Text

Proposed Tech Specs for Aot/Sti Extensions
	ML17164A580
Person / Time
Site:	Susquehanna
Issue date:	02/10/1995
From:	; PENNSYLVANIA POWER & LIGHT CO.
To:	;
Shared Package
ML17164A579	List: ML17164A578; ML17164A580; ML18026A267;
References
	NUDOCS 9502170194
	Download: ML17164A580 (163)
	v • d • e

ENCLOSURE C TO PLA-4249 PROPOSED CHANCES FOR SSES TECHNICALSPECIFICATIONS Units 1 and 2

,I 9502170194 950210 PDR ADOCK 05000387 P

PDR k

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 1 TS 3.3.1:

Reactor Protection System Instrumentation

N

~j.t A

'b Ih p

&d hT&t33.I-I shau be OPIHbhBLE with the REACTOR PROiKCHON SYSTEM RESPONSE TIME as shown in Table 33.1-2.

hCMH:

As shown in Table 33.1-1.

ense'6 s s.i b.

(s) tripped condition would not cause a (s) aad/or that trip system in the tripped

%ith the auraber of OPERABLE channels less than required by the Miaimu PERABLE Channels per Trip System requirement for oac trip system:

1.

lacing the inoperable channel(s) in the triIyad condition would e a scram, the le channel(s) shall bc restored to OPERABLE within6 hours or the h required by Table 3.3.1-1 hr the Functional Unitshall be taken; or 2.

Ifplacing the inoperable scram, place the inoperable condition within 12 hou

%hh the muaber of LE chatmcls less required by the Minimum OPERABLE per Trip System requiraaeat for systems, place at least one trip s in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take th ON required b

e 39.1-1.

The provisions of Specificatio 3.0.4 are not appl r entry mto Operational Condition'2 or 3 hem Operational Coadition 1 for the IRMs Neutron Flux - Upscale. Setdown hnctioa oithe APIMs.

49.1.1 43.12 49.19 43.1A ad p

a M~lh d I

pERASOLEby thc perfiormaacc of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNELCALIBRATIONoperations for the OPERATIONAL CONDITIONS aad at the

&equencics shown in Table 4.3.1.1-1.

LOGIC SYSTEM FUNCGONALTESTS and simulated automatic operation ofall channels shall be perfonacd at least once per IS months.

The REACIQR PROTECTION SHiiMRESPONSE TIMEof each reactor trip hmctioaal unit shown in Table 3.3.1-2 shall be demonstrated to be within its limitat least once per 18 momhs.

Each tcwt shall indude at least one channel per trip system such that all channels are tested a least once every N times 1$ momhs where N is thc total maaber of redundant channels ht a specifi reactor trip system.

Tbe provisions ofSpecificatio 4.0.4 are not applicable for entry into OIeratioaal Condition 2 or 3 hem Oleraioaal Condition 1 for the IRMs or the Neutron Flux - Upscale, Setdown hnaion of the APRMs.

hmendmcat No. 11 5 Ifmore channels are inoperable in one trip system than ia the other, place the trip system more inoperable channels in the tripped coadition, except when this would cause a scram to occur.

W SUSQUEHANNA - UNH' 3/4 3-1

Insert 3.3.C:

(Actions A, B, C and D from NUREG 1433, Section 3.3.1.1) a.

With one or more required channels inoperable in one trip system, place the inoperable channel(s) or the associated trip system in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one or more required channels inoperable inboth trip systems, place the inoperable channel(s) in one trip system or one trip system in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one or more RPS Functions with RPS trip capability not maintained, restore RPS trip capability within one hour.

d.

IfACTION a or b or c is not met, take the ACTION required by Table 3.3.1-1 forthe RPS Function.

The provisions of Specification 3.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 or 3 from OPERATIONAL CONDITION 1 for the IRMs or the Neutron Flux-Upscale, Setdown function for the APRMs.

CHANNEL CIKCK C HANNA.

FUNCTIONAL TESf OPERATIONAL CHANNEL CONDlTlONS FOR WHICE CALIBRATION )

SURVEILIANCSREQUIRED R

'I I.

lntcreaeduae Range Monitora:

~.

Neutron Flua - High b.

Inoleetive 2.

h g. Power Range M itort":

a.

Neutron Flua-Upacale. Setdown b.

Flow Bused Simulated 1lenna) h~.Upsca)e c.

Freed Neutnet Ftua-Upsca)e d.

Inoperative 3.

Reactor Vcaac) Stcam Dome Prcssure - High Reactor Vcaacl Water Level-Lovv, Level 3 S.

Main Stcam Line bolation

~

Valve - Closure 6.

Main Stcam Line Radiation-s High 7.

Drywall Prcaaure - High SIU,S,tb)

S NA SIU,S t")

S s D(g)

NA NA Nh SIUlc), W W

Siui'), W Srui'), W W

slut') q SIU(c) q Syg(c) q SA SA Nh SA SA

+dXe) Sh Rth)

Wi+, sh NA 2

3, 4, 5 2, 3, 4, S 2

3,5 I 2 3S l,2 l,2 2')

Io2

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.1:

Reactor Protection System Instrumentation

38.l A

hl Ih p

' ~ d ~d hTal $3.lE shan be OPERABLE with the REACTOR PROTECHON SYSTEM RESPONSE TIME as shown in Table 33.1-2.

hs shown in Table 3.3.1-1.

hCGQE:

b.

With the number of OPERABLE channels less than reluired by the Minimiim OPERABLE Channels per Trip System reituiremeat for one trip system:

Ifplacing the inoperable diannel(s) in the tripped coadition would a scram, inoperable channel(s) shall be restored to OPERABLE within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ON required by Table 33.1-1 forthe Functional Unitshall be taken; or 2.

Ifplacing the inop channel(s) 'ripped condition would aot cause a

scram, place the inoperab (s) and/or that trip system in the tripped condition within 12 ho With the number of LE cliaiinels

@quired by the Minimum OPERABLE per Trip System aquiremeat Sr systems, place at hast one 'n the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take CGON required le 3.3.1-1.

'Ibe provisions of Specificatioa 3.0.4 are not app i for entry into Operational CoadiYion 2 or 3 hem Operational Condition 1 for the the Neutron Flux - Upscale, Setdown hnction of the APRMs.

43.1.1 43.12 43.1D 49.1A Each reactor protection system instriuaentatioa channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL FUNCTIONAL TEST and CHANNELCALIBRATIONoperatioas 5or the OPERATIONAL CONDITIONS and at the

&equencies showa in Table 4.3.1.1-1.

LOGIC SYSTjEM FUNCGONALTEAKand simulated automatic operation of all channels shall be performed at least once per 18 months.

The REACTOR PROTECTION SYSTEM RESPONSE TIMEofeach reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limitat least once per 18 months.

Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 moaths where N is the total mimber of redundant channels in a specific reactor trip system.

The pnnrisioas ofSpecification 4.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs or the Neutron Flux - Upscale, Setdown fuaaion of the APRMs.

Ifmore channels are inoperable in one trip system than in the other, place the trip system wah more inoperable channels in the tripped coaditioa, except when this would cause a scram to occur, SUSQUEHANNA - UNIT2 3I4 3-1 hmeadment No. 84

Insert 3.3.1:

(Actions A, B, C and D from NUREG 1433, Section 3.3.1.1) a, b.

With one or more required channels inoperable in one trip system, place the inoperable channel(s) or the associated trip system in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With one or more required channels inoperable in both trip systems, place the inoperable channel(s) in one trip system or one trip system in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or more RPS Functions with RPS trip capability not maintained, restore RPS trip capability within one hour.

lfACTlON a or b or c is not met, take the ACTION required by Table 3.3.1-1 forthe RPS Function.

The provisions of SpeciTication 3.0.4 are not applicable for entry into OPERATIGNAL CONDITlON 2 or 3 from OPERATlONAL CONDlTlON 1 for the IRMs or the Neutron Flux-Upscale, Setdown function for the APRMs.

RJNCTIONALUNIT I.

intermediate Range Monitors; Neutron Fina High b.

Inoperative 2.

Avg, Power Range Monitored "t a.

Neutron Flua-Upecale, Sctclown b.

Row Biaaed Simulated Tlrerrnal Power-Upecale c.

Ftaed Neutron Flua-Upecale d.

inoperative 3.

Rcector Vessel Steam Dome Preaurre - High 4.

Reactor Vessel Water Level-Low, Levd 3 S.

Main Steam Une isolation Valve - Closure 6.

Main Steam Une Radiation-High 1.

Drywell Pressure - High CIIANNEL CIIECK Sru,S,+)

S sru.sP)

S S D(a)

NA NA Sru(c), W W

srul') w sru'l') W W

srut') Q Srutc), Q Srutc), Q CHhNNEL ChLIBRATION ~

SA SA NA SA SA WldXe) SA, Rt>>

+d) SA NA 0PERhTIONhL CONDIONS FOR WHICH SURVEILLhNCEREQUIRED 2

3,4,5 2, 3, 4, S 2

3,S l,2,3,5 l.2 Io2 l,i+

l,2

Extending STIs and AOTS for Susquehanna Technical Spec%cation Instrumentation Unit 1 TS 3.3.2:

Isolation Actuation Instrumentation

INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRNENTATION LINTINQ CQNGITION FOR OPERATION 3.3.2 The fsolatfon actuation fnstrusattatfon channels shown fn'able 3.3.2-1 shall be OPERABLE wfth their trip setpofnts set consfstent with the values shown fn the Trip Setpofnt column of Table 3.3.2-2 and with ISOLATION SYSTB/

RESPONSE

TINE as shown fn Table 3.3.2-3.

APPLICABILITY:

As shown fn Table 3.3.2-X.

ACT'Oil:

a.

Nth an isolation actuation instrumentatfan channel trip setpoint less conservative than th>> value shown fn the A11owable Values calumn of fable 3.3.2-2, declare the channel inoperable until the channel is restared ta OPERABLE status with its trfp setpoint adjusted consistent wfth the Trip Setpoint valw.

the number of OPERABLE channels less than requfred by the Nfn'P nels per Trip System requirement for onetrf, place the inoperabl ~

1(s) and/or that trip sys e tripped condition" within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The pro of Speci n 3.0.4 are not applicable.

c.

Nth the number of OP nels less fred by the Nnfmum OPERABLE r Trfp System requfreaent for systems,.

. pla east one trip system~ fn the tripped condition w hour take the ACTION requfred by Table 3.3.2-X.

~naperau e cnannel need not be placed in the tripped condftian where wau se the Trip Function to occur.

In these

cases, the inop e channel sha11 be ta OPERABLE status wfthfn 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the A

required by Table 3.3.2-1 fo t Trfp Function shall be taken.

dftion, for the HPCI.

system and RCIC system latfon, provided that undant isolation valve, inboard or outboard, as app 1 ~, fn e e fs OPERABLE and all required actuation fnstruaentatfan for tha s OPERABLE, one fnaperable channel need not be placed fn the tripp n

where this would cause the Trip Functfon to occur.

In th es, for the and RCIC systems, the inoperable channel s

restored to OPERABLE s within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ar the ACTION requf able 3.3.2-1, for that trfp Function 1 be taken.

If more ls are fnoperable fn one trfp system than in the er, place the system with more inoperable channels fn the trfpped candft ept when this would cause the Trip Function to occur.

SusquEHANNA - mIT Z 3/4.3H Amendment No.

29

Insert 3.32:

(Actions A, B and C from NUREG 1433, Section 3.3.6.1 and 3.3.62) b.

With the number of OPERABLE channels less than required'y the Minimum OPERABLE Channels per Trip System in one or more Trip Systems:

d.

For functions 1.a.1, 1.b, 1.e, 2.b, 3.b, 7.a, and 7.e, place the channel in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; and, For functions other than 1.a.1, 1.b, 1.e, 2.b, 3.b, 7.a, and 7.e, place the channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The provisions of Spec%cation 3.0.4 are not applicable.

With one or more automatic functions with isolation capability not maintained, restore isolation capability within one hour.

If ACTIONS b or c are not met, take the ACTION required by Table 3.3.2-1 for the function.

Insert 3.3.2 - Footnote:

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains isolation capability.

C CA C

TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUNENIATION I

C TRIP fUNCTION 1.

PR IHARY CONTAIIIIKNT ISOLATION HININjH APPLICABLE I SOLATION( )

OPERABLE CINNNELS OPERATIONAL ACTION a.

Reactor Vessel Mater Level 1)

Low, Level 3

2)

Lcnv Los, Level 2 3)

Lent Lmr Los, Level 1

2 2

1, 2,.3 1, 2,'3 lo 2o 3

20 20 20 b.

Drywell Pressure - High c.

Hanual lniti ation Y,Z,N d.

SGTS Exhaust Radiation-High R

e.

Hain Steaa Line Radiation-Nigh C

2.

SECONDARY CONTAIIIIENT ISOLATION 1, 2, 3 20 1, 2, 3 21 qAAA 54$ $

20 1, 2q 3 20 O +

IF b.

c.

d.

Reactor Vessel Mater Level-Lm Lmr, Level 2 Drywell Pressure -

High'efuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft, Exhaust Duct Radiation - High Refuel Floor Mall Exhaust Duct Radiation - High Hanual Initiation 2

1, 2, 3 and e 1,2,3 1,2,3and" g5 25 25 25 25 24

m C

M W

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUHENTATION TRIP FUNCTION 3.

MAIN STEAM LINE ISOLATION a.

Reactor Vessel Mater Level -

II Low, Low, Low, Level 1

b.

Main Steaw Line Radiation -

C High c.

Main Steaw l.ine Pressure

- Low P

d.

Main Steaa Line Flow - High 0

e.

Condenser Vacuum - Low UA f.

Reactor Building Main Steam line E

Tunnel Temperature - High g..

Reactor Bui)ding Hain Steaa line E

Tunnel h Teaperature - High h.

Manual initiation NA i.

Turbine Building Main Steam E

Line Tunnel Teaperature-High 4.

REACTOR MATER CLEANUP SYSTEM ISOLATION 1, 2, 3 1, 2, 3

1, 1,2,3 1,2,3 1,2,3

~

2 2/line 2

2 1, 2, 3 1, 2, 3

1, 2, 3 MINIMUM APPLKABLE ISOLATION OPERABLE CHANNELS OPERATIONAL SIGNAL s PER TRIP SYSTEM CONDITION ACTIQH 21 21 22 gQ 21 21 ader I

24 21 I'

jI k

'C goo C.

d.

e.

RMCU h Flow - High RMCU Area Teaperature - High RMCU Area Ventilation h Tesp.-

High SLCS Initiation Reactor Vessel Mater Level - Low Low, Level 2 INCU Flow - High Manual initiation J

M M

I B

J NA 1

3 3

2

.2 1,2,3 1,2,3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3

l,2,3 23 23 23 24

~

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION 1, 2, 3

HINIHUM APPLICABLE ISOLATION OPERABLE CHANNE

~ OPERATIONAL TRIP FUNCTION SIGNAL s PER TRIP SYSTE CONDITION 5.

REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION a.

RCIC Steaw Line h Pressure - High K

1 AC'fION 23 4J I

g CC b.

RCIC Steaw Supply Pressure

- Low KB c.

RCIC Turbine Exhaust Diaphraya K

Pressure - High d.

RCIC Equipment Room Teaperature

- High e.

RCIC Equipwent Room h Temperature - High f.

RCIC Eaergency Area Cooler Teaperature - High g.

RCIC Pipe Routing Area h Tewperature - High h.

RCIC Pipe Routine Area Teaperature

- High i.

Hanua I lnitiation Orywell Pressure

- High 1, 2, 3

1,'2,3 1, 2, 3

1,2,3 1, 2, 3 1,2,3 1, 2, 3',

2, 3 1, 2, 3

23 23 iA 23

~g 23 2h 23

~gg

<<<<o gl egal oo IO TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION NINIHUH ISOLATION OPERABLE CHANHE TRIP FUNCTION

~(((((

(

P(R (R(P (II ((h 6.

HIG}l PRESSURE COOLANT INJECTION SYSTEH ISOLATION a.

HPCI Steaa Line h Pressure L

High b.

HPCI Steaa Supply Pressure-Low LB c.

HPCI Turbine Exhaust Oiaphraga L

Pressure

- High L

d.

HPCI Equipient Rooa Temperature - High e.

HPCI Equipient Rooa h Tewperature - High f.

HPCI faergency Area Cooler Teeperature - High g.

HPCI Pipe pouting Area Teiperature - High h.

HPCI Pipe Routine Area 4 Teaperature

- High i.

Hanual Initiation Orywell Pressure

- High 2

APPLICABLE OPERATIONAL CONDITION 1, 2, 3

1,2,3 1, 2, 3 1, g, 3

1, 2, 3 li2e3 1, 2, 3 1, 2, 3

1, 2, 3

ACflOII 23 23 23 z4 24

P zR I

CR TASLE 3.3.2-1 (Continued)

ISOLATION ACTUATlONNSTRUMENTATION 914; 5'rip Function Isolation Slgndls)~

Minimum Operable Channels P Trip Syst Applicable Operational Condition Action 7.

RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION I

M cn e,

Reactor Vessel Water Level - Low, Level 3 b.

Reactor Vessel IRHR Cut-in Permissive)

Pressure - High c.

RHR Flow - High d.

Manual initiation e.

Drywell Pressure - High I

A UB 1,2,3 1,2,3 1,2,3 1,2,3 28 28 2I 28 0 bnlg en>, gati~ wys)ewt wegwreh m OP<RA7taQN Co~bITIOQS $ on/ Q up

<~N sh~$ Ia~n c..l g s'rsvp< i~4@',i a ~a,'~<~,g RR'

,4 TABLE 3.3.2-1 (Continued)

ISOLATION ACTVATION INSTRUMENTATION ACTION STATEMENTS ACTION 20 -

Be fn at least HOT SHUTDOWN within IR hours and fn COLD SHUTQON within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 21 Be in at least STARTUP with the associated fsolatfon valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be fn at least HOT SHUTDOWN within i2 hours and fn COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 22 -

Be fn at least STARTUP wfthfn 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

hs ACTION 23 -

Close the affected system isolation valves within I hour and declare the affected system fnoperable.

ACTION 24 -

Restore the manual fnftfatfon function to OPERABLE status wfthfn 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTGOWN within the next L2 hours and fn COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 25 -

Establ fsh SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 26 -

Lock the affected system fsolatfon valves closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and declare the affected system fnoperable.

~SELT: AC'fcoA ZV.

eaves

@hen handling frradfated fuel in the secondary containment and during CORE ALTERATIONS and operations wfth a potential for draining the reactor '.

~

vessel.

Actuates dampers shown fn Table 3.6.5.2-L Shen VENTING or PURGING the dr@well per Specification 3.X1.2.8.

(a)

See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated by these isolation signals.

c anne may e p ace n an noper e s us or up ours or re surveillance without placing the channe1 or trip sys the tripped co on provided at least one other OPERAS nel in the same trip system nftoring that parameter addftion, for the HPCI system and RCIC system on, pro at the redundant isolation valve, inboard or outboard, a

able, in each line is OPERABLE and a11 required actuation umentation at valve fs OPERABLE, one channel may be in an inoperable status to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for requir ef11ance without. placing the channe1 or s stem in ripped condition.

SUSQUEHANNA - UNIT 1 3'-16 Amendment No. 36

~'

Insert ACTION27:

(Actions A, B and C fram NUREG 1433, Section 3.3.6.1)

ACTlON 27 InNate action to restore channel to OPERABLE status; or, Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System.

l

~.::- ~

>c>

TABLE3.3.2-.2 tContlrtuedl 1

. ISOLATIONACTUATIONtIIISTRUllhENTATION'SETP01NTS'::-.::.-.i.:. "

TRIP. FUNCTION IContlnued) e.

Condenser Vacuum - Low

.Reactor Bulldlng Main Steam Une Tunnel Temperature - High Reactor Bulng Main Steam Une Tunnel h Temperature. High TRIP SETPOINT a 8,0 Inches Hg vacuen s177 F

s 884F ALLOWABLEVALUE a 8.8 inchea Hg.vacua 1844F c 'l08'Ig.

M I

gp I

Cl 4.

ar b.

Cr Turb'>> BuMlng Main Steam Une Tunnel Temperature - High RWCU h Row - High RWCU Area Temperature - High RWCU/Area Ventllatlon h Temperature - High SLCS Inltlatlon Reactor Vessel Water Level - low low, level 2 RWCU Row - High MaaNI fnltlatlon s 1874F s 80gpm s 1474F or 1314' 88'F or 40.64FN a -38 Inchea' 428 gpm NA s 2004F s 80gpm s 1644F or 1374FN s 72 F or 43.64F e AS hchea s 438 gpm 0

5QLHfQR a

RCIC Steam Une h Presere - High b.

RCIC Steam Supply Presare - Low c.

RCIC Turbine Exhaust OIaphragm Pressure-Hlgh s177 Hg a 80 pslg s 10.0 pslg

~r s 188'P a 63 pslg s 20.0 pslg

TABLE3.3.2-2 (Contlnuedl 0C x

zz CR TRIP fUNCTION EA OR O

Y r MISOLAtlO (Coorlnuedl TRlP SETPOINT d.

~o h.

flCC Equipment Room Temperature

- High RCC Equipment Room h Temperature - High RCC Pipe Routing Area Temperature

- High RCC Pipe Routing Area h Temperature

~ High RCC Emergency Area Cooler Temp. - High 1874F" s 8$ 4F s 187'Ftf s 884Fff.

s 1874F I.

Manual Initiation s 1.72 pslg ISOLATlONACTUATIONINSTRUMENTATlONSETPOlNTS ALLONASLRVAltJR s 'l744F'4 s SS' 174'Fft

. s 884Ff s 1744F s 1.bb pslg

~

'>so J,.p%.

~

M 4

CD crr 8.

HHHhHQR I N Y

e.

KPCI Steam line flow - High HPCI Steam Supply Pressure

- tow s 350 inches HqO a 104 psli

. S 387 Inches QO:i..;,"

2 80pslg Ce d.

e.

HPCI Tcabine Exhaust tHaphragm Preaaure -.

High HPCI Equipment Room Temperature - High HPCI Equipment Room h Temperature - High HPCI Emergency Area Cooler Temp. - High HPCI Pipe Routing Area Temperature - High s 10 pslg s 187'F

~ S 884F S 1874F

-i S 1874Fff s 20pslg s 1744F '-

r s 884F

~ -

- s 1744F s 1744Fff

CtlC CO0

~

)2 TABLE3.3.2-2 IContinued)

ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS i'

~

e r

~

~ s

'e...'.s j;jiheS.

~ '-'ee

- F/I e I

~Hi'a, )2 hie go Je

~ SKTfONf,-f;":....

,.- ALLOWASt%VALUE.""> 'qgw h,

I%2CI~ Ilaahy Ateeh Tenpaehae -Hah

~.-:.

~ 4 8$ F(t-'s 2<<"-'")2 '.)2.-.::

~ g bb Fl CD I.

Nmuel iniletion I.. Oywel Stooge - leach 5$hM5

=:-".i.':.'Ileertoi Vooeel Wder Lnnl - Lee, Lwel 3:'c.'-'"0:;.'-..:I' i.;R)A

~

e

~ V

~

g 1)72 IWIyss;.:,T..'-:;.=:.:.:,,

a...,:, ) S I)bb.lmiy.'>..".:..I;:;<'y",s;~g i ~

~ ~

~

e

) ~

';-: L:;,He)sf)I Vessel SSSI Onen Fen)Hole)i i'ps."~~~ Wqg Ifg SS 'RES,. ','

" g

. O'I OS Fstf..".,, " ':

'.:"2=L:lyNROW INgh

.< =";"--.-.'::

"='".-':.'-.:."'...:;.~:-kf.':"; P",.".'..:s..~:g 25,00Q ~gg.~~'QQ...'j;:Q-;-',++Pg'22jl,ojjg ~',g.":

~

~ ~

~

'I

":;"41 gaael allan ei<"..-2":- 2!;:.:

I'..p.-...-.

~

.-.. I"...';:;-:."2.'.'.~-"p, IIAy~>~~f4~>jg~gpgg,~

g-:~,y:";jIIAj~~~~

~'::. e 'lgltNhee0~

. INgh '.-;.f':.s *'-g:,.-1.f'-;::=.-4".~~'-'>~<i~>',~~+ I)72 Iwiygg~'~~[j~T".,~~:>gg"Ibb.lwiy

~'ee QN flQUFQ Q 3/g 3)I ~ I',H.Tj~s p' e...

~, '..i'i)s "e 2')go~+:> )epfgj re gjf..

se'1)rg'r.'S'-4'p

+$

e '+)1 '~~p~ip 2:Ia)ee) e)O))In') fH TSHOSS IHSOO 2, Fee)f TOSH<22'IH802 2;:F,';.",:>P~j:as:'~'Q+$% afF eOee)S)'esn.~'rIPQ'C

~4

~ ~

It) e e

I ~

KA CCll Cm IABLf 4.3.2.1-1 lSOLAIION ACIUAIlON INSIRLNENIAILON SURVE lLLANCE RE UlREHENIS IRIP FUNCIlON I.

PRlHARY CONYAlNENY 1 SOLAYtON a.

Reactor Vessel Mater Leyel-CHANNEL CHECK CHANNEL FUNGIlONAL YESI CHANNEL CALIBRAYlON OPERAYIONAL CONOl YlONS fOR MHYCH SURVE lLLANCE Rf YREO

~

~ gt 1)

Los, Level 3

2)

Los Low, Level 2 3)

Lm Lmt Lmt, Level 1

S h.

Oryvcll Pressure - High NA c.

Hanual lnitiat ion NA d.

SGIS fxhaust Radiation - High S

e.

Hain Steaa Line Radlqtion " High S 2.

SECONARY CONIAlhNENI lSOLAIION a.

eac or esse a er eve Low Lm, Level 2

b.

Orle'll Pressure

" High c.

Refuel Floor High Exhaust Ouct Radiation - High d.

Railroad Access Shaft Exhaust.

Ouct Radiation - liigh e.

Refuel Floor Mall Exhaust Guet Radiation - High S

NA R

R 1, 2, 3

lK 2H 3

1, 2c 3 f, 2, 3 3

)ATE*

g*Pg 1,',

and 1, 2, 3

~

O

~

f.

Hanual initiation NA t, 2, 3 and

~

fABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEIllANCE RE UIREHEHTS CHANNEL CHECK co TRIP FUNCTION 3.

MAIN STEAM LINE ISOLATION a.

Reactor Vessel Mater Leyel-Low, low low, l.evel 1

S b.

Hain Steaa Line Radiation - High S

Hain Steaa Line Pressure

- Low N

d.

Hain Steaa Line Flow - High S

e.

Condenser Vacuum - Log NA f.

Reactor Building Hain Steaa Line Tunnel Teeperature

- High N

g.

Reactor Building Hain Steaw gine Tunnel h Teaperature

- High N

h.

Hanual Initiation N

i.

Turbine Building Hain Steaa Line tih Tunnel Temperature - High 4.

REACTOR MATER CLEANUP SYSTEM ISOLATION 1, 2, 3

), 2, 3 Rq.

Q N

l, g 3

gki 3%A l,2,3 2,

3 Po 3

CHANNEL OPERATIONAL FUNCTIONAL CINNNEL CONDITlO)S FOR NICH TEST CALIBRATION SURVEILLANCE RE UIRED a.

b.

C.

d.

NCU h Flow - High RNU Area Teeperature

- High RMCU Area Ventilation. h Teaperature - High SLCS Initiation Reactor Vessel Mater level " Low low, level 2 RMCU Flow - High Manual initiation NA NA S

S NA

'l,2) 3

), 2) 3 1, 2, 1,2,3 l,2,3 I, 2) 3 l,2,3

lABLE 4.3.2.1-1 (Continued)

ISOlAIION ACIUAllON INSIRUHENIATION SURVEILLANCE RE UIREHENTS lRIP 5.

CllANNEL 1 UNCTION CIIECK REAC10R CORE lSOLAllON COOL lNG SYSTEH ISOLATION CIIAHNEL OPERAT IONAL FUNCT IOHAL CHAHHEL CONDIT IOHS FOR ltHICII TEST CALIBRATION SURVEIllANCE RE IREO 6.

a.

C.

e.

g.

BClC Steam Line h Pressure

- High RCIC Steaa Supply Pressure-Low RCIC Turbine Exhaust Oiaphraya Pressure - lligh RCIC Equipient Room Teaperature

- lligh RCIC Equipient Room h Temperature - lligh RCIC Pipe Routing Area Temperature - lligh RCIC Pipe Routing Area h Teeperature

- lligh HA HA h.

RCIC Ewergency Area Cooler Teaperature - lligh HA i.

Hanual Initiation.

HA j.

Orywell Pressure - High NA IIIGN PRESSURE COOLANT INJECTION SYSTEH ISOLAIION 1,2,3 1,2,3 Ie 2e 3

I, 2, 3 i,~,i 1,2,3 i,~,k(

II 2e 3 Ie 2e 3 I, 2, 3 b.

C.

HPCI Steaa Line h Pressure - High HPCI Steaa Supply Pressure

- low HPCI Turbine Exhaust Oiaphraya Pressure

- lligh 1,2,3 I,2,3 I,2,3

DC x

RR CK TRIP RJNCTION CHANNEL CHECK CHANNEL FUNCTIONAI.

TEST CHANNEL CALIBRATION OPERATIONALCONDITIONS RN WHICH SURVEILLANCERMUNED IGH RESSU ECO E

0 SYSTEM ISOLATION IContinuedl d.

HPCI Eydpment Room Temperature - High e.

HPCI Equipment Room 4 Temperature - High NA 1.2,3

1. 2,3 TABLE4.3.2.1-1 (Colttfntted)

ISOLATIONACTUATIONINSTRUNIENTATIONSURVEILLANCEREQUIREMENTS CO Col 0) 7.

f.

HPCI Emergency Area Cooler Temperature - High g.

HPCI PIpe Routing Area Temperature - Ngh h.

HPCI Rpe Routing Area 4 Temperature - High I.

Manual Initiation DryweN Pressure - High 0

OOL AD 0

0 1,2.3 1,2,3 5, 2, 1.2,3 1,2,3 8~+,8'.

Reactor Vessel Water Level - Low, Level 3 b.

Reactor Vessel IRHR Cut.h Permissive)

Pressure - High c.

RHR Row - High d.

Manual Initiation e.

Drywel Pressure - High S

R 1,2,3

5. 2, 3

1. 2, 3 1,2,3 re R

0

~ e

~ e ~

When handing Irradiated fuel in the secondary containment and during CORE ALTERATIONSend operations with e potential for draining the reactor vessel When reactor steam dome pressure > 5043 pslg and/or any turbine atop valve Is open.

When VENTINGor PURGING the drywe1 pet 8 ecmcation 3.51.2

Extending STIs and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.2:

Isolation Actuation Instrumentation

INSTRUMENTATION 3/4.3. 2 ISOLATION ACTUATION IHSTRUMEHTATION LIMITING CONOITION FOR OPERATION 3.3.2 Th f

t 5

\\

Si

\\

f TU1 LLR1 sha11 be OPERABLE with their trip setpofnts set consfstant wfth the values shown fn the Trip Setpofnt col~ of Table 3.3.2-2 and wfth ISOLATION SYSTEM

RESPONSE

TIME as shown fn Table 3.3.2 3.

APPLI ILITY:

As shown fn Table 3.3.2 L ACTIOll:

Nth an fsolatfon actuatfon fnstnaentatfon channel trip setpoint less conservatfve than the value shown fn the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with fts tip setpoint ad)usted consistent with the Tip Setpofnt value.

Nth the number of OPERABLE channels less than requfred by the Nfn'E Channels per Tip Systew requirement for one ti place erable channel(s) andlor that tip n the tripped condftfon wfth ur.

The provisions ecfffcation 3.0.4 are not appl fcable.

c.

Mfih the number Li channels less ufred by the Minimum QPERAB ne1s per Tip Systaa requirement for rip systems,

.at'east one trip system~ fn the tipped condftfon I hour and take the ACTION re ufred by Tabl 3 3 2 L "An arable channel need not be placed in the tipped condition where th would ca the Tr'ip Function to occur.

In these

cases, the inoper channel shall be resto to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the A quired by Table 3-3.2-1 for ip Function shall be taken.

In ion, for the HPr'I system and RCIC systaa fs fon, provided that th>>

dant fsolation valve, inboard or outboard, as applf fn each lf s OPERABLE and alLrequfred actuation fnstrumentatfon for that v ERABLE, one inoperable channel need not be placed fn the tipped fo re this would cause the Trip Functfon to occur.

In these s, for the HP RCIC systams, the inoperable channel shel restored to OPERABLE s thin 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or the ACTION requfred e 3.3.2-1 for that tip Function sha e taken.

~If more els are inoperable fn one trip system than fn the othe, ace the systea with more fnoperable channels fn the tripped condftfon, capt when this would ca e the Tip Functf to SUS)UEHANNA UNIT 2 3l4 3-9

'nsert 3.3.2:

(Actions A, B and C from NUREG 1433, Section 3.3.6.1 and 3.3.6.2) b.

With the number of OPERABLE channels less than required'y the Minimum OPERABLE Channels per Trip System in one or more Trip Systems:

For functions 1.a.1, 1.b, 1.e, 2.b, 3.b, 7.a, and 7.e, place the channel in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; and, For functions other than 1.a.1, 1.b, 1.e, 2.b, 3.b,.7.a, and 7.e, place the channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

With one or more automatic functions with isolation capability not maintained, restore isolation capability within one hour.

d.

If ACTIONS b or c are not met, take the ACTION required by Table 3.3.2-1 for the function.

Insert 3.3.2 - Footnote:

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains isolation capability.

TRIP FISC IIOH I.

PRIHNY COHTh SKI SOlhT IQH a.

Reactor Vessel Mater level I)

Lat, leve'I 3 lABlE 3.3.3-3 lsolhTIOH hCTUATIQH IHSTRtNKNThTIOH NINIIIII ISOI ATIQH OPERhalf CiNHHKL SIGHhl S

a PER TRIP SYSIEH hPPLICh81K OPERAT IOHAL COHOII IOH l ~ 2I 3

$ TIOH 20 b.

C<

d.

eo 2)

Low Lao, Level 2 3}

Lees Les Les, level j Orpull Pressure - High llanual initiation SGTS Exhaust Nadiation-Hlgh Hain Steaa Line Nadiation-Y,L N

l ~ 2, 3 l,2,3 l,2,3 l,2,3 j

2 3

i111 5111 j, 2, 3 20 20 20 2h 20 SECQOhlT CONAINKII lSO!.h l b.

c,.

eo Reactor Vessel Mater Level-Lar Los, Level 2 Oryx')1 Pressure - High Nefuel Floor High fxhaust Ouct Nadiation - High Nailroad hccess Shaft Exhaust Quet Radiation - iiigh Refuel Floor Mall Exhaust Quet Radiation - High Hanual lni tie'Lion 2

j,2, 3ead1 j, 2, 3 l,2, 3and1 24

TABLE3.3.2-1 ICorttlpued)

ISOLATIONACTUATIONINSTRUMENTATION tSOLATION SlQNAQyltal ayytaIIUtN OPEMykt Q,S AtPOCASLE est TS>> STS

~

OtyttATINLCOSttmoll ACTNtt

~.

Itaactor Vesaal Wat<< tevel-Low Low Low. Level 1 lIah Steam the IMatton - Hgh e.

Mah Steam Une hesatae

~ Low IIah Staara Lhe Row - Hgh e.

Condone<<Vaoaaa

- Low t.

Iteecter buMny lIaln Stum One Tunnel T<<nperatLae - Hgh

~.

Iteecter buMny llah Stum Lhe Tunnel 4 Temp<<ctree - Hgh L

Turbtne Suydhy Mah Steam Lhe Tunnel Temp<<atrae

~ Hgh lEKIHlhHQB a.

IIWCUS Row - Hgh k

IIWCUArea Tenyeratee - Hgh o.

IlWCUArea Ventyathn h TemperatLee - Hgh UA 1,2,$

1 ~ 2,$

1,2,$

1~ 2, $

1,4$

f~+$

ti2,$

1,4$

ti2,$

21 20 21 2$

eo tteactor Ve!a el Water Level Lew Lew. Level 2 1,2,$

t.l.

INfCURew Hgh tA.

tbrHley<<wratlve Heat Exchanger Nacharge Temp<<atee - Hgh 1N 1N t~+$

42,$

2$

24 or Unit 2 Cycle ~ opera Sre Rayon<<attve Heat Kachangar Hgh Channel S.

~mperaoie - fSph Channel ahoy Ire OPBIAlfh place et IIWCURow-

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUHENTATION TRIP 5.

FUNCTION REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION HINIHVM APPLICABI.E ISOLATION OPERABLE CHANNELS + OPERATIONAL

~III I I PtR tRIP I ttt II ttttll ACTION b.

RCIC Steam Supply Pressure

- Low c.

RCIC Turbine Exhaust Diaphragi Pressure

- High d.

RCIC Equipment Room Temperature - High e.

RCIC Equipment Rooa h Temperature - High f.

RCIC Pipe Routing Area

, Temperature " High g.

RCIC Pipe Routing Area h Temperature - High h.

RCIC Emergency Area Cooler Temperature

" High i.

Hanuai Initiation j.

Drywell Pressure

- High KB a.

RCIC Steaa Line h Pressure

-High K

I 2

1, 2, 3

lo2o3 1, 2, 3

1 ~ 2o 3 1 ~ 2o 3

1, 2, 3

23 23 23 23 I

23 OQ 23 23

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION HINIHUN ISOLATION OPERABLE CINttNELS TRIP FUNCTION SIGNAL S a

PER TRIP SYSTEH 6.

HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION a.

HPCI Steam Line h Pressure L

High APPLICABLE OPERATIONAL CONDITION 1, 2, 3

ACTION 23 b.

HPCI Steam Supp}y Pressure-Low LB c.

HPCI Turbine Exhaust Oiaphrago L

Pressure

- High d.

HPCI Equipment Room

'lemperature - High e.

HPCI'quipment Room 5 Temperature - High f.

HPCI Emergency Area Cooler Temperature - High g.

HPCI Pipe Routing Area Temperature - High h.

HPCI Pipe Routing Area h Temperature - High i.

Hanual Initiation j.

OryweII Pressure - High 2

2 l, 2, 3

l, 2, 3

),2,3 l, 2, 3

l, 2, 3

l~ 2 ~ 3 ls 2o 3

lo 2e 3

23 23 23 23 23 2$

23

U)C D

x zR CR TABLE3.3.2-1 (Contlnuedl tSaULTtON ACTUATtoN NSTttuNBiTATION Trip Function lso'latlon Signal(s)~

Mtnlrnurn Operable Channels P~Trlp Systehgg Applicable Operational Condition Actfon Cal C5l cn 7.

RHR SYSTEM SHUTDOWN COOLINGIHEADSPRAY MODE ISOLATlON e.

Reactor Vessel Water Level - Low, Level 3 b.

Reactor Vessel lRHR Cut-in Permissive)

Pressure

~ High c.

RHR Flow - High 1,2,3

1. 2, 3 2B d.

Manual initiation e.

Orywel Pressure - High NA 1,2,3 1,2,3 4f 0>i~ an5, trip ey5fen resui55A in cyrsAATto55AL c5<1 <cams 'f 5~$ e ~

84lg

%u'fJOIOA %4li55j sf5i'555 IJeseg C K'5<~6L~R Rz0

TABLE 3.3.2"1 {Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION STATENENTS

.ACTION 20 -

Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUTDOWN

~

within the next.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 21 -

Be fn at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or he in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUTMWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 22 -

Be in at least STARTUP wfthfA 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 -

Close the affected system isolation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and declare the affected system inoperable.

ACTION 24 -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affected system inoperable or be fn at least HOT SHUTDOWN withfn the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 25 -

Establish SECONDARY CONTAINNENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 26 -

Lock the affected system isolation valves closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months declare the affected system inoperable.

TABLES NOTATIONS When handling irradiated fuel fn the seconda~

containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

Actuates dampers shown in Table 3.6.5.2-1.

When VENTING or PURGING the drywell per Specification 3.11.2.8.

(a)

See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated by.

these isolation signals.

channe may be p ace n an snopera e s atus or up to ours req 'urveillance without placing the channel or trip s sn the tripped con rovided at least one other OPE annel in the same trip system is ring that parame n addition, for the HPCI system and RCIC system isola that the redundant isolation valve, inboard or outboard pl c in each line is OPERABLE and all required actua strumentation for ve is OPERABLE, one channel ma aced in an inoperable status for up urs for re 'urveillance wfthout placing the channel, or trip sys e tri ed condition.

SUSQUEHANNA - UNIT 2 3(4 3-16

Insert ACTION27:

(Actions A, B and C fram NUREG 1433, Section 3.3.6.1)

ACTION 27 Initiate action to restore channel to OPERABLE statu's; or, Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System.

TABM3.3.2-2 lCotttlrttted)

ISOLATlONACTUATIONtNSTRUNIENTATlONSETPOlNTS ALLOWABLEVALUS CR Cil D

~.

Condenaef VacLml ~ Low f.

Reactor Bulking Main Steam Line Tunnel Temperatwe - High g.

Reactor Buikinp Mekt Steam Une Tunnel h Temperatwe - High h.

Manual Initiation I.

Twbine Buiklnp Main Steam Une Tunnel Temperatwa - High 4.

REACTOR WATER CLEANIJP SYSTEM ISOLATION a.

RWCU h Flow - High b.

RWCU Area Temper atwe

~ High c.

RWCU/Area VenQatlon h Temperatwe - High d.

SI.CS Inltlatlon

~.

Reactor Veaael Water Level - Low Low, Level 2 f1. RWCURow-High f2.

Non'-Regenerative Heat Exchanger Dlacharge Temperatura -,.:

Hiph g..

Manual inithtlon.

5. REACTOR CORE ISOLATlONCOOLNO SYSTEM ISOLATION h 8.0 lnchea Hp vacuwn s 1774F s gg>>F s 187>>F.

s 80gpm s 147>> F or 131>>F>>

s eg For40.$ F>>.

NA

~

." a 48 hchea S 482 Ilxtt s 144>>F,s,

~..

a 8.8 inchee Hg vactaxn s 184'F s 108' 200>>F s 80gpm s 154'F or 137>>F>>

s 72>>F or 43.5>>F

'.::-'i'".'-iRN R 4$ ktchea,

.. s 472 Iixtt.::::~.q~q;j@

~ ".<.,z.'A

~.

RCIC Steam Une h Preaawe - High b.

RCIC Steam Supply Praaawe - Low c.

RC!C Twbine Exhauat Diaphragm Preaawe - High s 138'HO a eo palp s 10.0 palp s 143'aO h $3 palp s 20.0 pelg

TABLE3.3.2-2 {ContIntied)

DC Cz I 0 d.

RCIC Equipment Room Temperature - High

~.

RCIC Equfpment Room h Temperature - High f.

RCIC Pipe Routing Area Tem ture -High s IB74F s 884F s

ISOLATIONACTUATIQNINSTRUMENTATLQNSETPOINTS TRIP FUNCTION 0

0 IContinuedi ALLOWABLEVALLIS s 17F s 884 s 17I4Ftt le Cl O

R z0 I e-8.

~ <

b.

Ct

~t HPCI Steam Line Flow - High HPCI Steam Supply Praaaure - Low

\\

HPCI Turbine Exhaual Dfaphlol Preaalga-Hlgh HPCI Equipment Room Temperature - High HPCI Equfpment Room h Temperataaa -Qgh HPCI Emergency Area Cooler Thnp. - High 1

HPCI Pipe Routing Area Tempdt4ture - High h.

HPCI Pipe Routing Area d Tergerature - High Manual initiation DiyweffPreaaure - High g.

RCIC Pipe Routing Area d T rature - High h.

RCIC Emergency Area Cooler Mp. - High I.

Manual Initiation Drywall Praaaure - Hfgh HIGH PRESSURE COOLANT NJECTION SYSTEM ISOLATION

. s I.yea.'

'I 7!t'~.',

~

t

~

'Nh a

g

~ ',i.t s 1.72 paig S 387 lnchea HiO a 104 palg s 10 yafg s 187'IF sBStF s 1874F s 1874Ftt s 88'Ftt S 1.72 paig

~

t~ ~

~

I C'

884Ft S 17I4F NA s 1.88 palg s 388 inchea H>O h 80palg s 20 pafg s 17teF SBBF S 1744F S 1N4Ftt s 88'Ft

. s 1.88palg

~ >

.s.r;4i:.

... r>,'-.

~,

t ~

g.)

t,<

~ ~

~

t

I SOI A'I ION AClllAIIO!I INSIRIRIENIAIIOII SUAVE ISSANCE RE llIREHENIS lRIP FINCHlmI I.

PRIHNY CONAINKNl ISOlATION f.INHHfl CIILCK CNHHfL FUHCTIONl CINHHfl TfSl CALIBRhl IOII CL OPfRhllONL COHDIlIGNS FOR QIICII SIIRMEIllINCflf ION a.

b.

C.

Reactor Vessel Mater level-l)

Lat, Level 3 2)

Les La>, Level 2 3)

L~ Lee Los, level l Orpull treasure High Iiaaual laitlatiea SOTS Kaleeat Mlatlee - High Naia Stea Liae aadlatiea-Hlgh 5

S S

NA N

R R

R N

N l, 2, 3 l, 2, 3 li2R3 l,2,3 s, 2, 2, R~~~

s~~~

I l,2N3 SfCNSllY I IOWAN SOLI'i ao Weacter Vessel lhter level-Lce Les, Level 2 Orwell treasure - High lo 2N 3 and +

l, 2, 3 c.

Refuel fleet High Exhaust Ouct.

ka4iatioa - High d.

. Railroad Iccess Shaft fahauat Ouct Ra4iation - High eo Refuel Fleer 'All Exhaust Duct 44lation - High f.

Nanual initiation l,2,3aed

~ C dec

~ NRI

ISQEA'aDN ACTUATIONINS1RIIIAEQ7$QMIll/VEIISlaCA(gfgJI I:, -g fifo/}+ !

e. React>> Vaeeel Nt>> Lani ~

Lew Lew Lew. Leael l

~

l4NIIanna Qa IeONlan ~~

I%ISIN%Qo fteaaIN iLew 4

Ma1 Ite<<w 4w flw>>W

~.

Coatee Veewe LeIa l.

Iaaae>> aaay ~ Iten+ ue Zaenal feape~

~.

leeeeer~ Mala Iaaeet Liaa Twaal 4 'leeyeraan Hgh l4aael l&lal<<a L

teihe 54&g~It~Lie lweel f

~ lIIh

~.

NCUiRaw Hgh

~

NtNAeo t<<ty<<ann - lwgA e

IWCUAwVomatha iTenp<<aan Hgh 4

ILCIInkletlatt

~.

ltaeot>> Veeeel VAt>>Lenl Lew Lew, Lerel 0 t.lo NVNflow Hah~

lsf 3

~ e e ~

42

~ S fat 441

~ DR$NNtwe ~

80'.

Manual Inkhthn a..

v,':

~: <;,; t,"c

~

C~c

<X tlat.:

k'lr<1

~

i ~

IABlE 4. 3.c. I-I (Continued)

ISOthilaN ACIINIIQN INSIRIWENlhIION SNVElltANCE RE IRLHENIS CIIANNEl CIIANHEl fljNCTIQNAl CIIANEl lRIP fNCIIQN CIIEN IESI CAllBRAIIOH S.

RIACIOR CORE I50iAIIOHCMllHG SYSIIH ISOLAIIOH g

OPERAIINAl

'{NOI'5lNS fQR NICH SIJRVKllUNCE RE INEO OAO Pi wg4 Ze g Ql

-C C

'Nh

.Nh ',

.N-:.-

EN ISOlhllON a.

RCIC Steaa line h Prcssure - High b.

RCIC Steaa Supply tressure-lat c.

RCIC Turbine Exhaust Oiaphrage Pressure - High d.

RCIC Equipeent 1ooa leeperature - High e.

RCIC Equipoent aooe h leepcrature. High t.

RCIC Pipe Routing brea Ieeperature

- High 9.

NCIC Pipe Routing Area h Beperature

- High h,

RClC Eeergency Area Cooler.

~ leoperature - High i.

Manual Initiation

.j.,

Oryal I tressure - High 6.

IIIGH tRESSNE COOlANI INECIION SYSI

. '."-a.>s:- NCI Steaa line h

".';.;:" Pressure - High b.

HPCI Steaa Supply Pressure - ltd c.

IIPCI Iurbinc Exhaust OiaIIhraga Prcssure

- Illgll Q

Q,'h

'N.

I, 2, 3 3

l,2,3 I, 2, 3 I, 2, 3

TABLE1.3.2.1-1 {Contfnved)

ISOLATIOIIIACTUATIONINSTauSSESraTIoa SuaVEIaaaCE aEaulREMerrS CHANNEL CHECK CHANNEL RNCTIONAL TEST IConthuedl d.

HPCI Equipment Room Temperature - IIgh

~.

!%}CIEgutpment lloom h Temperature - Iggh f.

II}CIEmergency Area Cooler Temperature - Sgh g.

II}CIl}lpe Routhg Area Temperature - IIgh h.

SCI Ape Routhg Area h Temperature

- Iggh L

Manual Inltlatke NA.

Drywei heasure

~ Iggh 7.

IIHIISYSTEM SHtfTDOWN COOLNOh%AD StftAYMODE ISOLATION 4

1,2,3 1.2,3 1I 2.'3 1,2.3 1,2, 1,2,3 Ii2,3 t

~

r 'tI

~ ~

I / ~

~

P ~

Reactor Veaaal Water Level - Low, Level 3 Reactor Veaaal gIIICut& Permhalve) hearne - Iigh c.

RHR Row - IIgh d.

Manual InNadon

~.

Drywal heaaee - IIgh 8

NA

. NA ra;; 4

~,}

..'-..NA.,

~

- II w, '1 ~ 2t 3 t,t

.t

.,; 'I,2,3

'1) 2t 3 vr tr'r:,g }8rlj}tr}

le 2o 3

" ";~r~'4' When hanalng IrraSated fuel ln e>> aecondary containment and dwfng Col% ALTERATIONSend operetta whh a potential for draaeg the reactor When eny @abbe atop valve la open.

'When VENTIIGor PURGING the dryweg per fhatbn3.11.2.8.'pP,

Extending STls and AOTS for Susquehanna Technical Spec%cation Instrumentation Unit 1 TS 3.3.3:

Emergency Gore Cooling System Actuation Instrumentation

0 DC x

ZZ I

Z TRtP FUNCTION MiNBjst/M OPERABLE cHANNELB PER TIBP SYSTEM APPUCABLE OPERATIOI/AL COIIDITION8 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Water Level - Low Low Low, Level 1 2tal 1,2,3,4,6 TABLE3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION ACTIOff 30 b.

DrywaN Pressure~ High c.

Reactor Vessel Steam Dome Pressure

~ Low tPermlsslvel 2tal 2lal 1, 2, 3 30 B

Z O

d.

Manual Initiation 2.

LOW PRESSURE COOLANT INECTION MODE OF RHR SYSTEM e.

Reactor Vessel Water Level - Low Low Low, Level 1 b.

Drywel Pressure - High c.

Reactor Vessel Steam Dome Pressure

~ Low IPermlsslve) 1l System Initiation 2I Recirculation Discharge Valve aosure

.d.

Margret initiation 3.

HIGH PRESSURE COOLANT INECTION SYSTEMS e.

Reactor Vessel Water Level - Low Low, Level 2 b.

DrywallPrasswe - High c.

Condensate Storage Tank Level - Low d.

Suppression Pool Water Level - High e.

Reactor Vessel Water Level - High, Level 8 f.

Manual initiation 1/subsystem 2tal 2tal 2tal 2tal 1/subsystem 2ta) 2tal 2iaitbI 2tal 1/system 1,2,3,4,6 1,2.3.4,6 1,2,3 1~2. )

4.6

~

1.2,3,4.6 1, 2, 3 1.2,3 1.2,3 1,2,3 1.2,3 1,2,3 30 30 30 30

TABLE 3.3.3-1 {Con)IttuedI EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION TMfUatcTtoH i&IONMOPEttASLE CHAIORLS

~Etl TM SYSTEM AffLICASLEOffttlytONAL COIITtgttS ACTION i.

AUTOMATtCDFPRESSURt2ATNH SYSTfM a

Reactor Vessel Water Level - Lowlow Low, level I h.

Dryweg Pressree.

High c.

ADS Timer 4.

Core Spray Pump Discharge Presaiae. High )Permissive)

~.

Rt tR LPCI Mode Pump Discharge Pressure

~ High IP>>mhalve) 1.

Resctot Vessel Water Level

~ low. level 3 )P>>missive)

ADS Diyweb Pteasrae Bypass Timer h.

Manual Inhitrtt L

Manual Initiation 2t IIvalve I.2.3 I. 2, 3 I. 2. 3 I.2,3 I.2,3

).2,3

),2,3 l.2. 3

).2,3 33 33 TOTll HO.

Of CHANISLS CHANNELS TO~

IMWMUM CHAlOKLS OPERAS LOSS Of POWER

~.

4. Id iv ESS be Under voltage

)loss ol Vohage, c 20%)

h.

~.IB irv ESS Bus Under vohage

)Degraded Voltage, c BS%)

o. I.18 irvESS be Under vottage

)Degraded Voltage, c $3%)

d.

480V ESS be OB555 Under votlage

)Degraded Voltage. c 55%i fff

~.

4SOV ESS be OBSBS Urrrter voltage

)Degraded Voltage, c $2%) fsf See footnotes enneat page.

lltxe 2ltrre I,2,3.I

.S

),2. 3.i, S I. 2, 3, 1, S I,2,3,d,S l,2,3,4

.5 38

C mx Rz la)

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOUNG SYSTEM ACTUATION INSTRUMENTATION lb)

One trip system.

Provides signal to HPCI pump suction valves only.

Ic)

Two out of two logic.

(d)

Bther 4d or 4e muit be satisfied.

The ACTION ls required to be taken only If neither Is satisfied. A channel Is not OPERABLE unless Its associated pump ls OPERABLE per Specification 3.6.1.

{e)

Within an ADS Trip System there ere two logic subsystems, each of which contains an overall pump permlsslve. At least one channel associated with each of these overall pump permlsslves shell be OPERABLE.

When the system ls required to be OPERABLE per Specification 3.6.2 Zg~r

. rebecS:5-I

+lo4 (P Not required to be OPERABLE when reactor steam dome pressure Is less than or equal to 160 pslg.

Required when ESF equipment Is required to be OPERABLE.

Not required to be OPERABLE when reactor steam dome pressure Is less then or equal to 100 pslg.

Required to be OPERABLE only when Diesel Generator E ls either aligned to the Class 1E system or not aBgned to the Class 1E system but operating on the Test Facility.

The automatic transfer of HPCI pump suction from the condensate storage tank to suppression pool on high suppression pool water level occurs only when HPCI Injection valve is open.

i

TABLE34&1 (Cotttinuadl ACTION 30-X S rid~~

a.

b.

ACTION 3'1

~g~ ACE!M Bi ACTION 32 ACTION 33

~~+ 4cTr& 53 ACTION 34-eLY Acnot4 Sf ACTION 35 - With the number of OPERABLE channels less than the Total Number of Channels.

declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 36

~

al With the number of OPERABLE channels one less than the Total Number of Channels.

place the inoperable channel in the tripped condition within 1 hour:

operation may then continue until performance of the next required CHANNEL".

FUNCTIONALTEST.

bl With both ohannels rnooerabla an a 4.16Kv ESS bos, declare tha assordatad 4.16Kv ESS bus inoperable. and take the ACTIONrequiredby Specification 3.8.3.1 or 3.8.3.2 as appropnate.

c)

With both channels inoperable on the 480V ESS Bus 08565. declare the 480V ESS Bus 08565 not energized:

l1)

For the Diesel Generator E aligned to the Class 1E system, take the ACTION required by Specification 3.8.3.1 or 3.8.3e2 as. appropriate (2)

For the Diesel Generator E not aligned to the Class 1E system, declare the Diesel Generator E 125 VoltDC distribution system load group not energized and take the ACTION required by Specification 3.8.3.1 or 3.8.3.2 as appropriate.

SUSOUEMANNA - UNIT 1 3/4 3-30 Amendment No.124

Insert Action 30:

(Actions A, B and H

(except HPCI) from NUREG

1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

a.

b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or declare the associated ECCS inoperable; and, Within one hour from discovery of loss of initiation capability by this trip function, declare the associated ECCS inoperable..

Insert Action 31:

(Actions A, C and H from NUREG 1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare the associated ECCS inoperable; and, Within one hour from discovery of loss of initiation capability by this trip function, declare the associated ECCS inoperable.

(* ACTION 31b is not applicable to Function 3.e, Reactor Vessel Water Level-High, Level 8)

insert Action 32:

(Actions A;F and H fram NUREG 1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

b.

Within one hour ffum discovery of loss of ADS initiation capability by this trip function, declare the ADS valves inoperable; and, Within 4 days from discovery of an inoperable channel(s) concurrent with HPCI or RCIC inoperable, place the inoperable channel(s) in the tripped condNon; and, Within 8 days fmm discovery of an inoperable channel(s) ifboth HPCI and RCIC are OPERABLE, place the inoperable channel(s) in the tripped condition.

d.

IfACTION b or c is not met, declare ADS inoperable.

insert Action 33:

(Actions"A, G and H from NUREG 1433, Section 3.3.5.1)

A With one or more required channel(s) inoperable in one or more Trip Systems:

a.

Within one hour from discovery of loss of ADS initiation capability by this trip function, declare the ADS valves inoperable; and, b.

Within 4 days from the discovery of an inoperable channel(s) concurrent with HPCI or RCIC inoperable, restore the channel(s) to OPERABLE status; and, c.

Within 8 days from the discovery of an inoperable channel(s) if both HPCI and RCIC are OPERABLE, restore the channel(s) to OPERABLE status.

d.

IfACTION b or c is not met, declare ADS inoperable.

Insert Action 34:

(Actions A, D and H from NUREG 1433 Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Functions:

a.

b.

C.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or align the HPCI pump suction to the suppression pool; and, Within one hour of discovery of loss of initiation capability declare HPCI inoperable ifthe associated pump suction is not aligned to the suppression pool.

IfACTION a or b is not met, declare HPCI inoperable.

Insert:

Table 3.3.3-C Note (a):

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the-associated Trip Function maintains trip capability.

insert:

Table 3.3.34 Note (f):

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

TABLE h.3.3.7-7 CNNNEL OP ERATlONAi.

CHANEL FUHCTlONAL.

CNWEL CONnlTTONS FOR NTCH CIIECK TESI ChllORKIION SURUEIllhNCE RE lllREII Reactor Vessel Mater level "

Los lm Los, level 1

Or@tell Pressure

- High Reactor Vessel Steaa Ooae Pressure

- Lmr Kanual initiation a.

l, 2, 3, I>>, 5>>

S NA b.

C.

l, 2, 3

4>>, 5>>

HA HA d.

EHERGENCY CORE COOLiNG SYSTEH hCTUhllON TNSTRUHENTATlON SURVElllhNCE BE UlBEHEHTS TRIP FlNCTlON l.

CORE SPRAY SYSTEH W

20 I

a.

b.

C.

Reactor Vessel Mater i.evel-l.ov le Lo~, Level l Orywell Pressure - High Reactor Vessel Steaa Ooie Pressure - Low i)

Systea Initiation 2)

Recirculation Oischarge Valve Closure 5

HA d.

Kanual initiation HA 3.

NION PRESSURE COOIKNE INIECEION SUSSEX lOM PRESSURE COOlhNT 1HJECTTON NOE OF RHR SYSTEK lo 2o 3o I>>o 5" lR 2R 3 lR 2, 3, 4>>, 5>>

1, 2, 3, 4>>, 5>>

lo 2i 3R 4*o.5>>

ao b.

C.

d.

Reactor Vessel Mater level-Low Los, level 2 S

Or@tell Pressure

" High HA Condensate Storage Tank Level-Lov Nh Suppression Pool Mater i.evel-fligh

~

HA Reactor. Vessel Mater level-lligh, Level 8 Nh Kanual initiation Nh Q

NA 1, 2, 3 l, 2, 3

l, 2, 3 l, 2, 3

l

TABLE4.3.3.1-1 (Contintted)

EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATIONSURVEILLANCEREgUIREINENTS mx zz CR TAP FUNCTION 4.

AUT'OMATICOEPRESSURIZATON SYSTEM a

Reactor Vessel Water I.evel

~ low Low low, level 1

b.

Orywell Pressure

- High c.

ADS Timer d.

Core Spray Pump Discharge Pressure

- High e.

RHR lPCI Mode Pump Discharge Pressure

~ High I.

Reactor Vessel Water level low, Level 3 g.

ADS Orywell Pressure Bypass Timer h.

Manual Inhibit I.

Manual Initiation 5.

LOSS OF POWER CHANNEL CHECK NA NA CHANNEl FUNCTIONAL TEST CHANNEL CALRIRATION OPERATIONAL CONOTTION5 FOR yrNCH 5URVER.LANCE REQTINEO 1,2,3 I,2,3 1.2,3 1,2,3

1. 2, 3 1,2,3

1. 2,3 I. 2. 3

1. 2, 3 a.

4.18 kv ESS Bus Undervoftage ILoss ol Voltage) b.

4.18 kv ESS Bus Undervoltage IDegraded Vdtegel c.

4.18 kv ESS Bus Undervdtage IDegreded Voltage) d.

480V ESS Bus OBS85 Undervoltege IDegreded Voltage

< 85~v>>

e.

480V ESS Bus 08585 Undervoltage IDegraded Voltage cS2W>>'A 1 ~ 2e 3r 4

~ S le 2o 3e 4

~ 5 1.2.3,4

. S 1,2,3,4,5 1,2,3,4

.5 X

O IM When the system fs required to be OPERABLE. after being manually realigned, as applicable, per Specification 3.5.2.

Required OPERABLE when ESF equfpment fs required to be OPERABLE.

Not required to be OPERABLE when reactorsteam dome pressure ls less than or equal to 150 pslg, Not required to be OPERABLE when reactor steam dome pres'sure fs fess than or equal to 100 psig.

~ Requfred to be OPERABLE only'when Diesel Generator E is either aligned to the Case 1E system or not aligned to the Class 1E system but operating on the Test FecNty.

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.3:

Emergency Core Cooling System Actuation Instrumentation

TABLE3.3.3-1 I

EMERGENCY CORE COOLING SYSTEM ACTUATlONINSTRUMENTATlON TAP FUttCTION IwriNwla opERAILE cHAttNRs Pal TRP SYSTBl APPtlCASLE OPERATtONAL COrtDtttOIQ 1.

CORE SPRAY SYSTEM

~.

Reactor Veaael Water level - Low low Low, Level I b.

Drywei Prea¹re - Ngh c.

Reactor Veaad Steam Dome Prea¹ee - Low tPermtutve) d.

Manual tntttatton 2.

LOW PRESSURE COOLANT tNJECTION MODE OF RHR SYSTEM e.

Reactor Vyaaet Water Level - Low Lowlow, level 1 b.

Drywal Preaaue

- Ngh c.

Reactor Veud 8!sam Dome Preutae

~ Low tPermtaatve) 1l Syatem Intttatton 2l Rectrcutatton Dtacharge Vatve Cto¹re d.

Manual Intttatton 3.

NOH PRESSURE COOLANT NJECTtON SYSTEMt 2ta) 2tal 2tal tlaubayatem 2tal 2tal 2tat tiaubayatem 1.2,3,4,5

1. 2,3 1,2,$

4,5

~

'l,2.3,4 i 5 1,2,3,4,5 1,2,3 tt 2, )

4,5 tl 2, )

4,5 to 2,$,4 4

30 33 e.

Reactor Veaael Water Levd Low Low, Level 2 Drywae Prea¹ee - Ngh o.

Coetenaate Storage Tantr Level - low d.

SuppreaatonPool Water Level - Ngh e.

Reactor Veaael Water Level - Ngh, Level 5 l.

Manual tntttation 2taltbl

tal 1/ayatem 1,2,$

1. 2, 3 1,2.$

1,2,$

1,2,3 1, 2, 3 31

TABI.E3.3.3-1 {ConthlUed)

EMERGENCY CORE COOUNQ SYSTEN ACTUATIONINSTRUNIENTATION MlilrjalOfiltlCHAIIIRtS tfllflWSySTQI 4.

AUTOMATlCOKPl%$SUAQATSNSYSHM ee a.

lleactor Veeael Wall Level - Low Low Low, Level 1 Orywe0Preeaee-lleh 4.

Core Spray fuey INecharee Ptealae - Sgh tParrnieatve)

~.

SNLPQ Mo4e Peep Oiecharee Preaerne - Hah lPermiealvel I.

Ileaclor Veeael Weler Level - Low, Level 3 lPermieafvef 0.

AOS Orywel Pleelne Sypaea Timor 2'0%ie 1.2. 3

'I. 2. 3

1. 2. 3

l. 2. 3 1,2,3 1.2,3 1, 2, 3 1,2,3 1.2.3 31 33 TOTALIIOo Of CHANNKLS C81NIR0 TO~

IMROJM CHAIOKLS OfQMN AHtCMLS OtNATNNAL CMOITIDRS I

~g 0.

LOSS Of POWN o.

4.10 hi SSS 0LN Lhasa volle0e Sess ol Velta0e, C 2D%l L

4.10 hr ESS 0Lre Un4er volta0e ge0raM VChaee. c 0%%)

o.

4.10 hr NS 0Lre Un4er voiraae geara4e0 Veloce, c 03%i 4

40DV ASS 0ue O0iSi Under.voNa0e I ~va

.~0Salf>>

~

40OV CSS 0oe O0606 Ue$er vorrarre IDelerrei Voiraee. C 02%1 fee

-Ceo foe~ac enact.

~

l. 2,3,4

~ 0 1,2.3.4,5

l. 2. 3, 4, 6 la 2,3.4,5 1.2.3.1,6

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOUNG SYSTEM ACTUATION INSTRuMENTATION ia)

(b)

One trip system.

Provides signal to HPCI pump suction valves only.

Ic)

Two out of two logic.

Teart~

abc 8.5.8 I, hfsfe (Q (d)

Either 4d or 4e must be satisfie.

The ACTION ls required to be taken only lf neither ls satisfie.

A channel ls not OPERABLE unless its associated pump ls OPERABLE per Specificatio 3.6.$.

(e)

Within an AOS Trip System there are two logic subsystems, each of which contains an overall pump permlsslve. At least one channel associated with each of these overall pump parmlsslves shall be OPERABLE.

<<kv

~

4 P

When the system ls reqvlred to be OPERABLE per Specification 3.6.2 Not required to be OPERABLE when reactor steam dome pressure is less than or aqua} to 160 pslg.

Required when ESP equipment ls required to be OPERABLE.

Not required to be OPERABLE when reactor steam dome pressure is less )han or equal to 100 pslg.,

7am s.s.s-4oke g)

Required to be OPERABLE only when Diesel Generator E is e1ther aligned to the Class 1E system or not aligned to the Class 1E system but operating on the Test Facility.

The automatic transfer of HPCI pump suction from the condensate storage tank to suppression pool on high suppression pool water level occurs only when HPCI infection valve ls open.

TABLE3DW1 (Cotttfnuad)

ACTION 3 ACTION 31 CRr ~ad ~

ACTION 32 rAmyl32 ACTION 3

~mr Acr]eJ>3 ION 34

~asU'en~aJ A ACTION 35 - With the number of OPERABLE channels less than the Total Number of Channels.

declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2. as appropriate.

ACTION 36 -

a)

With the number of OPERABLE channels one less than the Total Number of

Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ,"

operation may then continue until performance of the next required CHANNEL FUNCTIONALTEST.

b)

With both channels inoperable on a 4.16Kv ESS bus, declare the associated 4.16Kv ESS bus inoperable. and take the ACTIONrequired by Specification 3.8.3.1 or 3.&.3.2 as appropnate.

c)

With both channels inoperable on the 4&OVESS Bus OB565, declare the 480V ESS Bus OB565 not energized:

(1)

For the Diesel Generator E aligned to the Class 1E system, take the ACTION required by Specification 3.8.3.1 or 3.8.3.2 as appropriate (2)

For the Diesel Generator E not aligned to the Class 1E system, dec)sre the Diesel Generator E 125 Vo)t DC distribution system load group not energized and take the ACTION required by SpecNcation 3.8.3.1 or 3.8.3D as appropriate.

SUSQUEHANNA - UNIT 2 3/4 3-30 Amendment No.+

Insert Action 30:

(Actions A,

B and H (except HPCI) from NUREG

1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or declare the associated ECCS inoperable; and, b.

Within one hour from discovery of loss of initiation capability by this trip function, declare the associated ECCS inoperable.

Insert Action 3C:

(Actions A, C and H from NUREG 1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare the associated ECCS inoperable; and, Within one hour from discovery of loss of initiation capability by this trip function, declare the associated ECCS inoperable.*

( ACTlON 31b is not applicable to Function 3.e, Reactor Vessel Water Level-High, Level 8)

Insert Action 32:

(Actions A, F and H from NUREG 1433, Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

a.

Within one hour from discovery of loss of ADS initiation capability by this trip function, declare the ADS valves inoperable; and, Within 4 days from discovery of an inoperable channel(s) concurrent with HPCI or RCIC inoperable, place the inoperable channel(s) in the tripped condition; and, C.

Within 8 days from discovery of an inoperable channel(s) ifboth HPCI and RCIC are OPERABLE, place the inoperable channel(s) in the tripped condition.

lfACTION b or c is not met, declare ADS inoperable.

Insert Action 33:

(Actions A, G and H from NUREG 1433, Section 3.3,5.1)

With one or more required channel(s) inoperable in one or more Trip Systems:

a.

Within one hour from discovery of loss of ADS initiation capability by this trip function, declare the ADS valves inoperable; and, b.

Within 4 days from the discovery of an inoperable channel(s) concurrent with HPCI or RCIC inoperable, restore the channel(s) to OPERABLE status; and, c.

Within 8 days from the discovery of an inoperable channel(s) if both HPCI and RCIC are OPERABLE, restore the channel(s) to OPERABLE status.

d.

IfACTION b or c is not met, declare ADS inoperable.

Insert Action 34:

(Actions A, D and H fram NUREG 1433 Section 3.3.5.1)

With one or more required channel(s) inoperable in one or more Trip Functions:

at Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or align the HPCI pump suction to the suppression pool; and, Within one hour of discovery of loss of initiation capability declare HPCI inoperable ifthe associated pump suction js not aligned to the suppression pool.

IfACTION a or b is not met, declare HPCI inoperable.

Insert:

Table 3.3.3-1 Note (a):

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains trip capability.

Insert:

Table 3.3.34 Note (f):

When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1ABLE 4.3.3.1-l EHERGEHCY CORE COOLING SYSTEH AC1UhllOH lNSlllNEHlhllOH SUllVEllLAHCE AE UIRENHlS X

IRIP fUNCIIGN

~

l.

CORE SPRAY SYS1EII a.

Reactor Vessel Mater l.evel-los let lee, lave) 1 t'.

Or~ll tressure - High c.

Reactor Vessel Stem Ooae I'ressure - tm d.

Ihnual Initiation CHANNEl.

NECK S

HA CHANNEL FUHC1 lOHAL IESl CtlANNEl ChllBRhl lOH OPE Rhl lOHAI CONGlllONS FOR slllCfl SURVEIllANCE RE lRED

~

l, 2, 3, 1>>, 5>>

ls 2s 3, I>>s 5>>

Cal I

a.

Reactor Vessel Mater level-los lm lan, level l 5

Or@sell tressure - High IN Reactor Vessel Stem Oooe tr~ssure - ler l)

Systea initiation ith 2)

Roc Ircuiat ion Discharge Vaive Closure N'A d.

manual initiation N

IIIGN I'RESSIIRE COOIIN ILIECIIRN SfSIEII b.

C.

2.

lOM PRESSURE CNLNIT INECflOIINOE OF RN SYSTEII's 2s 3s 4>>s 5>>

l, 2, 3, i>>, 5 l, 2, 3, 1>>s 5>>

l, 2, 3, 1>>, 5>>

b.

Co e.

Reactor Vessel Mater level-ler lcm, level 2 Orpull tressure - High Condensate Storage Tonk level-ler Suppression tool Mater leva)-

High Reactor Vessel Mater level-High, level e Ieanual initiation (jy Q@

0 ls 2, 3 l, 2, 3 1, 2, 3

l, 2, 3 l, 2, 3

ls 2, 3

TABLE4.3.3.1-1 ICottflnuedI EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS Cmx zz Cz Taa'UIICTION 4.

AUTOMATlCOEPRESSIJRIZATON SYSTEM a a.

Reactor Vessel Water Level - Low low low, Level 1 b.

Orywei Pressure

~ High c.

AOS Timer d.

Core Spray Pump Discharge Pressure

- High e.

RHR LPCI Mode Pump Discharge Pressure - High f.

Reactor Vessel Water level

~ Low, Level 3 g.

AOS Orywei Pressure Bypass Timer h.

Manual tnhfbft L

Manual initiation 5.

LOSS OF POWER CHAIIIIR FUIICTIONAL TEST a

OPEIIATIOIIAlCOIIOITTOIIS FOll WIOCII NIN%ktANCE TIEQUIaKD I. 2, 3 l,2,3

1. 2, 3

1. 2. 3 1, 2, 3

1. 2. 3 1.2,3

1. 2, 3

1. 2. 3

~.

1.1B kv ESS Bus Undervoltege ILoss of Vdtagel b.

4.10 kv FSS Bus Undervoltage g)egraded Voltage) c.

4.1B kv ESS Bua Undervdtage IOegraded Voltage) d.. 450V ESS Bus 0B555 Undervoltage fDegraded Vdtage c eSSIF" e.

4$ 0V ESS Bua OB585 Undervoltage lDegraded Voltage c $2%>nt 1, 2. 3. 1

. 5

l. 2. 3, 4, 5 I,2,3,4,$

f, 2, 3, 4

, 5 1,2,3,4,5

,O When the system fs required to be OPERABLE, alter being manuamy realigned, as eppncable, per Spedflcatlon 3.5.2.

Requfred OPERABLE when KSF equfpment fs requfred to be OPERABLE.

Not required to be OPERABLE when reactor steam dome pressure fs less than or equal to 150 psig.

Not requfrad to be OPERABl.E when reactor steam dome pressure Is less!han or equal to 100 pslg.

Required to be OPERABLE only when Diesel Generator E ls either eggned to the Class 1 E system or not aligned to the Class TE system but operating on the Test Facility.

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 1 TS 3.3.4.1:

ATWS Recirculation Pump Trip System Instrumentation

. INSTRUMENTATION 3/4.3.4 RECIRCULATIN PN6'QP ACTUATION Igl'TRlNENTATION A~ RECIRCULATION PlNP TRIP SYSTEM INSTRUIKNTATION LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pmap trip (ASS-RPT) system instnaentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint col~ of Table 3.3.4,1-2.

APPLICABILITY:

OPERATIONAL CONDITION l.

ACTION:

a.

Nth an ASS recirculation pmp trip system inst~ntation channel trip setpoint less conservative than the value sham in the Allowable Values col~ of Table 3.3.4.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint ad)usted consistent wiW the Trip SSC/NHnt value Nth the nutbar of OPERABLE channels one less than required by the Nnimum OPERABLE channels per Trip Systee mquiresent for ohe o th trip systeas, place the inoperable channel(s) in the trfppe dition within one hour.

Nth nueber of OPERABLE channels two or sore 1

than tequired '-.

by the N OPERABLE Channels per Trip Sys quireaent for one trip system 1.

If the inope channels consis f one reactor vessel water level channel reactor sel pressure

channel, place both inoperable chan i

tripped condition within one hour.

2.

If the inoperabl nnels inc e two reactor vessel ~ater level channels or reactor vessel pre re channels, declare the trip sys noper able.

Nth one p systee inoperable, restore the in able trip system to OP LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at lees ARTUP within t

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Nth both trip systees inoperable, restore at least one trip tew to OPERABLE status within, one hour or be in at lees STARTUP wi SVRVEILLANCE RE IRENENTS 4.3.4.1.1 Each ATMS recirculation pump instrmtntation channel shall be demonstrated OPERABLE by the perfonaance of the ClNNNEL CHECK, CHNlNEL FVNCT;ONAL TEST and CHANNEL ClLIBRATION operations at the frequencies shown in Table 4.3.4.1-1.

4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated autoaatic operation of all channels sha'.1 be perforaed at least once per XS months.

SUSg VEHANNA UNIT 1 3/4 3 36

Insert Actions 3.3.4.1: (Actions A, B, C and D from NUREG 1433 Section 3.3.4.2) b.

With one or more channels required by Table 3.3.4.1-1 inoperable:

1.

Within 14 days, restore the channel(s) to OPERABLE status; or, 2.

Within 14 days, place the channel(s) in the tripped condition ifthe inoperable channel(s) is not the result of an inoperable breaker.

c.

With one Trip Function in Table 3,3.4.1-1 with ATWS-RPT trip capability not maintained, restore ATWS-RPT trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

. d.

With both Trip Functions in Table 3.3.4.1-1 with AVOWS-RPT trip capability not maintained, restore ATWS-RPT trip capability for one Trip Function within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

e.

IfACTION b, c or d is not met, remove associated recirculation pump from service within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or, be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

TABLE 3.3.4.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEH INSTRUMENTATION C

M TRIP FUNCTION 1.

Reactor Vessel Water Level-Low Low, Level 2 2.

Reactor Vessel Steam Dome Pressure

- High NIRIIIUII OPERABLE CHAlgfLS PER TRIP SYSTEH Ca)

I (a)

One channel or trip system may be placed in an inoperable status for up t hours for required surveillance provided the other trip system is OPERABLE.

Upon determination that a trip setpoint cannot be restored to within its specified value during performance of the CHANNEL CALIBRATION, the appropriate ACTION shall be followed.

5 RCULA lO lNP Rl ACTUATlON NSTRtNENTATION SURVElllAHCE RE IREHENTS N

~III UCI l.

Reactor Vissel &ter 1evel-lme 1', level 2 2.

Reactor Vessel Steaa Ooae Pressure - IIlgh CHAHHEl CIIECK NA CINHHEL' UHCTIOHAI.

TEST CINHHEl CALISRATION

0 0

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.4.1:

ATWS Recirculation Pump Trip System Instrumentation

U 0

3/4.3.4 R '~J&s ON

>QHP ft

. ~ R~

N.NStff"tfPff'W>TION ASS RECIRCJLPe ION PVNP TR P BY~c.. IHST%1NBfiA iON t 9IIT.M ClNDIa.ON FOR OPHA..ON 3.3.4.1 The antfcfpated transfent without scram recfr~latfon pump trip (AT"5-RPT) system fnstr~ntatfon Cunnels shown fn Taole 3.3.-'. 1-'nal':e OPERABLE wi 1 uefr rfp setpoints set consistent <<f"o values snown !n -we Trip Setpofnt column of Table 3.3.4.1 2.

APP~ ICABILm:

OPgmTIONAL CONOITION l.

ACTION:

a.

Mftn an Aivs encfecuiatfcn pucp tefp systan instsuaentatfcn cnannei trip setpofnt less conse.vatfve than the vilue show in the Allowable Value's column of Table 3.3.4.1-2, declare the channel inoperable un

',1 the channel fs restored to OPERABLE status with fts trip setpoin ad)usted consistent wfth the Trfp Setpofnt value.

b.

Nth the number of OPERABLE channels one less than requfred by the Nnfmum OPERABLE channels per Trfp System acquirement for one or b trip systems, place the fnoperable channel(s) in the tripped ndftfon within one hour.

c.

fifth number of OPERABLE channels two or mre les an requfred by the OPERABLE Channels per Trip System ufrement for one trfp system

~

L If the fnope ctunnels consist one reactor vessel

~ater level channel and e reactor sel pressure channel; place both inoperable charm f

e tripped condition wfthfn one hour.

2.

If'he fnoperabl annels inc two reactor vessel wa e.

level Channels or reactor vessel pres

channels, declare the trip sys inoperab1 e.

Nth one ap system fnoperable, restore the fnop le trfp system to OP LE status wfthfn 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in it least RTVP within nex 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Wth both trip systems fnoperable, restore at least one trip s em to OPEQBLE status within one hour or be in at least STARTVP with the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MCE REOUIRPI 4.3.4.L-L Each ASS recirculation pump fnstrumentatfon channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FVNCTIONAL TEST and CHANNEL CALIBPATION operations at th>> frequencies shown in Table 4.3.4.L-L 3 4 L 2 LOQIC Q'STEH FVNCTIQNAL TESTS and simulated automatf c operatf on o all channels. shall be performed at least once per ZS months.

SUSQUEKJQOfA UNIi 2 3/4 3 36

Insert Actions 3.3.4.1: (Actions A, B; C and D from NUREG 1433 Section 3.3A.2) b.

With one or more channels required by Table 3.3.4.1-1 inoperable:

1.

Within 14 days, restore the channel(s) to OPERABLE status; or, 2.

Within 14 days, place the channel(s) in the tripped condition ifthe inoperable channel(s) is not the result of an inoperable breaker.

With one Trip Function in Table 3.3.4.1-1 with ATWS-RPT trip capability not maintained, restore ATWS-RPT trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

e.

With both Trip Functions in Table 3.3.4.1-1 with ATWS-RPT trip capability not maintained, restore ATWS-RPT trip capability for one Trip Function within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

IfACTION b, c or d is not met, remove associated recirculation pump from service within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or, be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

TRIP FUNCTION TABLE 3.3.4.1-1 ATMS RECIRCULATION PUMP TRIP SYSTBI INSTRUMENTATION HIHIHUH OPERABLE CHAg)LS PER TRIP SYSTEH 1.

Reactor Vessel Mater Level-Low Low, Level 2 2.

Reactor Vessel Steam Dome Pressure - High CAB I

EAR (a)

One channel or trip system may be placed in an inoperable status for up t hours for required surveillance provided the other trip system is OPERABLE.

Upon determinatio that a trip setpoint cannot be restored to within its specified value during performance of the CHANNEL CALIBRATION, the appropriate ACTION shall be followed.

0

AlMS RECIRCULATION PlNP TRIP ACTUATION INSTRNtENTATION SURVEILlAHCE RE IRENENTS TRIP FUNCTION Reactor Vestal lhter level-low le, level 2 Reactor Vessel Steaa Ooe Pressure - High CNXHEL CHECK K

5 CfNNHEL FUNCTIONAL TEST CNNNEL CAI.IBRATION

Extending STls and AOTS for Susquehanna Technical SpecNcation Instrumentation Unit 1 TS 3.3.4.2:

Endwf-Cycle Recirculation Pump Trip System Initiation

0

INSTRUMENTATION EHO-QF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONOmON FOR OPERATION msew4

+r(ox)S 3.5.4;2 3.3.4.2 The end of-cycle reef rculatfon pump trip (EOC-RPT) systea fnstnanenta-tfan channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip set-points set cansfstent with the values shown fn the Trfp Setpofnt coluae of Table 3.3.4.2-2 and with the EHHF CYCLE RECIRCULATION PUMP TRIP SYSTEM

RESPONSE

TIME as shown -fn Table 3.3.4;2-3.

APPLICABILITY:

OPERATIONAI CONOITION 1, when THERMAL POWER fs greater than or t ttim tktttI tnttt.

ACTION:

a.

With an end-of-cycle recfrculation puap trfp systea fnst~ntatfon channel trip setpofnt less conservative than the value shown in the Allowable Values coluan of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status wfth the channel setpof nt ~usted consf stent wfth the Trfp Setpofnt value.

h.

With the nuaber of OPERABLE channels one less than required by the Mfnfma OPERABLE Channels per Trip Systea requfrenent for one or th trfp systaas, place the fnoperable churl(s) fn the tH tfon wfthin.one hour.

c.

With uaber of OPERABLE channels Ceo or aore less an required by the Mfn OPERABLE Clunnels per Trip Systea freaent for one trip systaa 1.

If the fnope channels consist o

ne turbine control valve channel ind one fne stop valv annel, place both inoperable channels fn the tripp condft within one hour.

2.

If the fnoperabl ~ channe lude two turbfne control valve channels or two turbf stop ve channels, declare the trip systaa fnoperable.

d.

Wftb one trip sys fnoperable, restore noperable trfp systea to OPERABLE s wfthin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or evaluate PR to be equal to or greater an the applfcable MCPR lfaft without C-RPT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months o ke the ACTION required by Speci ffcation..3.

e.

Wf beth trip systeas fnoperable, restore at least one tr systan OPERABLE status wfthfn 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or evaluate MCPR to be equal or greater than tne applicable MCPR lfaft without EOC-RPT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or take the ACTION requfred by Specfffcation 3.2.3.

SUS)UEHANNA - UNIT 1 3/4 3-40 lt Aaendaent No.

78

Insert: Actions 3.3.4.2:

(Actions A, B, C and D fram NUREG 1433 Section 3.3.4.1) b.

With one or more channels required by Table 3.3.4.1-2 inoperable:

1.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , restore the channel(s) to OPERABLE status; or, 2.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , place the channel(s) in the tripped condition Ifthe inoperable channel(s) is not the result of an inoperable breaker.

With one or more Trip Functions in Table 3.3.4.1-2 with EOC-RPT trip capability not maintained; and, with MCPR less than the limitspecified in the COLR for inoperable EOC-RPT:

1.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , restore EOC-RPT trip capability; or, 2.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , apply the MCPR limitfor inoperable EOC-RPT as specified in the COLR and take the ACTION required by Specification 3.2.3.

e.

IfACTION b or c is not met:

V 1.

Remove associated recirculation pump from service within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, 2.

Reduce THERMALPOWER to less than 25% of RATED THERMALPOWER.

NLK 3.3.i.t-l BD-GF-CYCLE RECIRCULATIN PINP TRIP SYSTOI IHSTRlNENhTION TRIP RNCTIN I.

Turbine Stop Valve - Closure 2.

Turbine Control Valve-Fast Closure HIHINN OPERABLE CIINllEQ)

PER TRIP SYSTEH 2(b) 2(b) lHFBIPPV Vb p1 dl I~ dl il 1 et h

f 0 I d

provided that the other trip systeN is OPERhlLE.

(b)This function shall be autoaatically bypassed:shen turbine first stage pressure is.less than l08 psig or 17K of the value of first stage pressure in psia at valves side open (V.N.O) steaa fler.

This value is equivalent to TltERNl POMER of about 24K of RATEO NERNl. POMER.

TNLE 4.3.I.2.)-l EHO-OF-CYCLE RECIRCULATION PlNP TRIP SYSTEH SURVEILLANCE RE IRNEHTS TRIP FlNCTIN Turbine Stop Valve-Closure 2.

Turbine Contml Valve-Fast Closure

~ CHANNEL FUHCTIONLL TEST CNINKL CALIBRATI

Extending STls and AOTS for Susquehanna Technical SpeciTication Instrumentation Unit 2 TS 3.3.4.2:

Endwfycle Recirculation Pump Trip System Initiation

INSTRUHENTATIOK END-OF CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIHITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system fnstrumenta-tfon channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown fn the Trip Setpofnt column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRC!llATION PUMP TRIP SYSTEH

RESPONSE

TIME as shown in Table 3.3.4.2-3.

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL PSfER fs greater than or I

T. EETEE TEEEEIL TEEEII.

ACTION:

a.

Nth an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown fn the Allowable Values column of Table 3.3.4.2-2, declare the channel inoperable until the channel fs restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

ACrtcx40 S.w 4.a c.

Mith the er of OPERABLE channels two or more less by the Mini OPERABLE Channels per Trip System re trip system an.

required nt for one 1.

If the fnoperab hannels consist of e turbine control valve channel and one tu e stop valve annel, place both inoperable channels fn the trippe ondftio thorn one hour.

2.

If the inoperable channel ude two turbine control valve channels or two turbfn top va

channels, declare the trip system inoperable.

b.

fifth the number of OPERABLE channels one less than requfred by the Hinimum OPERABLE Channels per Trip System requirement for one or oth trip systems, place the inoperable channel(s) fn the trippe co ftion within one hour.

d.

Nth one trip sys inoperable, restore the erable trfp system to OPERABLE sta s within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or evaluate HC to be equal to or greater the applfcable HCPR-lfmit without EO PT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or ke the ACTION requf~ by Specfffcatfon 3.2.

N ath trip systems inoperable, restore at least one trip s tern OPERABLE status wfthin I hour or evaluate HCPR to be equal to greater than the applicable MCPR limit without EOC-RPT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or take the ACTION required by Specification 3.2.3.

SUS)UEHANNA - UNIT 2 3/4 3-40 Amendment No.

43

Insert: Actions 3.3.4.2:

(Actions A, 8, C and D from NUREG 1433 Section 3.3.4.1) b.

C.

With one or more channels required by Table 3.3.4.1-2 inoperable:

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , restore the channel(s) to OPERABLE status; or, 2.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , place the channel(s) in the tripped condition ifthe inoperable channel(s) is not the result of an inoperable breaker.

With one or more Trip Functions in Table 3.3.4.1-2 with EOC-RPT trip capability not maintained; and, with MCPR less than the limitspecified in the COLR for inoperable EOC-RPT'.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , restore EOC-RPT trip capability; or, 2.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , apply the MCPR limitfor inoperable EOC-RPT as specified in the COLR and take the ACTION required by Specification 3.2.3.

e.

IfACTION b or c is not met:

Remove associated recirculation pump from service within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, 2.

Reduce THERMALPOWER to less than 25% of RATED THERMALPOWER.

TAILE34'-1 ENlhO~CLE RECfRCULATlONPUiN'RP SYSTEM tNSTRUNBITATlON

1. Turbine Stop Vehre - Ciosure 2.

Turbine Comroi Valve - Fast Cioaure

{a)

A trip system may be pieced in en inoperabie statue for up for required aurveiNance provided that the other trip system ie

{b)

This function shaN not be automaticaNy bypassed when turbine first stage pressure ia greater than an aNowabie veiue of t38 paig.

SuSauEHaffua

- UWT 2 3/4 3%2 Amendment No. 103

TAQlE I.3.I.2. T" 1 EHD-OF-CVClE REClRCULATlON PINP TRlP SVSTEH SURVEllMHCK RE IREBENTS

'RIP INIIIIIR T.

Turbine Stop Va)ve-Closure 2.

Turbine Control Valve-Fast C)osure CINHHEL fUHCTTONl TEST CINWKl

~IIII Rll Sl

Extending STls and AOTS for Susquehanna. Technical Specification Instrumentation Unit 1 TS 3.3.5:

Reactor Core Isolation Cooling System Actuation Instrumentation

EAR I

EUNCT IONAL UNITS a.

Reactor Vessel Mater Level - Low Low, level 2 TABLE 3.3.5-I HIHINN OPERABLE CIIAHHEl.f i PER IRIP SESIEH 2

2(b) 2(c)

I/systeJ")

b.

Reactor Vessel Mater Level - High, Level 8 c.

Condensate Storage Tank Mater Level -. Low d.

Hanual Initiation REACTOR CORE ISOLATION COOLIHG SVSTEH ACTUATION IHSTRUHEHIATION ACEIOH 50 52 a

Ia

'(b)

(c)

(d) c anne aay be placed in an inoperable status, for up t ours for required surveillance without placing the trip systea in the tripped condition provide at least one other OPERABLE channel in the saic trip systea is aonitoring that parameter.

One trip systea with two-out-of-two logic.

One trip systea with one-out-of-two logic.

One trip systea with one channel.

TABLE 3.3. 5-l (Continued)

~

REACTOR CORE ISOLATION COOLING SYSTEM ACTION STATEHEHTS ACTION 50 -

fifth the number of OPERABLE channels less th n re uired by the Ilk'PBMBLe Ch 1 y, T,<p Sy J-~~ AClloQ Sa AKRON 51 -

14ith the number of OPERABLE channels less than re uired by the minimum OPERABLE channels per Trip System

~iJscg l4TtclA) Sl ACTION 52 -

With the number of OPERABLE channels less than re uired b

the Nni RABLE Channels er Trip System

~Nff Acr(ypJ 5Q ACTION 53-Zrdmg Acrsev 69 Nth the number of OPERABLE channels one less than re ired by the Nnimum OPERABLE Channels per Trip System

~'

SUSQUEHANNA - UNIT 1 3/4 3-48 Amendment Ho. 29

4f tq

Insert Action 50:

(Actions B and E fram NUREG 1433 Section 3.3.5.2) requirement in one or more Trip Systems:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or declare RCIC inoperable; and, b.

Within one hour frnm discovery of loss of RCIC Initiation capability, declare RCIC inoperable.

Insert Action 61:

(Actions C and E from NUREG 1433 Section 3.3.5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare RCIC inoperable.

Insert Action 62:

(Actions D and E from NUREG 1433 Section 3.3.5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or align the RCIC pump suction to the suppression pool; and, b.

Within one hour of discovery of loss of initiation capability, declare RCIC inoperable unless RCIC pump suction is aligned to the suppression pool; c.

IfACTION a or b is not met, declare RCIC inoperable.

Insert Action 63:

(Actions C and E from NUREG 1433 Section 3.3.5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare RCIC inoperable.

TABLE h.3.5. l"l REACTOR CORE ISOlATION COOLIHG SYSTEII ACTUATIOH IHSTRINEHTATIOH SURVEILLAHCE RE IREHEHTS Q fUHCl'IONL UHITS a

Reactor Vessel lhter level-ly Los, level 2 b.

Reactor Vessel Water level - IIIgh, level 8 c.

Condensate Storage Tank Mater Level - Low d.

lIanual In)ttatkon CINNIIEL GIKKK CIIAHHEL FUNCTlONI.

TEST CHNHEL CALIBRATION R

R

Extending STls and AOTS for Susquehanna Technical SpecNcation Instrumentation Unit 2 TS 3.3.5:

Reactor Core Isolation Cooling System Actuation Instrumentation

ThBlh 3.3.5" REhCTOR NRE ISOlhTIOH NOLIHQ SYSTEH hCTNTIOH IHSTRNEHThTIO FNCTIONL UHITS e.

Reactor Vessel Mater level - l.ov t.er, level 2 b.

Reactor Vessel Mater l.evel -. High, level 8 c.

Condensate Storage Tank Mater level - le d.

Hanual Initiation MIHINN GPEINBN CINNEL) )

PER TRIP SYSTEH 2

2(b) 2(c)

I/systea(")

ACll0$

53 i

pi*

i i

ii

\\

e placing the trip systea in the tripped condition provide saae trip systea is aonitoring that paraaeter.

(b)

One tr ip systea with too-out-of-t~o logic.

(c)

One trip systea arith one-out-of-too logic.

(d)

One trip systea with one channel.

hours for required surveillance without least one other OPENBlf channel In the

TABLE 3.3. 5-1 Contf nued REACTOR CORE ISOLATION CMLING SYSTEM ACTION STATENEW%

ACTION 50

'fifth the number of OPERABLE channels less than re ufred by the Nnimun OPERABLE Channels per Trip System N 51 -

Nth the number of OPERABLE channels less than uired by the X~~Ac%~ Gl e

OFERABLE Channels per Trip System ACTION 52 -

Nth the number of OPERABLE channels lass than uirea b the Nnfeum OPERABLE Channels per Trip System Z'n~ AWo~ aa ACTION 53 -

fifth the number of OPERABLE channels less than f

d'b the Nnfmnn OPERABLE Channels per Trf S s W~se+ Ad es SUS/UEHANNA - UNIT 2 3/4 3 48

Insert Action 50:

(Actions B and E from NUREG 1433 Section 3.3.5.2) requirement in one or more Trip Systems:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or declare RCIC inoperable; and, b.

Within one hour from discovery of loss of RCIC initiation capability, declare RCIC inoperable.

Insert Action 51:

(Actions C and E from NUREG 1433 Section 3.3.5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare RCIC inoperable.

Insert Action 62:

(Actions D and E from NUREG 1433 Section 3.3.5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place the inoperable channel(s) in the tripped condition or align the RCIC pump suction to the suppression pool; and, b.

Within one hour of discovery of loss of initiation capability, declare RCIC inoperable unless RCIC pump suction is aligned to the suppression pool; c.

IfACTION a or b is not met, declare RCIC inoperable.

Insert Action 63:

(Actions C and E from NUREG 1433 Section 3.3,5.2) requirement:

a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , restore the channel(s) to OPERABLE status or declare RCIC inoperable.

i' 1t l.t ll l t'

~

'Etll I

I 0

TABlE 4.3.5. l-l REACTOR NRE ISOlATlON NOllHG SYSTEH hCTNTlON lHSTRlNKNATION SURVEILLAHCE RE kf%HTS FlNCTTOHAL UHTTS e.

Reactor Vessel Mater level-ler lee, Level 2 b.

Reactor Vessel Mater leva) - High, level 8 c.

Condensate Storage Tank Mater Lave) - Los d.

Hanual lnitlatfon ClNHNEL CNNBEL FWCTIOHAL ClfNHEL Rill t

~URH R

Extending STls and AOTS for Susquehanna Technical SpecNcation Instrumentation Unit 1 TS 3.3.6:

Control Rod Block Instrumentation

INSTRUMENTATION-3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATIOX LIMITING CONDITION FOR OPERATION 3.3.6.

The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the A11owable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status ~h its trip setpoint adjusted consistent with the Trip Setpoint value~

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION re-quired by Table 3.3.6-1.

The provisions of Specification 3.D.4 are not applicable for entry into Operational Condition 2 or 3 from Opera-tional Condition 1 for the

IRMs, SRMs and the Neutron Flux - Upscale, Startup function of the APRMs.

SURVEILLANCE RE UIREMENTS 4.3.6 Each of the above required control rod ock trip systems and instrumen-tation channels shall be demonstrated OPERABLE y the performance of the CHANNEL

CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERA-TIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.

The provisions of oe ification 4.0.4 are not applicable for ntrv into Goerational Conaition 2 ol 3 =rom Ooerational Conoition I for the IR.'!s, SR:)s and the.'reutron Flux - upscale.

Startup function of the APRMs.

AE g r~n~) n,g~ Qp/n~<g w an inopnragla nQ~ Inr >p 6s

~ ~r+

'Fog'c$~r~

caweil(Nagms o

c Leut p~<~~ ~ +"p Ws~

p gv g g gf fggg o g g~

CKfNS<F

'+""5~ ~ ~"

C I IC 1t ICBM'gQ 3/4 3-51 Amendment No. A"6

0

(Continued) hGXtQR ACTION 60 -

Declare the RBM inoperable and take the ACTION required by Specification 3.1.4.3.

ACTION 61 -

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 62 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Functio uirement, place the inoperable channel in the tripped condition withi (z hours With THERMALPOWER 2 30% of RATED THERMALPOWER.

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

Not required when eight or fewer fuel assemblies (adjacent to the SRMs) are in the core.

a.

The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMALPOWER.

b.

This function shall be automatically bypassed if detector count rate is 2 100 cps or the IRM channels are on range 3 or higher.

c.

This function is automatically bypassed when the associated IRM channels are on range 8 or higher.

d.

This function is automatically bypassed when the IRM channels are on range 3 or higher.

e.

This function is automatically bypassed when the IAMchannels are on range l.

f.

This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.

SUSQUEHANNA-UNIT 1 3/4 3-53 Amendment No.<>> >40

TABLE4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCEREQUIREMENTS PC RR I

CZ Col CP Ql Ql TRIP FUNCTION ROD BLOCK MONITOR a,

Upscale b.

Inoperative c.

Downscale 2.

APRM a.

Row Biased Neutron Flux-Upscale b.

Inoperative c.

Downscale d.

Neutron Flux - Upscale, Startup 3.

SOURCE RANGE MONITORS a.

Detector not full in b.

Upscale c.

Inoperative d.

Downscale 4.

INTERMEDIATERANGE MONITORS a.

Detector not full in b.

Upscale c.

Inoperative d.

Downscale 5.

SCRAM DISCHARGE VOLUME a.

Water Level-High B.

REACTOR COOLANTSYSTEM RECIRCULATIONFLOW a.

Upscale b.

Inoperative c.

Comparator CHANNELCHECK NA NA NA 8

NA S

S NA NA NA NA NA S

NA S

NA NA NA NA CHANNEL FUNCTIONALTEST Ib) s/UIb),w s/ulb),w 8/ulb),w 8/ulb),w 8/u~),w 8/utb),W 8/utb),W s/u'b',w

"~a~

CHANNEL CALIBRATION Q

NA Q

SA NA SA SA NA Q

NA Q

Q NA Q

OPERATIONALCONDITIONS FOR WHICH SURVEILlANCE REQUIRED 1~

1~

1 1,2,6I ~ ~

1 2 60 ~ ~

2,6 2,6 2,6 2,6 2,6 2,6 2,6 2,6 1 2,6I~

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.6:

Control Rod Block Instrumentation

INSTRUMENTATION 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.

The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

With a control rod block instrumentation channel trip setpoint less conservative than the value shoWn in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.

The provisions of Specification 3.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition I for the IRMs, SRMs, and the Neutron Flux - Upscale, Startup function of the APRMs.

SURVEILLANCE RE UIREMENTS 4.3.6 Each of the above required control rod block tri systems and instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEI

CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.

The provisions of Specification 4.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1 for the IRMs,

SRMs, and the Neutron Flux - Upscale, Startup function of the APRNs.

A s4assg ense Lc pl~ccL Is sh snopsrcklg 4o C 4'~ fog- <cgocrrh Suave tl4wces > +444 plhc,4g 6s tr p sys4lh I~ 'Hlc 4v'ppcL cschLWIcrI pracic4$ gf leos) ohe c44er 6PXRASQ a,Ronne,)

lw ~.za.~ +)p hays~

Is INssu4aclg ~4cch pQrswc~.

~In 3-51 AMENDMENT NO.. 3

0

(Continued)

ACTION 60 -

Declare the RBM Inoperable and take the ACTION required by Specification 3.1.4.3.

ACTION 61 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 62 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function uirement, place the inoperable channel in the tripped condition withi ~cur I? ham With THERMALPOWER 2 30% of RATED THERMALPOWER.

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

Not required when eight or fewer fuel, assemblies (adjacent to the SRMs) are in the core.

(a)

The RBIVI shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMALPOWER.

(b)

This function shall be automatically bypassed if detector count rate is 2 100 cps or

, the IRM channels are on range 3 or higher.

(c)

This function is automatically bypassed when the associated IRIVI channels are on range 8 or higher.

(d)

This function is automatically bypassed when the IRM channels are on range 3 or higher.

(e)

This function is automatically bypassed when the IRM channels are on range 1.

(f)

This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Spedfication 3.10.3.

SUSQUEHANNA-UNIT2 Amendment No.Q, 110

roC PCmx zR I

TRIP FUNCTION ROD BLOCK MONITOR a.

Upscale b.

Inoperative c.

Downscale TABLE4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCEREQUIREMENTS CHANNEL FUNCTIONALTEST CHANNEL CAUBRATION'"

CHANNELCHECK NA NA NA SA NA SA b

OPERATIONALCONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1~

1 ~

1'al 4

Cal Ql QI 2.

APRM a.

Flow Biased Neutron Flux-Upscale b.

Inoperative c,

Downscale d.

Neutron Flux - Upscale, Startu 3.

SOURCE RANGE MONITORS a.

Detector not full ln b.

Upscale c.

Inoperative d.

Downscale 4.

INTERMEDIATERANGE MONITORS a.

Detector not full ln b.

Upscale c.

Inoperative d.

Downscale S.

SCRAM DWCHARGE VOLUME a.

Water Leva)-High 8.

REACTOR COOLANTSYSTEM RECIRCULAT)ONFLOW e.

Upscale b.

Inoperative c.

Comp arator S

NA S

S NA NA NA NA NA S

NA S

NA NA NA NA (b) b)

s/UIb),w s/ulb),w s/uib),w s/uib),w s/UIb),w S/utb),w s/utbi,w S/uib),W SA NA SA SA NA SA NA

.SA NA SA NA SA Q

NA Q

1 2 60 ~ ~

1 2 60 ~ 0 2,6 2,6 2,6 2,6 2,6 2,6 2,6 2,6 1,2,6~ ~

Extending STIs and AOTS for Susquehanna Technical Specification Instrumentation Unit 1 TS 3.3.7.1:

Radiation Monitoring Instrumentation

RADIATlONNNITORlNG lNSTRtNKNTATlON INSTRSKNTATlON I

1.

Nein Cental Rooe Outside Air intake Radlat)on Nonktor 2.

Area Nonltora a.

Critfcallty Non)tora NNlNN CHNSKlS APtllCAIlK ANN/TRlF OPERAS'ONDITIONS SETPOlNT Cc,')

2/Inta'k 1,2,3,5 and *

< 5 aR/hr

%AQNE%NT Olla O.Ol to lOO aR/hr 1)

Net Fuel Storage Vault 2)

Spent Fuel Storage Fool (a)

(b) c 15 aR/hr c 15 aR/hr 10 to 10 aR/ht 10 to 10 aR/hr

>>4f II >>l>>>>>>>>de

~>>

II (a) Nith fuel la the net fuel storage vault.

(b) Mlth fuel ln the spent fuel storage pool.

>~a.t: Wake(g4rl W~ s.s.p.i-)

INSERT: Note (c) forTable 3.3.784 (c)

When a channel ls placed In an inoperable status solely for performance of required Surveillances, ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided control room emergency filtration system initiation capability is maintained.

ThSLE 4.3.7. l-l RADlhTIOH NNITORIHG IHSTRNEHThTION SURVEILLANCE RE UIREHEHTS CslI KKK

~

IHSTRlNEHThTIOH 1.

Hain Control Room Outside hir Intake Radiation Honitor 2.

brea Honitors a.

Criticality Monitors Hew fuel Storage Vault CINNHEL CIIECK CllAHNEL fUNCTIONAL TEST CHANNEL CAI.IS IIA110II Q.

OPERhT IOHAL COHOI LIONS FOR Ml)CH SURVE1LI AHCE RE UIREO 1, 2, 3, 5 and ~

(a) 2)

Spent Fuel Storage Pool S

R (b) a ue n

he neo fuel storage vault.

(b)

Mith fuel in the spent fuel storage pool.

. Qhen irradiated fuel is being handled in the secondary containment.

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.7.1:

Radiation Monitoring Instrumentation

l/l C

AD C

I TABLE 3.3.7.1-1 RADIATION HONITORING INSTRINENTATION INSTRUNENTATION 1.

Hain Control Room Outside Air Intake Radiation Honitor 2.

Area Honitors a.

Criticality Honitors HININN CHANNELS APPLICABLE ALARH/TRIP OPERABLE CONDIT IONS 5ETPOINT (c) 2/intak 1,2,3,5 and *

< 5 wR/hr HEASUREHENT RANGE 0.01 to 100 aR/hr ACTI (c')

70 1)

New Fuel Storage Vault 2)

Spent Fuel Storage Pool (a)

(b)

< 15 aR/hr

< 15 WR/hr 10 to 10 wR/hr 10 to 10 wR/hr 71 71

Mhen irradiated fuel is being handled in the secondary containment.

(a) Mith fuel in the 'neo fuel storage vault.

(b) ifith fuel in the spent fuel storage pool.

nil&:gofa Cc7 4r ~~"~e 3.'5.'7. I-)

C

INSERT: Note (c) for Table 3.3.784 (c)

When a channel is placed in an inoperable status solely for performance of required Surveillances, ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided control room emergency filtration system initiation capability is maintained.

AQIATION NlIITOR IN IIISTRNENIAIIGH SljRVEIllANCE RE IREHENS ItltR~Itttt II 1.

Hain Control Room Outside Alr Intake Radiation Honitor 2.

Area Honitors a.

Criticality Honitors CINNHEl CllECK CININEl SIWCTIONI.

'ESI CIMNIIEl CALIBRA IO OPKRAlIONLl CONI LIONS fOR NIICII SNVEIllNICK IIIEI 1, 2, 3, 5 and a 2)

Hat Fuel Storage Vault Spent Fuel Storage Pool (a)

'(b) a ue n

he new fuel storage vault.

(b)

Mlth fuel in the spent fuel storage pool.

@hen irradiated fuel is being handled in the secondary containment.

V Extending STIs and AOTS for Susquehanna Technical Specification Instrumentation Unit 1 TS 3.3.9:

Feedwater/Main Turbine Trip System Actuation Instrumentation

INSTRUMENTATION 3/4.3. 9 FEEDMATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONOmON FOR OPERATION 3.3.9 The feedwater/aafn turbine trip. system actuation fnstrumentatfon channels shown fn Table 3.3.9-1 shall be OPERABLE with their trip setpofnts set consistent with the values shown fn the Trip Setpofnt column of Table 3.3. 9-2.

APPLICABILITY:

As shown fn Table 3.3.9-1.

ACTION:

aO b.

Co Nth a feedwater/main turbine trfp system actuation fnstrumentatfon channel trip setpofnt less conservative than the value shown fn the Allowable Values column of Table 3.3.9-2, declare the channel inoperable and either place the fnoperable channel fn the tripped condition until the channel fs restored to OPEABLE status wfth fts trip setpofnt adjusted consistent with the Trip Setpoint value, 'or declare the associated system inoperable.

fifth the number of OPERAB annels one less than required by the Mfnfmum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Nth the number of OPERAB~hannels two less than required by the Mfnimum OPERABLE Channels per Trip System requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be fn at least STARTUP within the next 6 ho'urs.

SURVEILLANCE RE UIREMENTS 4.3.9.1 Each feedwater/main turbine trip system actuation fnstrumentatfon channel shall be demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONOITIONS and at the freqwncfes shown fn Table 4.3.9.1-1.

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels. shall be performed at least once per 1S months.

SUSQUEHANNA - UNIT 1 3/4 3-95

INSERT:

3.3.9 When a channel is placed in an inoperable status solely for performance of required Surveillances, ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater/main turbine trip capability is maintained.

TABLE 4.3.9.1-1 FEEOMATER/HAIN TURBINE TRIP SYSTBI ACTUATION INSTRUHENTATION SURVEILLANCE RE UIREHENTS FUHCTIOHAL UHIT a.

Reactor Vessel Water Level-}ligh CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION.

OPERATIONAL CONDITIONS FOR WHICH SURVEILMNCE RE UIREO

Extending STls and AOTS for Susquehanna Technical Specification Instrumentation Unit 2 TS 3.3.9:

FeedwaterlMain Turbine Trip System Actuation Instrumentation

INFi%0ÃEHTATiON 3/<.3. 9 FEHSATER/MAIN TURBINE TRIP SYSTBl ACTUATION INSTRlNEHTATTON LmITIN6 CONOmON FOR OPERATIO~

3.3.9 The feedwatar/aafn turbine tHp system actuatfon fnstrumentatfon channels shown fn Table 3.3.9 1 shall be OPERABLE wfth their tHp secgofnts set consistent with the values shown fn the THp Setpoint column of Tao)e 3.3. 9-2.

APPLICABILITY:

As shown fn Table 3.3.9 L acnaM:

ae b.

C.

FJ fifth a feedwatar/main turbine rip system actuation fnstrumentation channel trip setpofnt less conservative than the value shown fn the Allowable Values column of Table 3.3.9 2, declare the channel in-operable and efther place the inoperable channel fn the tripped condftfon until the channel is reitored to OPERABLE status wfth fts tHp setpoint ad)usted consistent wfth the Trip Setpcfnt value, c.

declare the associated sys fnoperable.

4f

'fifth the number of OPERAS ls one less than required" by the Nnfaua OPERABLE Channels requfreaent, restore the fnoperable channel to OPERABLE status within 7 days or be fn at leas STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Nth the. number of OPERAB annals two less than requfred by the Nnfmum OPERABLE Channels per Trfp System requirement, restore at least one of the inoperable channels to OPERABLE status wf hfn 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be fn at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREHENTS 4.3.9.1 Each feedwater/main turbine tHp system actuation fnstrumentatfon channel shall be demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operatf ons for the OPERATIONAL CONOITIONS and at the frequencies shown fn Tabl ~ 4.3.9.1-1.

4-3.9.2 LAIC SYSTEM FUNCTIONAL TESTS and sfmulatad autoaatfc operatfon of all channels shall. be performed at least once per Xs aonths.

SUS)UEHANNA UNIT 2 3/4 3 96

EEOMAHRIHAIH NSINE lRIP SVSIEH AC uhlIOH IHSIRlaKH AlIOH Suay ILt E

E IRE%N S.

NC IONAL N Neactos Vessel Mates level-High CINHHEL ClNHHEL fOHCYIOHhl OthNHEL

~CA BQAllOg OPENhllOHAL CNNlllOHS fOW QIIOI S

VE CE R

R 8

INSERT:

3.3.9 When a channel is placed in an inoperable status solely for performance of required Surveillances, AG'nONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater/main turbine trip capability is maintained.

Extending STls and AOTS for Susquehanna Technical SpecNcation Instrumentation Unit,1 BASES

Thh Bh 5

df N t 5~

d Igg consequences of accidents by prescribing the OPERAB1L)TYtrip setpoints and response times isolation of the reactor systems.

When necessary, one channel may be inoperable for brief intervals to conduct required surveHlance.

Some ofthe tripsettings may have tolerances expHcitly stated where both the high and lowvalues are critical and may have a substantial effect on safety.

Yt NI E

h ~",~

ltd high h

I 0

hg bearing on safety, are estabHshed at a level away from the normal operating range to prevent inadvertent actuation of the systems involved.

Leak detection temperature setpoints are selected to prevent a high energy Bne break by detecting and isolating leakage below the flow rate corresponding to critical crack size for the respective system piping. The setpoints are also set below fire suppression setpoints (HPCl and RCIC) and high enough to avoid inadvertent isolation caused by normal temperature transients or abnormal transients caused by non-leak conditions {such as loss of ventHation).

Except forthe MSIVs, the safety analysis does not address individual sensor response times or the response times of the logic systems to which the sensors are connected.

For D.C. operated valves, a 3 second delay is assumed before the valve starts to move.

For A.C. operated valves, it is assumed that the A.C. power supply is lost and is restored by startup ofthe emergertcy diesel generators.

ln this event, a time of 13 seconds is assumed before the valve starts to move.

ln addition to the pipe break, the faHure of the D.C. operated valve is assumed; thus the signal delay sensor response is concurrent with the 10 second diesel startup.

The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunction with the 10 second delay. lt foHows that checking the valve speeds and the 10 second time for emergency power estabHshment wiH establish the response time for the isolation functions.

However, to enhance overall system reliabHity and to monitor instrument channel response time h5 h~

8 hCh a part of the ISOLATION SYSTEM RESPONSE TlME.

Operation with a trip set less conservative than its Trip Setpoint but withinits specified AHowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value, is equal to or less than the drift allowance assumed for each trip in the safety analyses.

The emergency core cooHng system actuation instrumentation is provided to initiate actions to mitigate the consequences ofaccidents that are beyond the abiBty of the operator to control. This specification provides the OPERAELITY requirements, trip setpoints and response times that wiH ensure effectiveness of the systems to provide the design protection.

Although the instruments are listed by system, in some cases the same instrument may be used to send the actuation signal to more than one system at the same time.

Operation with a trip set less conservative than its Trip Setpoint but withinits specified AHowable Value is acceptable en the basis that the difference between each Trip Setpoint and the AHowable Value is equal to or less than the drift aHowance assumed for each trip in the safety analyses.

SUSQUEHANNA - llNT 1 B 3I4 3.2 Amjndmjnt No. 119

INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occur rence of a failure ta scram during an anticipated transient.

The response of the plant to this postulated event falls within the envelope of study events in General Elec.ric Company Topical Report NE00-10349, dated March 1971 and NED0-24222, dated Oecemner L979.

The end-af-cycle recirculatian pump trip (EQC-RPT) system is a part of the Reactor Protection. System and is an essential safety supplement to the reactor trip.

The. purpose of'he EQC-RPT is ta recover the loss of thermal margin which occurs at the end-of-cycl ~.

The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can acid positive reactivity ta'the reactor system at a faster rate than the central rods add negative scram reactivity.

Each EQC-RPT system trips both recircula" tian pumps, recfucing coolant flow in orcier ta reduce the void callapse in the care during two of the mast limiting pressurization events.

The two events for which the EQC-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

A fast closure sensor from each of two turbine control valves provides input ta the EOC-RPT system; a fast closure sensor from each of the other two turbine cantrol valves provides input to the second EQC-.RPT system.

Similarly, a position switch for each af two turbine stap valves provides input to one EQC-RPT system; a position switch fram each of the other two stop valves provides input to the other EOC-RPT system.

For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-aut-of-2 logic for the fast closure of turbine control valves and a 2-aut-of-2 logic for the turbine stop valves.

The operation of either logic will actuate the EQC-RPT system and trip bath recirculation pumps.

Each EQC-RPT system may be manually bypassed by use of a keyswftch which is administratfvely controlled.

The manual bypasses and the automatic Operating Bypass at less than 30K of RATED THERMAL POWER are annunciated in the control The EQC-RPT response time fs the time assumed fn the analysis between initiation of valve motion anct complete suppression of the electric arc, f.e.,

175 ms.

Operation with a trip set less conservative than fts Trip Setpoint but within fts specified Allowable Value is acceptable on the basis that, the difference between each Trip Setpoint and the Allowable Value is equal. to or less than the drift allowance assumed for each trip in the safety analyses.

SUSQUEHANNA - UNIT 1 B 3/4 3-3

IHSTRUMBITATION f3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolatfon cooling system actuation instrumentation is provided to inftiate actfons to assure adequate core cooling fn the event of reactor isolation from fts primary heat sink and the loss of feedwater flaw to the reactor vessel without providing actuation of any of the emergency care cool ing equipment.

Operation with a trip set less conservative than fts Trip Setpoint but within fts specfffed Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

3/4.3.6 CONTROL RQO BLOCK INSTRUMEHTATION The control rod block functians are provided consistent with the requirements of the speciffcations fn Section 3/4.1.4, Control Rod Pragran Controls and Section 3/4.2 Power Ofstributfon Limits.

The trip logic is arranged so that a trip in any one of the inputs will result in a control rad block.

Operation with a trip set less conservative than its Trip Setpofm out within its specified Allawable Value fs acceptable an the basis that the difference between each Trip Setpoint and the Allowable Value is equal ca ar less than the drift a11awance assumed for each trip in the safety analyses.

The Rod Block Monftor (RBM) portion'of the control rad bl'ock instrumentation contains multfplexfng circuitry which interfaces with the reacto~ manual cantrol system.

The RBM fs a redundant system which includes two channels of informatian

)

which must agree before rod motion fs permitted.

Each of these redundant channels has a self-test feature which is implicitly tested during the performance of survefIIaace pursuant to this specificatian as well as the control rod opera-bility speci ficatfan (3/4. L3.1).

3/4.3. 7 MONITORING INSTRUMENTATION J 3/4.3.7. I RAOIATION MONITORING IHSTRUMEHTATIQN.

The OPERABILITY af the radiation monftoring instrumentatfan ensures that; (I) the radiatian levels are continually measured in the areas served by the individual channels; (2) the alarm or automatfc action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

Thfs capability fs consistent with the recommendations of HUREG-0737, "Clarfffcatfon af TMI Action Plan Requirements,"

November, 1980.

3.4.3.7. 2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monftorfng instrumentation ensures that sufficient capability is available ta promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the unit.

This fnstrumentatian is consis-tent with the recaaanendatfans of Regulatory Guide l. 12 "Instrumentation for Earthquakes",

April 1974.

SUSQUEHANNA - UNIT 1 8 3/4 3-4 Amendment No. 2 g

IN~iUMEHTATION BASES 3/4.3.8 TURBINE OVERSPEEQ PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE'and %11 protect the turbine from excessive overspeed.

Protection from turbine excessive.overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impac. and damage safety related components, equipment or structures.

3/4.3.9'HDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMEHTATION The feeWater/main turbine trip system acwation instrumentation is provided to initiate action of the faedwater system/main turbine trip system.'n the event of failure of feedwater controller under maximum demand.

SUS)UENANNA - UNIT 1 B 3/4 3-7

lNSERT: RHR SDC Bases f

The Reactor Vessel Water LevelLow, Level 3 Function that isolates the RHR System Shutdown Cooling is only required to be OPERABLE in OPERATIONAI CONDITIONS 3, 4, and 5 to prevent this potential flowpath from lowering the reactor vessel level to the top ofthe fuel.

Ifan inoperable channel is not restored to OPERABLE status or placed in trip within the allowed completion time, the associated penetration flow path should be, dosed.

However, if the shutdown cooling function is needed to provide core cooling, ACTION27 allows the penetration flowpath to remain unisolated provided action is immediately initiated to restore the channel to OPERABLE status orto isolate the RHR Shutdown Cooling System (i,e., provide alternate decay heat removal capabilities so the penetration flow path can be isolated).

ACTION 27 must continue until the channel is restored to OPERABLE status or the RHR Shutdown Cooling System is isolated.

Only one trip system is required in OPERATIONALCONDITIONS 4 and 5 when RHR shutdown cooling system integrity is maintained meaning piping is intact and no maintenance is being performed that has the potential fordraining the reactor vessel through the system.

0

INSERT:

8-3.3.2 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing 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 NEDC41677P-A,"Technical Specification Improvement Analyses for BWR Isolation Actuation Instrumentation."

INSERT:

8-3.3.3 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners'roup Technical Specification improvement Methodology with Demonstration forBWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE%22,"Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Susquehanna Steam Electric Station, Units 1 and 2."

INSERT:

8-3.3.4 CHANNEL FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance withGeneral Electric report GENE-770-06-1,"Bases for Changes to Surveillance Test Intervals and Allowed Outwfeivice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

INSERT:

8-3.3.5 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing 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.

INSERT:

B-3.3.6 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General Electric reports NEDC-30851 P-A, Supplement 1,"Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," and GENE-77046-2,"Bases for Changes to Surveillance Test Intervals and Allowed Out-ofervice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated September 13, 1991.

INSERT:

8-3.3.7 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing forthe main Control Room Outside AirIntake Radiation Monitor have been determined in accordance with General Electric report GENE-77046-1,"Bases for Changes to Surveillance Test Intervals and Allowed Out-ofNervice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

INSERT:

8-3.3.9.

CHANNEL FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance withGeneral Electric report GENE-770-06-1,"Bases for Changes to Surveillance Test Intervals and Allowed Outwfervice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

Extending STls and AOTS for Susquehanna Technical Specwcation Instrumentation Unit 2 BASES

dd I

>>>>I 'd>>

'd d

consequences of accidents by prescHbing the OPERABILITYtrip setpoints and response times for Isolation of the reactor systems.

When necessary, one channel may be inoperable for brief intervals to conduct required sunnillance.

Some ofthe tripsettings may have tolerances expHcitly stated where both the high and lowvalues are critical and may have a substantial effect on safety.

d>>WI >>>>>>'.

IF>>d>>>>1>>d>>'dl d

bearing on safety, are estabHshed at a level away from the normal operating range to prevent inadvertent actuation of the systems Involved.

~r6 RHR, M>

15+Sc5 Leak detection temperature satpoints are selected to prevent a high energy line break by detecting and isolating leakage below the flow rate corresponding to critical crack size for the respective system piping. The setpoints are also set below fire suppression setpoints (HPCI and RCIC) and high enough to avoid inadvertent isolation caused by normal temperature transients or abnormal transients caused by non4udc conditions (such as toss of ventilation).

Except forthe MSIVs, the safety analysis does not address individual sensor response times orthe response times of the logic systems to which the sensors are connected.

For D.C. operated valves, a 3 second delay Is assumed before the valve starts to move. for A.C. operated valves, itis assumed that the A.C. power supply is lost and Is restored by startup ofthe emergency diesel generators.

In this event. a time of 13 seconds is assumed before the valve starts to move.

In addition to the pipe break, the faHure ofthe D.C. operated valve is assumed; thus the signal delay sensor response Is concurrent with the 10 second diesel stanup.

The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunction with the 10 second delay. It follows that checking the valve speeds and the 10 second time for emergency power estabHshment wm establish the response time for the isolation functions.

However. to enhance overall system reliabB!ty and to monitor instrument channel response time trends, the isolation actuation Instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.

Operation with a trip set less conservative than its Trip Setpoint but within its spec¹ied Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

The emergency core cooHng system actuation instrumentation is provided to Initiate actions to mitigate the consequences ofaccidents that are beyond the ability ofthe opeaeor to control. This spec>>fiication provides the OPERABILITYrequirements, trip setpoints and response times that wm ensure effectiveness of the systems to provide the design protection.

Although the instruments are listed by system. in some cases the same instrument may be used to send the actuation signal to more than one system at the same time.

3'5 Operation with a trip set less conservative than its Trip Setpoint but within its spec¹ied Allowable Value is acceptable an the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or4ess than the drift allowance assumed for each trip in the safety analyses.

susauaaeNA

- eer Z B 3/4 3-2 Amendment No.87

The anticipated transient without scram (ATWS) recirculation pump tnp system provides a means of limitingthe consequences of the unlikely occurrence of a failure to scram dunng an anticipated transient.

The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NEDO-10349, dated March 1971 and NEDO-24222, dated December 1979.

The endef-cycle recirculation pump trip (EOC-RPTj system is a part of the Reactor Protection System and is an essential safety supplement to the reactor trip. The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the endwf-cycle.

The physical phenomenon involved is that the void reactivity feedback due to a

pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity.

Each EOC-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events.

The two events for which the EOC-RPT protective feature will function are closure ot the turbine stop valves and fast closure of the turbine control valves.

Afast closure sensor from each ot two turbine control valves provides input to the EOC-RPT system: a fast closure sensor from each of the other two turbine control valves provides input to the second EOC-RPT system.

Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch from each ofthe other two stop valves provides input to the other EOC-RPT system.

For each EOC-RPT system.

the sensor relay contacts are arranged to form a 2wutwf-2 logic for the fast closure of turbine control valves and a 2wutwf-2 logic for the turbine stop valves.

The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps.

This function is not required when THERMALPOWER is below 30% of RATED THERMAL POWER.

The Turbine Bypass System is sufficient at this low power to accommodate a

turbine stop valve or control valve closure without the necessity of tripping the reactor recirculation pumps. This function is automatically bypassed at turbine firststage pressures less than the analytical limitof 147.7 psig, equivalent to THERMALPOWER of about 30%

RATED THERMALPOWER. Turbine first stage pressure of 147.7 psig is equivalent to 22%

of rated turbine load.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled.

The manual bypasses and the automatic Operating Bypass at less than 30% of RATED THERMALPOWER are annunciated in the control room.

The EOC-RPT response time is the time assumed in the analysis between initiation of valve motion and complete suppression of the electric arc, i.e., 176 ms.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less then the drift allowance assumed for each trip in the safety analyses.

SUSQUEHANNA - UNIT 2 8 3/i 3-3 Amendmern No. 103

INSTRUMENTATION BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation fnstrumentatfon fs provided to initiate actions to assure adequate core cooling fn the event of reactor isolation from fts primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Operation with a trip set less conservative than fts Trip Setpofnt but within fts specified Allowable Value fs acceptable on the basis that the difference between each Tcfp Setpofnt and the Allowable Value fs equal to or less than the drift allowance assumed for each trip fn the safety analyses.

3/4.3. 6 CONTROL ROD BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications fn Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits.

The trip logic fs arranged so that a trip fn any one of the inputs will result fn a control rod block.

Operation with a trip set less conservative than its Trip Setpoint but within fts specified Allowable Value fs acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value fs equal to or less than the drift allowance assed for each trip fn the safety analyses.

The Rod Block Monitor (RBM) portion of the control rod block instrumentation contains multfplexing circuitry which interfaces with the reactor manual control system.

The RBM is a redundant system which includes two channels of information which must agree before rod motion is permitted.

Each of these redundant chan-nels has a self-test feature which fs fmplfcftlytested during the performance of surveillance pursuant to this specification as well as the control rod operability specfffcation (3/4.1.3.1).

3/4.3. 7 MONITORING INSTRUMENTATION 3/4.3.7. 1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring fnstrumentatfon ensures "that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm or automatic action fs initiated when the radiation lovel trip setpofnt fs exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability fs consistent with the recomendatfons of NUREG-0737, "Clarfffcatfon of TMI Action Plan Requirements,"

November, 1980.

3.4.3.7. 2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring fnstrcmentation ensures that sufficient capability is available to proiptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability fs required to permit comparison of the measured response to that used fn the design basis for the unit.

This instnmentatfon fs consis-tent with the recomendatfons of Regulatory Gufde 1.12 "Instrcmentatfon for Earthquakes", April 1974.

SUSQUEHANNA - UNIT 2 B 3/4 3-4

INSmmMENTATION ns>

'53~9 3/4.3.8 TURBINE OVERSPEEO PBOTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and we'll protect t!e turbine fry excessive overspeed.

Protection fram turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

3/4.3.9 FEHMATER/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRNENTATION The feedwater/main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system/main turbine trip system in the event of failure of feedwater controller under maximum demand.

SUS)UEHANNA - UNIT 2 B 3/4 3-7

INSERT: RHR SDC Bases The Reactor Vessel Water LevelLow, Level 3 Function that isolates the RHR System Shutdown Cooling is only required to be OPERABLE in OPERATIONALCONDITIONS 3, 4, and 5 to prevent this potential flowpath from lowering the reactor vessel level to the top ofthe fuel.

lfan inoperable channel is not restored to OPERABLE status or placed in trip within the allowed completion time, the associated penetration flow path should be dosed.

However, if the shutdown cooling function is needed to provide core cooling, ACTION27 allows the penetration flow path to remain unisolated provided action is immediately initiated to restore the channel to OPERABLE status orto isolate the RHR Shutdown Cooling System (t.e., provide alternate decay heat removal capabilities so the penetration flow path can be isolated).

ACTION 27 must continue until the channel is restored to OPERABLE status or the RHR Shutdown Cooling System is isolated.

Only one trip system is required in OPERATIONALCONDlTIONS 4 and 5 when RHR shutdown cooling system integrity is maintained meaning piping is intact and no maintenance is being performed that has the potential fordraining the reactor vessel through the system.

0

INSERT:

8-3.3.2 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been detenhined 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 Specificatio Improvement Analyses for BWR Isolation Actuation Instrumentation,"

INSERT:

8-3.3.3 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners'roup Technical Specification Improvement Methodology with Demonstration forBWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE%22,"Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Susquehanna Steam Electric Station, Units 1 and 2."

INSERT:

8-3.3.4 CHANNEL FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance withGeneral Electric report GENE-770-06-1,"Bases for Changes to Surveillance Test Intervals and Allowed Outwf-Service Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

INSERT:

B-3.3.5 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General Electric report GENE-770-06-2,"Bases for Changes to Surveillance Test Intervals and Allowed Outwf-Setvice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated September 13, 1991.

INSERT:

B-3.3.6 CHANNEL FUNCTIONALTEST friquencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General Electric reports NEDC-30851P-A, Supplement 1,"Technical Spedfication Improvement Analysis for BWR Control Rod Block Instrumentation," and GENE-77046-2,"Bases for Changes to Surveillance Test Intervals and Allowed Out-ofNervice Times for Selected Instrumentation Technical Spec Tiications," and the associated NRC Safety Evaluation Report dated September 13, 1991

~

INSERT:

B-3.3.7 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing for the main Control Room Outside AirIntake Radiation Monitor have been determined in accordance with General Electric report GENE-77046-1,"Bases for Changes to Surveillance Test Intervals and Allowed Outwfervice Times for Selected Instrumentation Technical SpecTiications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

INSERT:

B-3.3.9 CHANNEL FUNCTIONALTEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance withGeneral Electric report GENE-770-06-1,"Bases for Changes to Surveillance Test Intervals and Allowed Outwfervice Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992.

ML17164A580

Contents

Text

RESPONSE

RESPONSE

RESPONSE

RESPONSE

Navigation menu

ML17164A580

Text

RESPONSE

RESPONSE

RESPONSE

RESPONSE

Navigation menu

Search