolimittheconse- #- functionally tested as i quences of a failure to scram .{ indicated in Table 4.2.G. j during an anticipated transient. ._ j are given in Table 3.2.G. When - in the RUN or STARTUF Mode, the ' required minimum number of -
. instr.ument channels shall be 7 - -: 3' -- -'
. operable, with trip setpoints .A
- ^c ",. set consistent with the setting - ',
%_% L-
- NM(4 b specified in Table 3.2.G. The manual and automatic actuation i
- I
._/
/
logic, and actuation devices of both trip systems shall be
'(- f[ gg bd operable when in the RUN or STARTUP Mode.
M
)
E/WO rw.Y(A% W$D 4
. Amendment No. 141 o3-22-89
g n y.
- j. 3'
.g .
g . S TABLE 4.2.E x MINIMUM TEST AND CALTBRnTION FREOUENCY FOR DRYWELL LEAK DETECTION . es e . g - D Instrument Channel Instrument Functlonal
~
M
- Test Callbration Instrument Frequency Check n . -
D - R g . .
- 1) Equipment Drain sump riow Integrator . -g
- Once/3 month. Oncefaoy
,p 2) Floor Drain qump Flow Integrator -9 Once/3 months once/ day
- 3) Drywell Atmosphere Rad [oactivity -->
. Monitor Once/3 months 6nce/ day s .__
b iO
- ~
M ... a s . ~ - 1
,e o
D i e . .
- y -
1 Docket N2. 50-278 License No. DPR-56 i PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 1 ATTACHMENT 8B MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.E (Unit 3) i MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.F (Unit 3) List of Pages Affected: 59 TS 3.2.D.2 moved to new page 59a 59 TS 3.2.E moved to new page 59a 59a New page-- 60 TS 3.2.F moved to new page 59a 85 Table 4.2.E
- v. -
y 3 [ . PBAPS y;~geK . SURVEIT.TANCE REOUIREMENTS g " LIMITING CONDITIONS FOR-OPERATION-
- 3. 2. D. - ' Radiation Monitorina 4.2.D. Radiation Monitorina l Systema-Isolation and Systems-Isolation and '
' Initiation Functions- Initiation Functions l
- 1. - Reactor Buildincr Isolation 1. Reactor Buildina Isolation j and Standby Gas Treatment and Standbv Gas Treatment
^
System System ;
.l The. limiting. conditions Instrumentation shall be ,
for operation are given in functionally tested, cali-Table 3.2.D. brated and checked as indi- ! cated in Table 4.2.D.
. l2 '. Main Control Room System logic shall be .
-} .
The limiting conditions for
} - functionally tested as !
operation.are'given in ndicated in Table 4.2.D.
- l
-Table.3.2.D.
- 2. Main Control Room E. .Drvwell Leak Detection s
- Instrumentation shall be 3 -
functionally tested,
\~ The limiting conditions of- calibrated and checked as
\;. operation for the instru- ,
I mentation that monitors indicated in Table 4.2.D. t [ . drywell. leak detection are , ,
}
Drvwell Leak Detection
~~
given in Section 3.6'.C, E. i ,
" Coolant Leakage". i :
-e s Instrumentation shall be j
't i
}calibratedandcheckedasf'
\' indicated in table 4.2.E. ,
%___ j .
~
Meud re y l L & l
.C w:m,. ,
Amendment No. ZH, I62.189 ! MAY D 6 UM f i
PBAPS UNIT 3 r 8 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS c 3.2 Protective instrumentation (Continued) 4.2 Protective instrumentation (Continued) ,, d
'D. Radiation Monitorina Systems-isolation and D. Radiation Monitorina Systems-Isolation and initiation Functions initiation Functions
>- (Continued) (Continued) P D.2 M.a.jn Control Room D.2 Main Control Room s The limiting conditions for operation are given in Table 3.2.D. Instrumentation shall be functionally tested, calibrated and checked as indicated in Table 4.2.D. if - i E. Drvwell Leak Detection E. Drywell Leak Detection The limiting conditions of operation for the instrumentation shall be calibrated and instrumentation that monitors drywell leak checked as indicated in Table 4.2.E. detection are given in Section 3.6.C,
" Coolant Leakage".
1 F. Surveillance Information Readouts F. Surveillance information Readouts 3
- The limiting conditions for the instrumentation shall be calibrated and j instrumentation that provides surveillance checked as indicated in Table 4.2.F.
4 information readouts are given in Table 3.2.F. s. n A w E r
- 59a -
L-
. unit .$ o,
. i
, PBAPS 5'
.LIMITIE C'ONOTTIONS FOR OPERATION SURVEILLANCENEOUTREMENTS f'
l
- [F. - Surveillance
- Information. F. , Surveillance Information
. -Reacouts. Reacouts The_ limiting conditions for Instrumentation shall be I I the instrumentation that , . calibrated and checked as -
j prov' ides surveillance in- ~ indicated in Table 4.2.F. : formation readouts are given . -- ---- 7 in Table 3 g - heMY** Pp41 l G. Alternate Rod Insertion and G. !
.J'\ Recirculation Pumo Trio Recirculation Pumo Trio AlternateRodinsertienand^f
\ ,' !
T The limiting conditions for - Instrumentation shall be /
.\'1the instrumentation that functionally tested and ; !
initiates an Alternate Rod calibrated as indicated on ' i LInsertion'scramandtrips Table 4.2.G. ;
~~-
. I-the reactor recirculation System logic shall be I
' pumps to limit the conse -
functionally tested as
~
quences of a failure to scram indicated in Table 4.2.G. / t during an anticipated transient j are given in Table 3.2.G. When .. y , in the RUN or STARTUP Mode, the ;
, required minimum number of- ~~
instrument channels shall be ! operable with trip setpoints ' fi;.. . _ .;setconsistentwiththesetting specified in Table 3.2.G. The i
'C +
manual and automatic actuation : logic,-and actuation devices of l both trip systems shall be i operable when in the RUN or !
- STARTUP. Mode. 777 '
h% d N ! i w ( l l O - 60.. Amendment No. 143 o3-22-89
' ' 4-g, :s,y 'Qres}_
-) g j -
.,s -
g-
.~ ,
^
S TABLE 4.2.E [ MINIMUM TEST'AND CALIBRnTION FREQUEHCY FOR DRYWELL LEAR DETECTION
~'.
- Instrument Channel M ' Instrument Test Functional ' Calibration . Instrument Frequency Check e .
s 5 ' _ D, u . .. 1)- Equlpment Drain Sump Flow-Integrator 3 Once/3 months Once/ day
, 2) Floor Drain Sump Flow Integrator } Once/3 months
, Once/ day
. I
- 3) Drywell Atmosphere'Radloactivity --
(1) Once/3 months Once/ day
. Honitor e
i([ lI e e
. . - g n
s ( i,d - 8 ,, le
Dock't No. 50-277 Ucense No. DPR-44 l PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 P ATTACHMENT 9A MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.G (Unit 2) Ust of Pages Affected: 60 Page replaced 79 Table 3.2.G 88 Table 4.2.G < 9 l
)
l l
, ---.~~.--, ;
.,o.- = . - .
n ,1
.PBAPS ,
. Unit 2
- QMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
~
D.
=e ;4 [ Surveillance Information
~
l' F. Surveillance Information N , Reacouts , Readouts-
- T l
1
'The limiting conditions for
, Instrumentation shall be ;
the instrumentation.that -
, l provides.-surveil. lance in- .
s
.. w ' calibratedandcheckedas/
indicated in, Table 4.2.F. l
- ~ formation readouts are given
~
4 ! in: Table 3.2.Fi: w-M e, c _ l G. Alternate Rod Insertion and - [ . G. Alternate Red Insertion and - -
. ' ' Recirculation Pumo Trio - Recirculation Pumo Trio
~Ths'l.imiting conditions for ~ -
. Instrumentation shall be ,
i
'the instrumentation that 2.a.'l- functionally tested and 4
. . initiates an' Alternate Red- ~
-n ,, calibrated as indicated on Insertion scran and trips -- - .z 4: ' . Tabl e 4. Z.G.
'the reactor recirculation .
.* i- System-logic'shall be !
J- -{ pumps to limit the conse- A functionally tested as quences.of a failure to scram .y indicated in Table 4.2.G. f during an anticipated transient- ._ j are given in Table 3.2.G. When- ---- ,- in the- RUN or STARTUF Mode, the ' l' required minimum number of -- instr.ument channels shall be' _O -x r -- .:
.operabia with trip setpoints .:.'.
-9 5 set consistent with the setting-
~
4 specified in Table 3.2.G. The )
- I , WOM' -.LbM .
manual and automatic actuation logic, and actuation devices of both trip systems shall be . i
\%pww bd .
operable when in the RUN or - ' iSTARTUP Hode. tWN W (M ND
.~.
j
. . . . i k!. s
- Anendment No.141
~
o3-22-89
PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
~
3.2 Protective instrumentation (Continued) 4.2 Protective Instrumentation (Continued) G. Alternate Rod insertion (ARI) and G.L Altemate Rod Insertion (ARI) and Recirculation Pump Trio (RPT) ' Recirculation Pump Trio (RPT) ; Two trip systems consisting of two channels per Each RPT and ARI instrumentation channel trip system for each instrumentation function shall be demonstrated Operable by the that initiates an Alternate Rod insertion (ARI) performance of the Instrument Check, scram and trips the reactor recirculation pumps Instrument Functional Test, Channel Calibration (RPT)in Table 3.2.G shall be Operable; and, and Logic System Functional Test at the the manual and automatic actuation logic and Frequencies shown in Table 4.2.G. actuation devices of both trip systems shall be Operable. Applicability: Whenever the Reactor Mode Switch is in the Startup or Run positions. Conditions and Reouired Actions:(1)(2)
- 1. With one or more channels required by Table 3.2.G inoperable, restore channel to Operable status or place channelin trip within 14 days.(3) ,
- 2. With one instrument function with trip capability not rnaintained, restore trip capability within 72 hours.
- 3. With both instrument functions or an actuation device with trip capability not maintained, restore trip capability for one function within 1 hour.
- 4. ' If the required actions and associated ,
completion times of Action 1,2 or 3 are not i met, place the reactor in shutdown or refuel mode within 8 hours. (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, l initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function ; maintains ARl/RPT trip capability, i (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases,if the inoperable channelis not restored to Operable status within the required time, the Action required by Condition 4 for that trip Function shall be taken. (3) The action of placing the channelin trip is not applicable if the inoperable channelis the result of an
- inoperable breaker.
l
~
. /[ ,
'i sP TI,}4fs.2.G e[
- o
. a .
a INSTRllHENTATION TilAT INITIATES ALTERNATE RdD INSERTION . R' l AND RECIRCULATION PUMP TRIP - .s.
' .]
g ?, .
- ~
,,g '
~
. Minimum No. Instrument. Trip Level Settina Numberdfinstrument
'* of Operable -
Channels Provided ,
-' by Design.Per Trip w Instrument .
Channels Per . .y );; System M j Trin System -
. 4 f g,3 '...
. ~ "
O ' g l {1)(2)) . 7 4
~
l (1)* Reactor liigh Pressure i1120psl0], 2
}(3)(4) ,
[,1 2 Reactor Low-Low Water > -48 10 Indicated. '2 -' M : Level Tevel . V'(3)(4) V . s . M' g 3 INotes for Table 3.2.G ,
~~
'Y '
- i1. With the manual or automatic actuation logic or' actuation device of-a trip system inoperabl.e, declare . .
, the affected trip system (s) inoperable and take the actions of Note 3 or Note 4. -
} -
- 2. With the number of operable instrument channels less than the minimum number required by this table, g i declare the affected trip system (s) inoperable and take the:Jt;tions of Note 3 or Note 4. p
- 3. With one trip system inoperable,. place the inopbable tr'ip system in the tripped condit.lon, if .'
f possible, within one hour. If the inoperable trip system is not in the tripped condition within 48 hours, be in the SiluT00WN or REFUEL Hode within the next 8 hours. , l
- 4. With both trip systems inoperable, restore one trip system to an operable status and place the
/
inoperable trip system in the tripped condition within 48 hours or restore both trip systems to operable status within 48 hours. Otherwise, be in the Sl!UTDOWN or REFUEL Hode within the next ' ( 8 hours.
~ ~
\
-- - ~~-- - - - --
1
x' .- m '
"'Q. - . G'i
;;Jij
, ,.z J
3y p^ ~ .. .# 7 . . , .
.e.,.',..
- .. . 1J 1 LE 4.2.G. . . ..
. . 4
..E NINIMUM TEST AND CALIBRATION FREQUENCY FOR ALTERNATE R00 INSERTION AND RECIRCULATION PUNP-TRIP.
{a -l' .
~
ot . . . . . . ~ . Instrument Functional Test (1)". . Calibration Frequency (1)?/.v - o -2 u Instrument Channel- Instrument: Check (1) .
- e . a, .
.c.::. . .
a
..y
. = . - . . ... . .
,2 Reactor liigh ' Pressure once/ day- -
.- ;0pcg/ month f> j ,7:;. . Opce/ Operating Cycle
- M 6 ,o .
. . .e . :-
... . ._ ,. :( q". . :.. .~::1^ . ., .'. . .
S Reactor Low-Low Water Once/ day < Y'
. i, 2 .: ..!:.o . r./ . .'
!h?M 0 6c.e/ Operating Cycle. .TE
' .' u. - . eve .
o
. .. "Once."/s.onth.
, , %.: .,a.p.,
c.. . ,'. . ,d. ge .u-
-s
- a. n..t
- 26. .
c.,
. .- n, .
*. o "
* :s
..o 4 ..a. .. .n.i :. s.o e(. .3 . . ,N. c, . ...m.
N .. s 3 s u ...,. ,'. g., . ..,1
. .. m, g ,,., .. c . . . .
s . . . . .. g a . . .
.s.
. . . . .t ..4 . .
i, Logic System Functional
- Test (2) -
" ; '; 4* d ;. - . :?.fi Frequency'?!s h';Ijyi.k1._ , ,., ,. ' . . ,$
+ p - J .' '. :' & ,e5 j3 g g,
. , t. i"d -
b, . .:. Tri '.. :$f ,,; '
.; .i. . ' : %,. y ypq.;..:q:;u;y..";.-: '.. .. .: z Alternate Rod Insertion / Recirculation P -.1 Once./3..
'. :.w.4. , . . :. .. m.onth.s m
. . . f.C.. ,. .
; . ;n ... ; ;} . . 1. ,.
' Alternate Rod Insertion / Recirculation P Trip %W; r.y . .?iionce/Deerating'. Cycle'.'.'.9.V: 0J-
' 5( . W
.-(.pytr.k.:h'.M, ,l > ' ;' '-~' ,, ::. l : y i.. . .ff,. . ,.' @.[ly.tV.. .' i including air venting and breaker trip (
ca . . , s.
- ; * . .y ; -:. . .. 3 x, :s.
to . (.
- L, .
ff. .. - < u,y. ./: Ui/~
, . ,. . W;-Q.2
. . . .C. ;,.,,
,. 6 .
., :. y .
.~ . 3.;a R
.g ..
., . . , . ,c %.
. .. .p..s-- . . .
- a, . .'
~ :.
n Notes: '.
..'.~., .
q
..e.v.,
..... . x .,
- 1. In accordance with Table 4.2.B. These instrument channels'are the ~
same ones used'by.the Core anct l, Containment Cooling Systems. -
- 2. The recirculation pumps need not be tripped, '
- 4. '. .
.4
.- .n
- 3. This test, performed while shutdown, will include venting of the scram air header and tripping 'of the ,...5 recirculation pump breakers. The test will also verify operabjllty of the manual actuation logic.- ' . /.
6.; .. l -
. r. &G .
*'.* s t
. , . , / 4 ,
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l Docket No. 50-278 I License No. DPR-56 l PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 ATTACHMENT 9B MARKUP OF CHANGES AND NEW PAGES FOR TS 3.2.G (Unit 3) List of Pages Affected: 60 Page replaced 79 Table 3.2.G 88 Table 4.2.G [ t [ l 1
-_a
- Unit 3 -
i
'2 ~
PBAPS - l
- ~
l LIMITIE CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
, [F. . Surveillance Information F.
. Surveillance Inform -
,; _ Reacouts Reaoouts -
The limiting conditions for Instrumentation shall be ! the instrumentation that -s . calibrated and checked as / ; prov' ides surveillance in- indicated in Table 4.2.F. ) I
. formation readouts are given -
-r* O !
' in. Table 3 g hv.cVeMEW*Pl'd 7 C
- - - 1 fG. Alternate Rod Insertion and G. Alternate Rod insertion and N
\- - Recirculation Pumo Trio Recirculation Pumo Trio /
. . -The. limiting conditions for f
Instrumentation shall be g the instrumentation that functionally tested and : L initiates an Alternate Rod calibrated as indicated on '
\L Insertion' scram and trips Table 4.2.G. \
,:l != the reactor recirculation . System logic shall be ~ l i
pumps to 11mit the conse- ' functionally tested as ; ; _quences of a' failure to scram indicated in Table 4.2.G. / during an anticipated transient / are given in Table 3.2.G. When -- #
- in the RUN or STARTUP Mode, the '~
required minimum number of instrument channels shall be operable with trip setpoints
._ set. consistent with the setting SiL. ' specified in Table 3.2.G. The W
. manual and automatic actuation
~
},bothtripsystemsshallbe. logic, and actuation devices of I .
l operable when in the RUN or TARTUP Mod ^
] .
-- 1 1
+
l W Amendment No. 143
)
03-22-89 ; [
PBAPS UNIT 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protective Instrumentation (Continued) 4.2 Protective Instrumentation (Continued)
- G. Alternate Rod Insertion (ARI) and G. Alternate Rod Insertion and Recirculation Pump Trio (RPT) Recirculation Pump Trio [
Two trip systems consisting of two channels per Each RPT and ARI instrumentation channel trip system for each instrumentation function shall be demonstrated Operable by the that initiates an Altemate Rod Insertion (ARI) performance of the Instrument Check, scram and trips the reactor recirculation pumps instrument Functional Test, Channel Calibration (RPT)in Table 3.2.G shall be Operable; and, and Logic System Functional Test at the the manual and automatic actuation logic and Frequencies shown in Table 4.2.G. actuation devices of both trip systems shall be Operable. Applicability: Whenever the Reactor Mode Switch is in the Startup or Run positions. Conditions and Reauired Actions: (1)(2)
- 1. Wth one or more channels required by Table 3.2.G inoperable, restore channel to Operable status or place channel in trip within 14 days.(3)
- 2. With one instrument function with trip capability not maintained, restore trip capability within 72 hours.
- 3. With both instrument functions or an actuation device with trip capability not maintained, restore trip capability for one function within 1 hour.
- 4. If the required actions and associated completion times of Action 1,2 or 3 are not met, place the reactor in shutdown or refuel mode vithin 8 hours.
. (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains ARl/RPT trip capability.
(2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to Operable
- status within the required time, the Action required by Condition 4 for that trip Function shall be taken.
(3) The action of placing the channelin trip is not applicable if the inoperable channelis the result of an inoperable breaker. c
" +
) _; .
TautE:3.2.G-. ,
~EL INSTAtlHENTATION TilAT INITIATES ALTERNATE.R00 INSERTION o 1 AND RECIRCULATION PUMP TRIP N$
-o ? U Minimum No. Instrument tTrip Level Setting Number of Instrument of Operable Channels Provided' J [' by Design Per Trip
- g. Instrument System Channels Per y% Trip _ System w
. l Q1)(2pd l (1) .
Reactor liigh Pressure
- 11120 psig 2 (3)(4) -
@ ., Reactor Low-Low Water > -48 in. Indicated 2 (3)(4) l Level '
Tevel
. 2 u
;if .
' 5 for Table'3.2.G
~
'~bi. %
- 1. With the manual-or automatic actuation logic or actuation device of a trip system inoperable, declare the affected trip system (s) inoperable'and take the actit,as of Note 3 or Note 4.
- 2. With the number of operable instrument channels less than the minimum number required by this table, declare .the af fected trip system (s) inoperable and take the actions of Note 3 or Note 4. /
f
/
- 3. With one trip system inoperable,' place the inoperable trip system in the tripped condition, if / g; possible, within one hour. If the inoperable trip system is not in the tripped. condition within
/
48 hours, he in the SiluTDOWN or REFUEL Hode within the next 8 hours. [ ,
- 4. With both trip systems inoperable, restore one trip system to an operable status and place the inoperable trip system in the tripped condition within 48 hours or restore both trip systems to !
operable status within 48 hours. Otherwise, he in the SiluTDOWN or REftlEL Hade within the next , 8 hours. l 1 e
21 5x
- 1. _ d TABLE 4.2.G
~
]Q' "
k HINIMtM TEST AND CALIBRATION FREQUENCY FOR ALTERNATE ROD $NSERTION AND REC 1RC , a
~
Instrument Channel Instrument Check (1) Instrument Functional Test (1) Calibration Frequency (1) 8X F Once/ Operating Cycle
.E Heactor liigh Pressure Once/ day 0nce/monl}i
.E Reactor Low-Low. Water Once/ day } qance/monthj Once/ Operating Cycle g Level _ _ _
logic System Functional Test (2) m/3 ~~ti Frequency Alternate Rod Insertion / Recirculation Pump Trip Once/3 months Alternate Rod Insertion / Recirculation Pump Trip Once/ Operating Cycle including air venting and breaker trip (3) E
. g 3
3
~
Notes:
- 1. In accordance with Table 4.2.B. These instrument channels are the same ones used by the Core and Containment Cooling Systems.
- 2. The recirculation pumps need not be tripped.
- 3. This test, performed while shutdown, will include venting of the scram air header and tripping of the recirculation pump breakers. The test. will also verify operability of the manual actuation logic. g A
4.4 q . 61 . . . . . - _ .~ - .,_,c, . . _ . . . _ . _ . . . _
l Docket No. 50-277 l License No. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 ) TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 ATTACHMENT 10A MARKUP OF CHANGES AND NEW PAGES FOR THE BASES FOR TS 3.1 (Unit 2) List of Pages Affected: 47 51 52 53 53a 55 l l l l 1 I
l F3APS UE 2 f 3.1 2As?s ne reae == protecticn system a== aatically initiates a reae::: > scram to: , l1. P:sserve the integrity cf the fuel cladciing. I
- 2. P:sse:Te the integrity cf the : sac:== c clant syst em.
- 3. Minimi== the energy which sust be absc bed fcllowing a less of ecciant accident, and t udvertant criticality. >
hten there is no fuel in the reae . or, the scram serves ne functien; thersf==s, the react == p =tsc ice system is net recuired l to be cperable. -, 5.is specifi=atien pr:vides the limiting c=nditi==s f== ccera: .:n ' necessary te p sserre the ability cf the syntam t= perf :s its I intended f==ctica even d==ing per-M.s whe= instr = ment chan=els na, be out of service because of maintsnance. When necessarf, cne , channel may be made inoperahle fe: brief interva'* t-- ee-b e- l py asquired functis:nal tests and calibrati::ns.[r- yg
, ' ne reac.== p== tecti:n system is =f the dual e 'a s.el type Se system is made up cf two (Ref erenes subsecticn 7. 2 FSAR) .
E, ' indepe . der c irip systems, each ha ring twc subchannels cf tri :ine devices. %ct W'2nnel has an input from at least ene l inst == ment enannel which acnitors a critical parameter. . i t ne' outputs of the subchannels are combined in a 1 cut of 2 legie: i.e. an input signal en either cne er both of the subchannels w i - cause a trip system trip. Os outputs of the trip systems are - arranged so that a t ip en h=th systems is required t= producs a
- sacter scram. ,.
Ois system meets the intent of 1222 - 279 f== Nuclear Power Plan: , Pr=:eetica Systems. S e system has a reliability g:satt: than that of a 2 out of 3 system and somewhat less than that of a 1 cet j of 2 system. ;
- a '
With thif ezesytion of the Average Power Range Mcnit== (APRM) , channels 4 the Intermediate' Range Monitor (IRM) channels, the Main steam Isolation valve. closure and the yurbine step valve elesure,
- each subchannel has one instrument channel. hten the minimum '
l c=ndit' ion' for operation on the number of operable inst men: channels pe: untripped protection trip system is met er if it i cannot be met and the af f ected pretee.ic:n trip system is placed in
- a tripped c=nditien, the ef fec iveness - cf the p==tec icn system is !
l preserred. i Tivuut. APRM instrument channels are previded for each p==tec:icn
'- :: P O system. AFRM's A and I cperate - c=meacts i.n ene schchannel and f APRM's C and E cperate centacts in the cther subchannel. APEM's l B, .D and F are a :anged similarly in l 1
l
. Amendment No. 55, 129 l
p b
- lNSERT: Bases page 47 Allowed out of service times for repair and surveillance testing for Reactor Protection
- System instrumentation have been determined in accordance with General Electric
- report NEDC-30851P-A, " Technical Specification improvement Analyses for BWR Reactor Protection System," General Electric Company, March 1988.
ww f I
,Y 3 Nam *8 s .(.
A i
=
w :
.n ,.: ~. .2.0 RAsc.s (dat'dP .
W the c:her p ::m=:i:= ::ip syste=. Ia== p:::e=:i== ::ip sy::e= t i has c=e ==:e APM taa: is necessarf : =ee: the : -- ==:e: , required per c a=el. "his allevs the bypassing cf c=e A?M per ! p =tacti== trip sys:e= f : mal =:e=ance, tes:ing c: calibratien.
. Additic=al In channels have aise been previded t= allev f :
hypassing ' cf c=e such c:a==el. Tue, bases f== the scra= se::ing !
, f= - the M, APRN high reac::: pressure, reac:=r- 1=v vater >
1evel, M5: i c1=sure, ge= ara::: !=id rejecti==, turbine s::p valve
' ' c1=sure and Icas cd c==de=ser vacu== are discussed in . !
specificatien 2.1 and 2.2.
, , j I stru=estatics se=si=g drywell pressure is p:=vided t= deta=: a loss of c=clant se=ide== a=d i=itiate the c=re s s=dby c cling -
equipment. A high drywell pressure scram is p =vided at the sa=e setti=g as the c=re standby c cling systems (cscs) initia:i = := mini =i=e the energy whic: ==s: he ac=== eda:ed during a les: et c:=lan: acciden: and := preven: re:::= :: 'eriticali:y. Onis ins::=e=:2:i:= is a ha :=p :: :== rese::: vessel we:e: level iss::=e= 2:i =.
- Eigh radiati== levels i= the mais stea= 11=e tu=e1 aheve sta:
due t= the sc:=al nit:mgen a=d c yge= radicactivity is a: . i=dicati== cf leaking f:el. A scra= is i=itistsd whe=ever such
- [ radia i== level e==eeds fif tee: ti=es ner=al hachg::=d. One !
k-pu.pese cf this scra= is t= 11=1: fissi = pr:du=: . release m: :ha: 10 c?R Par: 100 guidelines are =c: e==eeded.. Discharge ef e=cessive a=c=ts cf radica=tivity t= the sita e=vi ==s is preve=:ed by the cff-gas trea:=en: system, which p :vides sufficie== delay time t= reduce fissi== p = duct release rates t: ' well helcw 10 CFR 20 guidelines. , A react == mede swit=h is previded which actuates c ' hypasses . :he varicus' scram fu=c:ic=s app cyria:e t= the particular plan: i
, operati=g status. Ref. paragraph 7.*.3.7 FSAR. ,
The manual scra= fu=cti=h is ac:ive is all =cdes, thus previding f== a ma=ual mez=s cf rapidl c== ::1 :=ds during all ' modes of reac == cperatic=. y i=serting The APRM (Eigh flu = 'i= Start-up c ' Refuel) systa= p =vides Jprotecti=n against e=cessive pcwer. levels and sh=== react : periods in the start-up a=d i=ter=ediate pcwer ra=ges.
~
The IRM system pr=vides protectics agai=st shcrt reac:== perieds in these.ra=ges. ~ The control rod drive scram system.is designed se that all cf the water. which is discharged- f cm the reac:= by a scram can be ac==amedated is the discharge., piping. 'The scram discharge vel ==e ac--~-da:es is e==ess cf 50 galle:s cf wa:e: a=d is :te 1:w pci== i= the pipi=g. No credit was taken f= enis vel =e in the design cf the disenarge piping as c== car:s
- x. .
. Amend:m=u Nc. Se#,
125 03/03/88 9 e f - - --
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s
- .c. s
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.. the a===== =f wa:e which =us: he a===== ia ed d=ing a
- ., sca=.
D=isc. ==::a1 cpe:sti = the discha::e vcLu=e is e==. :v: . i
+
hewever, sh=uld it fill with water, the water discharged t:
- e. e , .: . . .- .*- .- '.%. e . e n . . -. c-"
, . . . - - '. ' ..- *. ' e a --. .. .. da . e *. w'.. . . "...
weeld result- in slew sera = ti=es c
.i=serties. T: precluda this ce=::e= par:dal =s,. level e==:::1 switches redhave bee . p :vided i . the inst :=ent vel == which alar = a=d scrz:
the ' reac == when the vel =e of water reaches 50 call ==s. As
- indicated abcve, there is suf ficient vel ==e in tie pipi=g :=
ac=====date'the scra= with=ut i=pai =c= ef the sc a= ti=es
. er a==unt cf inserti== cf the e----' reds. nis f=== i==
shuts.the: react =: d=w= while suf fi=ie=t vel =e re=ai=s t= ac= - coate'the discharged wate: and precludes the situati==
.J ,. wp..J %. a s...
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. . e .4 -
its f===ti== adequately. A s==== rang e '::= iter (SEM) syste= is a*.se pr:vided :: s a.2J...4 e.... 1-..- eve? 4 .r. ,.J.....a...J.
,t
.i.i . . . . . . - - . . . . s.....
h Y has =C s::1: $u==~$==s {:e$t:a=Ce ;a:ag:3;h *I.f.~ .4 I5X.E) .
. .s... s , .s.
- e . =.u. n
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, . .e . , ., .cn.. ;. ) . . s. . . . s.... ,. , . . .u. .y,... 3s ...- . .
. . . ...J . e .8 3 .. ' ' . . .. .
' . .' "Run".=ede. '"h e A? E ' s c v e r ==1y th e pew e r r a ng a . he-
- Rw.'s and Ap?.'d.'s r := vide adequate c=verage is the start-up
-- and i=ter=ediate ra=:e. .
The high react : pressure, hich drywell press =e, reae::: 1:w . wate: level and scra= discharge v=1=e high level scra=s are required f== Startup and Ru= medes cf plant cperatic=. They are, theref=re, required t= be operatic =al f=r these medes cf react == cperati==. .
. s..e . e= ..a.- e.
. . . e.. . . . . s..a y , .s.
. .. . .... .- _s_.. . . .: . . s .. .s....s--.
.a .. .. . _. .a. 2..
Table 3.1.1 eperable in ethe Refuer zede ass =es that shifti=g t= the Refuel mede d=ing rea= = pcwer eperatic= d:es == di=isish the protectic= pr=vided by the sac::: p : ecti = systa=.
- The t= hine e==de=ser Icw vacuum scra= is. caly req = ired during pcwer eper,atics and must be bypassed t= start up the unit. .The main c==de=se: 1ew vacuu= trip is hypassed ===ept in the run pcsitten of the mode swit=h.
Turbine step valve elesure ec= s at 10% cf valve eles=e. Belew 220 psig t= hine first stage press =e (30% cf rated),
- the scra= signal due t= t= hine st=p valve elesure i.s bypassed because the f1= and press =e scra s are adequate t:
p:= ect.the amet= . I J t W. 117/121 .2/'.4/EE. .,49
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INSERT: Bases page 51 Channel functional test frequencies for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A,
" Technical Specification Improvement Analyses for BWR Reactor Protection System,"
General Electric Company, March 1988. f* N k&W
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3 a l Dacket ND. 50-278 Ucense No. DPR-56 i PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 ; TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 l ATTACHMENT 10B MARKUP OF CHANGES AND NEW PAGES FOR THE BASES FOR TS 3.1 (Unit 3) . i Ust of Pages Affected: ; 47 l 51 ! 52 l 53 53a l 55 i i i I I i
. .w; PBAPS UNIT 3 3.1 BASES The reactor protection system automatically initiates a reactor scram to:
- 1. Preserve the integrity of the fuel cladding.
~
- 2. Preserve the integrity of the reactor coolant system.
E 3. Minimize the energy which must be absorbed.following a loss of coolant accident, and praisent inadvertant criticality. Y when there is no fuel in the reactor, the scram serves no function; therefore, the reactor protectices system is not required' to be operable.
'This specification provides the. limiting conditions for operat on necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because of maintenance. When-necessary, one channel may be made inoperable for brief intervals to conduct r
~
krequire_d functional tests and calibrations.A[fd & Rug O s The reactor protection system is of the dual en nnel type (Ref erence subsect. ion 7. 2 PSAR) . The system is made up of two b; r independent trip systems, each having two subchannels of tripping devices. Each Whannel has an input from at least one instrument channel which monitors a critical parameter. The outputs of the subchannels are combined in a 1 out of 2 logic: i.e. an input signal on either one or both of the subchannels will cause a trip system trip. The outputs of the trip systems are arranged so that a trip on both systems is required to produce a reactor scram. This system meets the intent of IEEE - 279 for Nuclear Power Plant Protection Systesus. The system has a reliability greater than that of a 2 out of 3 system and somewhat less than that of a 1 out of 2 system. With t!ie exception of the Average Power Range Monitor (APRM) channels, the Intermediate Range Monitor (IRM) channels, the Main Steam Isolation valve closure and the Turbine stop valve closure, each subchannel has one instrument channei. When the minimum condition for operation on the number of . operable instrument channels per untripped protection trip system is met or if it cannot be met and the af fected protecticn trip system is placed in j a tripped condition, the of fectiveness of the protection system is l
,. preserved. p l
[. M inst sent channels are provided for each protection trip v system. APRM's A and E operate contacts in one subchannel and + APRM's C and E operate contacts in the other subchannel. APRM's B, D and r are arranged similarly in Amendment No. 6A, 132 .g_
M INSERT: Bases page 47 Allowed out of service times for repair and surveillance testing for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical Specification improvement Analyses for BWR ; Reactor Protection System," General Electric Company, March 1988. e.. I .,4 pts *
. - 1 l
l PEAPS Unit 3 c;
's 3.0 BASES (Cont'd) . .y * *##~
the other protection trip system. Each protection trip system
.has one more APRM than is necessary to meet the minimum number required per channel. This allows the bypassing of one APRM per ,
protection trip system for maintenance, testin'g or calibration. ' Additional IRM channels have also been provided to allow for. bypassing of one such channel.. The, bases for the scram setting
/ for the IRM, APRM, high' reactor pressure, reactor. low Qater '
level, MSIV closure, generator lead rejection, tu.rbine stop valve ) closure and loss of condenser vacuum are discussed in ' Specification 2.1 and 2.2.
)
Instrumentation sensing drywell pressure is provided to detect a
. loss of coolant accident and initiate the core standby cooling equipment. A high dryvell pressure scram is provided at the same setting as the core standby cooling syste=s (CSCS) initiation to minimire the energy which must be accommodated during a loss of j
coolant accident and to' prevent return to criticality. This instrumentation is a backuo to the reactor vessel water level l instrumentation. j i High radiation levels in the main steam line tunnel above that l due to the nor=al nitrogen and oxygen radioactivity is an indication of leaking fuel. A scram is initiated whenever such ; l ' radiation level exceeds fif teen ti=es ner=al background. The 1 s_ , purpose of this scram is to limit fission product release so that ;
10 CTR Part 100 guidelines are not exceeded. Discharge of ,
excessive amounts of radioactivity to the site environs is l prevanted by the off-gas treat =ent system, which provides sufficient delay ti=e to reduce fission product release rates to j well below 10 CFR 20 guidelines. A reactor mode switch is provided which actuates or bypasses the various scram functions appropriate to the particular plant operating status. Ref. paragraph 7.2.3.7 FSAR. The manual scra= function is active in all modes, thus providing for a nanual means of rapidly inserting control rods during all , modes of reactor operation.
';he APRM (High flux in Start-up or Refuel) system provides protection against excessive power levels and short reactor periods in the start-up and inter =ediate pcwer ranges.
1 The IRM system provides protection against short reactor periods ! in these ranges. The control red drive scram system is designed so that all of the - water which is discharged from the reactor by a scram can be accommodated in the discharge., piping. The scram discharge volume accccmodates in excess of 50 gallons of water and is the low point in the piping. No credit was taken for this volume in the
,/ design of the discharge piping as concerns m.
Amendment No. M132 4g_ 03/03/88 -
~ Unit 3 l 'o PBAPS e
SS 3.1 BASES (Cont'd) l the amount of water which must be accomodated during a scram. During normal operation the discharge volume is empty; however, should it fill with water, the water discharged to the piping from the reactor could not be accomodated which , would result in slow scram times or partial control rod insertion. To preclude this occurrence, level switches have been provided in the instrument volume which alarm and scram the reactor when the volume of water reaches 50 gallons. As indicated above, there is sufficient volume in the piping to accomodate the scram without impairment of the scram times or amount of insertion of the control rods. This function shuts the reactor down while sufficient volume remains to accomodate the discharged water and precludes the situation in which a scram would be required but not be able to perform its function adequately. A source range monitor (SRM) system is also provided to supply additional neutron level information during start-up but has no scram functions (reference paragraph 7.5.4 FSAR). Thus, the IRM and APRM are required in the " Refuel" and
" Start / Hot Standby" modes. In the power range the APRM a system provides required protection (reference paragraph ji;,'
f --L- 7.5.7 FSAR). Thus the IRM System is not required in the "Run" mode. The APRM's cover only the power range. The IRMs and APRMs provide adequate coverage in the start-up and intermediate range. The high reactor pressure, high dryvell pressure, reactor low water level and scram discharge volume high level scrams are required for Startup and Run modes of plant operation. They are, therefore, required to be operational for these modes of reactor operation. The requirement to have the scram functions indicated in Table 3.1.1 operable'in the Refuel mode assures that shifting to the Refuel mode during reactor power operation does not diminish the protection provided by the reactor protection systen. The turbine condenser low vacuum scram is only required during power operation and must be bypassed to start up the unit. The main condenser low vacuum trip is bypassed except in the run position of the mode switch. Turbine stop valve closure occurs at 10% of valve closure. Below 30% of rated reactor thermal power the scram signal due to turbine stop valve closure is bypassed because the flux and pressure scrams are adequate to protect the reactor.
;s, Amendment No. 121,193
-49
; l ' HM
. . . ,. . . _. . . ~ , . -. _
. ~ - . ,
v PBAPS Unit 3,
, t C. -
J 3.1; BASES ~(Cont'd.) ; 1 Turbine control valves fast closure initiates a scram based on; pressure switches sensing Electro-Hydraulic Control (EHC) system oil pressure. The switches are located be-tween fast closure-solenoids and the disc dump valves, and 4 are set relative-(500<P<850 psig) to the normal EHC oil
" pressure of 1600 psig gauge that, based on the small system
. volume,.they.can rapidly detect valve closure or loss of hy- !
draulic pressure. This scram signal is also bypassed when reactor thermal power is. lass than 30% of rated as indicated :
.by turbine first; stage pressure. ;
-The. requirement that the IRM's be inserted in the~ core when
-the APRM's read 2.5 indicated on the scale in the Startup and '
l Refuel modes assures that there is proper overlap in the
- neutron monitoring system functions and thus, that adequate coverage is provided for all ranges of reactor operat' ion.
l
-i '* Faw i
i i l l L r i r
'l i
i i i i s9l, .
~4e :
Amendment No.193 L
-50 _
i?R C 7 ISH I
. 1 PEAPS 1
i-
. N, . .
f#- k.1 EASES l f5- - ei n4 m functional' testing frequency used in this specifiention is A. based on,a reliability analysis using the concepts developed in reference (6). This concept was specifically adapted to the one out of two taken tvice logie of the reactor protection syste=. The analysis shows that the sensors are primarily responsible for the reliability of the reactor
~
protection syste=. This analysis makes use of " unsafe failure" rate ~ experience at conventional and nuclear power plants in a reliability model for the syste=. An " unsafe failure" is defined as one which negates channel operability and which, due to 'its nature, is revealed only when k the channel is fnsctionally tested or atte= pts to respond to a real signal. Failures such as blevn fases, ruptured beurden tubes, faulted amplifiers, and faulted cables, which result in " upscale" or "downscale" readings on i the reactor instru=entation are " safe" and vill be easily recognized by the operators during operation because they are revealed by an alar = or a scram. The channels listed in Tables k.1.1 and h.1.2 are divided into three groups for functional testing. These are: l A. On-Off sensors that provide a scra= trip function.
- 3. ' Anales devices coupled with bi-stable trips that provide a scram function.
**. l pd C. Devices which only serve a useful function during se=e restricted =ede !
ui of operation, such as startup or shutdown, or for which the only practical test is one that can be perfer=ed at shutdown. t i The sensors that =ake up group (A) are specifically selected frc= a=eng l the whole fa=ily of industrial en-off sensors that have earned an excellent reputation for reliable operation. 'During design, a geal of 0.99999 probability of success (at the 50% confidence level) vas adopted to assure j that a balanced and adequate design is achieved. The probability of success ' is pri=arily a function of the sensor failure rate and the test interval. A three-= cath test interval is planned for group (A) sensors. This is in keeping with good operating practices, and satisfies the design goal for the logic ccnfiguration utili:ed in the Reactor Protection Syste=, ) ( l To satisfy the icng-ter= objective of =aintaining a= adequate level of l
}
safety throughout the plant lifeti=e, a -4""~ geal of 0 9999 at the 95% confidence level is proposed. With the (1 out of 2) X (2) legic, this requires that each sensor have an availability of 0 993 at the 95% confidence level. This level of availability r.ay be naintained by adjusting the
- test interval as a function of the observed failure history (6). To facilitate I the imple=entation of this technique, Figure h.1.1 is provided to indicate I an appropriate trend in test interval. The precedure is as follows: I
- 1. Like sensors are pooled into one group for the purpose of data acquisition.- ._
-) ~
kg [M y 61 1 A=end=ent No. 30/29 J em -.. 1e-- ,
l l l INSERT: Bases page 51 Channel functional test frequencies for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A,
" Technical Specification Improvement Analyses for BWR Reactor Protection System " ,
General Electric Company, March 1988. Re N60 mg l
}
._ _ _ _ _ _ _ _ _ __ _ {
l
' PEA.PS *
- i. a i d%k.1 EiSES (Cont'd.)
g .
\
~
. The factor M is the exposure hours and is equal to the number of sensors-in a group, n, times the elapsed time T (M = nT).
- 3. The accumulated number of unsafe failures is plotted as an ordinate against M as an abscissa on Figure h.1.1. ~
- k. . . After a trend is established, the appropriate monthly test interval
.. to satisf/ the goal vill be the test interval to the left of the plotted points.
5 A' test interval of 1 month vill be used initially until a trend is established,,vhich is based on system availability analysis and j.., good sngineering judgnent plus operating experience. Group (31)* devices utilice an analog sensor followed by an,am:plifier and a bi-stable trip ci'rcuit. The sensor and a=plifier are active components and a failure is almost always acco=panied by an alarm and an indication of the ' source of trouble. . In the event of failure, repair or substitution can start i= mediately. ' An "as-is" failure is bue that " sticks" =id-scale i.
. and is not capable of going either up or down in response to an out- of-limit s . input. This' type of failure for analog devices is a rare occurrence
~ and is detectable by an operator who observes that one sig-a1 does not , )
track the other three. For . purpose of n-=1ysis, it is assumed that this .. !
-- rare failure vill be detectdd within tvo hours.
--r...
'The bi-stable trip circuit which is a part of the Group (31) devices can sustain unsafe failures which are revealed only on test. Therefore, it is necessary to test then periodically.
;(6) . Reliability of Engineered Safety iFeatures ,as a Function of Testing -
-Frequency, I.M. Jacobs, " Nuclear Safety", Vol. 9, No. h, July-Aug. I
- 1968,'pp. 310-312.
# -See note following Group (32)
~
~__
l
# o h
' Amendment No.' 30/29 _ ,
- January 3, 1977' - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ __ _. _ .__ __ _ _ _ _
i aa -
~
-A.1 nAsns (cont'd) . ,
b"'g "A study was conducted of the instrumentation channels included) - in the Group (D1) devices to calculate their ."unsaf e" f ailuro ratos. The analog devices (sensors and amplifiers) aru , predicted to hava The anbi-stable
'uncafe f trip ailure rate ofare circuits Icsspredicted than 20 Xto10-6 f ailt4re/ hour.
have unsafe failure rate of Icss than 2 X 10-6-failurcs/ hour. Considering the two hour monitoring interval for the analog
^
devices as acctuned above and a weekly tout interval for the bi-stable trip. circuit =, the design reliability goal of 0.99999 is attaine'd with ample margi'n. i
- The bi-stable devices are ' monitored dtiring plant operation to record their, failure history and establish a test interval
~
using the, curvc of Figure 4.1.1. There are numerouc identical' bi-stablo devices used throughout the plant's instrumentation
~
=, system. .Therefore, significant data on the failure ratos for. <
the bi-stable devices should be'apcumulated rapidly. . , The frequency cf . calibration: of the APM1 Flow Diasing'Notwork has been established as cach refueling outanc. The fles i
. biasing network is. functionally tested at least enco per mohth and in addition, cross ' calibration checks of the flow. inputs >
-to the flow-biasing network can be made during the functional l test.by direct noter rending. ~ There.are severil in~struments l which must be calibrated and it will take severalWhile daysthe to !
M(.Q. - perforn the calibration of the entir~c network. calibration is being performed, a zero flow signal will be sent to half of the APRM's resulting in a half scram and red block condition.- Thus, if the calibration were performed dur-inq , operation, . flux shaping would not be possible, , basedj en , experienco:st other generating stations, drift of instruments, such is . thoso- in the Flow niasing Network, is not significant l and.thorefore, to-avoid spurious scrans,. a calibration frequency
- of each refueling outage is'nstablished. !
Group (D2)* devices utilize an_ analog sensor Thefollowed by an sensor ilnd amplifier
-amplifior and a histabic trip circuit.
arc. activo components and~ a failure is almost always ~ accompaniod by an' alarm and an indication of the source of . troublu.. In. the event of failure, repair or substitution can l start l' mmediately., An "ac-in" f ailure is one that " sticks" l mid-scale and .is ~ not- tapabic of goingThis oither up or down in type of failurc ! response to an out-of-limits input. for analog- devices is a rare occurrence and is detcetabic track.the by
-an oporator. who observcc that .one signal ducs not* -
Qy 3 & dG Ff
'* Soc noto following Group (32)
, i Amendment No.' 30'/29l .
.(01/03/77T
y ,
. PEAPS ^
y W- ' A study was conducted of the instrunentatica enannels included in Group (32) devices to calculate their " unsafe" failure rates. The analog devices (sensors L and amplifiers) are predicted.to have an unsafe failure rate of less than 2 X 10-5 failures / hour. Th'e bistable trip circuits are predicted to have an unsafe failure j rate of less than 9 X 10-6 failures / hour. Considering the tventy-four hour monitoring interval for the analog devices and a monthly test interval for the ! l bi-stable trip circuits, the design reliability goal of 0 993 per channel is . i H attained. . As described in the above discussion for Group (A) devices, a per channel reliability of 0 993 yields an overall reliability of 0 9999 for this
- instr =entation. . !
a b 1 Note: Ahalog Icop indicators for Group (31) are located in the Control Room and therefore can be checked once per shift. Analog Loop indicators for faroup (32) are located, in the plant adjacent to the applicable equipment and ) therefore can be checked once per day. ( Group (C) devices are active only during a given porcion of the operational
} cycle. For exa=ple, the IRM is active during startup and inactive during full-power operation. Thus, the only test that is meaningful is the one perferned !
.. just prior to shutdown or startup; i.e. , the tests that are perferned jus .
, ( prior to use of the instr =ent. _
- Calibratics frequency of the instr =ent ca ~ el is divided into two groups. ,
l !. These are as follovs: - ,5
- * "< 1. Passive type indicating devices that can be ec= pared with like units cc a continuous basis.
- 2. Vacum tube er se=1-conductor devices and detectors that drift er lose sensitivity. t h
~
l. t i 6 Ameitament No. 30/29 -53a-
- January:3, 1977
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e . < , n a APRIL 1973 1330117d3dv5Mr.do uEgwnN
Docket No. 50-277 License No. DPR-44 PEACH BO'ITOM ATOMIC POWER STATION, UNIT 2 TECHNICAL SPECIFICTIONS CHANGE REQUEST 90-03 ATTACHMENT 11A ; MARKUP OF CHANGES AND NEW PAGES FOR THE BASES FOR TS 3.2.A THROUGH 3.2.G (Unit 2) List of Pages Affected: 89 91 i 94 95 : 96 98 r e i l l l l l l
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W.a addi:ica :: rea: :r pr::ecti:n instrumentaticn wni:n initia:es a rea:::r scram, prc active instrumenta:icn has been proviced wnich initiates a::icn :: citigate the c:nsecuences of ac:icents wnich are beycnd the cperat:r's amility to control, er terminates operater errers befcre they result in sericus
- cas:cuences. This sa: cf s ecificaticns pr: vices the limitinc c:ndi-icns Of cp; ration for the primary system isola-icn fun::icn, ini-iatic5 cf the c:re c: cling systems, c:n rci r:d bicek and s ancty cas raz ent systams. The
.ccj;ctives er the Specif.icati~cns are.(i) to assure tne effectiveness cf tne protective instrumentation wnen recu1 rec even cur 1ng per1ccs wnen pertiens cf L
such systems are out-of-service for maintenanca, anc (ii) to prescribe the t-ip. settings recuired to assure acecuate cerfer=ance.Jhen necessa:j, ena cninnel may ce mace ineperacie for brie' h a m lr is cencuct recuirec IM
. function,al tests and calibratiens. [
Semy of the se::ings en :ne instrumentatien that initia:e er ::n:r:i ::re an: k h c:ntainmen: c: cling have tcierancas ex: licitly s:2:sc wnere ne hi;n an: i:w values are beta critical Enc may nave a substantial effe:: en safa y. The re-points cf c:ner instruments:ica, wnere Only ::e hi;n er i w enc Of ne se::i ; . hn: a direc: bearing en safe:y, are enesen at a level away fr = :ne n:rmal -
- . cperating range c preven: inacvertent actua-icn cf tne safa:y sys ac invcive and expcsure to a:ncr=al situa i ns.
Actuatien cf primary ::ntaih en: valves is initia:ad by pr a::ive
'nstrumentaticn shown in Table I.2. A.wnich senses tnp c:ncitions for wnien us ciaticn is recuirac. Such instru=entatica mus: be available whenev= ~ -
rimary c:ntainmen; integrity is recuired. .- Tha instrumentation wnic.i initiates primary' system 1sciation is c:nnected in a dual bus arrangement. Tha low water level instrubentation set to trip at :erc inches indicated 1cvel (538 inches above vessel :ere) closas all iscia-icn valves excec: these in Groups 1, 4 anc 5. D.e ails of valve grou:inc anc recuitec c1: sine times . cre given in .,pec1 1 cation 4. /. rer valves wn..ica 1 scla:e at this level, this trip setting is adecuate to prevent the core frem being uncoverec in tne case [ cf a break in the largest line assuming a 60 sec:nc valve closing time. j Required closing times are less than this. The low-low reac:cr water level instrumentation is set te trip when reac cr Lwater level is minus 48 inches ~ indicated level (490' inches above vessel ~ zere). This trip initiates HPCI, RCIC, Alternate Red Insertion and trips the l recirculation pumps. The low-low-1cw reacter water level instrumentation is - set to trip when the reac:cr water level is minus 150 inches indicated level F (378 inches above vessel zerc). This trip closes Main Steam Line Isclation Valves, Main Steam Drain Valves and Recir: Sample valves (Group 1), activates th2 remainder of the CSC5 subsystem, and starts p_a.is page is e..:e :1ve u en c:::le:1cn c . tne n.../.._ n.ule n n._.5 in n; .-e i Mec.1 . .i ca:1:n (Medifica:icn E55)." , -- __ -
, .s-- ,
Amencmen: No. III, 141
.CC.
c3-22-29 --
INSERT: Bases page 89 Channel functional test frequencies and allowed out of service times for repair and surveillance testing for Isolation Instrumentation have been determined in accordance with General Electric reports NEDC-30851P-A, Supplement 2, " Technical Specification improvement Analysis for BWR isolation Instrumentation Common to RPS and ECCS
. Instrumentation," and NEDC-31677P-A," Technical Specification Improvement Analyses for BWR isolation Actuation Instrumentation." The AOT is 12 hours for Table 3.2.A Items 1,4, and 5 because these items have instrumentation that is common to the RPS. Other Table 3.2.A Items have an AOT of 24 hours.
Channel functional test frequencies and allowed out of service times for repair and sunteillance testing for ECCS Actuation Instrumentation have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners' Group Technical Specification improvement Methodology with Demonstration for BWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE-022," Technical Specification
- Improvement Analysis for the Emergency core Cooling System Actuation Instrumentation for Peach Bottom Atomic Power Station, Units 2 and 3."
Channel functional test frequencies and allowed out of service times for repair and surveillance testing for miscellaneous instruments have been determined in w accordance with General Electric report GENE-770-06-1," Bases for Changes to Surveillance T ast intervals and Allowed Out-of-Service Times for Selected Instrumentaticn Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21,1992. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for RCIC instrumentation have been determined in accordance with General Electric report GENE-770-06-2," Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated September 13,1991. t 8
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Icss such that fuel is cc: une=vered, fuel te=peratures peak a apprcxi=.ately 1000 degrees F and release cf radicactivity t= the - envir=== is helew L:n 100 cuidelines. Re'erence See:ic: 14.5.5 FsAR.
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Righ rakiatien acnit=:s in the main steam line tunnel have been l pecvided ac=ident. teWith detect the g =ss fuel failure established set:ingas c' in 15the times c=n::=1 ner=al -red backg:cund, d::p - and main steam 11=e isciatica valve closure, fissica p:=due: release
~is limited se tha: 10 Cra 100 guidelines are ne: e===eded ':: this accident. Ref erence Sectics 14.6.2 PSAK.
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tive. of r.eactor. coolant l.eakage. A.Drywell Atmo.schere Radioactivity Monitor is provicec to cive succorting in:ormation to tnat supplied , by the reactor coolant leakage monitoring system. (See Bases for , 3.6.C and 4.6.C) . Some of the surveillance instrumentation listed in Table '
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a_ ._ -w.w ._ c c - ._4. .a . n. w m c. .4 +w .,_ +_ u c. - . e _ _- -a a.. ~ a- c _' NUREG-0737, Clarification of 'TMI Action Plan Recuirements. This instrumentation and the applicable NUREG-0737 requirements are:
- 1. Wide range drywell pressure (II.F.1.4) ;
- 2. Subatmospheric drywell pressure (II.F.1.4)
- 3. Wide rance sucoression chamber water level (II.F.1.5)
- 4. Main stack high range radiation monitor (II.F.1.1) i
- 5. Reactor building roof vent high range radiation monitor i (II.F.1.1)
- 6. Drywell hydrogen concentration analyzer and monitor .
(II.F.1.6)
- 7. - Drywell high range radiation monitors (II . F.1. 3 )
- 8. Reactor Water Level - wide and fuel range (II.F.2) !
- 9. Safety-Relief Valve position indication (II.D.3) i I
i x i I 1 kencment Nc.132, II2. II3.156 c.
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- n ne event or a. les.s cf the rea::cr ,ulacine o
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i , . . . . ~ 2. . 2. . .... source, Ine uncervel:ac.e sensinc. rela.vs cCerate *: initiate a timing s- .==.en.=..n...=. ine timinc secuence orovices constant anc inverse time voltace chara: eristics. Dec. raced voltac.e prc'tection incluces: (1) An instantaneous relay (27N) initiated at 98% voltage which initiates a 60 second time delay relay which is inhibited (locked out) from initiating transfer in the presence of a safety-injecti.on.sicnal; (2) An instantaneous relay (27N) initiated at 89% vel: ace wn1cn intiatec a 9 seC:nc time Celay relay Whicn recultes tn.e cresen e :7. a saTety inj.eC;1CD sic.nal t: initiate transTer; -) An inverse time voltage
. . -, e relay (CV :.) initia:ad at e/,. voltage with a maximum e0 sec:nc ceiay anc l
cperates at 70% voltage in 30 seconcs; and (a) An inverse time vol: ace relav - (IAV) initia:ec at appr:ximately Su,e. voltage anc ccera es a: 1.5 se :ncs a-- . zero volts. When the timing sequence is completed, the corresponding akV emergency circuit breakers are tripped and the emergency buses are transferred to the alternate source. The 60-second timing sequences were selected to prevent unnecessary transfers durinc. motor star s and to allow the autcmatic tacchanc.er on the . startuo. transformer to resocnd to the voltac.e conditien. The 9-second timinc. sequence is necessary to prevent separation of the emergency buses from tne off-site source during motor starting transients, ye still be contained witn..1n the time enve,ioce in r:n,R iable c.:.1. N-
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Docket N3. 50-278 License No. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 ATTACHMENT 11 MARKUP OF CHANGES AND NEW PAGES FOR l THE BASES FOR TS 3.2.A THROUGH 3.2.G (Unit 3) List of Pages Affected: 89 91 94 95 96 98
PBAPS Unit 3 -
~
'3.2
' ~
BASES I
- l . -
S In-addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which . initiates action to mitigate the consequences of accidents which are beyond the operator's ability to control, or terminates operator errors before they result in serious consequences. This. set of specifications provides the limiting conditions of cperation for the primary system isolation function, initiation of the core cooling systems, control rod block and standby gas treatment systems. The objectives of the Specifications are (i) to assure the effectiveness of the protective instrumentation when required even during periods when portions of . such systems are out-of-service for maintenance, and (ii) to prescribe the trip settings required to assure adequate performance.Jnen necessary, one) (channel may be made inoperable for Drief intervals to conduct recuired/ Ju vM
% nctional tests and calibration _sg .
.c_ -
gNg Some of the settings on the instrumentation that.thitiate or control core and containment cooling have tolerances explicitly stated where the high and icw values are both critical and may have a substantial effect on safety. The set points of other instrumentation, where only the high or low end of the setting has a direct bearing on safety, are chosen at a level away from the normal operating range to crevent inadvertent actuation of the safety system involved ' and exposure to abnormal situations. .. Actuation of primary containment valves is initiated by protective instrumentation shown in Table 3.2. A which sense - 'he conditions for which isolation is required. Such instrumentation mun ,e available whenever g_ primary containment integrity is required. e ' The instrumentation which initiates primary system isolation is connected in a dual bus arrangement. The low water level ins'trumentation set to trip at.zero inches indicated - level ~(538 inches above vessel.zero) closes all isolation valves except those
-in Groups 1, 4 and 5. Details of valve grouping and required closing times are given in Specification 3.7. For valves which isolate at this level, this trip setting is adequate to prevent the core from being uncovered in the case l of a break in the largest line assuming a 60 second valve closing time.
Required closing times are less than this. The low-low repctor water level instrumentation is set to trip when reactor water level is minus 48 inches indicated level (490 inches above vessel zero). This trip initiates HPCI, RCIC, Alternate Rod Insertion and trips the l recirculation pumps. The low-low-low reactor water level instrumentation is set to trip when the reactor water level is minus 160 inches indicated level (378 inches above vessel zero). This trip closes Main Steam Line Isolation Valves, Main Steam Drain Valves and Recire Sample Valves (Group 1), activates the remainder of the CSCS subsystem, and starts T his page is effective upon completion of the ATWS Rule ARI/RPT Modi ,,y_ t (Modification 865)." ( ' Amendmen t No. IIS,143 l 39 03-22-39 l 4
~
4 l l l INSERT: Bases page 89 Channel functional test frequencies and allowed out of service times for repair and ) surveillance testing for isolation Instrumentation have been determined in accordance with General Electric reports NEDC-30851P-A, Supplement 2, " Technical Specification ;
- Improvement Analysis for BWR isolation Instrumentation Common to RPS and ECCS )
i Instrumentation," and NEDC-31677P-A," Technical Specification improvement Analyses for BWR isolation Actuation Instrumentation." The AOT is 12 hours for Table 3.2.A Items 1,4, and 5 because these items have instrumentation that is common to the RPS. Other Table 3.2.A Items have an AOT of 24 hours. < Channel functional test frequencies and allowed out of service times for repair and surveillance testing for ECCS Actuation instrumentation have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners' Group Technical Specification Improvement Methodology with Demonstration for BWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE-022," Technical Specification Improvement Analysis for the Emergency core Cooling System Actuation Instrumentation for Peach Bottom Atomic Power Station, Units 2 and 3." Channel functional test frequencies and allowed out of service times for repair and surveillance testing for miscellaneous instruments have been determined in ~ accordance with General Electric report GENE-770-06-1," Bases for Changes to Surveillance Test Intervals and Allowed Out-of-SerAce Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21,1992. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for RCIC instrumentation have been determined in accordance with General Electric report GENE-770-06-2," Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated September 13,1991. 9
i . I POAPS Unit 3 3.2 BASES (Cont'd) , (][~ the emergency diesel generators. These trip level settings were _ chosen to be high enough to prevent. spurious actuation but low enough to initiate CSCS operation and primary system isolation so that post-accident cooling can be accomplished and the guidelines of 10 CFR 100 will not be exceeded. For large breaks up to the complete circumferential break of a 28-inch recirculation line and with the trip setting given above, CSCS initiation and primary system isolation are initiated in, time to meet,the above criteria. Reference paragraph 6.5.3.1 FSAR. -
~
The high drywell. pressure instrumentation is a diverse signal for malfunctions to the water level instrumentationl and in addition to initiating CSCS, it causes isolation of Group 2 and 3 isolation valves. For the breaks discussed above, this instrumentation will generally initiate CSCS operation before the low-low-low water level instrumentation; thus the results given above are applicable here also. See Spec. 3.7 for Iselation valve C1csure Group. The water level instrumentation initiates protection for the full' spectrum of loss-of-coolant accidents and causes isolation of all isolation valves except Groups 4 and 5. . Venturis are provided in the main steam lines as a means of measuring steam flow and also limiting the loss of mass inventory from the vessel during a steam line break accident. The primary function of the instrumentation is to detect a break in the main sceam line. For S the worst case accident, main steam line break outside the drywell, a t'~~ trip setting of 140% of rated steam flow in conjunct. ion with the flow limiters and main steam line valve closure, limits the mass inventory loss such that fuel is not uncovered, fuel temperatures peak at '" approximately 1000 degrees F and relea'se of radioactivity to the environs is below CFR 100 guidelines. Reference Section 14.6.5 FSAR. Temperature monitoring instrumentation is provided in the main steam line tunnel exhaust duct and along the steam line in the turbine building to detect leaks in these areas. Trips are provided on this Instrumentation and when exceeded, cause closure of isolation valves. See Spec. 3.7 for Valve Group. The setting is 200 degrees F for the main steam line tunnel detector. For large breaks, the high steam ; flow instrumentation is a backup to the temperature instrumentation.
~
High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure as in the control red drop accident. With the established setting of 15 times normal background, ' and main steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this i accident. Reference Section 14.6.2 FSAR. l l l i i Amendment No. 132 h~~ 03/03/88-
.-. ... \
l
PDAPS 3.2 BASIS (cont'd)
;; y ~([" -~
Pressure instrumentation -is erovided to close the main steam isolation valves in KUN Mode when the main steam line nressure drons below q90
-nsiq.
The Reactor' Pressure Vessel-thermal transient due 1 inadvertent omening of the turbine bypass valves when not toin an
- g '
Mof e is less severe than the loss of feedwater analyzed in section the RUS t L : 14.5 of the FSAR: .therefore, closure of the Main Steam Isolation valves for thermal transient crotection when not in RUN Mode is not b recuired. - The HPCI .high' flow and temperature instrumentation are erovided to J^* E
' detect 's break in' the HPCI steam 'piming. Tripoing of this ,-
L instrumentation Tripning logic for results in actuation the high flow is 1ofout HPCIof 2isolation logic. valves. Tempe ra ture is . B ' monitored each at four location. Two(4)-locations (2) sensorswithat each fourlocation (4) temeerature are neweredsensors by "A"at DC
' e.g.,
control bus and two-(2)lnr "B" DC control bus. Each nair of sensors, "A".or "3" at "A" each location are physically senarated and th e ' l tripping of either or "B" bus sensor will actuate HPCI L ' valves. The trip settings' of < 100% of design' flow for highisolation flow and-200 degrees F for high prevented and- fission product temperature are such that core uncovery is release is within limits. ; The RCIC high flow and temperature instrumentation are arranged the same.as that for the HPCI. The trip settinc of < 3005 for hich flew r
- and '100 degrees F for temcerature are based on tee same' criteria as
*he HPCI.
t r -. ewi M- --The similar Reactor. to.thatWater for the _Cleanum System high flow instrumentation is arranged HPCI System. i F core-uncovery is prevented and _ fission productThe trip settinns are such that within: limits. The high . temperature instrumentation release is maintained L nen-regenerative heat downstream of the
. exchanger is erovided to crotect the ion '
exchange resin in the demineralizer - from damace due to hinn ' temperature.- Such damage could impair the resins' ability to remove impurities from-the primary coolant and nossihlv result in the release : of previously esptured impurities back'into the coolant in large y concentrations. '
^.
J: , Thesystem. bus instrumentatien which initiates C5CS action is arranged in a dual , As for other vital ins trucenta tion arranged in this b fashion, the specification preserves the effectiveness of the system .
- even .during periods when maintenance or testing is being nerformed. l An' exception to'this is when logic functional testi,nq is being 7 p.erformed.
L l' The-control rod block functions are provided to prevent excessive n control' cladding redintegriAy-safety withdrawal so that MCPR does not decrease to the fuel limit.
~ l ' out of _ nf e.g., any trip on one ofThe trip logic.for this function is 6 APRM's , 8 IRM's, or 4 SRM's will result in a rod block. '
'The minimun instrument channel requirements assure instr ==entation to assure the sinqle failure criteria is met. The p sufficient 4 rmthi.ws instrument channel requirements for the RBM may be reduced by J Jad' onetfor maintenance, testinc or calibration. This time peried is only 1
' i
[ , 3t rof the operating time in a month 'and does not significantly increase the risk of nreventing an inadvertent control red withdrawal J -
- i. s i
faendment Ho. 7),$.79.104/108 9 t 1 toc i
.u. ~ _. ~ - - . - - . - . . . -. . . . - ..-
1.[ .
. PEAPS
-m 73 1.2 BASES.(Cent'd)
[ Tho APRM red bicek functica is ficw biased and prevents a significant reduction in MCPR, especially. during operation at reduced ficw. The APRM -prevides- gross core protectica: i.e. , limits . the gress core power
; increase f rom withdrawal of centrol rods in the normal withdrawal coquence. The trips are set so that MCPR is maintained greater than 1tha fuel cladding integrity safety limit. i .y Tho REM red bicek functica provides local protecticn of the cere; 11.o., the prevention of boiling transition in the-local region of the cera, for a single red withdrawal error frem a limiting centrol red , -pattern.
Tho IRM ' red' bicek functicn provides local as well as gross core
.pretection. .The scaling- arrangement is such that trip setting is less
-than a factor of-10 above the indicated level. ,
Tho- downscale . indicatica en an APRM cr IRM is ' an indicatien the inctrument has failed cr the inetrument is not sensitive enough. In . cither cas's the instrument will not respend to changes in the centrcI i 1E cd actica and-thus, centrol red metien is prevent ed. The dcwnscale . , . 7 tips are set at 2.5 indicatedicn scale. . -;. . , 7
-: .w. : . .
- L Tho.' flow. ecmparator and scram discharge volume high level ecmpenents
--havo- only one icgic channel and are not required fer saf ety.
The ficw ; cc2parator must be bypassed when operating with cne recirculatien ' l
. water. pump. 1 I
1 Tho, refueling 'intericeks also operate one icgic channel, and are
. required for saf ety cnly when the mcde switch is in the refueling yesitien.- i l
.Fcr effective emergency core ecoling for small pipe breaks, the HPCI cystes' aust functica since reacter pressure does not decrease rapidly
.enzug:F to allow either core spray or LPCI to operate in time. The cutomatic; pressure relief functicn is provided as a backup to the HPCI lin the ,' event the HPCI does not provide this functicn when necessary.
land minimize spurious operaticn. The trip settings given in the cpecification are adecuate to assure the above criteria are met. The cpecificatien preserves the ef fectiveness of the system during perieds of caintenance, testing, or calibratien, and also mini =izes the risk icf inadvertent operatien; i.e.,.enly one instrument channel cut of
'cervica. . ,
Q -! 'v Am:ndment No. 75, 9, 70', N ,102 no,4 December 31,-1984 ;
Unit 3
./ - PBAPS
,~3.2. BASES (Cont'd)
N*#" Four sets of two radiation monitors are provided which
' initiate:the Reactor Building Is,olation function and operation of
-the standby gas treatment system. Four instrument channels monitor the radiation from the refueling area ventilation exhaust. ducts and four instrument channels monitor the building ventilation below the refueling floor. Each set of instrument channels is arranged in a 1 out of.2 twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-
-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the ! refueling. accident leaves _the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack.- Trip signals from these monitors are h required only when purging the containment through the SGTS and The trip signals isolate pri-containment integrity is required. mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open. . This signal is added to fulfill the requirements of .i. tem II.E.4.2 (7) of NUREG-0737, 42! - 'Four channels of in-duct radiation monitors are provided which T$ks -Each set of instrumentinitiate the Main Control Room Emergency Ventilation System. channels are arranged in a one (1) out of two
.(2) twice trip logic.
Flow integrators are used to record the integrated flow The integrated flow is indic'a-of liquid from the drywell tive of reactor coolant leakage. sumps. ' A Drywell Atmosphere Radioactivity L' ' Monitor.is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system. (see Bases for
- 3. 6.C and 4. 6.C)
Some of the surveillance instrumentation listed in Table I 3.2.F are required.to meet the accident monitoring requirements This of NUREG-0737, Clarification of TMI Action Plan Requirements.
. instrumentation and the applicable NUREG-0737 requirements are:
L 1. Wide range drywell pressure (II.F.1.4) 2.. Subatmospheric drywell pressure (II.F.1.4) ;
- 3. Wide range suppression chamber. water level (II.F.1.5) '
i Main. stack high range radiation monitor (II.F.1.1) I 4. 5.- Reactor building -roof vent high range radiation monitor L l ii -(II.F.1.1) Drywell hydrogen concentration analyzer and monitor 4
- 6. .
(II.F.1.6) Drywell high range radiation monitors (II.F.1.3) 7.. t,-- S. Reactor Water Level - wide and fuel range (II.F.2) ,
~ * '~
- 9. Safety-Relief Valve position indication (II.D.3) p Amendment No. IN, II6, II7,158,189 '
pf,y 0 5 '5% L
~
~
l PBAPS Unit 3 ;
'3.2 Bd5ES-(Cont'd.) _
The recirculation pump trip limits the consequences of an anticipated transient . without scram (ATWS) event. The response of the plant to this postulated event ' is within the bounds of study events given in General Electric Company Topical Report, NE00-10349, dated March, 1971. An alternate rod insertion scram limits the consequences of a Reactor Protection System failure to scram during an anticipated transient. The ARI/RPT System is electrically diverse from the RPS logic and actuation circuitry, which'significantly reduces the potential for ATWS events caused by common mode electrical failures in RPS. The ARI/RPT system is required by 10 CFR 50.62.
~
In the event of a loss' of the reactor building ventilation system, radiant i heati'ng in the vicinity of the main steam lines raises the ambient temperature above 200 degrees F. Restoration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures. The momentary temperature increase can cause an unnecessary main steam line isolation and reactor scram. Permission is provided to increase the ; temperature trip setpoint to 250 degrees F for 30 minutes during restoration of ventilation system to avoid an unnecessary plant transient.
.The Emergency Aux. Power Source Degraded Voltage trip function prevents damage to safety-related equipment in the event of a sustained period of low ,
voltage. The voltage supply to each of the 4kV buses will be monitored by
- undervoltage relaying. With a degraded voltage condition on the off-site source, the undervoltage sensing relays operate to initiate a timing Q. sequence.
The timing sequence provides constant and inverse time voltage characteristics. Degraded voltage protection includes: (1) An instantaneous relay (27N) initiated at 98% voltage which initiates a 60 second time delay relay which is '
. inhibited (locked out) from initiating transfer in the presence of a safety injection signal; (2) An instantaneous relay (27N) initiated at 89% voltage i which'intiates a 9 second time delay relay which requires the presence of a safety injection signal to initiate transfer; (3) An inverse time voltage relay (CV-6) initiated at 87% voltage with a maximum 60 second delay and operates at 70% voltage in 30 seconds; and (4) An inverse time voltage relay l .
.(IAV) initiated at approximately 60% voltage and operates at 1.8 seconds at zero volts.
When the timing sequence is completed, the corresponding 4kV emergency circuit breakers are tripped and the emergency buses are transferred to the alternate source. The 60-second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the startup transformer to respond to the voltage condition. The 9-second timing l sequence'is necessary-to ' prevent separation of the emergency buses from the off-site source during motor starting transients, yet still be contained
.within the time envelope in FSAR Table 8.5.1. I i
l 1
-93a- Amendment No. SI, 99,127. If 3,145 ot./13/89
Q ; .,.
)
1
' ,- . l
- PBAPS' ,
- 4
)
;I R . ;
??- .
. @* " L4 .2 BASE 5 i
The instrumentstion listed in Tabic 4.2. A thru 4.2.F will ; be'functienally tested and calibrated at reculariv sche-
-duled- intervals.aTThe sa,me desi~gn reliability goal as the'
~ Reactor Protection System of- 0.99999 is generally applied-for- all applications of (1 out of 2) X (2) logic. There-fore, ;on-off . sensors are tested once/3 months, and bi- -
i i stable trips associated with analog senscrs and ampli-fie'rs are tested once/ week. ~
- These instruments which, when tripped, result in a rod block have their contacts arranged in aFor 1 out of n logic, i I
and all are capable of being bypassed. such a trip- _ ping arrangement with bypass capability provided, there - is an optimum test in.terval that should be maintained in crder to maximi =a the reliability of a given channel (7).
^ !
~
This take's account of the fact that testing degrades reliability and the optimum interval between tests is ' ; approximately given by:-
- i. 2e .
5 7 Where: 1 = the optimum interval between, tests. C.~.-
%a t = the time the trip contacts are disabled :
;\ ,
.from performing their function while the i
. test.is in progress. ;
X-
~
i
- r = the expected fai1ure rate of the relays., '
l i L l To test the -trip relays requires that the channel be by- . 4 passed,: the - test made, and the system returned to its ini- l tisi state.. It is assumed this task requires an estimated
'30 minutes to completc in a' thorough and workmanlike man- li j
sner and that the relnys have a failure rate of 10-G failures per hour. -Using this data and the above opera-
' tion, the optimum-test interval is f
2(0 5L = 1 x 103 hedrs . i =, 3 10
- t i ;
= 40 days - i For additional marein a test interval of once eer menth.
vill be used initia11v. , (7)- UCRL-50451, Improving Availability and Readiness of Field' Equipment Through Periodic Inspection, Benjamin
- Epstein, Albert.Shiff, July 16, 1968, page 10, Equa-tien -(24) , Lawrence Radiation Laboratory.
r 3 Amendment No. 82/81' i
~ ~~ ~+ . . . , _ .
I
y -- PBAPS gg 4.2- BASES: (Cont'd.)- . j
- w , -!
The-sensors and electronic apparatus have not been included j here as these are analog devices with readouts in the con- 1 trol room and the sensors and electronic apparatus can be
' checked by comparison with other like instruments. .The ,
checks which.are made on a daily basis are adequate to assure operability of the sensors and electrcnic apparatus,
^
and the test interval given above provides for optimum ~ testing of1 the. relay circuits. The above calculated test interval optimizes each indivi- ; dual-channel, considering it to be independent of all
- others. As an example, assume that there'are two channels -
. with an individual technician assigned to each. Each tech- -[
*nician tests his channel at the optimum frequency,.but the !
two technicians are not allowed to communicate so that one i can advise the other that his channel is under test. Und.er these conditions, it is possible for both channels to be f ; under- test simultaneously. Now,' assume that the techni- ; cians are required to communicate and that two channels are j never tested at the same time. i Forbidding simultaneous testing' improves the availability . of the' system over'that which would be achieved by testing !
. M" # each channel independently.- These one out of n trip sys- !
tems will be tested one at a time in order to take advan- t
- tage.of this inherent' improvement.in availability. l Optimizing each channelindependently may not tiruly optimize !
the. system considering the overall rules of system opera- ! tion. However, true system optimization is a complex prob- l
'lem. _ The optimums are broad, not sharp, and optimizing the
' individual. channels. is . generally adequate for the systeri. l
<Thedormulagiven'above'minimizestheunavailabilityofa -
sing'le channel which must be bypassed during testing. The i minimization of the availability is . illustrated by Curve ! No. 1 of Figure 4.2.2 which assumes that a channel has a ' failure rate of 0.1'x 10-6/ hour and that 0.5 hours is re- l quired to test-it.- The unavailability is a minimum at a ; test' interval.1, of 3.16 x 103 hours. ;
. cj. If two similar channels are used in a l'out of 2 configura-
~
1 f: tion, the t'est interval for minimum unavailability changes !
- as aEfunction of-the rules for testing. The simplest case :
to' test each one' independent of the other. In this
)
. j i # k A
~
APRIL 1973 i I
- . ._______i
PBAPS - J 4.2 BASES (Contd . )
, 1
- s. .u m
% case, there is assumed to be a finite probability that
~
both may be bypassed at one time. This case is shown by Curve No. 2. Note that the unavailability is lower as expected for a redundant system and the minimum occurs at the same test interval. Thus, if the two channels are tested independently, the eqtiation above yields the test interval for minimum unavailability. A more usual case is that the testing is not done inde-pendently. If both channels are bypassed and tested at the same time, the result is shewn in Curve No. 3. Note that the. minimum occurs' at about 40,000 hours , much longer than for cases 1 and 2. Also, the minimum is not - nearly as low as case 2 which indicates that this method . of testing does not take full advantage of the redundant channel. Bypassing both channels for simultaneous test-ing should be avoided. < The most likely case would be to stipulate that one chan-nel be bypassed, tested, and restored, and then immedi-ately following, the second channel be bypassed, tested, and restored. This is shown by Curve No. 4. Note that there is no true minimum. The curve does have a definite knee and very little reduction in system unavailability (yfi a- is achieved by testing at a shorter interval than compu- ' b ted by the equation for a single channel. The best test procedure of all those examined is to per-fectly stagger the tests. That is, if the test interval is fcur months , test one or the other channel every two months. This is shown in Curve No. 5. The difference between Cases 4 and 5 is negligible. There may be other argn=ents, however, that more strongly support the per- .
. factly staggered tests, including reductions in human error.
The conclusions to be drawn are these:
- 1. A 1 out of n system may be treated the same as a single channel in terms of choosing ,a test interval; and
- 2. more than one channel should not be bypassed for ,
testing at any cne time. M L
. h[ +.
eQ-APRIL 1973
- Unit 3
~PBA S .y . 4.2 BASES (cont'd)
The radiation monitors in the refueling area ventilatien duct which initiate building isolation and standby gas treatment operation are arranged in a 1 out of 2 twice logic system. The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency. The air ejector off-gas monitors are connected in a 2 out of 2 logic arrangement. Based on the experience with instruments of similar design, a ;L, testing interval of once every three months has been found ,j/m
$b5'~
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required only during containment purging through the SGTS and when containment integrity is required, an activity which occurs infrequently. Therefore; a twelve (12) month calibration interval is appropriate. The Control Room Intake Air Radiation Monitors are safety-related and are required to be operable at all times when secondary containment is required. E he calibracion interval is asj'-t-(Bescribed in section 4.11.A. The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also. L ;-+ i l a. Amendment No. 158, 189 MM 0 51994 4 I
E PBAPS . - _ _ . _ _ _ ,_ _ _ _ _ .J
< i 4 . l
\
, .] - jg ] 2
; ~
ma _ 1 . . X'- 10 2 :CURYE 1 -, .- 1 ' .' L .* 10 3
' ._= .:::
a : . '. a .
.'s\
4 i H CURVE 3 s',7,". . - l
' # '~ I
< 10""d '. . :::
1 . 3 // m
- "l' lu '.
y '. . ::. : w , s o '.'.
'l l .-
=
*> 10-5 ._
, t .
r-:,, , 5
. ~ ,.' -
r a
-)
sc , , . e .
~~~ 4 .
e " o . CURVE 2 - . m . . 7 m,, . .. :: . i M 10 ' .' CURVE 4 ' . '.'
*tI1 tt 'tI s m to-7 '.'
%',' - CURV,E5 ff f in-a tal 102 30 3
io '4 gas [ TEST !NTERVAL -(J) HOUR 5
~ <
'4 %
. o.3 .
w/ 1 Figure 4.2.2 APRIL 1973 ! l
Docket Nos. 50-277 50-278 j License Nos. DPR-44 DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CHANGE REQUEST 90-03 ATTACHMENT 12 RE-TYPED REPLACEMENT PAGES FOR ALL PAGES AFFECTED BY TSCR 90-03 l Wa- _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - - - - - - - -
1 PBAPS ! i UNIT 2 LIMITING CONDITIONS FOR OPERATIOJ SURVEILLANCE REQUIREMENTS 3.1 Reactor Protection System (RPS) 4.1 Reactor Protection System A. The RPS instrumentation for each trip function A. Each RPS instrument channel shall be in Table 3.1.1 shall be Operable; and, there demonstrated Operable by performance of a ! shall be two Operable or tripped trip systems channel functional test and channel calibration for each Trip Function. at the Frequencies shown in Tables 4.1.1 and j 4.1.2, respectively. The designed system response times from the Ree sponse time measurements (from the opening of the sensor contact up to and opening of the sensor contact up to and including the opening of the trip actuator including the opening of the trip actuator contacts shall not exceed 50 milliseconds. contacts) are not part of the normal instrument test. The RPS response time of each reactor Applicability: trip function shall be demonstrated to be within its limits once per operating cycle. According to Table 3.1.1. Conditions and Reauired Actions: (1)(2)
- 1. With one or more channel (s) required by Table 3.1.1 inoperable in one or more trip functions, place the inoperable channel or associated trip system in trip within 12 hours.
- 2. With one or more trip functions with one or more channels required by Table 3.1.1 inoperable in both trip systems, place channel in one trip system in trip or place one trip system in trip within 6 hours.
- 3. With one or more automatic trip functions or two or more manual trip functions (Mode Switch in Shutdown, Manual Scram and RPS Channel Test Switches) with RPS trip capability not maintained, restore RPS trip capability within one hour,
- 4. If the required actions and associated completion time of Action 1 or 2 or 3 are not met, take the action required by Table 3.1.1 for the Trip Function.
(1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated trip function maintains RPS trip capability. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channel is not restored to Operable status within the required time, the Action required by Table 3.1.1 for that trip function shall be taken immediately. l PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Reactor Protection System (continued) 4.1 Reactor Protection System (continued)
. B. N/A B. Deleted i~
C. N/A C. Deleted D. Reactor Protection System D. Reactor Protection System Power Supolv Power Supolv D.1 Reactor Protection System Power Supply: D.1 The following RPS power supply (MG set) protective devices shall be functionally lne trip train
- per RPS MG set may be in tested at least once every six months and u.a bypassed or inoperative condition for a calibrated once each refueling outage, period of 72 hours. If this condition cannot be satisfied, or if both trip trains are Acceptable inoperative, the RPS bus shall be Device Settina transferred to the afternate source or de-energized within 30 minutes. Undervoltage 113 i 2 Volts Overvoltage 131 i 2 Volts Underfrequency 57 Hz i .2 Hz Underfrequency Time Delay 6 sec i 1 sec D.2 One trip train
- of the RPS alternate power D.2 The following RPS alternate power supply supply may be in the bypassed or protective devices shall be functionally inoperative condition for a period of 72 tested at least once every six months and hours. If this condition cannot be satisfied, calibrated once each refueling outage.
or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS Acceptable MG set or de-energized within 30 minutes. Device Settina Undervoltage 11312 Volts Overvoltage 131 i 2 Volts Underfrequency 57 Hz i .2 Hz Undervoltage , Time Delay Max. 4 secs. A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic. r j PBAPS UNIT 2 P Intentionally Blank l l l l l l l 1 i
-36a-
.. y PBAPS Unit 2 Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENI Modes in which Function Minimum No. of Must Be Operable Number of instrument Operable Instrument Channels per Channels Provided Acton l ltem Trip System Trio Function Trip Level Setting Refuel (7) Startup Run by Design (1) 1 1 Mode Switch in x x x .1 Mode Switch A Shutdown (4 Sectons) 2 1 Manual Scram x x x 2 Instrument Channels A 3 3 IRM High Flux 1120/125 of Full Scale x x (5) 8 instrument Channels A 4 3 IRM Inoperative x x (5) 8 instrument Channels A 5 2 APRM High Flux (0 66W+71%0 66AW) x 6 instrument Channels A or B (Clamp @ 120%) , (12)(13) y u
7 6 2 APRM inoperative (11) x x x 6 Instrument Channels A or B kin 7 2 APRM Downscale 22.5 Indicated (10) 6 Instrument Channels A or B on Scale 8 2 APRM High Flux in 115% Power x x 6 instrument Channels A Startup 9 2 High Reactor Pressure 11055 psig x (9) x x 4 Instrument Channels A 10 2 High Drywell Pressure 5 2 psig x (8) x (8) x 4 Instrument Channels A 11 2 Reactor Low Water 2 0 in. Indicated x x x 4 Instrument Channels A Level Level C E
-i FO
._, _ _ .- , _ __________._______m
PBAPS Unit 2 Table 3.1.1 (continued) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.of Modes in which Function Operable Instrument Must Be Operable Number of Instrument Channels per Channels Provided Action I item Trip System Trip Function Trip Level Setting Refuel (7) Startup Run by Design (1) 12 2 High Water Level in 150 Gallons X(2) X X 4 Instrument Channels A Scram Discharge Volume 13 2 Turbine Condenser Low 2 23 IN. Hg. Vacuum X 4 Instrument Channels A or C Vacuum 14 2 Main Steam Line Hgh i 15 X Normal X X X 4 Instrument Channels A Radiation Full Power Background g 15 8 Main Steam Line 1 10% Vatve Closure X (6) 16 Insia: ment A $ m a isolation Valve Closure Channels > T 16 2 Tu bine Control Valve 500( P( 850 psig 4 Instrument Channels A or D U X (4) Fast Closure control Oil Pressure Between Fast Closure Solenoid and Disc Dump Valve l 17 4 Turbine Stop Valve i 10% Valve Closure X (4) B instrument Channels A or D Closure 18 2 RPS Channel Test X X X 4 Instrument Channels A Switches C E
-4 to
p, Unit 2 PBAPS h NOTES FOR TABLE 3.1.1 1.. -If the-required actions and associated completion time of Specification 3.1.A, Actions 1 or 2 or 3 are not met, take the action listed below for the affected trip function as required by Table 3.1.1.
~
A. Initiate insertion of operable rods and complete insertion of all operable rods within 12 hours. B.. . Reduce power level to IRM range and-place mode switch-in the start up position within 6 hours. C. Reduce turbine load and close main steam line isolation valves within 6 hours. l D. Reduce power to less than 30% rated within 4 hours.
- 2. Permissible to bypass, in refuel and shutdown positions of the reactor mode switch.
- 3. Deleted.
- 4. Bypassed when reactor thermal power is less than 30% of rated as indicated by turbine first stage pressure.
o
; 5 '. IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position.
- 6. The design permits' closure of'any two lines without a scram being initiated.
- 7. When the reactor is subcritical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be operable:
A '. . Mode switch.in shutdown L B.. -Manual scram C. High flux-IRM L D. Scram discharge instrument volume high level Not required to be ope'rable.when primary containment
~
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' integrity is not required.
; 9. Not: required to-be operable.when the reactor pressure vessel l head is not bolted to the vessel.
l 1 Unit 2 - TABLE 4.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2) Functional Test Minimum Frequency (3) Mode Switch in Shutdown A Place Mode Switch Each refueling outage. In Shutdown Manual Scram A Trip Channel and Alarm Every 3 months. l RPS Channel Test Switch A Trip Channel and Alarm Once/ week or after channel maintenance. IRM High Flux C Trip Channel and Alarm (4) One per week during refueling or m b ' startup and before each startup. $ x Inoperative C Trip Channel and Alarm (4) One per week during refueling or " startup and before each startup. APRM High Flux B1 Trip Output Relays (4) Once/3 months Inoperative B1 Trip Output Relays (4) Once/3 months Downscale B1 Trip Output Relays (4) Once/3 months Flow Bias B1 Calibrate Flow Bias Signal (4) Once/ month High Flux in Startup or Refuel C Trip Output Relays (4) One per week during refueling or startup and before each startup. High Reactor Pressure (6) B2 Trip Channel and Alarm (4) Once/3 months High Drywell Pressure (6) B2 Trip Channel and Alarm (4) Once/3 months C ( Reactor Low Water Level (5)(6) B2 Trip Channel and Alarm (4) Once/3 months E;
-4 PJ
Unit 2 TABLE 4.1.1 (Continued) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUlTS Group (2) Functional Test Minimum Frequency (3) High Water Levelin Scram A Trip Channel and Alarm Once/3 months Discharge instrument Volume Turbine Condenser Low Vacuum (6) B2 Trip Channel and Alarm (4) Once/3 months m h Main Steam Line High Radiation B1 Trip Channel and Alarm (4) Once/3 months y 7 Main Steam Line Isolation A Trip Channel and Alarm Once/3 months M Valve Closure Turbine Control Valve A Trip Channel and Alarm Once/3 months EHC Oil Pressure Turbine First Stage Pressure A Trip Channel and Alarm Once/3 months Permissive Turbine Stop Valve Closure A Trip Channel and Alarm Once/3 months E a N
PBAPS l UNIT 2 f HQTES FOR TABLE 4.1.1
- 1. Deleted.
- 2. A description of each of the groups is included in the Bases of this Specification.
t 3. Functional tests are not required on the part of the system L that is not required to be operable or are tripped. l l If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system 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 functional test program.
- 6. These' channels consist of analog transmitters, indicators and electronic trip units. Instrument checks shall be performed once per day.
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-TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS
' Calibration Minimum Frequency (2)
Instrument Channel Group (1) l Comparison to APRM on Maximum frequency once IRM liigh Flux C-Controlled Shutdown per week. APRM liigh Flux Twice per week. B1 Heat Balance Output Signal Every eighteen months. Flow Bias Signal B1 With Standard Pressure- , Source
-TIP System Traverse Every 6 weeks.
LPRM Signal .B1 B2 Standard Pressure Source Once per operating i liigh Reactor Pressure cycle. Standard Pressure Source Once per operating B2 liigh Drywell Pressure cycle. Pressure Standard Once per operating B2 ' Reactor low Water level cycle. A Water Column Every refueling outage. liigh Water level in Scram Discharge Instrument Volume Standard Vacuum Source Once per operating B2 Turbine Condenser Low Vacuum cycle. A Note (5) Note (5) Main Steam Line Isolation Valve Closure B1 Standard Current Source (3) Every 3 months. Main Steam Line liigh Radiation A Standard Pressure Source Every 6 months. Turbine first State Pressure Permissive i
*~~ ^ - - , , - - ,
Unit 2 Tant 2 4.1.2 (Cont'd. )'
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. REACTOR PROTECTION SYSTEM (SCRAH) IySTRUMENT CAI,IBRATION -
L. MINIMUM CALIBRATION FREQUENCIES'FOR REACTOR PROTECr!ON IHSTRUMENT.CitANNELS . Instrument Channel Group (1) Calibration Minimum Fregtency (2) l l Turbine Control Valve Fast - A. . Standard Pressure Source Once per operating closurc 011 Pressiere Trip cycle. Turbine Stop Valve Clostare A Note (5) Note (5) , 8 .. . L. 4 '
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Unit 2 NOTES FOR TABLE 4.1.2 5
- 1. A description of these groups is included in the bases of this Specification.
- 2. Calibration test is not required on the part of the system that are not required to be operable or are tripped but is required prior to return to service.
- 3. The current source provides an instrument channel alignment. Calibration using a radiation source shall be made each refueling outage.
- 4. Deleted.
- 5. Physical inspection and actuation of these position switches will be performed during the refueling outages.
i [ 6
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P i i l l l { i Unit 2 ! T PBAPS BASES l h The reactor protection system automatically initiates a reactor scram ; y to. 3 f < [F 1. . Preserve the integrity of the fuel cladding.
,.2. Preserve the integrity of the reactor coolant system. l r
- 3. Minimize the energy which must be absorbed following a loss of {
l- coolant accident, and prevent inadvertent criticality.
.vmen there-is not fuel in the reactor, the scram serves no function; ,
therefore, the reactor protection-system is not required to be '
-operable.
' Allowed out of service times for repair and surveillance testing for g Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical l Specification Improvement Analyses for BWR Reactor. Protection System," ;
General Electric Company, March 1988. The reactor protection system is of the dual channel type (Reference
-subsection 7.2 FSAR). The system is made up of two independent trip i systems, each having two subchannels of tripping devices. Each j subchannel has an input from at least one instrument channel which j monitors a critical parameter.
l The outputs of the subchannels are combined in a 1 out of 2 logic; i.e., an input 1 signal on either.one or both the subchannels will cause. , a trip system trip. The outputs of the. trip systems are arranged so ;
'that.a. trip on both systems is required to produce a reactor scram.
- This system meets the intent of IEEE - 279 for Nuclear Power Plant Protecti'on Systems. The system has a reliability greater than that of a 2 out of'3' system and somewhat less than that of a 1 out of 2 ,
system. j i With the exception of the Average Power Range Monitor (APRM) channels, ! the Intermediate Range Monitor (IRM) channels, the Main Steam l "Isolat' ion' Valve closure and the Turbine stop valve ~ closure, each c I subchannel has one instrument channel. When the minimum condition for operation on the number of operable instrument channels per untripped ! protection crip system is met or if it~cannot be met and the affected j protection trip ~ system is placed in a tripped condition, the effectiveness:of the protection system is preserved. ! ll Three APRM instrument' channels'are provided for each protection trip APRM's A and E operate contacts in one subchannel and APRM's
- system.
C'and E~ operate contacts in the other subchannel. APRM's B, D and F j 4 _are_ arranged similarly in i l l l
= - - -- ._.
c-1 1 l I PBAPS f UNIT 2 ) t i 4.1 Bases A. Channel functional test frequencies for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical Specification improvement Analyses for ' i u BWR Reactor Protection System," General Electric Company, March 1988. i h a f r. k , L. h' , p: i i 1 P [ i I k - - - _ - -
! 1 PBAPS .
UNIT 2 4.1 Bases (Con'td.) Intentionally Left Blank f J r i i i l l l 1 l I
PBAPS UNIT 2 4.1 Bases (Con'td.) Intentionally Left Blank i l l l i
- - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - ~ _ - - - - - - - -
PBAPS UNIT 2 4.1 ' Bases -(Con'td.) i: Calibration frequency of the instrument channel is divided into two groups. These are as follows:
- 1. Passive type indicating devices that can be compared with like units on a continuous basis.
- 2. Vacuum tube or semi-conductor devices and detectors that drift or lose sensitivity.
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T jt ' I. PBAPS UNIT 2 ; i 4.1 Bases (Con'td.) i i Intentionally Left Blank 1 i L
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PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVE!LLANCE REQUIREMENTS 3.2 Protective instrumentation 4.2 Protective Instrumentation A. Primary Containment Isolation Functions A. Primary Containment Isolation Functions The primary containment isolation Instrumentation shall be functionally tested and instrumentation for each function in Table 3.2.A calibrated as indicated in Table 4.2.A. shall be Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as function. indicated in Table 4.2.A. Applicabilit,y: Whenever Primary Containment integrity is required. Conditions and Reauired Actions: (1)(2)
- 1. With one or more channels required by Table 3.2.A inoperable, place channel in trip within 12 hours for items 1,4, and 5; and, place channel in trip within 24 hours for items other than 1,4, and5.
2.' With one or more automatic functions with primary containment isolation function not maintained, restore primary containment isolation capability within one hour.(3)
- 3. If the required action and associated completion time of Action 1 or 2 are not met, take the action required by Table 3.2.A for the function.
(1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.2.A for that trip function shall be taken. (3) This Action not applicable to item 11, Reactor Cleanup System High Temperature. ________________-_-_______j
. .. =. .
PBAPS UNIT 2 UMITING CONDITIONS FOR OPERATION LIMITING CONDITIONS FOR OPERATION ; i - 3.2 Protective Instrumentation (Continued) 4.2 Protective Instrumentation (Continuec., B, Core and Containment Coolina Systems - B. Core and Containment Coolina Systems - Initiation and Control initiation and Control Core and containment cooling system initiation Instrumentation shall be functionally tested, ! and control instrumentation for each Trip calibrated and checked as indicated in j Function in Table 3.2.B shall be Operable; and, Table 4.2.B. there shall be two Operable or tripped trip i systems for each Trip Function except as noted System logic shall be functionally tested as in Table 3.2.B. indicated in Table 4.2.B. l Applicability: Each Trip Function listed in Table 3.2.B shall be Operable whenever the system (s)it initiates or controls are required to be Operable as specified in Section 3.5. Conditions and Reauired Actions: With one or more channel (s) required by Table 3.2.B inoperable in one or more Trip Functions, 1 take the Action required by Table 3.2.B. ' 4 h 5 I r i I
l l PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j 3.2 Protective Instrumentation (Continued) 4.2 Protective Instrumentation (Continued) C. Control Rod Block (CRB) Actuation C. Control Rod Block (CRB) Actuation The Control Rod Block Actuation Instrumentation shall be functionally tested, instrumentation for each function in Table 3.2.C calibrated and checked as indicated in shall be Operable; and, there shall be two Table 4.2.C. Operable or tripped trip systems for each function except as noted in Table 3.2.C. System logic shall be functionally tested as indicated in Table 4.2.C. Applicability: (1) The Rod Block Monitor (RBM) shall be Operable with setpoints as required by Table 3.2.C and the Core Operating Limits Report (COLR). The APRM,IRM and SRM Control Rod Block (CRB) functions shall be Operable whenever the Reactor Mode Switch is in the Startup or Run positions except as follows: The SRM and IRM functions are not required when the Reactor Mode Switch is in Run. The APRM and RBM functions are not required to be Operable when the Reactor Mode Switch is in Startup cxcept for the APRM Upscale (Startup Mode) which is not required to be Operable when the Reactor Mode Switch is in Run. The scram discharge instrument volume high level rod block is required to be Operable whenever the Reactor Mode Switch is in the Startup or Run positions or in the Refuel position whenever more than one control rod is withdrawn. Conditions and Reauired Actions: i With one or more channel (s) required by Table 3.2.C inoperable in one or more trip functions, take the Action required by Table 3.2.C. (1) Section 3.3.B.5 is Applicable during operation with a limiting control rod pattern. l l l
l PBAPS I UNIT 2 l I 1.lMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS . 1 3.2 Protective instrumentation 4.2 Protective Instrumentation (Continued) (Continued) D. Radiation Monitorina Systems-Isolation and D. Radiation Monitorina Systems-Isolation and initiation Functions initiation Functions}}