Text

Proposed Tech Specs for Aot/Sti Extensions
	ML17164A580
Person / Time
Site:	Susquehanna
Issue date:	02/10/1995
From:	; PENNSYLVANIA POWER & LIGHT CO.
To:	;
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ML17164A579	List: ML17164A578; ML17164A580; ML18026A267;
References
	NUDOCS 9502170194
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ENCLOSURE C TO PLA-4249 PROPOSED CHANCES FOR SSES TECHNICAL SPECIFICATIONS 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.

As shown in Table 33.1-1.

ense'6 s s.i hCMH:

%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 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the h required by Table 3.3.1-1 hr the Functional Unit shall be taken; or

2. Ifplacing the inoperable (s) tripped condition would not cause a scram, place the inoperable (s) aad/or that trip system in the tripped condition within 12 hou

b. %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 oi the APIMs.

49.1.1 ad p a M~lh d I pERASOLEby thc perfiormaacc of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATIONoperations for the OPERATIONAL CONDITIONS aad at the

&equencics shown in Table 4.3.1.1-1.

43.12 LOGIC SYSTEM FUNCGONAL TESTS and simulated automatic operation of all channels shall be perfonacd at least once per IS months.

49.19 The REACIQR PROTECTION SHiiM RESPONSE TIME of each reactor trip hmctioaal unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at 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.

43.1A Tbe provisions of Specificatio 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.

If more 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 hmendmcat No. 11 5

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 for the 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.

C HANNA. OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDlTlONS FOR WHICE CIKCK TESf CALIBRATION ) SURVEILIANCS REQUIRED I. lntcreaeduae Range Monitora:

~. Neutron Flua - High SIU,S,tb) SIUlc), W SA 2 S W SA 3, 4, 5

b. Inoleetive NA Siui'), W Nh 2, 3, 4, S

2. h g. Power Range M itort":

a. Neutron Flua- SIU,S t") Srui'), W SA 2 Upacale. Setdown S W SA 3,5

b. Flow Bused Simulated 1lenna) h~.Upsca)e s D(g) slut') q +dXe) Sh Rth)

c. Freed Neutnet Ftua-Upsca)e SIU(c) q Wi+, sh

d. Inoperative Syg(c) q NA I 2 3S

3. Reactor Vcaac) Stcam Dome Prcssure - High NA l,2 Reactor Vcaacl Water Level-Lovv, Level 3 l,2 S. Main Stcam Line bolation

~

Valve - Closure NA

6. Main Stcam Line Radiation-s High 2')

7. Drywall Prcaaure - High Nh Io2 R

'I

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 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.

~d hTal $ 3.lE hCGQE:

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 for the Functional Unit shall be taken; or

2. If placing the inop channel(s) 'ripped condition would aot cause a (s) and/or that trip system in the tripped

'n scram, place the inoperab condition within 12 ho

b. With the number of LE cliaiinels @quired by the Minimum OPERABLE per Trip System aquiremeat Sr systems, place at hast one 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 Each reactor protection system instriuaentatioa channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATIONoperatioas 5or the OPERATIONAL CONDITIONS and at the

&equencies showa in Table 4.3.1.1-1.

43.12 LOGIC SYSTjEM FUNCGONAL TEAK and simulated automatic operation of all channels shall be performed at least once per 18 months.

43.1D The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at 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.

49.1A The pnnrisioas of Specification 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.

If more 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 - UNIT 2 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, 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 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 for the 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.

0PERhTIONhL CIIANNEL CHhNNEL CONDIONS FOR WHICH RJNCTIONAL UNIT CIIECK ChLIBRATION ~

SURVEILLhNCE REQUIRED I. intermediate Range Monitors; Neutron Fina High Sru,S,+) Sru(c), W SA 2 S W SA 3,4,5

b. Inoperative srul') w NA 2, 3, 4, S

2. Avg, Power Range Monitored "t

a. Neutron Flua- sru.sP) sru'l') W SA 2 Upecale, Sctclown S W SA 3,S

b. Row Biaaed Simulated Tlrerrnal Power-Upecale S D(a) srut') Q WldXe) SA, Rt>>

c. Ftaed Neutron Flua-Upecale Srutc), Q +d) SA

d. inoperative Srutc), Q NA l,2,3,5

3. Rcector Vessel Steam Dome Preaurre - High NA l.2

4. Reactor Vessel Water Level-Low, Levd 3 Io2 S. Main Steam Une isolation Valve - Closure NA

6. Main Steam Une Radiation-High l, i+

1. Drywell Pressure - High 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 inoperabl ~

nels per Trip System requirement for one within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The pro 1(s) and/or that trip sys of Speci trf, the number of OPERABLE channels less than requfred by the Nfn'P place e tripped condition" 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 the more ls are fnoperable fn one trfp system than in the er, place 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:

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.

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.

TABLE 3.3.2-1 C

CA C

ISOLATION ACTUATION INSTRUNENIATION HININjH APPLICABLE I I SOLAT ION( OPERABLE CINNNELS OPERATIONAL TRIP fUNCTION ) ACTION C

1. PR IHARY CONTAIIIIKNT I SOLAT ION

a. Reactor Vessel Mater Level

1) Low, Level 3 1, 2,.3 20

2) Lcnv Los, Level 2 2 1, 2,'3 20

3) Lent Lmr Los, Level 1 2 lo 2o 3 20

b. Drywell Pressure - High Y,Z,N 1, 2, 3 20

c. Hanual lni ti ation 1, 2, 3 21

d. SGTS Exhaust Radiation-High R qAAA 54$ $ 20

e. Hain Steaa Line Radiation-Nigh C 1, 2q 3 20

2. SECONDARY CONTAIIIIENT ISOLATION Reactor Vessel Mater Level-Lm Lmr, Level 2 1, 2, 3 and e g5

b. Drywell Pressure - 1,2,3 25 High'efuel

c. Floor High Exhaust Duct Radiation - High 25

d. Railroad Access Shaft, Exhaust Duct Radiation - High 25 O+ Refuel Floor Mall Exhaust Duct IF Radiation - High 2 25 Hanual Initiation 1,2,3and" 24

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUHENTAT ION m

MINIMUM APPLKABLE ISOLATION OPERABLE CHANNELS OPERATIONAL C

TRIP FUNCTION SIGNAL s PER TRIP SYSTEM CONDITION ACTIQH M 3. MAIN STEAM LINE ISOLATION W a. Reactor Vessel Mater Level - II 1, 2, 3 21 Low, Low, Low, Level 1

b. Main Steaw Line Radiation - C 1, 2, 3 21 High

c. Main Steaw l.ine Pressure - Low P 2 1, 22

d. Main Steaa Line Flow - High 0 2/line 1,2,3 gQ

e. Condenser Vacuum - Low UA 2 1,2,3 21

f. Reactor Building Main Steam line E 2 1,2,3 ~

21 Tunnel Temperature - High g.. Reactor Bui)ding Hain Steaa line E 1, 2, 3 ader I Tunnel h Teaperature - High

h. Manual initiation NA 1, 2, 3 24

i. Turbine Building Main Steam E 1, 2, 3 21 Line Tunnel Teaperature-High

4. REACTOR MATER CLEANUP SYSTEM ISOLATION I' RMCU h Flow - High J 1 1,2,3 RMCU Area Teaperature - High M 3 1,2,3 jI k C. RMCU Area Ventilation h Tesp.- M 3 1, 2, 3 High I 1, 2, 3

'C goo d.

e.

SLCS Initiation Reactor Vessel Mater Level - Low Low, Level 2 B

2

.2 1, 2, 3 23 23 INCU Flow - High J 1, 2, 3 23 Manual initiation NA l,2,3 24

~ ~

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION HINIHUM APPLICABLE ISOLATION OPERABLE CHANNE ~ OPERATIONAL TRIP FUNCTION SIGNAL s PER TRIP SYSTE CONDITION AC'f ION

5. REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION

a. RCIC Steaw Line h Pressure - High K 1 1, 2, 3 23

b. RCIC Steaw Supply Pressure - Low KB 1, 2, 3 23

c. RCIC Turbine Exhaust Diaphraya K 1,'2,3 Pressure - High 4J

d. RCIC Equipment Room 1, 2, 3 23 Teaperature - High I

e. RCIC Equipwent Room Temperature - High h 1,2,3 iA

f. RCIC Eaergency Area Cooler 1, 2, 3 23 Teaperature - High

g. RCIC Pipe Routing Area h Tewperature - High 1,2,3 ~g

h. RCIC Pipe Routine Area 1, 2, 23 Teaperature - High 3',

g i. Hanua I lni tiation 2, 3 2h CC Orywell Pressure - High 1, 2, 3 23

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION NINIHUH APPLICABLE ISOLATION OPERABLE CHANHE OPERATIONAL TRIP FUNCTION ~((((( ( P(R (R(P (II ((h CONDITION ACflOII

6. HIG}l PRESSURE COOLANT INJECTION SYSTEH ISOLATION

a. HPCI Steaa Line h Pressure - L 1, 2, 3 High

b. HPCI Steaa Supply Pressure-Low LB 1,2,3 23

c. HPCI Turbine Exhaust Oiaphraga L 1, 2, 3 Pressure - High

d. HPCI Equipient Rooa L 1, g, 3 Temperature - High

e. HPCI Equipient Rooa h 1, 2, 3 23 Tewperature - High

f. HPCI faergency Area Cooler li2e3 Teeperature - High

g. HPCI Pipe pouting Area 1, 2, 3 23 Teiperature - High

h. HPCI Pipe Routine Area 4 Teaperature - High 1, 2, 3 z4

~gg i. Hanual Initiation 1, 2, 3 24

<<<<o gl Orywell Pressure - High 2 1, 2, 3 oo egal IO

P z

R I 914; C

R TASLE 3.3.2-1 (Continued)

ISOLATION ACTUATlON NSTRUMENTATION 5'rip Minimum Operable Applicable Function Isolation Slgndls)~ Channels P Trip Operational Action Syst Condition

7. RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION I e, Reactor Vessel Water Level - Low, Level 3 I A M

cn b. Reactor Vessel IRHR Cut-in Permissive) UB 1,2,3 28 Pressure - High

c. RHR Flow - High 1,2,3 28

d. Manual initiation 1,2,3 2I

e. Drywell Pressure - High 1,2,3 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 R

R'

,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 - I Close the affected system isolation valves within 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 f sh 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 f rradfated 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 ACTION 27: (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 TABLE 3.3.2-.2 tContlrtuedl

~ .::- ~ >c> 1

. ISOLATION ACTUATION tIIISTRUllhENTATION'SETP01NTS '::-.:: .-.i.:.

TRIP. FUNCTION TRIP SETPOINT ALLOWABLEVALUE IContlnued)

e. Condenser Vacuum - Low a 8,0 Inches Hg vacuen a 8.8 inchea Hg.vacua

.Reactor Bulldlng Main Steam Une Tunnel s177 F 1844F Temperature - High Reactor Bulng Main Steam Une Tunnel h s 884F c 'l08'Ig.

Temperature . High Turb'>> BuMlng Main Steam Une Tunnel s 1874F s 2004F Temperature - High 4.

M I I ar RWCU h Row - High s 80gpm s 80gpm gp Cl b. RWCU Area Temperature - High s 1474F or 1314' s 1644F or 1374FN Cr RWCU/Area Ventllatlon h Temperature - High 88'F or 40.64FN s 72 F or 43.64F SLCS Inltlatlon Reactor Vessel Water Level - low low, level 2 a -38 Inchea' e AS hchea RWCU Row - High 428 gpm s 438 gpm MaaNI fnltlatlon NA 5QLHfQR a RCIC Steam Une h Presere - High s177 Hg s 188'P

b. RCIC Steam Supply Presare - Low a 80 pslg a 63 pslg

c. RCIC Turbine Exhaust OIaphragm Pressure- s 10.0 pslg s 20.0 pslg 0 Hlgh

~ r

TABLE 3.3.2-2 (Contlnuedl 0C ISOLATlON ACTUATION INSTRUMENTATlONSETPOlNTS x f TRIP UNCTION TRlP SETPOINT ALLONASLRVAltJR zz EA OR O Y r MISOLAtlO (Coorlnuedl C

d. flCC Equipment Room Temperature - High 1874F" s 'l744F'4 R s 8$ 4F

~o RCC Equipment Room h Temperature - High s SS' RCC Pipe Routing Area Temperature - High s 187'Ftf 174'Fft

~

RCC Pipe Routing Area h Temperature ~ High s 884Fff. . s 884Ff

h. RCC Emergency Area Cooler Temp. - High s 1874F s 1744F I. Manual Initiation s 1.72 pslg s 1.bb pslg

'>so

~

J,.p%.

~

M 8. I N Y 4 HHHhHQR CD crr e. KPCI Steam line flow - High s 350 inches HqO . S 387 Inches QO:i..;,"

HPCI Steam Supply Pressure - tow a 104 psli . 2 80pslg .

Ce HPCI Tcabine Exhaust tHaphragm Preaaure - .

s 10 pslg s 20pslg High

d. HPCI Equipment Room Temperature - High s 187'F . s 1744F '-

e. HPCI Equipment Room h Temperature - High ~

S 884F r s 884F HPCI Emergency Area Cooler Temp. - High S 1874F -i ~ - - s 1744F HPCI Pipe Routing Area Temperature - High S 1874Fff s 1744Fff

Ctl ~

C ~

CO 0

)2 hie TABLE 3.3.2-2 IContinued) ~

s

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g bb Fl I. Nmuel iniletion i .;R)A ~ .', e ~ V ~

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=:-".i.':.'Ileertoi Vooeel Wder Lnnl - Lee, Lwel 3:'c

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~ 'I

":;"41 gaael allan ei<"..-2":- 2!;:.: I'.. p .-...- . ~ .-..

~ '::. e 'lgltNhee0~ . INgh '.-; .f':.s *'-g:,.-1.f'-;::=.-4".~~'-'>~<i~>',~~+ I)72 Iwiygg~'~~[j~T".,~~:>gg"Ibb.lwiy QN flQUFQ Q 3/g 3)I ~ I',H.Tj~s p' e... ~, '..i'i)s 2')go~+:> )epfg j gjf.. se'1)rg'r .'S'-4'p +$ '+)1 '~~p~ip "e re e

~'ee 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 C

IABLf 4.3.2.1-1 Cll C

m lSOLAIION ACIUAIlON INSIRLNENIAILON SURVE lLLANCE RE UlREHENIS CHANNEL OPERAYIONAL CHANNEL FUNGI lONAL CHANNEL CONOl YlONS fOR MHYCH IRIP FUNCI lON CHECK YESI CAL I BRAY lON SURVE lLLANCE Rf YREO I. PRlHARY CONYAlNENY 1 SOLAY tON

a. Reactor Vessel Mater Leyel-

1) Los, Level 3 1, 2, 3

2) Los Low, Level 2 lK 2H 3

3) Lm Lmt Lmt, Level 1 S 1, 2c 3

h. Oryvcll Pressure - High NA f, 2, 3

c. Hanual lni tiat i on NA NA fxhaust Radiation - High d.

e.

SGIS Hain Steaa Line Radlqtion " High S

S R

R 1,',3 )ATE* g*Pg

2. SECONARY CONIAlhNENI l SOLAI ION

a. eac or esse a er eve Low Lm, Level 2 and

b. Orle'll Pressure " High 1, 2, 3

c. Refuel Floor High Exhaust Ouct Radiation - High

d. Railroad Access Shaft Exhaust.

Ouct Radiation - liigh

e. Refuel Floor Mall Exhaust Guet gt Radiation - High

~ ~

S

~ O

~ ~

f. Hanual initiation NA t, 2, 3 and ~

fABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEIllANCE RE UIREHEHTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CINNNEL CONDITlO)S FOR NICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE UIRED

3. MAIN STEAM LINE ISOLATION

a. Reactor Vessel Mater Leyel-Low, low low, l.evel 1 S 1, 2, 3

b. Hain Steaa Line Radiation - High S ), 2, 3 co Hain Steaa Line Pressure - Low N

d. Hain Steaa Line Flow - High S R l, g 3

e. Condenser Vacuum - Log NA q. gki 3%A

f. Reactor Building Hain Steaa Line Tunnel Teeperature - High N l,2,3

g. Reactor Building Hain Steaw gine Tunnel h Teaperature - High N Q

h. Hanual Initiation N N 2, 3

i. Turbine Building Hain Steaa Line tih $< Po 3 Tunnel Temperature - High

4. REACTOR MATER CLEANUP SYSTEM ISOLATION

a. NCU h Flow - High 'l,2) 3

b. RNU Area Teeperature - High ), 2) 3 C. RMCU Area Ventilation. h Teaperature - High NA 1, 2,

d. SLCS Initiation NA 1,2,3 Reactor Vessel Mater level " Low low, level 2 S l,2,3 RMCU Flow - High S I, 2) 3 Manual initiation NA l,2,3

lABLE 4.3.2.1-1 (Continued)

ISOlAIION ACIUAllON INSIRUHENIATION SURVEILLANCE RE UIREHENTS CIIAHNEL OPERAT IONAL CllANNEL FUNCT IOHAL CHAHHEL COND I T IOHS FOR ltHICII lRIP 1 UNCTION CIIECK TEST CALIBRATION SURVEIllANCE RE I REO

5. REAC10R CORE lSOLAllON COOL lNG SYSTEH ISOLATION

a. BClC Steam Line h Pressure - High HA 1,2,3 RCIC Steaa Supply Pressure-Low 1,2,3 C. RCIC Turbine Exhaust Oiaphraya Pressure - lligh Ie 2e 3 RCIC Equipient Room .

Teaperature - lligh I, 2, 3

e. RCIC Equipient Room h Temperature - lligh HA i,~,i RCIC Pipe Routing Area Temperature - lligh 1,2,3

g. RCIC Pipe Routing Area h Teeperature - lligh i,~,k(

h. RCIC Ewergency Area Cooler Teaperature - lligh HA II 2e 3

i. Hanual Initiation . HA Ie 2e 3

j. Orywell Pressure - High NA I, 2, 3

6. IIIGN PRESSURE COOLANT INJECTION SYSTEH ISOLAI ION HPCI Steaa Line h Pressure - High 1,2,3

b. HPCI Steaa Supply Pressure - low I,2,3 C. HPCI Turbine Exhaust Oiaphraya Pressure - lligh I,2,3

TABLE 4.3.2.1-1 (Colt tfntted)

D ISOLATION ACTUATION INSTRUNIENTATIONSURVEILLANCE REQUIREMENTS C

x TRIP RJNCTION CHANNEL CHANNEL CHANNEL OPERATIONAL CONDITIONS RN R CHECK FUN CTIONAI. CALIBRATION WHICH SURVEILLANCE RMUNED R TEST IGH RESSU ECO E 0 SYSTEM ISOLATION C IContinuedl K

d. HPCI Eydpment Room Temperature - High 1.2,3

e. HPCI Equipment Room 4 Temperature - High NA 1. 2,3

f. HPCI Emergency Area Cooler Temperature - High 1,2.3

g. HPCI PIpe Routing Area Temperature - Ngh 1,2,3

h. HPCI Rpe Routing Area 4 Temperature - High 5, 2, CO I. Manual Initiation 1.2,3 DryweN Pressure - High 1,2,3 Col 0)

7. 0 OOL AD 0 0 8~+,8'.

Reactor Vessel Water Level - Low, Level 3

b. Reactor Vessel IRHR Cut.h Permissive) 1,2,3 Pressure - High

c. RHR Row - High S 5. 2, 3

d. Manual Initiation R 1. 2, 3

e. Drywel Pressure - High 1,2,3 When handing Irradiated fuel in the secondary containment and during CORE ALTERATIONS end operations with e potential for draining the reactor re vessel

~e When reactor steam dome pressure > 5043 pslg and/or any turbine atop valve Is open.

~e~

When VENTING or PURGING the drywe1 pet 8 ecmcation 3.51.2 R

0

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 with the Tip Setpofnt value.

tip setpoint ad)usted consistent Nth the place Channels per Tip Systew requirement for one erable channel(s) andlor that ti number of OPERABLE channels less than requfred by the tipecfffcationn 3.0.4 Nfn'E the tripped condftfon wfth ur. The provisions 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 uf red 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 system and RCIC systaa fs ip Function shall be taken. In fon, provided that th>>

ion, for the HPr'I 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.

lABlE 3.3.3-3 lsolhTIOH hCTUATIQH IHSTRtNKNThTIOH NINIIIII hPPLICh81K ISOI ATIQH OPERhalf CiNHHKL OPERAT IOHAL TRIP FISC I IOH SIGHhl S a PER TRIP SYSIEH I COHOI IOH $ TIOH I. PRIHNY COHTh SKI SOlhT IQH

a. Reactor Vessel Mater level I) Lat, leve'I 3 l ~ 2I 3 20

2) Low Lao, Level 2 l ~ 2, 3 20 3} Lees Les Les, level j l,2,3 20

b. Orpull Pressure - High Y,L l,2,3 20 C< llanual initiation N l,2,3 2h

d. SGTS Exhaust Nadiation-Hlgh j 2 3 i111 5111 eo Hain Steaa Line Nadiation-j, 2, 3 20 SECQOhlT CONAINKII lSO!.h l Reactor Vessel Mater Level-Lar Los, Level 2 j,2, 3ead1

b. Oryx')1 Pressure - High j, 2, 3 c,. Nefuel Floor High fxhaust Ouct Nadiation - High Nailroad hccess Shaft Exhaust Quet Radiation - iiigh eo Refuel Floor Mall Exhaust Quet Radiation - High 2 Hanual lni tie'Lion l,2, 3and1 24

TABLE 3.3.2-1 ICorttlpued)

ISOLATION ACTUATIONINSTRUMENTATION tSOLATION SlQNAQyltal ayytaIIUtN OPEMykt est TS>> STS ~

Q,S AtPOCASLE OtyttATINLCOSttmoll ACTNtt

~. Itaactor Vesaal Wat<< tevel- 1,2,$ 21 Low Low Low. Level 1 lIah Steam the IMatton - Hgh 1~ 2,$

e. Mah Steam Une hesatae ~ Low IIah Staara Lhe Row - Hgh 1,2,$ 20

e. Condone<<Vaoaaa - Low UA 1,2,$

t. Iteecter buMny lIaln Stum One 1~ 2, $

Tunnel T<<nperatLae - Hgh

~. Iteecter buMny llah Stum Lhe Tunnel 4 Temp<<ctree - Hgh 1,4$

L Turbtne Suydhy Mah Steam Lhe f~+$ 21 Tunnel Temp<<atrae ~ Hgh lEKIHlhHQB

a. IIWCU S Row - Hgh ti2,$

k IIWCU Area Tenyeratee - Hgh 1,4$ 2$

o. IlWCU Area Ventyathn h TemperatLee - Hgh ti2,$

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

Lew Lew. Level 2 t.l. INfCU Rew Hgh 1N 2$

tA. tbrHley<<wratlve Heat Exchanger Nacharge 1N t~+$

Temp<<atee - Hgh 42,$ 24 or Unit 2 Cycle ~ opera Sre Rayon<<attve Heat Kachangar ~ mperaoie - fSph Channel ahoy Ire OPBIAlfh place et IIWCU Row-Hgh Channel S.

TABLE 3.3.2-1 (Continued)

I SOLAT ION ACTUATION INSTRUHENTATION HINIHVM APPLICABI.E ISOLATION OPERABLE CHANNELS I ttt

+ OPERATIONAL II ttttll TRIP FUNCTION ~III I I PtR tRIP ACTION

5. REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION

a. RCIC Steaa Line h Pressure -High K 1, 2, 3 23

b. RCIC Steam Supply KB 1, 2, 3 23 Pressure - Low

c. RCIC Turbine Exhaust lo2o3 23 Diaphragi Pressure - High

d. RCIC Equipment Room 1, 2, 3 23 Temperature - High

e. RCIC Equipment Rooa 1 ~ 2o 3 I h Temperature - High

f. RCIC Pipe Routing Area 1 ~ 2o 3 23

, Temperature " High

g. RCIC Pipe Routing Area 1, 2, 3 OQ h Temperature - High

h. RCIC Emergency Area Cooler 1, 2, 3 23 Temperature " High

i. Hanuai Initiation I 1, 2, 3

j. Drywell Pressure - High 2 1, 2, 3 23

TABLE 3.3.2-1 (Continued)

I SOLAT ION ACTUATION INSTRUMENTATION HINIHUN APPLICABLE ISOLATION OPERABLE CINttNELS OPERATIONAL TRIP FUNCTION SIGNAL S a PER TRIP SYSTEH CONDITION ACTION

6. HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION

a. HPCI Steam Line h Pressure - L 1, 2, 3 23 High

b. HPCI Steam Supp}y Pressure-Low LB 2 l, 2, 3 23

c. HPCI Turbine Exhaust Oiaphrago L l, 2, 3 23 Pressure - High

d. HPCI Equipment Room

'lemperature - High

),2,3 23

e. HPCI'quipment Room

- High 5 l, 2, 3 23 Temperature

f. HPCI Emergency Area Cooler Temperature - High

g. HPCI Pipe Routing Area l, 2, 3 23 Temperature - High

h. HPCI Pipe Routing Area h Temperature - High l ~ 2~ 3 2$

i. Hanual Initiation ls 2o 3

j. OryweII Pressure - High 2 lo 2e 3 23

U)

C D

x z

R C

R TABLE 3.3.2-1 (Contlnuedl tSaULTtON ACTUATtoN NSTttuNBiTATION Mtnlrnurn Operable Applicable Trip Function lso'latlon Signal(s)~ Channels P~Trlp Operational Actfon Systehgg Condition

7. RHR SYSTEM SHUTDOWN COOLINGIHEAD SPRAY MODE ISOLATlON Cal

e. Reactor Vessel Water C5l Level - Low, Level 3 cn b. Reactor Vessel lRHR Cut-in Permissive) 1,2,3 Pressure ~ High

c. RHR Flow - High 1. 2, 3 2B

d. Manual initiation NA 1,2,3

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

84lg %u'fJOIOA %4li55j sf5i'555 I Jeseg C K'5<~6L~R R

z0

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 ACTION 27: (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.

TABM 3.3.2-2 lCotttlrttted)

ISOLATlON ACTUATION tNSTRUNIENTATlON SETPOlNTS ALLOWABLEVALUS

~. Condenaef VacLml ~ Low h 8.0 lnchea Hp vacuwn a 8.8 inchee Hg vactaxn C

R f. Reactor Bulking Main Steam Line Tunnel Temperatwe - High s 1774F s 184'F

g. Reactor Buikinp Mekt Steam Une Tunnel h Temperatwe - High s gg>>F s 108'

h. Manual Initiation I. Twbine Buiklnp Main Steam Une Tunnel Temperatwa - High s 187>>F. 200>>F

4. REACTOR WATER CLEANIJP SYSTEM ISOLATION

a. RWCU h Flow - High s 80gpm s 80gpm Cil b. RWCU Area Temper atwe ~ High s 147>> F or 131>>F>> s 154'F or 137>>F>>

c. RWCU/Area VenQatlon h Temperatwe - High s eg For40.$ F>>. s 72>>F or 43.5>>F D

d. SI.CS Inltlatlon NA '.::-'i '".'-iRN

~. Reactor Veaael Water Level - Low Low, Level 2 ~ ." a 48 hchea R 4$ ktchea, f1. RWCURow-High S 482 Ilxtt .. s 472 Iixtt .::::~.q~q;j@

f2. Non'-Regenerative Heat Exchanger Dlacharge Temperatura -,.: s 144>>F,s, ~ ..

Hiph g.. Manual inithtlon. ~ ".<.,z. 'A

5. REACTOR CORE ISOLATlON COOLNO SYSTEM ISOLATION

~. RCIC Steam Une h Preaawe - High s 138'HO s 143'aO

b. RCIC Steam Supply Praaawe - Low a eo palp h $ 3 palp

c. RC!C Twbine Exhauat Diaphragm Preaawe - High s 10.0 palp s 20.0 pelg

TABLE 3.3.2-2 {ContIntied)

D ISOLATION ACTUATIQN INSTRUMENTATLQNSETPOINTS C

TRIP FUNCTION ALLOWABLEVALLIS I 0 0 0 IContinuedi C

d. RCIC Equipment Room Temperature - High s IB74F s 17F z ~. RCIC Equfpment Room h Temperature - High s 884F s 884

f. RCIC Pipe Routing Area Tem ture -High s s 17I4Ftt

g. RCIC Pipe Routing Area dT rature - High . s I.yea.' 884Ft

~

h. RCIC Emergency Area Cooler Mp. - High 'I 7!t'~.', ~ ~

~

I t~

S 17I4F t ~

I. Manual Initiation a . g ',i.t

~

'Nh C' NA Drywall Praaaure - Hfgh s 1.72 paig s 1.88 palg le 8. HIGH PRESSURE COOLANT NJECTION SYSTEM ISOLATION

~< HPCI Steam Line Flow - High S 387 lnchea HiO s 388 inchea H>O Cl ~>

b. HPCI Steam Supply Praaaure - Low a 104 palg h 80palg

\

Ct HPCI Turbine Exhaual Dfaphlol Preaalga- s 10 yafg s 20 pafg .s.r;4i:.

... r>,'-.

Hlgh

~, t ~

HPCI Equipment Room Temperature - High s 187'IF s 17teF

~t HPCI Equfpment Room h Temperataaa -Qgh sBStF . SBBF g.)

HPCI Emergency Area Cooler Thnp. - High s 1874F S 1744F ..;, ! t,<

~ ~ ~

1 HPCI Pipe Routing Area Tempdt4ture - High s 1874Ftt S 1N4Ftt ~ t

h. HPCI Pipe Routing Area d Tergerature - High s 88'Ftt s 88'Ft O

Manual initiation R

Diyweff Preaaure - High S 1.72 paig . s 1.88palg z0 I e-

I SOI A'I ION AClllAIIO!I INSIRIRIENIAIIOII SUAVE ISSANCE RE llIREHENIS CNHHfL OPf RhllONL f.INHHfl FUHCT IONl CINHHfl COHDIl IGNS FOR QIICII lRIP FINCH lmI CIILCK Tf Sl CAL I BRhl IOII SIIRME IllINCf lf ION I. PRIHNY CONAINKNl I SOlAT ION CL

a. Reactor Vessel Mater level-l) Lat, Level 3 5 R l, 2, 3

2) Les La>, Level 2 S R l, 2, 3

3) L~ Lee Los, level l S R

b. Orpull treasure High NA N li2R3 C. Iiaaual laitlatiea N N l,2,3 SOTS Kaleeat Mlatlee - High s, 2, 2, R~~~ s~~~ I Naia Stea Liae aadlatiea-Hlgh l,2N3 SfCNSllY I IOWAN SOLI'i ao Weacter Vessel lhter level-Lce Les, Level 2 lo 2N 3 and +

Orwell treasure - High 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

~ NR I

QM Ill/VEIISlaCA(gfgJI ISQEA'aDN ACTUATIONINS1RIIIAEQ7$ I:, -g

' fifo/}+ !

e. React>> Vaeeel Nt>> Lani ~

Lew Lew Lew. Leael l

~ l4NI Ianna Qa IeONlan ~ ~

I%I SIN% Qo fteaaIN i Lew 4 Ma1 Ite<<w 4w flw>> W lsf 3

~e e~

~. Coatee Veewe LeIa 42 S

~

l. Iaaae>> aaay Iten+ ue

~.

Zaenal leeeeer Twaal

~

feape~

Mala Iaaeet Liaa 4 'leeyeraan Hgh l4aael l&lal<<a L teihe 54&g lweel f

~ It~~ lIIh Lie

~. NCUi Raw Hgh fat

~ NtN Aeo t<<ty<<ann - lwgA 441 e IWCU Aw Vomatha i Tenp<<aan Hgh 4 ILCIInkletlatt

~. ltaeot>> Veeeel VAt>> Lenl Lew Lew, Lerel 0 tlat.:

t.lo NVN flow Hah~

~ DR$NNtwe ~ 80'.

Manual Inkhthn a.. v,': ~: <;,; t,"c ~ ~ ~ C~c

<X k'lr<1 i~~ ~

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

ISOthilaN ACIINIIQN INSIRIWENlhIION SNVElltANCE RE IRLHENIS CIIANNEl OPERAIINAl CIIANHEl fljNCTIQNAl CIIANEl '{NOI'5lNS fQR NICH lRIP fNCIIQN CIIEN IESI CAllBRAIIOH SIJRVKllUNCE RE INEO S. RIACIOR CORE I50iAIIOH CMllHG SYSIIH ISOLAIIOH g

a. RCIC Steaa line h Prcssure - High 'Nh I, 2, 3

b. RCIC Steaa Supply tressure-lat 3

c. RCIC Turbine Exhaust Oiaphrage Pressure - High l,2,3

d. RCIC Equipeent 1ooa leeperature - High

e. RCIC Equi poent aooe OAO h leepcrature . High Q

t. RCIC Pipe Routing brea Ieeperature - High

9. NCIC Pipe Routing Area h Beperature - High .

h, i.

~

RClC Eeergency Area leoperature - High Manual Initiation Cooler.

.Nh ', .N-:.-

Q,'h

'N.

.j., Oryal I tressure - High

6. IIIGH tRESSNE COOlANI INECI ION SYSI EN ISOlhllON Pi . '."-a.>s:- NCI Steaa line h

".';.;:" Pressure - High I, 2, 3

b. HPCI Steaa Supply wg4 Pressure - ltd I, 2, 3 Ze g

c. IIPCI Iurbinc Exhaust Ql OiaIIhraga Prcssure - Illgll

-C C

TABLE 1.3.2.1-1 {Contfnved)

ISOLATIOIIIACTUATION INSTauSSESraTIoa SuaVEIaaaCE aEaulREMerrS CHANNEL CHANNEL CHECK RNCTIONAL TEST IConthuedl

d. HPCI Equipment Room Temperature - IIgh 1,2,3

~. !%}CI Egutpment lloom h Temperature - Iggh 1.2,3

f. II}CIEmergency Area Cooler Temperature - Sgh 4 1I 2.'3

g. II}CIl}lpe Routhg Area Temperature - IIgh 1,2.3 t ~ r 'tI

~ ~

h. SCI Ape Routhg Area h Temperature - Iggh 1,2, L Manual Inltlatke NA. 1,2,3 I / ~

~ P ~

Drywei heasure ~ Iggh Ii2,3

7. IIHIISYSTEM SHtfTDOWN COOLNOh%AD StftAY MODE ISOLATION Reactor Veaaal Water Level - Low, Level 3 8

'. Reactor Veaaal hearne - Iigh gIIICut& Permhalve) ra;; 4

~,}

w,

'1 ~ 2t 3 t,t .t '!$:

c. RHR Row - IIgh .,; 'I,2,3

d. Manual InNadon NA ..'- ..NA ., ~ '1) 2t 3 vr tr'r:,g }8 rlj}tr}

~. Drywal heaaee - IIgh . NA ;- II le 2o 3 " ";~ r~'4' When eny @abbe atop valve la open.

'When VENTIIGor PURGING the dryweg per fhatbn 3.11.2.8.'pP, When hanalng IrraSated fuel ln e>> aecondary containment and dwfng Col% ALTERATIONS end operetta whh a potential for draaeg the reactor

Extending STls and AOTS for Susquehanna Technical Spec%cation Instrumentation Unit 1 TS 3.3.3: Emergency Gore Cooling System Actuation Instrumentation

0 TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION D

C x MiNBjst/M OPERABLE cHANNELB PER TIBP SYSTEM APPUCABLE OPERATIOI/AL COIIDITION8 ACTIOff TRtP FUNCTION Z

Z

1. CORE SPRAY SYSTEM I

2tal Z a. Reactor Vessel Water Level - Low Low Low, Level 1 1,2,3,4,6 30

b. DrywaN Pressure~ High 2tal 1, 2, 3 30

c. Reactor Vessel Steam Dome Pressure ~ Low tPermlsslvel 2lal

d. Manual Initiation 1/subsystem 1,2,3,4,6

2. LOW PRESSURE COOLANT INECTION MODE OF RHR SYSTEM

e. Reactor Vessel Water Level - Low Low Low, Level 1 2tal 1,2.3.4,6 30

b. Drywel Pressure - High 2tal 1,2,3 30

c. Reactor Vessel Steam Dome Pressure ~ Low IPermlsslve) 1l System Initiation 2tal 2I Recirculation Discharge Valve aosure 2tal 4

1~2.

.6

)

~ ~

.d. Margret initiation 1/subsystem 1.2,3,4 .6

3. HIGH PRESSURE COOLANT INECTION SYSTEMS

e. Reactor Vessel Water Level - Low Low, Level 2 2ta) 1, 2, 3 30

b. Drywall Prasswe - High 2tal 1.2,3 30 B c. Condensate Storage Tank Level - Low 2iaitbI 1.2,3

d. Suppression Pool Water Level - High 2tal 1,2,3

e. Reactor Vessel Water Level - High, Level 8 1.2,3 Z

O f. Manual initiation 1/system 1,2,3

TABLE 3.3.3-1 {Con)IttuedI EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION i&IONMOPEttASLE CHAIORLS AffLICASLEOffttlytONAL TM f UatcTtoH ~ Etl TM SYSTEM COIITtgttS ACTION

i. AUTOMATtCDFPRESSURt2ATNH SYSTf M a Reactor Vessel Water Level - Low low Low, level I I.2.3

h. Dryweg Pressree. High I. 2, 3

c. ADS Timer I. 2. 3

4. Core Spray Pump Discharge Presaiae. High )Permissive) 2t I.2,3

~. Rt tR LPCI Mode Pump Discharge Pressure ~ High I.2,3 IP>>mhalve)

1. Resctot Vessel Water Level ~

low. level 3 )P>>missive) ).2,3

$. ADS Diyweb Pteasrae Bypass Timer ),2,3

h. Manual Inhitrtt l.2. 3 33 CHANNELS L Manual Initiation IIvalve ).2,3 33 IMWMUM TOTll HO. CHAlOKLS Of CHANISLS TO~ OPERAS

$. LOSS Of POWER

~. 4. Id iv ESS be Under voltage I,2,3.I .S

)loss ol Vohage, c 20%)

h. ~ .IB irv ESS Bus Under vohage ),2. 3.i, S

)Degraded Voltage, c BS%)

o. I. 18 irv ESS be Under vottage I. 2, 3, 1, S 38

)Degraded Voltage, c $ 3%)

480V ESS be OB555 Under votlage 2ltrre I,2,3,d,S d.

)Degraded Voltage. c 55%i fff

~. 4SOV ESS be OBSBS Urrrter voltage lltxe l,2,3,4 .5

)Degraded Voltage, c $ 2%)

fsf See footnotes enneat page.

C TABLE 3.3.3-1 (Continued) m x EMERGENCY CORE COOUNG SYSTEM ACTUATION INSTRUMENTATION zR la) 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 rebecS:5-I +lo4 (P Zg~r .

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 TABLE 34&1 (Cotttinuadl ACTION 30-XS 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 Volt DC 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. 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 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:

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

b. 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) if both HPCI and RCIC are OPERABLE, place the inoperable channel(s) in the tripped condition.

d. If ACTION 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. If ACTION 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. 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,

b. Within one hour of discovery of loss of initiation capability declare HPCI inoperable ifthe associated pump suction is not aligned to the suppression pool.

C. If ACTION 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 EHERGENCY CORE COOLiNG SYSTEH hCTUhllON TNSTRUHENTATlON SURVElllhNCE BE UlBEHEHTS CNNNEL OP ERAT lONAi.

CHANEL FUHCTlONAL . CNWEL CONnlTTONS FOR NTCH TRIP FlNCT lON CIIECK TESI ChllORKI ION SURUEIllhNCE RE lllREII

l. CORE SPRAY SYSTEH W

a. Reactor Vessel Mater level "

Los lm Los, level 1 S l, 2, 3, I>>, 5>>

b. Or@tell Pressure - High NA C. Reactor Vessel Steaa Ooae Pressure - Lmr HA l, 2, 3 4>>, 5>>

d. Kanual initiation HA 20 lOM PRESSURE COOlhNT 1HJECTTON NOE OF RHR SYSTEK

a. Reactor Vessel Mater i.evel-I l.ov le Lo~, Level l 5 lo 2o 3o I>>o 5"

b. Orywell Pressure - High HA lR 2R 3 C. Reactor Vessel Steaa Ooie Pressure - Low i) Systea Initiation lR 2, 3, 4>>, 5>>

2) Recirculation Oischarge 1, 2, 3, 4>>, 5>>

Valve Closure

d. Kanual initiation HA lo 2i 3R 4*o .5>>

3. NION PRESSURE COOIKNE INIECEION SUSSEX ao Reactor Vessel Mater level-Low Los, level 2 S 1, 2, 3

b. Or@tell Pressure " High HA C. Condensate Storage Tank Level-Lov Nh l, 2, 3

d. Suppression Pool Mater i.evel-fligh ~

HA l, 2, 3 Reactor. Vessel Mater level-lligh, Level 8 Nh Q l, 2, 3 Kanual initiation Nh NA l

TABLE 4.3.3.1-1 (Contintted)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSURVEILLANCE REgUIREINENTS m

x CHANNEL CHANNEl CHANNEL OPERATIONAL CONOTTION5 zz TAP FUNCTION CHECK FUNCTIONAL TEST CALRIRATION FOR yrNCH 5URVER.LANCE REQTINEO

4. AUT'OMATICOEPRESSURIZATON SYSTEM C

R a Reactor Vessel Water I.evel low Low low, level

~

1 1,2,3

b. Orywell Pressure High I,2,3

c. ADS Timer 1.2,3

d. Core Spray Pump Discharge Pressure - High 1,2,3

e. RHR lPCI Mode Pump Discharge Pressure ~

High NA 1. 2, 3 I. Reactor Vessel Water level low, Level 3 1,2,3

g. ADS Orywell Pressure Bypass Timer NA 1. 2,3

h. Manual Inhibit I. 2. 3 I. Manual Initiation 1. 2, 3

5. LOSS OF POWER

a. 4.18 kv ESS Bus Undervoftage ILoss ol Voltage) 1~ 2e 3r 4 ~ S

b. 4.18 kv ESS Bus Undervoltage IDegraded Vdtegel le 2o 3e 4 ~ 5 c.

S2W>>'A 4.18 kv ESS Bus Undervdtage IDegreded Voltage)

d. 480V ESS Bus OBS85 Undervoltege IDegreded Voltage e.

c

< 85~v>>

480V ESS Bus 08585 Undervoltage IDegraded Voltage When the system fs required to be OPERABLE. after being manually realigned, as applicable, per Specification 3.5.2.

1.2.3,4 1,2,3,4,5 1,2,3,4 .5

. S 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, X

O 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 IM 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

TABLE 3.3.3-1 I

EMERGENCY CORE COOLING SYSTEM ACTUATlON INSTRUMENTATlON IwriNwla opERAILE cHAttNRs APPtlCASLE OPERATtONAL TAP FUttCTION Pal TRP SYSTBl COrtDtttOIQ

1. CORE SPRAY SYSTEM

~. Reactor Veaael Water level - Low low Low, Level I 2ta) 1.2,3,4,5

b. Drywei Prea¹re - Ngh 2tal 1. 2,3 30

c. Reactor Veaad Steam Dome Prea¹ee - Low tPermtutve) 2tal 1,2,$

4,5

d. Manual tntttatton tlaubayatem 'l,2.3,4 ~ i 5 ~

2. LOW PRESSURE COOLANT tNJECTION MODE OF RHR SYSTEM

e. Reactor Vyaaet Water Level - Low Low low, level 2tal 1

1,2,3,4,5

b. Drywal Preaaue - Ngh 1,2,3

c. Reactor Veud 8!sam Dome Preutae ~ Low tPermtaatve) 1l Syatem Intttatton 2tal tt 2, 2l Rectrcutatton Dtacharge Vatve Cto¹re 2tat 4,5 )

tl 2, 4,5 )

d. Manual Intttatton tiaubayatem to 2,$ ,4 4 33

3. NOH PRESSURE COOLANT NJECTtON SYSTEMt

e. Reactor Veaael Water Levd Low Low, Level 2 1,2,$

Dr ywae Prea¹ee - Ngh 1. 2, 3

o. Coetenaate Storage Tantr Level - low 2taltbl 1,2.$

SuppreaatonPool Water Level - Ngh

tal

d. 1,2,$

e. Reactor Veaael Water Level - Ngh, Level 5 1,2,3 31

l. Manual tntttation 1/ayatem 1, 2, 3

TABI.E 3.3.3-1 {ConthlUed)

EMERGENCY CORE COOUNQ SYSTEN ACTUATION INSTRUNIENTATION MlilrjalOfiltlCHAIIIRtS tfllflW SySTQI

4. AUTOMATlCOKPl%$ SUAQATSN SYSHM ee

a. lleactor Veeael Wall Level - Low Low Low, Level 1 1.2. 3 Orywe0Preeaee- lleh 'I. 2. 3

1. 2. 3

4. Core Spray fuey INecharee Ptealae - Sgh tParrnieatve) l. 2. 3 2'0%ie

~. SNLPQ Mo4e Peep Oiecharee Preaerne - Hah 1,2,3 lPermiealvel I. Ileaclor Veeael Weler Level - Low, Level 3 lPermieafvef 1.2,3

0. AOS Orywel Pleelne Sypaea Timor 1, 2, 3 31 1,2,3 33 1.2.3 IMROJM AHtCMLS TOTAL IIOo C81NIR0 CHAIOKLS OtNATNNAL Of CHANNKLS TO~ OfQMN CMOITIDRS

0. LOSS Of POWN

o. 4.10 hi SSS 0LN Lhasa volle0e l. 2,3,4 ~ 0 Sess ol Velta0e, C 2D%l L 4.10 hr ESS 0Lre Un4er volta0e 1,2.3.4,5 ge0raM VChaee. c 0%%)

o. 4.10 hr NS 0Lre Un4er voiraae l. 2. 3, 4, 6 geara4e0 Veloce, c 03%i 2,3.4,5 I

4 I

40DV ASS 0ue O0iSi Under.voNa0e

~va .~0Salf>>

la

~ 40OV CSS 0oe O0606 Ue$ er vorrarre 1.2.3.1,6

~g IDelerrei Voiraee. C 02%1 fee

-Ceo foe~ac enact. - ~

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. Teart~ abc 8.5.8 I, hfsfe (Q Ic) Two out of two logic.

(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 7am s.s.s-Not required to be OPERABLE when reactor steam dome pressure is less than or aqua} to 160 pslg. 4oke g)

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.,

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.

TABLE 3DW1 (Cotttfnuad)

ACTION 3 ACTION 31 CRr ~ad ~

ACTION 32 r Amyl 32 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 FUNCTIONAL TEST.

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

c) With both channels inoperable on the 4&OV ESS 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) if both HPCI and RCIC are OPERABLE, place the inoperable channel(s) in the tripped condition.

lf ACTION 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. If ACTION 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.

If ACTION 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

's CHANNEL OPE Rhl lOHAI X

IRIP fUNCIIGN CHANNEl.

NECK FUHC1 lOHAL IESl CtlANNEl Chl l BRhl lOH CONG lllONS FOR slllCfl SURVE I llANCE RE lRED t'.

~

~ l. CORE SPRAY SYS1EII

a. Reactor Vessel Mater l.evel-los let lee, lave) 1

- High S l, 2, 3, 1>>, 5>>

Or~ll tressure HA

c. Reactor Vessel Stem Ooae I'ressure - tm ls 2s 3, I>>s 5>>

d. Ihnual Initiation

2. lOM PRESSURE CNLNIT INECflOII NOE OF RN SYSTEII

a. Reactor Vessel Mater level-Cal los lm lan, level l 5 2s 3s 4>>s 5>>

b. Or@sell tressure - High IN C. Reactor Vessel Stem Oooe I tr~ssure - ler l) Systea initiation ith l, 2, 3, i>>, 5

2) Roc I rcuiat ion Discharge Vaive Closure N'A l, 2, 3, 1>>s 5>>

d. manual initiation N l, 2, 3, 1>>, 5>>

IIIGN I'RESSIIRE COOIIN ILIECIIRN Sf SIEII Reactor Vessel Mater level-ler lcm, level 2 ls 2, 3

b. Orpull tressure - High l, 2, 3 Co Condensate Storage Tonk level-ler Suppression tool Mater leva)-

(jy Q@ 1, 2, 3 High 0 l, 2, 3

e. Reactor Vessel Mater level-High, level e l, 2, 3 Ieanual initiation ls 2, 3

TABLE 4.3.3.1-1 ICottflnuedI EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATIONSURVEILLANCE REQUIREMENTS C

m x CHAIIIIR OPEIIATIOIIAlCOIIOITTOIIS Taa'UIICTION FUIICTIONAL FOll WIOCII NIN%ktANCE zz TEST TIEQUIaKD

4. AUTOMATlCOEPRESSIJRIZATON SYSTEM a C

z a. Reactor Vessel Water Level - Low low low, Level 1 I. 2, 3

b. Orywei Pressure ~

High l,2,3

c. AOS Timer a 1. 2, 3

d. Core Spray Pump Discharge Pressure - High 1. 2. 3

e. RHR LPCI Mode Pump Discharge Pressure - High 1, 2, 3

f. Reactor Vessel Water level Low, Level 3

~

1. 2. 3

g. AOS Orywei Pressure Bypass Timer 1.2,3

h. Manual tnhfbft 1. 2, 3 L Manual initiation 1. 2. 3

5. LOSS OF POWER

~. 1.1B kv ESS Bus Undervoltege ILoss of Vdtagel 1, 2. 3. 1 .5

b. 4.10 kv FSS Bus Undervoltage g)egraded Voltage) l. 2. 3, 4, 5

c. 4.1B kv ESS Bua Undervdtage IOegraded Voltage) I,2,3,4,$

d.. 450V ESS Bus 0B555 Undervoltage fDegraded Vdtage f, 2, 3, 4 , 5 c eSSIF"

e. 4$ 0V ESS Bua OB585 Undervoltage lDegraded Voltage 1,2,3,4,5 c $ 2%>nt 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.

,O 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 tri p 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 if the 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. If ACTION 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 NIRIIIUII OPERABLE CHAlgfLS TRIP FUNCTION PER TRIP SYSTEH C

M 1. Reactor Vessel Water Level-Low Low, Level 2

2. Reactor Vessel Steam Dome Pressure - High (a) One channel or trip system may be placed in an inoperable status for up t hours for required Ca) 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.

I

5 RCULA lO lNP Rl ACTUATlON l NSTRtNENTATION SURVE llAHCE RE I REHENTS CINHHEL' CHAHHEl UHCT IOHAI. CINHHEl N ~III UCI CIIECK TEST CALISRATION

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

2. Reactor Vessel Steaa Ooae Pressure - IIlgh NA

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.-'.

OPERABLE wi 1 uefr rfp setpoints set consistent <<f"o values snown !n -we 1-'nal':e 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 nex LE status wfthfn 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in 6 hours.

it least RTVP within 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 hours.

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 UNI i 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 if the 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. 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 .

e. If ACTION 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 ATMS RECIRCULATION PUMP TRIP SYSTBI INSTRUMENTATION HIHIHUH OPERABLE CHAg)LS TRIP FUNCTION PER TRIP SYSTEH

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

2. Reactor Vessel Steam Dome Pressure - High (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.

CAB I

EAR

0 AlMS RECIRCULATION PlNP TRIP ACTUATION INSTRNtENTATION SURVEILlAHCE RE IRENENTS CfNNHEL CNXHEL FUNCTIONAL CNNNEL TRIP FUNCTION CHECK TEST CAI.IBRATION Reactor Vestal lhter level- K 5 low le, level 2 Reactor Vessel Steaa Ooe Pressure - High

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 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 msew4

+r(ox)S

1. If the fnope channels consist o ne turbine control valve channel ind one fne stop valv annel, place both inoperable 3.5.4;2 channels fn the tripp condft within one hour.

2. If the fnoperabl ~ channe lude two turbf ne control valve channels or two turbf stop ve channels, declare the trip systaa f noperable.

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.

lt SUS)UEHANNA - UNIT 1 3/4 3-40 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 If the 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 limit specified 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 limit for inoperable EOC-RPT as specified in the COLR and take the ACTION required by Specification 3.2.3.

e. If ACTION 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 THERMAL POWER to less than 25% of RATED THERMAL POWER.

NLK 3.3.i.t-l BD-GF-CYCLE RECIRCULATIN PINP TRIP SYSTOI IHSTRlNENhTION HIHINN OPERABLE CIINllEQ)

TRIP RNCTIN PER TRIP SYSTEH I. Turbine Stop Valve - Closure 2(b)

2. Turbine Control Valve-Fast Closure 2(b) lHFBIPPV Vb p1 dl I~ dl il provided that the other trip systeN is OPERhlLE.

1 et h f . 0 I d (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

~

CHANNEL FUHCTIONLL CNINKL TRIP FlNCTIN TEST CALIBRATI Turbine Stop Valve-Closure

2. Turbine Contml Valve-Fast Closure

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.

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.

c. Mith the er of OPERABLE channels two or more less required by the Mini OPERABLE Channels per Trip System re nt for one ACrtcx40 trip system an .

S.w 4.a 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.

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 I status wfthin 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. 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 if the inoperable channel(s) is not the result of an inoperable breaker.

C. 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 limit specified 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 limit for inoperable EOC-RPT as specified in the COLR and take the ACTION required by Specification 3.2.3.

e. If ACTION 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 THERMAL POWER to less than 25% of RATED THERMAL POWER.

TAILE 34'-1 ENlhO~CLE RECfRCULATlON PUiN'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 CINHHEL fUHCTTONl 'RIP CINWKl INIIIIIR TEST ~IIII Rll Sl T. Turbine Stop Va)ve-Closure

2. Turbine Control Valve-Fast C)osure

Extending STls and AOTS for Susquehanna. Technical Specification Instrumentation Unit 1 TS 3.3.5: Reactor Core Isolation Cooling System Actuation Instrumentation

EAR TABLE 3.3.5-I REACTOR CORE ISOLATION COOLIHG SVSTEH ACTUATION IHSTRUHEHIATION HIHINN I OPERABLE CIIAHHEl.f EUNCT IONAL UNITS PER IRIP SESIEH i ACEIOH

a. Reactor Vessel Mater Level - Low Low, level 2 2 50

b. Reactor Vessel Mater Level - High, Level 8 2(b)

c. Condensate Storage Tank Mater Level -. Low 2(c) 52

d. Hanual Initiation I/systeJ")

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

'(b) One trip systea with two-out-of-two logic.

(c) One trip systea with one-out-of-two logic.

(d) 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-~~

Sa AClloQ 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(y pJ 5Q ACTION 53- Nth the number of OPERABLE channels one less than re ired by the Nnimum OPERABLE Channels per Trip System Zrdmg Acrsev 69 ~ '

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. If ACTION 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 CIIAHHEL CINNIIEL FUNCTlONI. CHNHEL Q fUHCl'IONL UHITS GIKKK TEST CALIBRAT ION a Reactor Vessel lhter level-ly Los, level 2 R

b. Reactor Vessel Water R level - IIIgh, level 8

c. Condensate Storage Tank Mater Level - Low

d. lIanual In)ttatkon

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 MIHINN GPEINBN CINNEL)

FNCTIONL UHITS PER TRIP SYSTEH

) ACll0$

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

b. Reactor Vessel Mater l.evel -. High, level 8 2(b)

c. Condensate Storage Tank Mater level - le 2(c)

d. Hanual Initiation I/systea(") 53 placing the itrip pi*

systea i i ii \ e in the tripped condition provide hours least for required surveillance without one other OPENBlf channel In the 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.

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 fifth 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 - 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. If ACTION 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' 1

t 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 ClNHNEL CNNBEL ' FWCTIOHAL ClfNHEL FlNCTTOHAL UHTTS Rill t ~URH

e. Reactor Vessel Mater level-ler lee, Level 2 R

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

c. Condensate Storage Tank Mater Lave) - Los

d. Hanual lnitlatfon

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 with the Trip Setpoint value~

~h its trip setpoint adjusted consistent

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~)

'Fog'c$ ~r~

n,g~ Qp/n~<g w an inopnragla caweil(Nagms o Leut p~<~~

c ~nQ~ +"

Inr >p 6s ~ ~r+

p Ws~

g~ ~ CKfNS<F p gv g g gf fggg o g

'+""5~ ~"

C I I C 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 THERMAL POWER 2 30% of RATED THERMAL POWER.

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 THERMAL POWER.

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 IAM channels 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

TABLE 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCE REQUIREMENTS P OPERATIONAL CONDITIONS C CHANNEL CHANNEL TRIP FUNCTION CHANNEL CHECK FUNCTIONALTEST CALIBRATION FOR WHICH SURVEILlANCE REQUIRED R

R ROD BLOCK MONITOR a, Upscale NA Q 1~

I C b. Inoperative NA Ib) NA Z c. Downscale NA Q 1~

2. APRM

a. Row Biased Neutron Flux-Upscale 8 SA 1

b. Inoperative NA NA 1,2,6I ~ ~

c. Downscale S SA 1

d. Neutron Flux - Upscale, S SA 2 60 ~ ~

Col Startup

3. SOURCE RANGE MONITORS CP a. Detector not full in NA s/UIb),w NA 2,6 Ql b. Upscale NA s/ulb),w Q 2,6 Ql

c. Inoperative NA 8/ulb),w NA 2,6

d. Downscale NA Q 2,6 8/ulb),w

4. INTERMEDIATERANGE MONITORS

a. Detector not full in NA 8/u~),w NA 2,6

b. Upscale S 8/utb),W Q 2,6

c. Inoperative NA NA 2,6 8/utb),W

d. Downscale S Q 2,6 s/u'b',w

5. SCRAM DISCHARGE VOLUME

a. Water Level-High NA 1 2,6I~

B. REACTOR COOLANT SYSTEM RECIRCULATION FLOW

a. Upscale NA Q b.

c.

Inoperative Comparator NA NA

"~a~ NA Q

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 tr 6s p sys4lh I~

leos) ohe c44er 6PXRASQ a,Ronne,) lw hays~ Is INssu4aclg ~4cch pQrswc~.

~

'Hlc 4v'ppcL cschLWIcrI pracic4$

.za.~ +)p gf

~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 THERMAL POWER 2 30% of RATED THERMAL POWER.

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 THERMAL POWER.

(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

TABLE 4.3.6-1 ro CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCE REQUIREMENTS C

P C CHANNEL CHANNEL OPERATIONAL CONDITIONS m

x TRIP FUNCTION CHANNEL CHECK FUNCTIONALTEST CAUBRATION'" FOR WHICH SURVEILLANCE z

R ROD BLOCK MONITOR REQUIRED I

a. Upscale NA SA 1~

b. Inoperative NA NA 1

~

c. Downscale NA b SA

2. APRM

a. Flow Biased Neutron Flux-Upscale (b)

S SA 1'al 1

b. Inoperative NA NA 2 60 ~ ~

c, Downscale S b) SA 1

d. Neutron Flux - Upscale, S SA 2 60 ~ 0 Startu 4 3. SOURCE RANGE MONITORS Cal a. Detector not full ln NA s/UIb),w NA 2,6 Ql b. Upscale NA SA QI s/ulb),w 2,6

c. Inoperative NA NA 2,6

d. Downscale s/uib),w NA .SA 2,6 s/uib),w

4. INTERMEDIATERANGE MONITORS

a. Detector not full ln NA s/UIb),w NA 2,6

b. Upscale S S/utb),w SA 2,6

c. Inoperative NA NA 2,6

d. Downscale s/utbi,w S SA 2,6 S/uib),W S. SCRAM DWCHARGE VOLUME

a. Water Leva)-High NA 1,2,6~ ~

8. REACTOR COOLANT SYSTEM RECIRCULAT)ON FLOW

e. Upscale NA Q

b. Inoperative NA NA

c. Comp arator NA Q

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

RADIATlON NNITORlNG lNSTRtNKNTATlON NNlNN CHNSKlS APtllCAIlK ANN/TRlF %AQNE%NT INSTRSKNTATlON OPERAS'ONDITIONS SETPOlNT Olla I Cc,')

1. Nein Cental Rooe 2/Inta'k 1,2,3,5 and * < 5 aR/hr O.Ol to lOO aR/hr Outside Air intake Radlat)on Nonktor

2. Area Nonl tora

a. Cr itfcallty Non)tora

1) Net Fuel (a) c 15 aR/hr 10 to 10 aR/ht Storage Vault

2) Spent Fuel (b) c 15 aR/hr 10 to 10 aR/hr Storage Fool

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

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

~>> II (b) Mlth fuel ln the spent fuel storage pool.

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

INSERT: Note (c) for Table 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 OPERhT IOHAL CllAHNEL COHOI LIONS FOR CINNHEL fUNCTIONAL CHANNEL Ml)CH SURVE1LI AHCE IHSTRlNEHThTIOH CIIECK TEST CAI. IS IIA110II RE UIREO

1. Hain Control Room Q.

Outside hir Intake Radiation Honitor 1, 2, 3, 5 and ~

2. brea Honitors

a. Criticality Monitors Hew fuel Storage (a)

Csl I

Vault KKK ~

2) Spent Fuel Storage S R (b)

Pool 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

TABLE 3.3.7.1-1 l/l RADIATION HONITORING INSTRINENTATION C

AD C

HININN CHANNELS APPLICABLE ALARH/TRIP HEASUREHENT INSTRUNENTATION OPERABLE COND I T ION S 5ETPOINT RANGE ACTI (c) * (c')

I 1. Hain Control Room 2/intak 1,2,3,5 and < 5 wR/hr 0.01 to 100 aR/hr 70 Outside Air Intake Radiation Honitor

2. Area Honitors

a. Criticality Honitors

1) New Fuel (a) < 15 aR/hr 10 to 10 wR/hr 71 Storage Vault

2) Spent Fuel (b) < 15 WR/hr 10 to 10 wR/hr 71 Storage Pool

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 C

Cc7 4r ~~" ~e 3.'5.'7. I-)

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 SljRVE I llANCE RE I REHENS OPKRAlIONLl CININEl CONI LIONS fOR CINNHEl SIWCTIONI. CIMNIIEl NIICII SNVEIllNICK ItltR~ Itttt II CllECK 'ESI CALIBRA IO IIIEI

1. Hain Control Room Outside Alr Intake Radiation Honitor 1, 2, 3, 5 and a

2. Area Honitors

a. Criticality Honitors Hat Fuel Storage (a)

Vault

2) Spent Fuel Storage '(b)

Pool 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 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.

b. 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 .

Co 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 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUHCTIOHAL UHIT CHECK TEST CALIBRATION. SURVEILMNCE RE UIREO

a. Reactor Vessel Water Level-}ligh

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:

FJ ae 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

b. '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 .

C. 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.

CINHHEL OPENhllOHAL ClNHHEL fOHCYIOHhl OthNHEL CNNlllOHS fOW QIIOI NC IONAL N ~CA BQAllOg S VE CE R R 8 Neactos Vessel Mates level-High

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 consequences of accidents by prescribing the OPERAB1L)TY trip setpoints and response times isolation of the reactor systems. When necessary, one channel may be inoperable for brief Yt NI h ~",~

Igg intervals to conduct required surveHlance. Some of the trip settings may have tolerances expHcitly stated where both the high and low values are critical and may have a substantial effect on safety.

ltd high h E 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 for the 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 of the 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 within its 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 of accidents that are beyond the abiBty of the o perator 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 within its 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 The REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 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 Level Low, 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 flow path from lowering the reactor vessel level to the top of the fuel.

If an 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, ACTION 27 allows the penetration flow path to remain unisolated provided action is immediately initiated to restore the channel to OPERABLE status or to 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 OPERATIONAL CONDITIONS 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 for draining the reactor vessel through the system.

0 INSERT: 8-3.3.2 CHANNEL FUNCTIONAL TEST 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 FUNCTIONAL TEST 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 for BWR 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 with General 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 FUNCTIONAL TEST 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 FUNCTIONAL TEST 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 FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing for the main Control Room Outside Air Intake 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 with General 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 consequences I

of accidents by

>>>>I 'd>>

prescHbing the OPERABILITY trip setpoints and

'd d response times for Isolation of the reactor systems. When necessary, one channel may be inoperable for brief d>>WI >>>>>>'.

intervals to conduct required sunnillance. Some of the trip settings may have tolerances expHcitly stated where both the high and low values are critical and may have a substantial effect on safety.

IF>>d>>>>1>>d>>'dl bearing on safety, are estabHshed at a level away from the normal operating range to prevent inadvertent actuation of the systems Involved.

d Leak detection temperature satpoints are selected to prevent a high energy line break by detecting

~r6M>

RHR, 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 15+Sc5 high enough to avoid inadvertent isolation caused by normal temperature transients or abnormal transients caused by non4udc conditions (such as toss of ventilation).

Except for the 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 of the 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 of the D.C. o perated 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 of accidents that are beyond the ability of the opeaeor to control. This spec>>fiication provides the OPERABILITY requirements, 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.

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 3'5 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 limiting the 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.

A fast 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 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 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 THERMAL POWER 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 first stage pressures less than the analytical limit of 147.7 psig, equivalent to THERMAL POWER of about 30%

RATED THERMAL POWER. 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 THERMAL POWER 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 fmplfcftly tested 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 3/4.3.8 TURBINE OVERSPEEO PBOTECTION SYSTEM we'll This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and 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 ns> in the event of failure of feedwater controller under maximum demand.

'53~9 SUS)UEHANNA - UNIT 2 B 3/4 3-7

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

lf an 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, ACTION 27 allows the penetration flow path to remain unisolated provided action is immediately initiated to restore the channel to OPERABLE status or to 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 OPERATIONAL CONDlTIONS 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 for draining the reactor vessel through the system.

0 INSERT: 8-3.3.2 CHANNEL FUNCTIONAL TEST 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 FUNCTIONAL TEST 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 for BWR 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 with General 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 FUNCTIONAL TEST 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 FUNCTIONAL TEST 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 FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing for the main Control Room Outside Air Intake 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 FUNCTIONAL TEST frequencies and allowed out of service times for repair and surveillance testing have been determined in accordance with General 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

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