ML20072E670

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Proposed Tech Specs Eliminating Requirement to Perform Manual Testing of solid-state Logic Independently from self-test Sys
ML20072E670
Person / Time
Site: Clinton Constellation icon.png
Issue date: 08/12/1994
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20072E651 List:
References
NUDOCS 9408230044
Download: ML20072E670 (61)
v • d • e


Text

Attachment 3

- Page 1 of 13 3/4.3 IttSTRUMEttTATI0tt 3/4.3.1 REACTOR PROTECTI0tt SYSTEM IflSTRUMEttTATI0tt LIMITING C0tl0lTI0ft FOR OPERAT10ft 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION: ,

a. For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdown Position.
1. With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
2. With two of the four channels required for any Trip Function inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already exists. The provisions of Specification 3.0.4 are not applicable.
3. With three of the four channels required for any Trip Function inoperable, take the ACTION requi. red by Table 3.3.1-1.
b. For Reactor Mode Switch Shutdown Position take the ACTION as shown in Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown .in Table 4.3.1.1-1. ]

a 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18y i I

months.lReacto protect n system ai sional log' and porti s of the i c chanr3el coinc ent logi shall be m ually teste independen of the SELF ST T at l

i cach re eling outag such that' trip fun ions are test SYSJEM duri 196st once very fo fuel cyclee. l l

  • A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for re. quired surveillance provided at least two OPERABLE channels are monitoring that parameter.

CLINTON - UNIT 1 3/4 3-1 Amendment No. 71 9408230044 940812 PDR ADOCK 05000461 P PDR l

)

Attachment 3 s

  • k to U-602297 LS-94-001 l a-W .b(. Page 2 of 13 f INSTRUMENTATI0tl COONOUlh 00 .

l REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVElltANCE REQUIREMENTS (Continued) i 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip l 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 two logic j trains such that all logic trains are tested at least once per 36 months and one channel per trip function such that all channels are tested at least once  ;

every N times 18 months where N is the total number of redundant channels. in a specific reactor trip function. l l

4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the ,

Intermediate Range Monitor Surveillance Requirements for entry into 1 J

OPERATIONAL CONDITION 2 or 3 from Operational Condition 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL )

CONDITION 2 or 3.

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CLINTON - UNIT 1 3/4 3-2 Amendment No. 79

pg {Qg ,

Attachment 3

' to U-602297 7 fdV dp

( LS-94-001

  • age 3 of D INSTRUMENTATION 3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.3.2 The containment and reactor vessel isolation control system (CRVICS) channels shown in Table 3.3.2-1 shall be OPERABLE
  • with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION: >

a. With a CRVICS channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value,
b. For CRVICS Main Steam Line Isolation Trip Functions:
1. With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
2. With two of the four channels required for any Trip Fun'ction inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already exists. The provisions of Specification 3.0.4 are not applicable.
3. With three or four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.2-1.
c. For other CRVICS Isolation Trip Functions: i
1. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in -

the tripped condition ** within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The provisions of 3 Specification 3.0.4 are not applicable.

  • For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance provided at least two OPERABLE channels are monitoring that parameter.

For other CRVICS Isolation Trip Function, a channel may be placed in an in- '

operable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance provided the requirements of Table 3.3.2-1 are fulfilled.

    • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable j channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION  !

required by Table 3.3.2-1 for that Trip Function shall be taken.  !

CLINTON - UNIT 1 3/4 3-11 Amendment No. 85 o

Attachment 3 to U-602297  ;

LS-94-001

  • Page 4 of 13 JNSTRUMENTATION CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING C01DITION FOR OPERATION (Continued) 3.3.2 EIiON (Continued):
2. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system
  • in the tripped condition within I hour and take the ACTION required by Table 3.3.2-1.

SURVElltANCE REQUIREMENTS 4.3.2.1 Each CRVICS channel shall be demonst' rated OPERABLE by the performance' of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be per'ormed at least once per 18 Y

_ months. \ CRVICS ain steam line isol tion divisicnal logic and porti ns of the chann coinc ent logic all be m ually test indepe ent of t SELF TEST SYST durin e.ach refu ing outa . Each of he two p system or

}div'sions the CRVI trip sy em logic st 1 be al rnately d manuall t ted i ependent the SELF EST SYSTE uring e ry other efueling utage. All manua testing all be com eted su that all rip funct) ns are te ted at le t once ev y four fu cycles j 4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train tested at least once per 36 months, and one channel per trip function such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific CRVICS trip function.

  • The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both i systems have the same number of inoperable channels, place either trip l system in the tripped condition. '

1 CLINTON - UNIT 1 3/4 3-12 Amendment No. 71

Attachment 3 e . to U-602297 LS-94-001 1

. INSTRUMENTATION Page 5 of 13 l 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDTTION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.

APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

a. With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.3-2, 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 one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
c. With .either ADS trip system "1" or "2" inoperable, restore the inoperable trip system to OPERABLE status within:
1. 7 days, provided that the HPCS and RCIC systems are OPERABLE, or
2. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, provided either the HPCS or RCIC systems are inoperable.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to s 100 psig within the following 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

SURVElllANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once_ per 18 months. \Th actuation system log 1 associated w h each of tn LLL5 r div' ions sh be manu y tested i dependent of e SELF TEST STEM d ng alt ate refue ng. outages uch that all ivisions an all trip Lfnctions/aretested t least on every four el cycles.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the 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 months where N is the total number of redundant channels in a specific ECCS trip system.

CLINTON - UNIT 1 3/4 3-33 Amendment No. 71

Attachment 3

, IrlSTRUMENTAT10tj Page 6 of 13 END-OF-CYCLE RECIRCULATI0fl PUMP TRIP SYSTEM INSTRUMENTATION

[lMITING CONDITION FOR OPERATION j 3.3.4.2 The end-of-cycle recirculation pump trip (E0C-RPT) system instrumen-tation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

MPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is 2 to 40% of RATED THERMAL POWER.

ACTION:

a. With an end-of-cycle recirculation pump trip function instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.
b. With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
c. With two of the four channels required for any Trip Function inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip function already exists. The provisions cf Specification 3.0.4 are not applicable,
d. With three of the four channels required for any Trip Function inoperable, reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVElltANCE REQUIREljENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations at the frequencies shown in Tabl e 4.3.4.2-1.

4.3.4.2.2 _ LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per F

_18 months.1 D' isional ogic and p rtions of he channel incident logic ' 'I f shal be man 11y tes id indepen nt of th ELF TEST SY EM during each re eling o age suc that all ip functi ns are test at least once very Lf ur fuel ycles. j =

CLINTON - UNIT 1 3/4 3-52 Amendment No. 71

4 jg p{)

  • Attachment 3 to U-602297 H IflSTRUMENTATION b id '/ f LS-94-001 1 C40i nueY e/ .

00 .

Page 7 of 13 1 END-OF-CYCLE RECTRCULA N PUMP TRIP YS . INSTRUMENTATION  ;

I SURVEILLANCE REQUIREMENTS (Continued) 4.3.4.2.3 The END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.4.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least'the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months. The measured time shall be added to the most recent breaker arc suppression time and the resulting END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be verified to be within its limits.

4.3.4.2.4 The time interval necessary for breaker arc suppression from energization of the recirculation pump circuit breaker trip coil shall be measured at least once per 60 months.

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l CLINTON - UNIT 1 3/4 3-53 Amendment No. 74

u tachment 3 e

to U-602297 LS-94-001 Page 8 of 13

, INSTRUMENTATION 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-tion channels shown in Table 3.3.5-1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 150 psig.

ACTION:

a. With an RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.5-2, 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 one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1.

SURVEILLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.1-1.

4.3.5.2 _ LOGIC SYSTEM FUNCTIONAL TESTS shall be norfnrmod at least once Der 18_9La

. months. All CIC act tion sysMm logiyshall bef.anually/ tested ind endent 7 M such Vat all Vip functWns are fested at 1 stoncej f(~ofyie5ELFTESTSYS ev/ry fou fuel cy es.j l

CLINTON - UNIT 1 3/4 3-58 Amendment No. 71

~

Attachment 3 d '

to'U-602297 )

' INSTRUMENTATION Pes.'ded COAYSOU' 7 00

[e r{ , LS-94-001 Page 9 of 13 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION 1

i LIMITING CONDITION FOR OPERATION 3.3.9 The plant systems actuation instrumentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2.

APPLICABILITY: As shown in Table 3.3.9-1.

ACTION:

a. With a plant system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.9-2, 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 one or more plant systems actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.9-1.

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CLINTON - UNIT 1 3/4 3-97 Amendment No. ff), 71

. . . _ ~ _ . . . -- _. .. . - _ .

Attachment 3.

, INSTRUMENTATION Page 10 of 13 PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.9.1 Each plant system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.1-1.

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per j%#

_18 months. FEac trip syst or divis' n of the p1 nt system ac uation logic Easso 'ated wit the Nucle r System P tection Syr em shall be anually test indr sendent the SELF EST SYSTE during sepa ate refuelin outages such th- all di sions and 11 trip f ctions are ested at le t once every our y uf.el cycle .f-- -

CLINTON - UNIT 1 3/4 3-98 Amendment No. 40 71

~ Attachment 3

. . to U-602297 pg ,

LS-94-001 Page 11 of 13 REACTOR COOLANT SYSTEM 7(dv' / h O

3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 The safety valve function of at least six of the following valves and the relief valve function of at least five additional valves, other than those sat.isfying the safety valve function requirement, shall be OPERABLE with the specified lift settings; and the acoustic monitor for each OPERABLE valve shall be OPERABLE.*

Number of Valves Function Setpoint** (psig) 7 Safety 1165 11.6 psi 5 Safety 1180 11.8 psi 4 Safety 1190 11.9 psi 1 Relief 1103 15.0 psi 8 Relief 1113 15.0 psi 7 Relief 1123 15.0 psi APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety and/or relief valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With one or more safety / relief valves stuck open, provided that suppres-sion pool average water temperature is less than 110 F, close the stuck open sa'fety/ relief valve (s); if suppression pool average water tempera-ture is 110 F or greater, place the reactor mode switch in the Shutdown position.
c. With one or more safety / relief valve acoustic monitor (s) inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least' HOT SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
  • One relief valve pressure actuation channel and/or one acoustic monitor channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the purpose of performing surveillance testing in accordance with Specifica--

tions 4.4.2.1.1 and 4.4.2.1.2.

^^ The lif t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

CLINTON - UNIT 1 3/4 4-9 Amendment No. 71

- . , -- . . . . - . . ~ - - .. ._. - - . . .. - . - .

Attachment.3

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, , REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES l

SURVEILLANCE REQUIREMENTS i 4.4.2:1.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE by performance of a:

a. CilANNEL FUNCTIONAL TEST at least once per 31 days, and a
b. CIWINEL CALIBRATION at least once per 18 months.*

4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CilANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least once per 92 days.
b. CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at 'least once per 18

. months. J Each o? the two trip system; or civisi ns of the clief val func ton actua lon logi associatec/with the N clear Syst m Protect n (Sys m shall manual tested i .ependent o the SELF EST SYSTE du ing separ to refue ing outage such that oth divis ns and al __ _}

tc annel tri s are t ted at lea t once eve four fue cyclesg-j

'The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter reactor steam pressure and flow are adequate to perform the test.

3/4 4-10 Amendment No. 81 CLINTON - UNIT 1

Attachment 3 to U-602297 LS-94-001 age 13 of 13

. REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION l' LIMITING CONDITION FOR OPERATION 3.4.2.2 The low-low set function of the following reactor coolant system  ;

safety / relief valves shall be OPERABLE with the following settings *:

Low-Low Set Function Setpointa (psig) i 15 psi Valve No. Open Close F0510 1033 926 F051C 1073 936 F047F 1113 946 F0518 1113 946 F051G 1113 946 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION: .

a. With the low-low set function of one of the above required reactor coolant system safety / relief valves inoperable, restore the inoperable low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With the low-low set function of more than one of the abo _ve' required reactor coolant system safety / relief valves inoperable, be in at least.

HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

c. With either low-low set function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least H0T SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i SURVEILLANCE REQUIREMENTS 4.4.2.2 The low-low set function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FUNCTIONAL TEST, including cal'ibration of the trip unit, at least once per 92 days, i b. CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18

_ months.I Each of the two Ip systems r division of the lo iow'ser, i

fun ion act tion logic ssociated th the Nuc ear System rotection (Sy em shal be manuall tested ind endent of . e SELF T SYSTEM d inQ

s. arate r fueling out es such tt t both div ions and I channel ips l L re teste at least a ce every f r fuel cyc s . f- _--

f

  • 0ne channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the pur-pose of performing surveillance testing in accordance with Specification 4.4.2.2.

^^The lif t setting pressure shall correspond to ambient conditions of the valves '

at nominal operating temperatures and pressures.

.CLINTON - ' UNIT 1 3/4 4-11 Amendment No. N. 71

.. . -= ,_ _. - -- . - _ - - - - - - . . -

LS-94-001 a

Page 1 of 48

. RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY f~ SR 3.3.1.1.17 NOTES------------------

1. Only applic le to the portions of the logic >sted by the Self Tes System.
2. For th - purposes of determi 'ng the STAG .1ED TEST BASIS Frequ icy, all cha iels for all Functior , are c sidered together anc 'n" equal our.

Perform LOGIC SYSTEM UNCTIONAL TEST 18 mon is on a independent of the Lel f Test System. STAGG~ ED TEST BAS a 17 SR 3 . 3 .1.1. ke' ------------------NOTES- ----------------

1. Neutron detectors are excluded.
2. The STAGGERED TEST BASIS Frequency

.l for each Function shall be determined on a per channel basis.

Verify the RPS RESPONSE TIME is within 18 months on a limits. STAGGERED TEST BASIS

, l

)

l l

l l

CLINTON 3.3-6 Amendment No. A l

1 l

Attachment 4 to U-602297 LS-94-001 Page 2 of 48

' RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reac tor Protection System Instrunentat ion CONDtil0NS APPLICABLE REQUIRED REFERENCE 0 MODES OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCIlON CONDITIONS FUNCil0N ACil0N 0.1 REQUIREMEN1S VALUE

1. Intermediate Range Monitors
a. Neutron Flux - High 2 4 H SR 3.3.1.1.1 1 122/125 SR 3.3.1.1.4 divisions SR 3.3.1.1.6 of full SR 3.3.1.1.7 scale SR 3.3.1.1.13 SR 3.3 m y ,.1.1.15, 5(3) 4 I SR 3.3.1.1.1 5 122/125 SR 3.3.1.1.5 divisions SR 3.3.1.1.13 of futt SR 3.3.1.1.15 scale i,,

7

b. Inop 2 4 H SR 3.3.1.1.4 NA SR

~ 3 . 3 .1.1.15, .

33 S

IUI 4 i SR 3.3.1.1.5 NA SR 3.3.1.1.15 7 ....

2. Average Power Range Monitors
a. Neutron Flux - High, 2 4 H SR 3.3.1.1.1 5 207. RTP Setdown SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 7 :
b. Flow Stased Simulated 1 4 G SR 3.3.1.1.1 5 0.66 W +

Thermal Power - High SR 3.3.1.1.2 67% RTP and SR 3.3.1.1.3 5 113%

SR 3.3.1.1.8 RTP(b)

SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 1 SR 3.3.1.1.17 1 7 7,, ,io (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

1 (b) Allowable Value is 5 0.66 (W 8) + 51% RIP when reset for single loop operation per LCO 3.4.1, ]

" Recirculation Loops Operating " l l

1 CLINTON 3.3-7 Amendment No. A

Attachment 4 to U-602297 LS-94-001 Page 3 of 48

. RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3) I Reactor Protection System Instrumentation I l

APPLtCABLE CONDIT10NS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CON 0!TIONS FUNCTION ACil0N D.1 REQUIREMENTS VALUE

2. Average Power Range Monitors (continued)
c. Fixed Neutron 1 4 G SR 3.3.1.1.1 5 120% RTP F lu.x - H i gh SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3,3.1.1.15 SR 3.3,.1.1.17
d. Inop 1,2 4 H SR 3.3.1.1.8 NA SR 3.3.1.1.9 SR 3.3.1.1.15
3. Reactor vesset steam Dome 1,2 4 H SR 3.3.1.1.1 5 1080 psig Pressure - High SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 c, 2 , . .

.g.

4 Reactor Vessel Water 1,2 4 H $2 3.3.1.1.1 1 8.3 inches Level - Low, level 3 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3,.3.1.1.17

- , . .g i

5. Reactor vessel Water 2 25 % RIP 4 F SR 3.3.1.1.1 5 52.6 inches Level - High, Level 8 SR 3.3.1,1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 J^  ? ? t 1 10
6. Main Steam Isolation 1 4 G SR 3.3.1.1.9 5 12% closed Valve - Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 e ,f 1 1 10
7. Drywell Pressure - High 1,2 4 H SR 3.3.1.1.1 5 1.83 psig SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15

, , . ., l (continued)

CLINTON 3.3-8 Amendment No. A

Attachment 4 to U-602297 LS-94-001 Page 4 of 48 RPS Instrumentation 3.3.1.1 table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CON 0!TIONS M00ES OR REQUIRED REFERENCE 0 OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCil0N CONDITIONS FUNCTION ACil0N 0.1 REQUIREMENIS VALUE

8. Scram Discharge Volume Water Levet - High
a. Transmitter 1,2 4 H SR 3.3.1.1.1 5 40 1/4 inches SR 3.3.1.1.9 for 1C11 SR 3.3.1.7 10 N601A,8 and SR 3.3.1.1.13 5 39 3/16 SR 3.3.1.1.15 inches for

_  : IC11-N601C,0 5(*) 4 i SR 3.3.1.1.1 1 40 1/4 inches SR 3.3.1.1.9 for ICII-SR 3.3.1.1.10 N601A,8 ant SR 3.3.1.1.13 5 39 3/16 SR 3.3.1.1.15 inches for

: ictl N601C,0
b. Float Switch 1,2 4 H SR 3.3.1.1.9 s 763 ft. 3 1/4 SR 3.3.1.1.13 inches mst for SR 3.3.1.1.15 ICII N013A,8 5(a) 4 i SR 3.3.1.1.9 5 763 ft.

SR 3.3.1.1.13 1 11/16 inches SR 3.3.1.1.15 mst for LC!!-

~^ ' ' ' ' ' '

N013C,0

9. Turbine Stop Valve closure e 40% RTP 4 E SR 3.3.1.1.9 s 7% closed SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

, ; . .n 10 Turbine Control Valve 2 40% RTP 4 E SR 3.3.1.1.9 2 405 psig Fast Closure, Trip Oil SR 3.3.1.1.13 Pressure - Low SR 3.3.1.1,15 SR 3.3.1.1.16 SR 3,3.1.1.17

, , . . . s

11. Reactor Mode 1,2 4 H SR 3.3.1.1.12 NA Switch - Shutdown Posi tion SR 3.3.1.1.15 -
. 3.

5(a) 4 i SR 3.3.1.1.12 NA SR 3.3.1.1.15

,2 4 4 i,
12. Manual Scram 1,2 4 H SR 3.3.1.1.9 NA SR J, . 3.1.1.15, 5(') 4 I SR 3.3.1.1.9 NA SR 3.3.1.1.15

. I (a) With any control rod withdrawn f rom a core cell containing one or nere fuel assemblies.

CLINTON 3.3-9 Amendment No. A

Attachment 4 to U-602297 LS-94-001

. Page 5 of 48 E0C-RPT Instrumentation 3.3.4.1 l l

SURVEILLANCE REQUIREMENTS (continued) I SURVEILLANCE FREQUENCY SR 3.3.4.1.5 ------------------NOTES------------------ l

1. Breaker interruption time may be I assumed from the most recent '

performance of SR 3.3.4.1.7.

2. The STAGGERED TEST BASIS Frequency shall be determined on a per Function basis.

Verify the EOC-RPT SYSTEM RESPONSE TIME 18 months on a is within limits. STAGGERED TEST BASIS

%,, ~

SR 3.3.4.1.r ...............

--NOTES------------------ .),

1. Only appi'nable to the porti is of the logi. tested by the Sel Test System
2. For he purposes of de rmining the S GGERED TEST BASIS equency, all iannels. for all fu tions are

...$$"  !$$.. ..!!".....$$I.'.......... /

'erform LOGIC SYS M FUNCTIONAL TEST 18 months on a independent of tie Self Test System. STAGGERED TEST -

BASIS ,j/

(2 SR 3.3.4.1.7' j Determine RPT breaker interruption time. 60 months CLINTON 3.3-28 Amendment No. A

Attachment 6 to U-602297

LS-94-001 Re6g{CYInstrumentation

. 3.3.5.1 A_ .___

vy T SURVEILLAtlCE REQUlpfMEtlTS (continued)/

SURVEILLAt FREQUENCY

]

t SR 3.3.5. 7 -------- ---

NOTE--------- -------

Only appli ble to the portion of the f logic tee ed by the Self Tes 'ystem.

Per rm LOGIC SYSTEM FU TI0ilAL TEST i ependent of the Se) Test System. 7 months CLINTON 3.3-39 Amendment flo. A

Attachment 4 to U-602297 LS-94-001 Page 7 b $nstrumentation

. 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System instrumentation APPLICABLE CON 0!!!ONS MODES OR REFERENCE 0 OTHER REQUIRED FROM I SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWASLE I

FUNCTION CONDITIONS FUNCil0N ACilON A.1 REQUIREMENTS VALUE i

1. Low Pressure Coolant '

injection-A (LPCI) and Low Pressure Core Spray (LPC3)

Subsystems

a. Reactor Vessel Water 1,2,3, 2(b) 8 SR 3.3.5.1.1 t -147.7 Level - Low Low L ow, SR 3.3.5.1.2 inches '

Levet 1 4(a),$(a) SR 3.3.5.1.3 SR 3.3.5.1.4 ,

SR 3.3.5. .5 '

SR 3.3. .6

b. Dryweli Pressure - High 1,2,3 2 IDI B SR 3,3.$.1.1 5 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
L l

c LPCI Plop A 1,2,3, 1 C SR 3.3.5.1.2 2 4.5 seconds

' tart - Time Delay SR 3.3.5.1.4 and 5 5.5 Logic Card 4(a),5(a) SR 3.3.5.1.5 seconds l l

d. Reactor vessel 1,2,3 4 C SR 1.3.5.1.1 2 452 psig Pressure - Low SR 3.3.5.1.2 and (Injection Permissive) SR 3.3,5.1.3 5 478 psig SR 3.3.5.1.4 SR 3.3,.5.1.5 i e ,-

g AI 'I,5(a) 4 8 SR 3.3.5.1.1 1 452 psig SR 3.3.5.1.2 and SR 3. 3.5.1. 3 5 478 psig SR 3.3.5.1.4 SR 3.3.5.1.5

.  : 1

e. LPCS Pump Distharge 1,2,3, 1 E SR 3.3.5.1.1 1 750 gpm flow - Low (Bypass) SR 3.3.5.1.2 4(a) $(a)

, SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5,

,e ,

f. LPCI Pump A Discharge 2,3, 1 E SR 3.3.5.1.1 2 900 gpm Flow - Low (Bypass) SR 3.3.5.1.2 4(a),5(a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 I i

- ,, 1

g. Manual Initiation 1,2,3, 1 C SR 3.3.5.1.5 NA 4(a) $(a)

, (continued) 8 (a) When associated subsystem (s) ai e required to be OPER ABLE.

(b) Also required to initiate the associated diesel generator.

CLINTON 3.3-40 Amendment flo. A 1

l l

Attachment 4 to U-602297 LS-94-001 Page la - 48 L Instrumentation 3.3.5.1 Table 3.3.5.1 1 (page 4 of 5)

Emergency Core Coot ing System Instrumentat ion APPLICA0LE CONDITIONS MODES OR REFERENCE 0 OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CON 0lflCNS FUNCil0N ACTION A.1 RE0V!REMENTS VALUE

3. High Pretrure Core Spray (HPCS) Systen (continued)
h. Manual Initiation 1,2,3, 1 C SR 3.3.5.1.5 NA 4(a) 5(a) 4 Automatic Depre >u iration Systet (ADS) Trip Systen (Logic A and E) O
a. Reactor veiset 1,2(d),3(d) 2 F SR 3.3.5.1.1 2 147.7 inches Water Levet - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.4 sa 3.3.5.1.5,

,,c .

b. Dryuelt 1,2(d),3(d) 2 F SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.

, 3. 5 .1. 5,

_3e ,

c. ADS Initiation 1,2(d),3(d) 1 G SR 3.3.5.1.2 5 117 seconds Timer SR 3.3.5,1.4 SR
3. 3. 5.1, . 5 .

,;e ,

d. Reactor vessel 1,2(d) 3(d)

, 1 F SR 3.3.5.1.1 2 8.3 inches water Level - Low, tR 3.3.5.1.2 Level 3 SR 3.3.5,1.3 (Confirmatory) SR 3.3.5.1.4 SR 3, ., 3.e 5.1.

, 5,

e. LPCS Pump 1,2(d),3(d) 2 G SR 3.3.5.1.1 1 125 psig Discharge SR 3.3.5.1.2 Pressure - H igh SR 3.3.5.1.3 sR 3.3.5.1.4 sa 3, .,3.e 5 1

, .1. 5, l

f. LPCI Pump A 1,2(d) 3(d)

, 2 G SR 3.3.5.1.1 1 115 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3,5.1.3 SR 3 ~.5.1.4 SR 3.3.5.1.5,

,,c ,

1 l

g. AOS Orywelt 1,2(d) 3(d)

, 2 G SR 3.3.5.1.2 s 6.5 minutes Pressure Bypass SR 3.3.5.1.4 timer SR 3.3.5.1.5 y, . ,

h. Manual Initiation 1,2(d),3(d) 2 G SR 3.3.5.1.5 NA

-  !! (continued)

(d) With reactr team donc pressure > 150 psig.

CLINTON 3.3-43 Amendment No. A

~ ~ ~

l ttachment 4 to U-60'2297 LS-94-001

, , Page 11 of 4R ECCS Instrumentation 3.3.5.1 table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System instrumentation APPLICABLE CON 0lil0NS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHAhNELS PER REQUIRED SURVElLLANCE ALLOWABLE FUNCTION CON 0!!!ONS FUNCil0N ACTION A.1 REculREMENTS VALUE

5. ADS d t'm 2 (Logic B

=AF 1,2(d),3(d)

a. d Vessel Water 2 F SR 3.3.5.1.1 a -147.7 Level - Low Low Low, SR 3.3.5.1.2 inches Level 1 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3. 3, .5.1. 5 .

g

b. Drywell Pr essure - High 1,2(d),3(d) p p gg 3,3,3,3,3 3 g,gg pggg SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 **

7 7 t

c. ADS Initiation fimer 1,2(d),3(d) 1 G SR 3.3.5.1.2 5 117 seconds SR 3.3.5.1.4 SR 3.3.5.1.5 a a

l

d. Reactor Vessel Water 1,2(d),3(d) I f SR 3.3.5.1.1 1 8.3 inches Level - Low, Level 3 SR 3.3.5.1.2 (Conffrmatory) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 a m y 2 c ,,
e. LPCI Pumps 8 & C 1,2(d),3(d) 4 C SR 3.3.5.1.1 1 115 psig Discharge SR 3.3.5.1.2 Pressure - High 2 per purnp SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 ,,

- 77e

f. ADS Drywell Pressure 1,2(d) 3(d)

, 2 G SR 3.3.5.1.2 5 6.5 minutes sypass Timer ,

SR 3.3.5.1.4 SR 3.3.5.1.5

, , c ,

l

g. Manual Initiation 1,2(d),3(d) 2 G SR 3.3 5.1.5 NA I

(d) With reactor steam done pressure > 150 psig.

CLINTON 3.3-44 Amendment No. A

Attachment 6 to U-602297 LS-94-001

, , Page 12 of 48 RCIC System Instrumentation

, 3.3.5.2 SURVEILLANCE REQUIREMENTS

....................................-NOTES------------------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC function.
2. When a cSannel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2 and 5; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.
URVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform >ANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Calibrate the analog trip module. 92 days SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months gr - > > l SR 3.3.5.2. ------------

NOTE--------- .-------

Only appli ble to the portio s of the logic te ed by the Self Tec System. }

Perfo m LOGIC SYSTEM FU' TIONAL TEST inde endent of the Sel Test System.

/

j 72 months

/ _j l

l 1

l l

i i

CLINTON 3.3-47 Amendment No. A )

1

Attachment 4 to U-602297 LS-94-001

, , Page 13 of 48

. RCIC System Instrumentation 3.3.5.2 l Tabte .t.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cccling System Instrumentation a --- --

CONDITIONS REQUIRED REFERENCEO CHANNELS PER FROM REQUIRED SURVE!LLANCE ALLOWABLE FUNCTION FUNCil0N ACiivk A.) REQUIREMENTS VALUE

1. Reactor vesset Water 4 B SR 3.3.5.2.1 e 47.7 inches Level - Low Low, Level 2 SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5
2. Reactor vessel Water 2 C SR 3.3.5.2.1 s 52.6 inches level - H igh, Level E SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5
3. RCIC Storage Tank 2 0 SR 3.3.5.2.1 a 0 inches L evel - t ow SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5
Sh l
4. Suppression Poot Water 2 0 SR 3.3.5.2.1 1 -3 inches Level - High SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3, ., 3. 5, ., 2. 5
5. Manual initiation 1 C SR 3.3.5.2.5 NA

,,,1 l

l CLINTON 3.3-48 Amendment No. A l

Attachment 4 to U-602297 LS-94-001

, , Page 14 of 48 Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

% "'SR 3.3.6.1.7 ---------- -------

TES---------------- -

1. Only applica e to the portions of the isolati i Functions logic tested by the Se Test System.
2. For the purposes of determining ie STAGGr ED TEST BASIS Frequenc' for the SL isolation Functions all ch< inels for all Function. are c asidered together and ' n" equals our.

18 m nths on a erform LOGlC SYSTEM NCTIONAL TEST STt GERED TEST independent of the S I f Test System. B. IS L ._

)

SR 3.3.6.17F' ------------- -- -NOTE--- -- ------------

nI The STAGGERED TEST BASIS Frequency for each Function shall be determined on a per channel basis.

Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a is within limits. STAGGERED TEST BASIS CLINTON 3.3-55 Amendment No. A

Attachment 4 to U-602297 LS-94-001

. . , Page 15 of 48 Primary Containment isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 1 of 8)

Primary Containment isolation Instrumentation APPLICABLE CON 0!TIONS MODES OR REculRED REFERENCE 0 ofMER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENis VALUE

1. Main Steam Line isolation
a. Reactor Vessel Water 1,2,3 4 G SR 3.3.6.1.1 1 147.7 inches Level - Low Low Low, SR 3.3.6.1.2 Levet 1 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7

,7 1 , a

b. Main Steam Line 1 4 H SR 3.3.6.1.1 2 837 psig Pressure -Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3, . 3. 6.1. 7

- , a

c. Main Steam Line 1,2,3 4 G SR 3.3.6.1.1 1 178 psid F low - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 e

l

d. Condenser vacuun - Low 1,2(a) , 4 G SR 3.3.6.1.1 2 7.6 inches SR 3.3.6.1.2 Hg vacuum 3(a) SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 e, 1 2 1 4 7 s
c. Main Steam tunnet 1,2, 4 C SR 3.3.6.1.1 5 171*F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 e9 7 7 L 4 7
f. Main Steam Tunnet 1,2,3 4 G(b) SR 3.3.6.1.1 5 63*F Differential SR 3.3.6.1.2 Terrperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 . ,

7 7,

g. Main Steam Line Turbine 1.2,3 4 G SR 3.3.6.1.1 Modules 1-4 Building SR 3.3.6.1.2 3 142*F t emperature - H i gh SR 3.3.6.1.5 Module $

SR

3. 3, . 6.1. 6, 5 150*F
h. Manual Initiation 1,2,3 4 J SR 3.3.6.1.6 NA I

(continued)

(a) With any turbine stop valve not closeo.

(b) The Coapletion Times for Required Actions G.1 and G.2.1 may be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided at teast two Function f.e channels remain OPERABLE.

CLINTON 3.3-56 Amendment No. A

Attachment 4 to U-602297 LS-94-001 Page 16 of 48 Primary Containment Isolation Instrumentation

. 3.3.6.1 Table 3.3.6.1 1 (page 2 of 8)

Primary Containment isolation Instrumentation APPLICABLE CON 0lf!ONS HOCES OR REQUIRED REFERENCE 0 OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVE!LLANCE ALL.0WABLE FUNCTION CON 0li!ONS FUNCTION ACil0N F 1 REQUIREMENTS VALUE

2. Primary contairenent Isolation
a. Reactor Vessel Water 1,2,3 4 K SR 3.3.6.1.1 z - 47.7 inches Level - Low Low, Level 2 :R 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

-!^  ?.?.! ' '

b. Drywell Pressure - High 1,2,3 4 K SR 3.3.6.1.1 5 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 l S^  ?.? f ' '

l

c. Reactor Vesset Water 1,2,3 4 i SR 3.3.6.1.1 2 -47.7 inches Level - Low Low, SR 3.3.6.1.2 Levet 2 (ECOS SR 3.3.6.1.3 Divisions 1 and 2) SR 3.3.6.1.5 SR 3.3.6.1.6 C^ 2.3.1." '-
d. Drywell Pressure - High 1.2.3 4 i SR 3.3.6.1.1 1 1.88 psig (ECCS Divis6cns 1 SR 3.3.6.1.2 and 2) SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

^^

2.2._ '

e. Reactor vessel Water 1,2,3 4 i SR 3.3.6.1.1 1 -47.7 Level - Low Low, Level SR 3.3.6.1.2 inches 2 (HPCS NSPS Div 111 SR 3.3.6.1.3 and IV) SR 3.3.6.1.5 SR

'^

3.3.6.1.6 2.?.'

f. Drywell Pressure - High 1,2,3 4 i SR 3.3.6.1.1 5 1.88 psig (HPCS NSPS Div !!! and SR 3.3.6.1.2 IV) SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 3 em 1 7 L 1 7
g. Contairunent Buitding (c) 4 N SR 3.3.6.1.1 5 500 mR/hr

, fuel Transfer root SR 3.3.6.1.2 Ventilation Plenun SR 3.3.6.1.5 Radiatlo mHigh SR 3.3.6.1.6 e, ,

,y5 (continued)

(b CLINTON 3.3-57 Amendment No. A

Attachment 4 to U-602297 LS-94-001 Page 17 of 48 l Primary Containment Isolation Instrumentation 3.3.6.1 ,

1 Table 3.3.6.1 1 (page 3 of 8)

Primary Contairvnent isolation instrunentation )

l APPLICABLE REQUIRED CONDITIONS H00ES OR CHANNELS REFERENCE 0 j OlHER PER FROM SPECIf!ED FUNCil0N REQUIRE 0 SURVEILLANCE ALLOWABLE FUNCTION CON 0!Il0NS ACTION F.1 REQUIREMENIS VALUE l l

i

2. Primary Containment '

! solation (continued)

h. Cont airment Building 1,2,3 4 i SR 3.3.6.1.1 5 400 rnR/hr Exhaust SR 3.3.6.1.2 Radiat ion - H igh SR 3.3.6.1.5 SR 3.3.6.1.6

??6 ' '

(c) 4 N SR 3.3.6.1.1 5 400 mR/hr SR 3.3.6.1.2 sR 3.3.6.1.5 SR 3.3.6.1.6

-  ??1

i. Containment Buttding 1,2,3 4 I SR 3.3.6.1.1 5 400 mR/hr continuous containment SR 3.3.6.1.2 Purge (CCP) Exhaust SR 3.3.6.1.5 R adi a t iory-H igh SR 3.3.6,1.6
I'_ ' '

(c) 4 N SR 3.3.6.1.1 5 400 trR/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6,1.6

j. Reactor Vessel Water 1,2,3 4 i SR 3.3.6.1.1 t - 147.7 inches level-Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 771 , ,

(c) 4 N SR 3.3.6.1.1 2 -147.7 inche5 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR c,

3.3.6.1.6

,,1 <,

k. Contairnent Pressure-- (d) 2 1 SR 3.3.6.1.1 5 3.0 psid High SR 3.3.6.1.2

$R 3.3.6.1.5 SR 3, . 3.6.1. 6 3

(e) 2 N SR 3.3.6.1.1 5 3.0 psid SR 3.3.6.1.2 SR 3.3.6.1.5 i SR 3.3.6.1.6 c 1 ,1 s ,

(continued) '

(c) During CORE ALIERAil0Ns, movement of irradtated f uel assentt les in primary or secondary containment, or operations with a potential for draining the reactor vessel.

(d) NODES 1, 2, and 3 with the associated PCIVs not sealed closed.

(c) Ouring CORE ALTERATIONS, movement of irradiated fuel assemblies in primary or secondary containment, or operations with a potential for draining the reactor vesset, with the aHociated PCIVs not sealed closed.

CLINTON 3.3-58 Amendment No. A

Attachment 4 to U-602297 LS-94-001 Page 18 of 48 Primary Containment Isolation Instrumentation 3.3.6.1 l

Table 3.3.6.1 1 (page 4 of 8)

Primary Contairvnent Isolation Instrunentation APPLICA8LE CON 0!TIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS paOH SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CON 0!! IONS FUNCil0N ACil0N F.1 REQUIREMENTS VALUE l

2. Primary Containment  !

Isolation (continued) j

l. Manual Initiation 1,2,3 2 J SR 3.3.6.1.6 NA j r  ?.I.'% l 1
3. Reactor Core Isolation i Cooling (RCIC) System '

isolation

a. RCIC Steam Line 1.2,3 2 I SR 3.3.6.1.1 5 118.5 inches .

I F low - H igh SR 3.3.6.1.2 water SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 ea T T 1 1 7

b. RCic Steam Line 1,2,3 2 i SR 3.3.6.1.2 5 13 seconds F low - H i gh SR 3.3.6.1.5 Time Delay SR 3.3.6.1.6

-f^  ?.? ! ' '

c. RCIC Steam Supply Line 1,2,3 2 i SR 3.3.6.1.1 e 52 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 l x  ?.I.! * ' ,
d. PCic Turbine Exhaust 1,2,3 4 1 SR 3.3.6.1.1 5 20 psig Diaphragm SR 3.3.6.1.2 l Pressure - High SR 3.3.6.1.3 i SR 3.3.6.1.5 SR 3.3.6.1.6

=  !'i*'

e. RCIC Equipnent Room 1,2,3 2 i SR 3.3.6.1.1 5 M7'F Ambient SR 3.3.6.1.2 Tenperature - High SR 3.3.6.1.5 SR
3. 3, .6.1.6,

._c.,

f. RCIC Equipment Room 1.2,3 2  !(') SR 3.3.6.1.1 5 43*F Differential SR 3.3.6.1 2 Temperature - High SR 3.3.6.1.5 SR 3.3, . 6.1.6, 7, ,
g. Main Steam Line Tunnel 1,2,3 2 i SR 3.3.6.1.1 5 171*F Ambient SR 3.3.6.1.2 T emperature - H igh SR 3.3.6.1.5 SR 3, . 3,1. 6.1. 6, (continued)

(f) The Completion Time for Required Action 1.1 may be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided all Required Channels Per Function of the associated area's Ambient Temperature - High Function remain OPERABLE.

CLINTON 3.3-59 Amendment No. A

1 Attachment 4 to U-602297 1 LS-94-001 Page 19 of 48 l Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (pa2e 5 of 87)

Primary Containment isolation Instrunentation APPLICABLE CONDifl0NS MODES OR REFERENCED

)

OTHER REQUIRED FROM l

$PECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWA8LE l FUNCTION CON 0lil0NS FUNCTION ACTION F.1 REQUIREMENTS VALUE l

3. RCic System Isolation (continued)
h. Main Steam Line Tunnel 1,2,3 2  !(I) SR 3.3.6.1.1 s 63*F Offferential SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 i SR 3.3.6.1.6 )

Mn ?Id*'- l

t. Main Steam Lire tunnet 1,2,3 2 i SR 3.3.6.1.2 5 28 minutes l Temperature Timer SR 3.3.6.1.5  !

SR  !

t 1 3 . ,3 L. 6 .1. 6, 1 t

j. RHR Heat Exchanger 1,2,3 2 per room I SR 3.3.6.1.1 s 160*F Ambient SR 3.3.6.1.2 Tempera ture - H igh SR 3.3.6.1.5 l SR 3.3.6.1.6 es ,T I 4 ,
k. RHR Heat Exchanger 1,2,3 2 per room  !(f) SR 3.3.6.1.1 5 79.6*F Differential SR 3.3.6.1.2 temperature - High SR 3.3.6.1.5 SR c, 3, .,a3 . 6.1.

6,

l. RCIC/RHR Steam Line 1,2,3 2 i SR 3.3.6.1.1 5 188 inches F low - High SR 3.3.6.1.2 water SR 3.3.6.1.3 SR 3.3.6.1.5 SR en 3.3.6.1.6,

,t I t i

m. Drywell Pressure - High 1,2,3 2 1 SR 3.3.6.1.1 s 1.88 psig )

SR 3.3.6.1.2 l SR 3.3.6.1.3 l SR 3.3.6.1.5 l SR 3.3.6.1.6 C"  ?.I.i

n. Manual Initiation 1,2,3 2 J SR 3.3.6.1.6 NA I I c, ,,1 , , \

l 1

4 Reactor Water Cleanup l

(RWCU) System isolation '

l

a. Dif f erential Flow - High 1,2,3 2 1 SR 3.3.6.1.1 s 66.1 spn SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

?!..-

(continued)

(f) The Completion Time for Required Action 1.1 may be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided att Required Channels Per Function of the associated area's Ambler t Temperature - High Function remain OPER ABLE.

1 CLINTON 3.3-60 Amendment No. A

Attachment 4 to U-602297 I LS-94-001 Page 20 of 48 Primary Containment isolation Instrumentation l 3.3.6.1 l

l i

Table 3.3.6.1 1 (page 6 of 8) er T-s. . .

' "-t a i nmen t isolation Instrumentation l

APPLICABLE CONDITIONS j MODES OR REFERENCE 0 OTHER REQUIRED FRCH SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CON 0lTIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE

4. RWCU System Isolation (continued)
b. Differential 1,2,3 2 1 SR 3.3.6.1.2 5 47 seconds F low - T imer SR 3.3.6.1.4 SR 3.3.6.1.6

~ '. i

c. RWCU Heat Exchanger 1,2,3 2 per room  ! SR 3.3.6.1.1 5 20$*F Equipment Room SR 3.3.6.1.2 Temperature - H igh SR 3.3.6.1.5 SR 3.3.6.1.6 ea T T f 1 7 q
d. RWCU Peat Exchanger 1,2,3 2 per room 1(I) SR 3.3.6.1.1 5 63'F Equipment Room SR 3.3.6.1.2 Differential SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6 3 em 7 7 f 1 9
e. RWCU Pw p Rooms 1,2,3 2 per room i SR 3.3.6.1.1 5 202*F T empera ture - High SR 3.3.6.1.2 SR 3.3.6.1.5 .

SR I e, 3, .,3.t 6.1.

,r 6

, l 1

f. RWCU Pwp Rooms 1,2,3 2 per room 1(I) SR 3.3.6.1.1 5 63*F Differential SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 er 1 T L 1 9
g. Main Steam Line funnel 1,2,3 2 i SR 3.3.6.1.1 5 171*F  ;

Ambient SR 3.3.6.1.2 '

Temperature - H igh SR 3.3.6.1.5 SR en 3.3, T 6.1.6 L 4 ?

h. Main Steam Line Tunnel 1,2,3 2 1(I) SR 3.3.6.1.1 5 63*F Differential SR 3.3.6.1.2  ;

Temperature - H i gh SR 3.3.6.1.5 '

SR 3.3.6.1.6 i (continued)

(c) During CORE ALTERAil0NS, movement of irradiated fuel assemblies in primary or secondary containment, or operations with a potential for draining the reactor vessel.

(f) The Completion Time for Required Action 1.1 may be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided all Required Channels Per Function of the associated area's Ambient Tenperature - High Function remain OPERABLE. l CLINTON 3.3-61 Amendment No. A

Attachment 4 to U-602297

  • LS-94-001 Page 21 of 48 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 7 of 8)

Primary Contairvnent isolation Instrumentation APPLICABLE CON 0lil0NS MODES OR REFERENCE 0 OTHER REQUIRED FROM SPECIFILO CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCil0N C040!!!ONS FUNCTION ACilCN F.1 REQUIREMENTS VALUE

4. RWCU System Isolation (continued)
1. Reactor Vessel Water 1,2,3 4 i SR 3.3.6.1.1 1 -47.7 inches Levet - Low Low, Level 2 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 T  !.?.i.*_b (c) 4 N SR 3.3.6.1.1 1 -47.7 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

,, 7734 3 J. Standby Liquid Control 1,2 2 L SR 3.3.6.1.6 N/A l System initiation  ?.2.f * ' I

k. Manual Initiation 1,2,3 2 J SR 3.3.6.1 6 N/A th 1 1 1 e (c) 2 N SR 3.3.6.1.6 N/A

_rn 1 7 1 1 7 S. RHR System isolation

a. RHR Heat Exchanger 1,2,3 2 per room l SR 3.3.6.1.1 s 160'F Anti ent SR 3.3.6.1.2 T emperature - High SR 3.3.6.1.5 SR 3.3.6.1.6 r  !.?.i.* '
b. RHR Heat Exchanger 1,2,3 2 per room I U) SR 3.3.6.1.1 5 79.6*f Differential SR 3.3.6.1.2 t empera ture - H i gh SR 3.3.6.1.5 SR

-y 3, . 3,1 ., 6.1. 6, (continued)

(c) During CORE ALTERATIONS, movement of irradiated fuel assemblies in primary or secondary containment, or operations with a potential for draining the reactor vessel.

(f) The Completion Time for Required Action 1.1 inay be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided att Required Channels Per Function of the associated area's Arnbient Temperature - High Function remain OPERABLE.

CLINTON 3.3-62 Amendment No. A ,

1 1

Attachment 4 to U-602297 LS-94-001 Page 22 of 48 Primary Containment Isolation Instrumentation 3.3.6.1 table 3.3.6.1 1 (page 8 of 8) 1 Primary Containment Isolation Instrunentation APPLICABLE CONOlIl0NS  !

MODES OR REFERENCE 0 OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVELLLANCE ALLOWABLE FUNCil0N CON 0lfl0NS FUNCil0N ACTION F.1 REQUIREMENTS VALUE

5. RHR System Isolation (continued)
c. Reactor vessel Water 1,2,3(h) 4 i SR 3.3.6.1.1 t 8.3 inches Level - Low, Level 3 SR 3.3.6.1.2 l SR 3.3.6.1.3 l SR 3.3.6.1.5 i SR I 3,.3.6.1.6

, 1 . ,

d. Reactor Vessel Water 3(II,4,5 4(9) M SR 3.3.6.1.1 2 8.3 inches I Level - Low, level 3 SR 3.3.6.1.2  ;

SR 3.3.6.1.3 i SR 3.3.6.1.5 j SR

_y 3,.3.6.1.6

,1 , ,

a l

e. Reactor vessel Water 1,2,3 '

i SR 3.3.6.1.1 2 -147.7 Level - Low Low Low, SR 3.3.6.1.2 inches i Level 1 h g,$M' SR 3.3.6.1.5 3, . 3,,. ,6.1.

, 6 j

1 1

l i

f. Reactor vesset 1,2,3 '

i SR 3.3.6.1.1 5 150 psig Pressure + High {

SR 3.3.6.1.2 1 3.3.6.1.3 SR I SR 3.3.6.1.5 )

SR 3.3.6.1.6 i

>i ,,1 1 7

g. Drywell Pressure - High 1,2,3 4 1 SR 3.3.6.1.1 5 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 1 SR 3.3.6.1.5 i SR 3.3.6.1.6 e l

-- g  ;,f.> g

h. Manual Initiation 1,2,3 2 J SR 3.3.6.1.6 N/A

- ,,1 < ,

(g) Only one trip system required in M00ES 4 and 5 with RHR S5utdown Cooling System integrity maintained.

(h) With reactor steam dome pressure greater than or equal to the RHR cut in permissive pressure.

(i) With reactor Jome pressure less than the RMR cut in permissive pressure, i

)

i CLINTON 3.3-63 Amendment No. A

Attachment 4 to U-602297 l LS-94-001 Page 23 of 48 i

Secondary Containment Isolation Instrumentation 3.3.6.2 l l

SURVEILLANCE REQUIREMENTS (continued) l SURVEILLANCE FREQUENCY SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Calibrate the anelog trip module. 92 days i

l 3.3.6.2.4 SR Perform CHANNEL CAllBRATION. 18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months N

g g , g,c,3f( .-

/ /Jo7E -

^7~^'~

, /

/' Chh o.ppliche 40 hy[erh'uo6 6

/ m4.twe9e ewTe s M[- /

/ /s r\ FvNoiw L ~7 ^AT T%T in&Med of M ' I TC 9 w / w// , '

)

CLINTON 3.3-66 Amendment No. A l

1

Attachment 4 to U-602297 LS-94-001 Page 24 of 48 Secondary Containment Isolation Instrumentation 3.3.6.2 table 3.3.6.2 1 (page 1 of 1)

Secondary Centairimynt Isalation Instrunentat ion t=xt---__-===---

APPLICA8LE MODES AND R NUlREO ofMER CHAN4ELS SPECIFIED PER TRIP SURVEllLANCE ALLOWABLE FUNCTION CCN0lil0NS SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1,2,3,(a) 2 sR 3.3.6.2.1 a 47.7 inches Level - Low Low, level 2 SR 3.3.6.2.2 SR 3.3.6.2.3 st 3.3.6.2.4 SR 3.3.6.2.5 a; 3.'.6.2.u
2. Drywell Pressure - High 1,2,3 2 SR 3.3.6.2.1 3 1.88 psig SR 3.3.6.2.2 SR 3.3.6.2.3 st 3.3.6.2.4 SR 3.3.6.2.5 5 A-3 S a s ?; 4 -
3. Con t a i rwnt Building fuel (a),(b) 2 SR 3.3.o.2.1 5 500 mR/hr Transfer Pool Ventilation SR 3.3.6.2.2 P t erun E xhaus t sa 3.3.6.2.4 R ad i a t i on - H i gh SR 3.3.6.2.5

-M 3 hs/s+O

4. Contairosent Building 1,2,3 2 SR 3.3.6.2.1 5 400 mR/hr Exhaust Radiation - High (a),(b) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 4H 34.M-
5. Con t a t orien t Guildiov 1,2,3 2 SR 3.3.6.2.1 5 400 rra/hr cont inuous cont ainnent (a),(b) SR 3.3.6.2.2 Purge (CCP) Exhaust SR 3.3.6.2.4 R adi a t i on - H i gh SR 3.3.6.2.5 SS-%hke2% l
6. Fuel Building Exhaust 1,2,3 2 SR 3.3.6.2.1 s 17 rrR/hr R adi at ion - H i gh (c) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 4 b Jr3 4,2, b l
7. Manual Initiation 1,2,3, 1 SR 3.3.6.2.5 NA (a),(b) $_ g, J,Q4 g.--_..--,=,.- _ . - - = , - - . _ __

(a) During operations with a potential for draining the reactor vessel.

(b) During CORE AlfERATIONS, arvi during movement of irradiated fuel assemblies in the primary or secorajory con t a i rvient .

(c) During movement of irradiated f uel assentt ies in the f uel building.

CLINTON 3.3-67 Amendment No. A

... .- - .. . ..- =

Attachment 4 to U-602297 LS-94-001 Page 25 of 48

. RHR Containment Spray System Instrumentation 3.3.6.3 i

""*L_'r _ _

GF I '

SURVEILLANCEREQULdEMENTS(continued) / /

j/ SURVEILLANCE / / FREQUENCY SR 3.3.6. 6 -------------- - --NOTES- --------- -- -

1. Only appli able to the portions o the logi tested by the Self Tec System.
2. For e purposes of determi ng the STA ERED TEST BASIS Frequ ncy, all ch nnels for all Functio , are nsidered together and n" equals our.

erform LOGIC SYSTEM fi ;CIl0NAL TEST - months on a independent of the Sel Test System. STAGGERED TEST i

L / BASIS l

CLIN 10N 3.3-71 Amendment No. A

~ ~

Attachment 4'to U-602297 LS-94-001

, . Page 26 of 48 RHR Containment Spray System Instrumentation 3.3.6.3 fable 3.3.6.3 1 (page 1 of 1)

RHR Contairvnent Spray System Instrunentation CONDlfl0NS REQUIRED REFERENCED CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCil0N SYSTEM ACT104 A.1 REQUIREMENTS VALUE

1. Drywell Pressure - High 2 8 SR 3.3.6.3.1 5 1.88 psig SR 3.3.6.3 2 SR 3.3.6.3.3 SR 3.3.6.3.4 SR 3.3.6.3.5

?.

^

2..

2. Contairvnent Pressure - High 2 8 SR 3.3.6.3.1 5 22.4 psia SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.4 SR 3.3.6.3.5 9

L 7 /T L

3. Reactor Vesset water 2 B SR 3.3.6.3.1 1 -147.7 inches Level - Low Low Low, SR 3.3.6.3.2

! Level 1 SR 3.3.6.3.3 SR 3.3.6.3.4 SR 3.3.6.3.5 a

' ?.? ' ? '

l

4. Timers, System A 1 C SR 3.3.6.3.2 1 10.10 minutes and and System B SR 3.3.6.3.4 5 10.23 minutes SR 3.3.6.3.5

': '?

5. Timer, System B Only 1 C SR 3.3.6.3.2 5 90.6 seconds SR 3.3.6.3.4 SR

-s 3, . 3, . 6. 3,1 . 5

6. Manual Initiation 1 C SR 3, . 3, .6. 3,, . 5 NA 1

l 1

l l

CllNTON 3.3-72 Amendment No. A

~ ^

Attachment 4 to'U-602297 LS-94-001 Pa SPdbe 27 of'40 System Instrumentation 3.3.6.4

}l SURVEILLANCEREQdIREMENTS (cont inuedd _'N SURVEILLA FREQUENCY SR 3.3 .4.8 -----------

NOTES--------- -------

1. Only < plicable to the port' ns of the gic tested by the Se Test Sy em.
2. or the purposes of d ermining the STAGGERED TEST BASIS 'requency, all channels for all Fi ctions are considered togeth r and "n" equals four.

Perform LOGIC SY TEM FUNCTIONAL TEST 18 months on independent of he Sel f Test System. STAGGERED Tr T g BASIS J

=

i l

l l

l l

CLINTON 3.3-76 Amendment No. A

Attachment 4 to U-602297 LS-94-001 p m. 28 of 48 59MU System Instrumentation ,

3.3.6.4 l i

tabte 3.3.6.4 1 (page 1 of 1)

Suppre.;sion Poot Makeup System Ins trwentat ion REQUIRED CON 0lfl0NS CHANNELS REFEAENOED PER FRCH TRIP RE0VIRED SURVEILLANCE ALLOWA8tE FUNCfl0N SYSTEM ACil0N A.1 REQUIREMENTS VALUE

1. Drywet t Pressure - High 2 8 SR 3.3.6.4.1 5 1.8S pstg SR 3.3.6.4.2 SR 3.3.6.4.3 SR 3.3.6.4.6 SR 3.3.6.4.7
2. Reactor vessel Water 2 6 SR 3.3.6.4.1 2 147.7 inches Level - Low L ow Low, SR 3.3.6.4.2 Level 1 SR 3.3.6.4.3 SR 3.3.6.4.6 SR 3.3.6.4.{
3. Suppression Poot Water 2 6 SR 3.3.6.4.1 3 29 inches

. Level - Low Low SR 3.3.6.4.2 SR 3.3.6.4.4 SR 3.3.6.4.6 SR 3.3.6.4.7

4. Ilmer 1 C SR 3.3.6.4.2 5 30 minutes SR 3.3.6.4.5 SR 3.3.6.4.7 t

1

5. Manual Init6ation 2 C SR 3.3.6.4.7 NA

- ,, ,e m

ClitlTON 3.3-77 Amendment flo. A i

Attachnent 4 to U-602297 '

LS-94-001 Page 29 of 4f.

Relief and LLS Instrumentation 3.3.6.5 SURVEILLANCE yE0VIREMENTS (cont)nued) ,

SURV LANCE UENCY SR 3 .6.5.5 -------

- -- - ---NOTE -------- --- --

Only )plicable to the ortions of the log' tested by the S .f Test System.

'erform LOGIC SYS EM FUNCTIONAL TE independent of )fie Self Test Syst m. 72 m iths m

CLINTON 3.3-80 Amendment No. A ,

~ ^

Attachment 4 to U-602297 LS-94-001 bS1nstrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.l.l.14 REQUIREMENTS (continued) The Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function uses an electronic filter circuit to generate a signal proportional to the core THERMAL POWER from the APRM neutron flux signal. This filter circuit is representative of the fuel heat transfer dynamics that produce the relationship between the neutron flux and the core THERMAL POWER. The filter time constant is specified in the COLR and must be verified to ensure that the channel is accurately reflecting the desired parameter.

The Frequency of 18 months is based on engineering judgment and reliability of the components.

SR 3.3.1.1.15 mmj T .3.1. 17 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The functional testing of control rods, in LCO 3.1.3, " Control Rod OPERABILITY," and SOV vent and drain valves, in LCO 3.1.8, " Scram Discharge Volume (SDV) Vent and Drain Valves," overlaps this Surveillance to provide complete testing of the assumed safety function.

The Self lest System may be utilized to perform this testing for those components that it is dosioned to monitor, THowever manual testing, inde endent of the Seit ist % f Syste must be .r formed . his may t accompli ied by 7gg test g any num >r of chan i alterna ng basis is or Fu tions ev y 18 mon s ch that on I channel for all I

~

w

^

F ctions ar_ tested ev y 72 mon is . This requenc is /

ased on t logic in rrelatior. hips of e varlo /J channels equired to roduce a RPS scra signal. E E '

The 18 month Frequency ef " 3.3. ' ' !5: is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued) i l

CLINTON 8 3.3-28 Revision No. A l

l

LS-94-001 Page 31 of 48 RPS Instrumentation B 3.3.1.1 UASES SURVEILLANCE SR 3.3.1.1.16 REQUIREMENTS (continued) This SR ensures that scrams initiated from the_ Turbine Stop Valve Closure and Turbine Control Valve fast Closure, Trip Oil Pressure-Low functions will not be inadvertently bypassed when THERMAL POWER is a 40% RTP. This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodology are incorporated into the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from turbine first stage pressure), the main turbine bypass valves must remain closed at THERMAL POWER a 40% RTP to ensure that the calibration remains valid.

If any bypass channel setpoint is nonconservative (i.e., the Functions are bypassed at n 40% RTP, either due to open main turbine bypass valve (s) or other reasons), then the affected Turbine Stop Valve Closure and Turbine Control Valve fast Closure, Trip Oil Pressure-Low functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition, this SR is met and the channel is considered OPERABLE.

The Frequency of 18 months is. based on engineering judgment and reliability of the components.

SR 3.3._1.1.Jgl~/ l This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. The RPS RESPONSE TIME acceptance criteria are included in plant Surveillance procedures.

As noted, neutron detectors are excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time, n

RPS RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. Note 2 of SR 3.3.1.1.)C requires STAGGERED TEST BASIS Frequency for each Function to be l determined separately based on the four channels as specified in Table 3.3.1.1 1. This Frequency is based on the logic interrelationships of tne various channels required to produce an RPS scrarr signal .

-(continuedJ CLINTON 8 3.3 29 Revision No. A

Ls-94-001 Page 32 of 48

  • RPS Instrumentation 8 3.3.1.1 BASES l7 SURVEILLANCE SR 3.3.J.l.1d* (continued)

REQUIREMENTS Therefore, staggered testing results in response time verification of these devices every 18 months. This frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious time degradation, but not channel failure, are infrequent.

REFERENCES 1. USAR, Section 7.2.

2. USAR, Section 5.2.2.
3. USAR, Section 6.3.3.
4. USAR, Chapter 15.
5. USAR, Section 15.4.1.2.
6. NE00-23842, " Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978.
7. USAR, Section 15.4.9.
8. Letter, P. Check (NRC) to G. Lainas (NRC), "8WR Scram Discharge System Safety Evaluation," December 1, 1900, as attached to NRC Generic letter dated December 9, i 1980.
9. NE00-30851-P A, " Technical Specification improvement Analyses for 8WR Reactor Protection System,"

March 1988.

i i

i 9

i ll CllNTON 8 3.3-30 Revision No. A

Attachment 4 to U-602297 LS-94-001

  1. 8[0hRN h strumentation 8 3.3.4.1 BASES SURVEllLANCF SR 3.3.4.1.3 C c" '

. 2." 7 l REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific l channel. The system functional test of the pump breakers is  !

included as a part of this test, overlapping the LOGIC SYSTEM FUNCTIONAL TEST, to provide complete testing of the 1 associated safety f unction. Therefore, if a breaker is 1 incapable of operating, the associated instrument channel would also be inoperable.

The Self Test System may be utilized to perform this testing for those components that it is designed to monitor. p "liowever, ianual testing, indeper ient of the Self Test- -

m System, .ust be per ormed. Th', may be ac mplished k

$$ I '

testin' any numbe of channel or functi s every 18 ionths on at alternatin< basis suct that all c nnels for 11 Func tons are .sted every /2 months. his Fregt ncyis/

ba id on the gic interr.lationshipe of the va lous

/J channels rent red to pr uce an EOC- PT signa f The 18 month Frequency o f 21 3. : . ' . 2 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance test when performed at the 18 month Frequency.

SR 3.3.4.1.4 This SR ensures that an E0C-RPT initiated from the TSV Closure and TCV Fast Closure, frip Oil Pressure-Low Functions will not be inadvertently bypassed when THERMAL POWER is a 40% RTP. This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure), the main turbine bypass valves must remain closed at THERMAL POWER 2 40% RTP to ensure that the calibration remains valid. If any bypass channel's setpoint-is nonconservative (i.e., the functions are bypassed at 2 40% RTP either due to open main turbine bypass valves or other reasons), the affected TSV Closure and TCV Fast Closure, Trip Oil Pressure-Low functions are considered (continued)

CLINTON 8 3.3-73 Revision No. A

Attachment 4 to U-602297 LS-94-001 EdCk[Tfnstrumentation 8 3.3.4.1 BASES SURVEILLANCE SR 3.3.4.1((p '

REQUIREMENTS '

(continued) This SR ensures that the RPT breaker interruption time is provided to the E0C-RPT SYSTEM RESPONSE TIME test. Breaker Interruption time is defined as Breaker Response time plus Arc Suppression time. Breaker Response is the time from application of voltage to the trip coil until the main contacts separate. Arc Suppression is the time from main contact separation until the complete suppression of the electrical arc across the open contacts. The 60 month Frequency of the testing is based on the difficulty of performing the test and the reliability of the circuit breakers.

REFERENCES 1. USAR, Section 7.6.1.8.

2. USAR, Section 5.2.2.
3. USAR, Sections 15.1.1, 15.1.2, and 15.1.3.
4. USAR, Sections 15.2.2, 15.2.3, and 15.2.5.
5. USAR, Sections 15.3.2 and 15.3.3.
6. GENE-770-06-1, " Bases for Changes To Surveillance Test Intervals And Allowed Out-0f-Service Times For Selected Instrumentation Technical Specifications,"

February 1991, i

i l

I CLINTON 8 3.3-75 Revision No. A l

Attachment 4 to U-602297 LS-94-001 kCbfnstrumentation B 3.3.5.1 UASES SURVEILLANCE SR 3.3.5.1.3 REQUIREMENTS (continued) The calibration of ATMs provides a check of the actual trip setpoints. The channel must be declared inoperable if the trip setting is discovered to be not within its required Allowable Value specified in Table 3.3.5.1-1. If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology, but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analyses. Under these conditions, the setpoint must be readjusted to be equal to or more conservative than the setting accounted for in the appropriate setpoint methodology.

The Frequency of 92 days is based on the reliability analysis of Reference 4.

SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CAllBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

Ihe Frequency of SR 3.3.5.1.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3 . 3 , 5 .1. 5 -! c " ' 3.5.

. .7 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LC0 3.5.1, LC0 3.5.2, LCO 3.8.1, and LC0 3.8.2 overlaps this Surveillance to p.rovide complete testing of the assumed safety function.

The Self Test System may be utilized to perform this testing

" for those components that it is desianed to monitor.

gy j

'Howevyt,manuaytesting,/ independent /oftheSe

, Sys tpfn, must y, a performfd. Thism/jbeaccom Test ished by t~ w (continued) i CLINTON 8 3.3-120 Revision No. A l

l

LS-94-001

  1. 8 CS nstrumentation B 3.3.5.1 BASES SURVE!LLANCE SR 3.3.5.l.5 " "" 1 ? ? L], (continued)

REQUIRtMENTS _

testing < l channels nd Functions .ssociated w an ECCS divistor or the RCl 'ystem ever 18 months o an altern- ing basis <ach that all CCS and RCI channels f -

all F nctions are ested every 2 months. is Freque y is bas on the lor c interrela onships of ' e various ch inels requ ed to produc an ECCS ini/iation sig 1. j The 18 month frequency " So ' 't ' 5 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for unplanned transients if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month frequency.

SR 3.3.5.1.6 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in Reference 5.

ECCS RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. This frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent.

This SR is modified by a Note that requires the STAGGERED TEST BASIS Frequency for each function in each trip system to be determined separately based on the number of redundant channels for that function specified on Table 3,3.5.1-1.

This frequency is based on the logic interrelationships of the various channels required to produce an ECCS initiation signal.

REFERENCES 1. USAR, Section 5.2.2.

2. USAR, Section 6.3.
3. USAR, Chapter 15.

(continued)

CLINTON B 3.3-121 Revision No. A l

l

Attachment 4 to U-602297 LS-94-001 Page 37 of 48 RCIC System Instrumentation 8 3.3.5.2

%ASES SURVEILLANCE SR 3.3.5.2.2 (continued)

RfQUIREMENTS consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 92 days is based on the reliability analysis of Reference 2.

SR 3.3.5.2.3 The calibration of analog trip modules provides a check of the actual trip setpoints. The channel must be declared inoperable if the trip setting is discovered to be less conservative than the Allowable Value specified in Tabl e 3.3. 5. 2-1. If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology, but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analysis. Under these conditions, the setpoint must be re-adjusted to be equal to or more conservative than accounted for in the appropriate setpoint methodology.

The Frequency of 92 days is Jased on the reliability analysis of Reference 2.

SR 3.3.5.2.4 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter with the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Frequency is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.2.5 - " " 2.3.5. .v The LOGIC SYSlEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system func ional testing perfot med in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

(continued _1 CLINTON B 3.3-133 Revision No. A l

Attachment 4 to U-602297  :

' . . N 3bf48 RC[CSystemInstrumentation l B 3.3.5.2 i BASES SURVEILLANCE SR 3.3.5.2.5 or" T :.2.5.:'.-O (continued)

REQUIREMENTS The Self Test System may be utilized to perform this testing K _for those components that it is desianed to monitor

' Howeve , manual testing, independent of the Self T st Syste , must b performed. This may > accompli ed by test og all c nnels and unctions < sociated w' h an ECCS 1

{ di sion or ie RCIC Sy< em every v months o an gl a ernatin asis suc hat all 1 Funct' ns are tee ed every CS and RC1' channels months. lis Frequ cy is r

3 W- channel < required oiterrelat' based on he logic nships of ie various produce n RCIC ac ation sig 1.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually -

pass the Surveillance when performed at the 18 month Frequency.

REFERENCES 1. USAR, Section 15.4.9.

2. NEDE-770-06-2, " Addendum to Bases for Changes to Surveillance Test latervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.
3. U$AR, Section 5.4.6.

l CLINTON 8 3.3-134 Revision No. A I

LS-94-001 Page 39 pf 48 Primary Contai:.-;ent Isolation Instrumentation B 3.3.6.1 BASES 4

SURVEILLANCE SR 3.3.6.1.3 (continued)

REQUIREMENTS (continued) Allowable Value, the channel performance is still within the requirements of the plant safety analysis. Under these

~ conditions, the setpoint must be readjusted to be equal to-or more conservative than accounted-for in the appropriate setpoint methodology.

The Frequency of 92 days is based on the reliability analysis of References 5 and 6.

SR 3.3.6.1.4 and SR 3.3.6.1.5 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel '

responds to the measured parameter within the necessary range and accuracy. CHANNEL CAllBRATION leaves the channel 1 adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The frequency of SR 3.3.6.1.4 and SR 3.3.6.1.6 is based on-the assumption of the magnitude of equipment drift in the setpoint analysis.

3.3.6.1.6 ;.2 "" '

_S R 2.2.5.'

The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the

.0PERABILITY of the required isolation logic for_ a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant

, outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

l Operating experience has shown these components usually pass j the Surveillance when performed at the 18 month Frequency.

The Self Test System may be utilized to perform this testing

_ _for_those components that it is designed to monitor. ;6, I__

[Howeer,manu i testing, noependent t the delt est 1 IMk -

""[Syc em, must be perforrr .d.

t stino This m be accompl'shed by I

(continued)

CLINTON B 3.3-171 Revision No. A

Attachment 4 to U-602297 LS-94 01 P e ,0f 48 PrimaryContainmentifol ion instrumentation 8 3.3.6.1 BASES SURVFILLANCE SR 3.3.6.1.6- " " E (continued} cp REQUIREMENTS _ /

any nu ber of channe s or Functions ery 18 months an alt ating basis e ch that all ch inels for all F ctions are ested every months. Thic Frequency is b ed on the 1 ic interrela onships of th various channe > required t roduce a Pri ry Containmen solation init' tion signa SR 3.3.6.1./'7 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. The instrument response times must be added to the PCIV closure times to obtain the ISOLATION SYSTEM RESPONSE TIME. ISOLATION SYSTEM RESPONSE TIME acceptance criteria are included in applicable plant procedures.

The Note to SR 3.3.6.1. requires the STAGGERED TEST BASIS Frequency for each function to be determined seperately based on the number of channels as specified on Table 3.3.6.1-1. This Frequency is based on the logic interrelationships of the various channels required to produce an isolation signal.

ISOLATION SYSTEM RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent.

REFERENCES 1. USAR, Section 6.2.

2. USAR, Chapter 15.
3. NE00-31466, " Technical Specification Screening Criteria Application and Risk Assessment,"

November 1987.

4. USAR, Section 9.3.5.
5. NEDC-31677-P-A, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

June 1989.

(continued)

CLINTON B 3.3-172 Revision No. A

Attachment 4 to U-602297 LS 001 Page 41 of 48 Secondary Containment IsolEtion Instrumentation B 3.3.6.2 BASES SURVEILLANCE SR 3.3.6.2.3 (continued)

REQUIREMENTS The Frequency of 92 days is based on the reliability analysis of References 3 and 4.

SR 3.3.6.2.4 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.2.5 w rd GR 3.3.42.k The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing, performed on SCIDs and the SGT System in LCO 3.6.4.2 and LCO 3 6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

".ffMI Operating experience has shown these components usually pass '

l@th the Surveillance when performed at the 18 month Frequency.

REFERENCES 1. USAR, Section 6.2.3.

2. USAR, Chapter IS.
3. NED0-31677-P-A, " Technical Specification Improvement Analysis for BWR lsolation Actuation Instrumentation,"

July 1990.

(continued)

CLINTON B 3.3-184 Revision No. A

. - Attachment 4 to U-602297 LS 001 Page 42 of 48 Insert 184A

. The Self Test System may be utilized to perform this testing for those components that it is designed to monitor .  ::m. . . , .m m . ~ 1 m

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! Attachment 4 to U-602297 LS-94-001 l . .

Page 43 of 48 l

B 3.3.6.3 l

BASES SURVEILLANCE SR 3.3.6.3.5 " " ' ?.E.? E REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.6.1.7, " Residual Heat Removal (RHR) Containment Spray," overlaps this Surveillance to provide complete testing of the assumed safety function.

The Self Test System may be utilized to perform this testing for those components that it is designed to monitor.

i However manuai testing, incepenuent o i- ne auii test  ;

Syste , must be erformed. )is may b' accomplishe y tes ng any nt aer of cha els or Ft tions ever 8 months 7%$ r o an altern- ing basis nctions ~e tested ch that 1 channels or all ery 72 mo hs. This equency is /

~

based on e logic i errelati ships of t _ various channel < required produce n RHR Conta nment Spra System,

@iti< ion signal . J lhe 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at pcwer.

Operating experience has shown these components usually pas; the Surveillance when performed at the 18 month Frequency.

REFERENCES 1. USAR, Section 7.3.1.1.4.

2. USAR, Section 6.2.1.1.5.
3. GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

CLINTON B 3.3-196 Revision No. A

Attachment 4 to U-602297 LS-94-001 P ge 44 of 48 l SPd7 System Instrumentation B 3.3.6.4 BASES  ;

i SURVEILLANCE SR 3.3.6.4.3 and SR 3.3.6.4.4 '

REQUIREMENTS (continued) The calibration of analog trip modules and analog comparator units provides a check of the actual trip setpoints. The channel must be declared inoperable if the trip setting is discovered to be less conservative than the Allowable Value specified in Table 3.3.6.4-1. If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analysis. Under these conditions, the setpoint must L ceadjusted to be equal to or more conservative than accounted for in the appropriate setpoint methodology.

The Frequency of 92 days is based on the reliability analysis of Reference 3.

SR 3.3.6.4.5 and SR 3.3.6.4.6 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The frequency of SR 3.3.6.4.5 and SR 3.3.6.4.6 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

r" SR 3.3.6.4.7 - "  ? . 2 . E . " S- ,

The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in LCO 3.6.2.4, " Suppression Pool Makeup (SPMU) System,"

overlaps this Surveillance to provide complete testine of ,

the assumed safety function. l The Self Test System may be utilized to perform this testing for_those components that it is designed to monitor.

/*M ("JC"%'""J tt F;28""""7 f ' F """/"" h jm, 1

(continued)

CLINTON B 3.3-206 Revision No. A

Attachment 4 to U-602297  !

LS-94-001 1

, . Pag ~e 45 of 48 1 SPMU System Instrumentation B 3.3.6.4 BASES SURVEILLAtlCE SR 3.3.6.4.7 . J "' '3 (continued)

REQUIREMEt1TS k ,

f This m, be accor lished b testing a y number channels '

or F ctions e .ry 18 mo is on an - ternatin asis suc tha all cha els for Functio are tes d every 7 m ths. Th'> frequen is base on the 1 ic iterrela onships the vari s channe required o

[ produce Suppress'on Pool Ma eup Syst ,, initiati. signal.j The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFEREilCES 1. USAR, Section 7.3.1.1.10

2. USAR, Section 6.2.7.
3. GEtlE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

Clif4T0f4 83.3. Revision flo. A

Att-achment 4 to U-602297 l LS-94-001 j Page 46 of 48 l Relief and LLS Instrumentation '

B 3.3.6.S BASES SURVEllLAtlCE SR 3.3.6.5.2 (continued)

REQUIREMENTS SR 3.3.6.5.3. If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analysis. Under these conditions, the setpoint must be readjusted to be equal to or more conservative than accounted for in the appropriate setpoint methodology.

The frequency of 92 days is based on the reliability analysis of Reference 3.

SR 3.3.6.5.3 A CHANilEl CAllBRATI0tl is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHAtlNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

The frequency is based upon the assumption of the magnitude of equipment drif t in the setpoint analysis.

SR 3.3.6.5.4 mut T ' 2.c r .E The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel. The system functional testing performed for S/RVs in LC0 3.4.4, LCO 3.5.1, and LC0 3.6.1.6 overlaps this Surveillance to provide complete testing of the assumed safety function.

The Self Test System may be utilized to perform this testing y for these components that it is designed to monitor, f 7Iow ver, c mual te' ting, nutpunu! m u ip uu aui7 sen IM M I[ > -

S em, t be form (continued)

CLINTON 8 3.3-213 Revision tio. A L. ---.

Attachment 4 to U-602297 LS-94-001 Pay,e 47 of 48 Relief and LLS Instrumentation

  • 8 3.3.6.5 BASES SURVEILLANCE SR 3. 3. 6. 5. 4 ' ' co 2 ' ^ E; 5 (continued) y REQUIREMENTS /

[hisrequenc isbasfrJonthef.gicintfrelations/ipsofl.

the arious iannel/crequired/o produM a relief /nd LLS /

L_1 iation mignalg The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES 1. USAR, Section 5.2.2.

2. USAR, Section 7.3.1.1.1.4.2.
3. GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

CLINTON B 3.3-214 Revision No. A l l

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Attachment 4 to U-602297 LS-94-001 Page 48 of 48 l

INSIURfor Ilags gages B 3.3-28 mB 3.3-73. D 3.3-120. B 3.3-134. B 3.3-171dl 3.3-L96JL3 3-206.

m and 113.3-213 Those portions of the solid-state logic not monitored by the SelfTest System may be tested at the frequency recommended by the manufacturer, rather than at the specified 18-month I requency. The frequencies recommended by the manufacturer are based on mean time between failure analyses for the components in the associated circuits.

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'[? Attachment 4 to U-602297

  • LS-94-001 48 Page 8 E2b5 Instrumentation a

3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentat ion APPLICABLE CONDITIONS H00ES OR REFERENCEO OTHER RECulRED FROM SPECIFitD CHAhNELS PER REQUIRED SURVE!LLANCE ALLOWABLE TUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI 8 and LPCI C Subsystems
a. Reactor vessel Water 1,2,3, 2(D) B SR 3.3.5.1.1 2 147.7 Level - Low Low Low, SR 3.3.5.1.2 inches Level 1 4(a) ,$t a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

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b. Drywell Pressure - High 1,2,3 2(b) B SR 3.3.5.1.1 5 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 SR
3. 3, .5.1.

, e . 6,

c. LPCl Punp 8 1,2,3, 1 C SR 3.3.5.1.2 2 4.5 seconds Start - Time Delay SR 3.3.5.1.4 and Logic Card 4("I,5(a) SR 3.3.5.1.5 5 5.5 seconds

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d. Reactor vessel 1,2,3 4 C SR 3.3.5.1.1 a 452 psig Pressure - Low SR 3.3.5.1.2 and (Injection Permissive) SR 3.3.5.1.3 5 478 psig SR 3.3.5.1.4 SR 3.3.5.1.5 4(a),$(a) 4 8 SR 3.3.5.1.1 1 452 psig SR 3.3.5.1.2 and SR 3.3.5.1.3 5 478 psig SR 3.3.5.1.4 SR -
3. 3, .e5.1.

, 5,

- 7
e. LPCI Pump B and LPCI 1,2,3, 1 per pump E SR 3.3.5.1.1 2 900 gpm Pump C Discharge SR 3.3.5.1.2 Flow - Low (8ypass) 4(a) 5(a)

, 3g 3,3,$,j,3 )

SR 3.3.5.1.4 l SR 3, .7 3.E5.1. 5, l r 1 l l 1

f. Manual Initiation 1,2,3, 1 C SR 3.3.5.1.5, NA i

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4(a) $(a)

(continued)

(a) When asscciated subsystem (s) are required to be OPERABLE.

(b) Also required to initiate the associated diesel generator.

CLINTON 3.3-41 Amendment No. A

Attachment 4 to U-602297

  • 1,S-94-001 Page 9 of 48 ECCS Instrumentation l 3.3.5.1 )

fable 3.3.5.1 1 (page 3 of 5)

Emergency Core Cooling Systein Instrumentation APPLICA8LE CON 0lfl0NS HOCES OR REFERENCE 0 OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCf!DN CONDITIONS FUNCfl0N ACTION A.1 REQUl#EMENTS VALUE

3. High Pressure Core

$ pray (HPCS) System

a. Reactor Vessel 1,2,3, 4(b) 8 SR 3.3.5.1.1  ! 47.7 inches Water Level - Lo= . SR 3.3.5.1.2 Low, Level 2 4 I8) ,5I ") SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3 3.5.1.5 SR 3.3.5.1.6
b. Drywell 1,2,3 4(b) g g, 3,3,5,;,9 3 g,g3 p3;g Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
77 _n
c. Reactor Vessel 1,2,3, 2 C SR 3.3.5.1.1 5 54.2 inches Water sa 3.3.5.1.2 Level - H igh, 4Idl,5 I ") 54 3.3.5,1.3 Levet 8 SR 3.3.5.1.4 SR 3.3.5.1.5 '

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d. RCIC Storage tank 1,2,3, 2 0 SR 3.3.5.1.1 1 0 inches level - Low SR 3.3.5.1.2 4IC) $IC)

, SR 3.3.5.1.3 SR 3.3.5.1.4 SR s 3.3,.5.1.5 e , ,

7

e. Suppression Pool 1,2,3 2 D SR 3.3.5.1.1 5 12 iruhes Water Level - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

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f. HPCS Pi.rp 1,2,3, 1 E SR 3.3.5.1.1 a 120 psig Discharge SR 3.3.5.1.2 Pressure - High 4(4),5(a) gp 3,3,$,j,3 (Bypass) SR 3.3.5.1.4 SR 3.3.5.1.5 1

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g. HPCS System Flow 1,2,3, 1 E SR 3.3.5.1.1 t 500 gra Rate - t ow SR 3.3.5.1.2 (8ypass) 4 I8),5(a) SR 3.3.5.1.3 SR 3.3.5.1.4 sa 3.3.5.1.5

?'r (continued)

(a) When a s soc i a t ed subs ys t em( s ) are required to be OPERABLE.

(b) Also required to inttlate the associated diesel generator.

(c) When HPCS is OPCRABLE f or compliance wi th LCO 3.5.2, "ECCS - Shutdown," and aligned to the RCIC storage tank while tank water levet is not within the Limits of SR 3.5.2.2.

CLINTON 3.3-42 Amendment No. A

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