Text

Amend 71 to License NPF-62,revising Both Surveillance Test Intervals & Allowed out-of-svc Times for Reactor Protection Sys,Eccs,Control Rod Block Sys & Containment & Reactor Vessel Isolation Control Sys Instrumentation
	ML20035F642
Person / Time
Site:	Clinton ; (NPF-62-A-071, NPF-62-A-71)
Issue date:	04/09/1993
From:	Dyer J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20035F643	List: ML20035F642; ML20035F646;
References
	NUDOCS 9304220122
	Download: ML20035F642 (63)
	v • d • e

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>S tig e

jo UNITED STATES g.

8.

NUCLEAR REGULATORY COMMISSION n

.y ap WASHINGTON D.C.20555

%...../

i l

ILLIN0IS POWER COMPANY. ET AL.

.i DOCKET NO. 50-461 l

CLINTON POWER STATION. UNIT NO. 1 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 l

License No. NPF-62 l

1.

The Nuclear Regulatory Comission (the Comission) has found that.

i A.

The application.for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated September 20, 1991, and supplemented by letters dated August 17, 1992, and February 17, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. set forth in 10 CFR Chapter I;

'j B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the

.[

Comission, i

C.

There is reasonable assurance'(i) that the activities authorized

-by this amendment ~can be conducted without endangering the health-

-i and safety of the public, and (ii).that such activities _ will be conducted in compliance with the Comission's regulations; 1

D.

The issuance of this amendment will not be inimical to the comon i

defense 'and security'or to the' health and safety of the public; and j

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements I

have been satisfied.

2.

Accordingly, the' license is amended by changes to the Technical Specifi-

[

cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby-l amended to read as follows:

Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc.- and has. exclusive responsibility and control over the physical construction,. operation and ~ maintenance of the facility.

j i

9304220122 930409 I

PDR ADOCK 05000461.

P PDR.

I

(2)

Technical Specifications and Environmental Protection Plan i

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 71, are hereby incorporated into this license.

Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective immediately to be implemented within 30 days from its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

W bk James E. Dyer, Director l

Project Directorate III-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulatjon

Attachment:

t Changes to the Technical Specifications Date of issuance: April 9, 1993 L

i L

h L

~

FACIllTY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages, indicated by an asterisk, are provided to maintain document completeness.

t Remove Insert Remove Insert 3/4 3-1 3/4 3-1 3/4 3-54 3/4 3-54 3/4 3-2*

3/4 3-2*

3/4 3-57 3/4 3-57 l

3/4 3-7*

3/4 3-8 3/4 3-8 3/4 3-58 3/4 3-58 3/4 3-9 3/4 3-9 3/4 3-59*

3/4 3-59*

3/4 3-10 3/4 3-10 3/4 3-60 3/4 3-60 3/4 3-11 3/4 3-11 3/4 3-61*

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3/4 3-70*

3/4 3-33 3/4 3-33 3/4 3-71*

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3/4 3-34 3/4 3-34 3/4 3-72 3/4 3-72 3/4 3-35 3/4 3-35 3/4 3-73 3/4 3-73 3/4 3-36 3/4 3-36 3/4 3-74*

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3/4 3-38 3/4 3-38 3/4 3-98 3/4 3-98 3/4 3-38a 3/4 3-99 3/4 3-99 3/4 3-43*

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3/4 3-100 3/4 3-100 3/4 3-44 3/4 3-44 3/4 3-101* 3/4 3-10l*

3/4 3-45 3/4 3-45 3/4 3-102 3/4 3-102 3/4 3-46 3/4 3-46 3/4 4-9 3/4 4-9 3/4 3-47 3/4 3-47 3/4 4-10 3/4 4-10 3/4 3-48*

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3/4 4-11 3/4 4-11 3/4 3-49 3/4 3-49 3/4 3-50*

3/4 3-50*

3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 3/4 3-53*

3/4 3-53*

I

p i

3/4.3 INSTRUMENTATION I

3 /4. 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

{

LIMITING CONDITION FOR OPERATION i

3.3.1 As a minimum, the reactor protection system instrumentation channels -

l shown in Table 3.3.1-1 shall be OPERABLE

with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

j APPLICABILITY: As shown in Table 3.3.1-1.

j ACTION:

l a.

For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdow.i 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The.

provisions of Specification 3.0.4 are not applicable.

j 2.

T th 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 l

exists. The provisions of Specification 3.0.4 are not applicable.

{

t 3.

With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.1-1.

j b.

For Reactor Mode Switch Shutdown Position tah the ACTION as shown in l

Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS i

4.3.1.1. Each reactor protection system instrumentation channel shall be -

i 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.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed 'at least once per 18 months.

Reactor protection system divisional logic and portions of the l

channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage such that all trip functions are tested at a

least once every four fuel cycles.

-l:

i

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for l

required surveillance provided at least two OPERABLE channels are monitoring-that parameter.

l i

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

i

~

INSTRUMENTATION i

REACTOR PROTECTION SYSTEM INSTRUMENTATION t

SURVEILLANCE REQUIREMENTS (Continued) 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 2% sonths.

Each test shall include at least'two logic j

trains such that all log (c trains are tested at least once per 36 months and one channel per trip fur <ction such that all channels are tested at least once i

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

l

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d e

l 1

i i

)

CLINTON - UNIT 1 3/4 3-2

~

t

+

TABLE 3.3.1-2 b

REACTOR PROTECTION SYSTEM RESPONSE TIMES 5

E RESPONSE TIME c

FUNCTIONAL UNIT (Seconds) 5 1.

Intermediate Range Monitors:

a.

Neutron Flux - High NA b.

Inoperative NA 2.

Average Power Range Monitor *:

a.

Neutron Flux - High, Setdown NA b.

Flow Biased Simulated Thermal Power - High

< 0.09'*

c.

Neutron Flux - High

< 0.09 d.

Inoperative RA 3.

Reactor Vessel Steam Dome Pressure - High

< 0.33 4.

Reactor Vessel Water level - Low, level 3 7 1.03 w2 5.

Reactor Vessel Water Level - High, level 8 7 1.03 6.

Main Steam Line Isolation Valve - Closure 7 0.04 w

4 7.

Main Steam Line Radiation - High RA 8.

Drywell Pressure - High NA 9.

Scram Discharge Volume Water level - High a.

Level Transmitter HA b.

Float Switches NA 10.

Turbine Stop Valve - Closure

< 0.04 11.'

Turbine Control Valve Fast Closure, Valve Trip System

~

Oil Pressure - Low

< 0.05, 12.

Reactor Mode Switch Shutdown Position NA 13.

Manual Scram NA

Neutron detectors are exempt from response time testing.

Response time shall be measured from the detector output or from the input of the first electronic component in the channel.

- Not including a simulated thermal power time constant of 6 1 0.6 seconds.

Measured from start of turbine control valve fast closure.

TABLE 4.3.1.1-1 P

- 8

. REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

z CilANNEL OPERATIONAL

. g CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH q

FUNCTIONAL UNIT CHECK TEST CALIBRATION (3)

SURVEILLANCE REQUIRED 1.

Intermediate Range Monitors:

' Neutron Flux - High S/U.S,(b)-

S/U(c),W R

2 a.

S W

R 3,4,5

b. -

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor:(I)

IC) a.

Neutron Flux - High, S/U,5,(b)

S/U

,W SA 2

Setdown S

W SA 3,4,5 b.

Flow-Blased Simulated

{

Thermal Power - High-S S/U(c),q y(d)(e),SA,R(I) 1 c.

Neutron Flux - High S

.S/U(c),q y(d)(e), SA.

1

[

d.

Inoperative NA Q

NA 1,2,3,4,5 3.-

Reactor Vessel Steam Dome Pressure - High-S Q

R(9) 1,2(I) 4.

Reactor Vessel Water Level -

Low, Level 3 5

Q R(9) 1, 2 k

5.

Reactor Vessel Water level -

y High, Level 8 5

Q R(9) 1 a

l P.

6.

Main Steam Line Isolation L

Valve - Closure NA Q

R 1-z 7.

Main Steam Line Radiation -

High S

Q R

1,2())

I9)

'1, 2(I)

- 8.

.Drywell Pressure - High' S

Q R

,m_

=_._____.._._____._.m.__........--......_..~,.-_s.__.,-~.._-....-

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

.~.4

....,,-.,....._..,,..-4

TABLE 4.3.1.1-1 (Continued) -

f!-

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ya z

CilANNEL OPERATIONAL CllANNEL FUNCTIONAL-CllANNEL CONDITIONS IN WillCH g

FUNCTIONAL UNIT CilECK TEST CALIBRATION (,)

SURVEILLANCE REQUIRED Z

- y 9.

Scram Discharge Volume Water Level - High

. Q R(9) 1, 2, 5(k) a.

Level Transmitter S

b.

Float Switches NA Q

R 1, 2, 5(k)

10. - Turbine Stop Valve - Closure NA Q(")

R(")

1

11.. Turbine Control Valve Fast Closure Valve. Trip System 011 Pressure - Low NA Q(,)

R(,)

i.

1 l

R 12.

Reactor Mode Switch Shutdown Position NA R

NA 1,2,3,4,5 13.

Manual Scram NA Q

NA 1,2,3,4,5 l

g.

a E

,_+--.-,w,,we---v%-,-.-,-t---w,.,

.e-.vv-swe~.-,

--,e%.w-,-w

. w e E - w -,

,,.m,,--w-,www,y

..w.-.--~

e.-w--'

..w'.,2...-r-e--

--m.---w,-

.m-,,w--,-

v-v:3.<,, - +- - - - -

e.--.

e v,, *,.- - -e-,e tr

-, - ~

P TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 de-cade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1 decade dur-ing each controlled shutdown, if not performed within the previous-7 days.

(c) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup, if not performed within the previous 7 days.

(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.

Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

(e) This calibration shall consist of a setpoint verification of the Neutron Flux-High and the Flow Biased Simulated Thermal Power-High trip functions.

l The Flow Biased Simulated Thermal-High trip function is verified using a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.

(g) Calibrate the analog trip module at least once per 92 days.

l (h) Deleted.

(i) This calibration shall consist of verifying the 610.6 second simulated thermal power time constant.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is. removed per Specification 3.10.1.

(k) With any control rod withdrawn.

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

(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required to be OPERABLE per Special Test Exception 3.10.1.

(m) The CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION shall include the turbine first stage pressure instruments.

i i

CLINTON - UNIT 1 3/4 3-10 Amendment No.30' 71

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . 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 l

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 required by Table 3.3.2-1.

c.

For other CRVICS Isolation Trip Functions:

1.

With the number cf OPERABLE channels less than required.by the Minimum OPEPABLE 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The provisions of l

Specification 3.0.4 are not applicable.

For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed i

in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided the l

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 channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION l

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

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

INSTRUMENTATION CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM I

LIMITING CONDITION FOR OPERATION (Continued) 3.3.2 ACTION (Continued):

2.

With the number of OPERABLE channels less than required by the t

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.

SURVEILLANCE RE0VIREMENTS 4.3.2.1 Each CRVICS 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 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. CRVICS main steam line isolation divisional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage.

Each of the two trip systems or divisions of the CRVICS trip system logic shall be alternately and manually tested independent of the SELF TEST SYSTEM during every other refueling outage. All manual testing shall be completed such that all trip functions are tested at least once every four fuel cycles.

l 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 r

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 i

system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

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

IABli 3.3.2_1_LContinuedl CRVICS INSTRUMENTAi!ON P5$

MINIMUM OPERABLE APPLICABLE ISOLAil0N CilANNELS PER TRIP OPERATIONAL 7

1 RIP FUNCTION

$10.NAL_Lal SYST(M CONDITION ACTION l

5.

RHR SYSTEM ISOLATION a.

RHR Heat Exchanger A, 8 Ambient Temperature - liigh T

1/roomIkI 1, 2, 3 28 b.

RHR Heat Exchanger A, B ATemp. - High S

1/ room (k) 1, 2, 3 28 c...

Reactor Vessel. Water 2 ")

I Level - Low, tevel 3 A

1, 2, 3 28 g

d.

Reactor Vessel Water Level -

Low Low Low, Level 1 U

2gg) 1, 2, 3 28 wi e.

Reactor Vessel (RNR Cut-in I2 *)

1, 2, 3 -

28'

. Permissive). Pressure - High X

f.

Drywell Pressure - High

1).RHR Test Lines--

L 2(k)

I I, 2, 3 28 2 *I 1, 2, 3 28

- 2) Fuel Pool Cooling L

g.

Manual Initiation R

1 1, 2, 3 26-5 af Yr+7t=a T

rr f

'T-eee*

tv k

=*4 wee m

9'

W

=*t m

--M 9-4 e-tv

-.e w-pg g

-wt

-t-vT e'

-'umae.

1 wi "w

re g-eesu w

ev 1-e erwe ereew'*ewew m

e e

.=W-etmre*P-fw-ew e

-w

i TABLE 3.3.2-1 (Continued)

CRVICS INSTRUMENTATION TABLE NOTATIONS When handling irradiated fuel in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

When any turbine stop valve is greater than 95% open or the reactor mode switch is in the run position.

t Main steam line isolation trip functions have 2-out-of-4 isolation logic except for the main steam line flow - high trip function which has 2-out-of-4 isolation logic for each main steam line.

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required l surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the standby gas treatment system.

(c) Deleted (d) Also trips and isolates the mechanical vacuum pumps.

(e)

Isolates RWCU valves 1G33-F001 and JG33-F004 only.

(f) Also actuates secondary containment ventilation isolation dampers.

(g) Manual Switch closes RWCU system inboard isolation valves F001, F028, F053, F040 and outboard isolation valves F004, F039, F034 and F054.

(h)

Vacuum breaker isolation valves require RCIC system steam supply pressure low coincident with drywell pressure high for isolation of vacuum breaker isolation valves.

(i) A single manual isolation switch isolates outboard steam supply line isolation valve (F064) and the RCIC pump suction from suppression pool valve (F031) only following a manual or automatic (Reactor Vessel Water Level 2) RCIC system initiation.

(j) Only actuates secondary containment ventilation isolation dampers.

(k) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required l surveillance without placing the trip system in the trip condition provided tha,t the redundant trip system is OPERABLE and monitoring that parameter.

CLINTON - UNIT 1 3/4 3-18 Amendment No. 71

TABLE 4.3.2.I-1 0

-5 CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CllANNEL OPERATIONAL c:

CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH h

TRIP FUNCTION CHECK TLST CALIBRATION SURVEILLANCE REQUIRED 1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

Low Low, level 2 S

Q R(b) 1, 2, 3, #

b.

Reactor Vessel Water Level -

Low Low, Level 2 (ECCS Ib)

Div. I and II)

S Q

R 1, 2, 3 c.

Reactor Vessel Water Level -

Low Low, level 2 (ECCS Div. III)

S Q

R(b) 1, 2, 3 g

d.

Drywell Pressure - High 5

Q R(b) 1, 2, 3 e.

Drywell Pressure - High (ECCS Ib) 4 Div. I and II)

S Q

R 1, 2, 3 f.

Drywell Pressure - High (ECCS Div. III)

S Q

R(b) 1,2,3 g.

Containment Building Fuel Transrar Pool Ventilation Plenum Radiation - High S

Q R

h.

Containment Building Exhaust Radiation - High S

Q R

1,2,3,#

1.

Containment Building Contin-E uous Containment Purge (CCP) Exhaust Radiation -

?.

High S

Q R

1,2,3,#

E

TABLE 4.3.2.1-1 (Continued)

E CRVICS INSTRllMENTATION SURVEILLANCE REQUIREMENTS z

CilANNLL OPERAT10NAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WillCH E

TRIP FUNCTION CllECK TEST CALIBRATION SURVEILLANCE REQUIRED Q'

w 1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION (Continued) j.

Reactor Vessel Water Level-Low Low Low, level 1 5

Q R(b) 1, 2, 3, #

l k.

Containment Pressure - High 5

Q R

1,2,3,#

l 1.

Main Steam Line Radiation -

High S

Q R

1, 2, 3 l

m.

Fuel Building Exhaust Radiation - High S

Q R

1,2,3,#

l n.

Manual Initiation HA R

NA 1, 2, 3, #

g 2.

MAIN STEAM LINE ISOLATION a.

Reactor Vessel Water Level -

w b) 4 Low Low Low, level 1 S

Q R

1,2,3 l

b.

Main Steam Line Radiation -

High S

Q R

1,2,3 l

c.

Main Steam Line Pressure -

Low S

Q R(b) 1 l

d.

Main Steam Line Flow - High S

Q R(b) 1, 2, 3 l

e.

Condenser Vacuum - Low S

Q R(b) 1, 2**, 3**

l R

f.

Main Steam Line Tunnel l

9 Temp. - High S

Q R

1,2,3 l

e m

g.

Main Steam Line Tunnel A Temp. - High S

Q R

1,2,3 l

l g

h.

Main Steam Line Turbine Bldg.

l Temp. - High S

Q R

1,2,3 l

i.

Manual Initiation NA R

NA 1,2,3 i

r 8

e

,m-

+

TABLE 4.3.2.1-1 (Continued)

Py CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS z

CHANNEL OPERATIONAL g

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WhICH q

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High 5

Q R

1,2,3 b.

A Flow Timer NA Q

Q 1,2,3 c.

Equipment Area Temp. - High 1.

Pump Rooms - A, B, C S

Q R

1,2,3 2.

Heat Exchanger Rooms -

East, West S

Q R

1,2,3 d.

Equipment Area a Temp. - High 1.

Pump Rooms - A, B, C S

Q R

1,2,3

,s 2.

Heat Exchanger Rooms -

[

East, West S

Q R

1,2,3 E

e.

Reactor Vessel Water Level - Low Low, Level 2 5

Q R(b) 1, 2, 3, #

f.

Main Steam Line Tunnel Ambient Temp. - High S

Q R

1, 2, 3 l

g.

Main Steam Line Tunnel l

g a Temp. - High S

Q R

1, 2, 3 g

h.

SLCS Initiation NA Q(a)

NA 1, 2, 5*

k 1.

Manual Initiation NA R

NA 1,2,3,#

4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION O

l a.

RCIC Steam Line Flow - High S

Q R(b) 1, 2, 3 b.

RCIC Steam Line Flow - High l

Timer NA Q

R 1,2,3

TABLE 4.3.2.1-1 (Continued) n C

CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

c:

CilANNEL OPERATIONAL

- 5 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICH

[

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) c.

RCIC Steam Supply Pressure -

Low.

S Q

R(b) 1,2,3 d.

RCIC Turbine Exhaust Diaphragm Pressure - High S

Q R(b) 1,2,3 e.

RCIC Equipment Room Ambient Temperature - High S

Q R

1,2,3 R

f.

RCIC Equipment Room a Temp. -

High S

Q R

1,2,3 d,

g.

Main Steam Line Tunnel Ambient Temp. - High S

Q R

1, 2, 3 h.

Main Steam Line Tunnel a Temp. - High S

Q R

1,2,3 1.

Main Steam Line Tunnel Temp. Timer NA Q

R 1, 2, 3

- [

j.

Drywell pressure - High S

Q R(b) 1, 2, 3 5-k.

Manual Initiation.

NA R

NA 1, 2, 3 id=

1.

'RHR/RCIC Steam Line Flow -

[

High 5

Q R(b) 1, 2, 3 P

m.

RHR Heat Exchanger A, B g

Ambient Temperature - High S

Q R

1,2,3 n.

RHR Heat Exchanger A, B a Temp. - High 5

Q R

1, 2, 3

_,m e

..r

.... _., ~..,

TABLE 4.3.2.1-1 (Continued)

CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS z

e CHANNEL OPERATIONAL e

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 5.

RHR SYSTEM ISOLATION a.

RHR Heat Exchanger Rooms A, 8 Ambient Temp. - High 5

Q R

1, 2, 3 b.

RHR Heat Exchanger Rooms A, B a Temp. - High 5

Q R

1,2,3 c.

Reactor Vessel Water Level -

Low, level 3 S

Q R(b) 1, 2, 3 d.

Reactor Vessel Water level -

Low Low Low, level 1 S

Q R(b) 1, 2, 3 R

e.

Reactor Vessel (RHR Cut-in Permissive) Pressure - High S

Q R(b) 1, 2, 3 wa f.

Drywell Pressure - High I)

1) RHR Test Line S

Q R

1, 2, 3 I)

2) Fuel Pool Cooling S

Q R

1, 2, 3 g.

Manual Initiation NA R

NA 1,2,3 N

ait a.

O.

TABLE 4.3.2.1-1 (Continued)

CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS

When handling irradiated fuel in either the secondary or the primary containment and during CORE ALTERATIONS and operations with a potential for draining the. tactor vessel.

1. When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

With any control rod withdrawn.

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

- When any turbine stop valve is greater than 95% open or the reactor mode switch is in the run position.

(a) Each train or logic channel shall be tested at least every other 92 days.

l (b) Calibrate the analog trip modules at least once per 92 days.

l t

CLINTON - UNIT 1 3/4 3-32 Amendment No.44 71

INSTRUMENTATION 3 /4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION 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 t

Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.

APPLICABilfTY: As-shown in Table 3.3.3-1.

ACTION:

With an ECCS actuation instrumentation channel trip setpoint less a.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , provided either the HPCS or RCIC systems are inoperable.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to s 100 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE 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. The actuation system logic associated with each of the ECCS divisions shall be manually tested independent of the SELF TEST SYSTEM i

during alternate refueling outages such that all divisions and all trip functions are tested at least once_ every four fuel cycles.

l 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 i

system.

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

.x.,

1 TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

.y.

E' MINIMUM OPERABLE APPLICABLE g

CHANNELS PER TRIP OPERATIONAL

j. J TRIP FUNCTION:

FUNCTION CONDITIONS ACTION

~

A.-

p_IVISION I TRIP SYSTEM

.l.

RHR-A (LPCI MODEl &'LPCS SYSTEM a.

Reactor Vessel Water level - low Low Low,

. Level 1 2 (6"'"

1, 2, 3, 4*, 5*

30 b.

Drywell Pressure - High 2 ( b' '

1, 2, 3 30

-c.

Reactor Vessel Pressure-Low 4'*"

I, 2, 3 32 (LFCI and LPCS Injection Valve Permissive) 4*, 5*

33 d.-.LPCIPumpl(A)StartTimeDelaygogicCard I"'

1, 2, 3, 4*, 5*

32 LPCS Pump Discharge Flow ' Low 1"'

1, 2, 3, 4*, 5*

40 3

e;.

f.

LPCI Pump (A) Discharge Flow - Low

1"'

1, 2, 3, 4 *, 5*

g.,

. Manual Initiation 1(6' 1, 2, 3, 4*,

5*.

40 35 2.

@T0MATIC 'DEPRESSURIZATION SYSTEM TRIP SYSTEM'"1"'

ADS LOGIC "A" AND "E"

a.. ' Reactor Vessel Water level - Low Low Low, Level 1 2""

1, 2, 3 30 b.

Drywell. Pressure - High 2""

1, 2, 3 30 c.

! ADS. Timer 1")

1, 2, 3 32

^

d.

LReactor Vessel Water. Level

Low, 3'

e.

LPCS Pump Discharge Pressure-High-.

1"'

I, 2, 3 30

~ Level 3'(Permissive)

J-(Pemissive) 2 ""

1, 2, 3 32 a.-

f.

LPCI Pump (A) Discharge Pressure-High

3

'(Pemissive) 2""')

1, 2, 3 32

.E' g.

- ADS Drywell Pressure Bypass Timer 2"'

1, 2, 3 32

=

h.-

Manual Inhibit ADS Switch-1 1, 2, 3 35

?

1. -- l Manual Initiation 2'

- 1, 2,- 3 35 0

G i."- a m ~.-.-..

...-.--..-.----,v...w

.,,.,.,mw......

...w..+.m..-.,..,.-.

e.#-..-.--..wm.--.c.

s.

.-u...-%-

,.., - *4.e.

..E.-=,-..-,e

=,---.~~...,,.,..--..n.

El TABLE 3.3.3-1 (Continued)

Es g

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE APPLICABLE y

CilANNELS PER TRIP OPERATIONAL TRIP FUNCTION FUNCT10N CONDITIONS ACTION B.

DIVISION II TRIP SYSTEM 1.

RHR B & C (LPCI MODE) a.

Reactor Vessel Water level - Low low Low, level 1 2'b''

1, 2, 3, 4*, 5*

30 b.

Drywell Pressure - liigh 2'6" * "

1, 2, 3 30 c.

Reactor Vessel Pressure-Low 4 "' '

1, 2, 3 32 (LPCI Injection Valve Permissive) 4*,

5*

33 w-d.

LPCIPump(B)StartTimeDelayLoggCard l

1, 2, 3, 4 *, 5*

32 e.

LPCI Pump (B) Discharge Flow - Low l

1, 2, 3, 4*, 5*

40 m

4, f.

LPCI Pump (C) Discharge Flow - Low,

I

1, 2, 3, 4*,

5*

40 g

g.

Manual Initiation Icb>

1, 2, 3, 4*, 5*

35 m

2.

AUTOMATIC _DEPRESSURIZATION SYSTEM TRIP SYSTEM "2"#

&DS LOGIC "B" AND "F" a.

Reactor Vessel Water Level - Low Low Low, Level 1 2'*"

1, 2, 3 30

b..

Drywell Pressure - liigh 2 ' * "

1, 2, 3 30 c.

ADS Timer l

I, 2, 3 32 d.

Reactor Vessel Water Level - Low, level 3 y

(Permissive) l

1, 2, 3 30 e.

LPCI Pump (B and C) Discharge Pressure -

a-h liigh (Permissive) 2[p, ump'*"

1, 2, 3 32 g

f.

ADS Drywell Pressure Lypass Timer 2

1,2,3 32 g.

Manual Inhibit ADS Switch 1

1, 2, 3 35 r+

y h.

Manual Initiation 2

1, 2, 3 35 0

TABLE 3.3.3-1 (Continued)

P-g EMERGENCY CORE COOLING' SYSTEM ACTUATION INSTRUMENTATION El g

MINIMUM OPERABLE APPLICABLE E

CilANNELS PER TRIP OPERATIONAL q.

-TRIP FUNCTION.

FUNCTION CONDITIONS ACTION

~

C.

DIVISION III TRIP SYSTEM 1.

' HPCS SYSTEM-a.

- Reactor Vessel Water Level-Low, Low, level 2 4"'"*"'"

1, 2, 3, 4*, 5*

36 b.

Drywell Pressure - High t 4 "'" * " '"' )

1, 2, 3 36 c.

Reactor Vessel Water Level-High, level 8 2""

1, 2, 3, 4*, 5*

35

' d.-

RCIC~ Storage Tank Level-Low 2 (d"

1, 2, 3, 4 *, 5

37 e.

Suppression Pool Water level-High 2(d"*)

1, 2, 3, 4*, 5*

37 g

f.

- HPCS Pump Discharge Pressyge-High,

1 1, 2, 3, 4*, 5*

41 m1

- g.-

HPCS: System Flow Rate-Low 1-1, 2, 3, 4*, 5*

41 h.-

- Manual Initiation't 1

1, 2, 3, 4*, 5*

35 w

de m

MINIMUM APPLICABLE l

TOTAL NO.

CHANNELS OPERABLE OPERATIONAL l-0F CHANNELS TO TRIP-CHANNELS CONDITIONS-ACTION l

D.

LOSS:OF POWER-1.

4.16 kV Emergency Bus Undervoltage

-(Loss of Voltage)

L a.

- Divisions I & II 2/ Division 2/ Division 2/ Division 1, 2, 3, 4**, 5**

38 l

lb.

Division III 4

2 4

1, 2, 3, 4**, 5**

38 2.

-4.16 kV Emergency Bus Undervoltage y

(Degraded Voltage) g a..

Divisions I & II

. 2/ Division 2/ Division 2/ Division 1, 2, 3,_4**, 5**

39 g.

b.

Division III-it~

3 3

3

. 1, 2, 3, 4**, 5**

39

.E.

X em,.s,---.

-e-,,me,-

, su N, re,-,ee

-wweA-r n

-ve<

v-e-

,mm, s o-se w w--

w e vetv-m mA-,

=m

, e.. s s ens-s,--s

+>,c,<.,em-,,rs

,-en,-e r

re, e r.-,s.-..~,-e-n.-

e----

o ~~ - -,<-n-

~ ~ - - < - - -

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION TABLE NOTATIONS (a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during l

periods of required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the associated division diesel generator.

(c)

Provides signal to close HPCS pump injection valve only.

(d)

Provides signal to HPCS pump suction valves only.

(e)

These channels are required in order to maintain automatic trip capability as ider.tified in the associated ACTION statements.

(f) Deleted.

(g) One-half of these trip channels is associated with Nuclear Systems Protection System (NSPS) Division III; the other half is associated with NSPS Division IV.

When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.

Required when ESF equipment is required to be OPERABLE.

Not required to be OPERABLE when reactor steam dome pressure is s 100 psig.

These Trip Functions are not required for ECCS actuation.

t The HPCS initiation functions of the Drywell Pressure - High and Manual Initiation are not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level-8 setpoint coincident with the reactor steam dome pressure less than 600 psig.

tt One relay with three inputs in 3 out of 3 logic.

e v

h CLINTON - UNIT 1 3/4 3-37 Amendment No. 71

l l

l TABLE 3.3.3-2 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION i

ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirements, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic actuation capability of either Division I or Division II ECCS and either ADS Trip System I or Trip System 2, and place the inoperable channel (s) in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *. Otherwise, declare the associated system (s) inoperable.

ACTION 31 -

Deleted.

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE or are in the tripped condition to maintain automatic actuation capability of either Division I or Division II ECCS and either ADS Trip System I or Trip System 2, and restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare the associated ADS trip system (s) or ECCS inoperable.

ACTION 33 -

With the number of OPERABLE channels less than the Minimum i

OPERABLE Channels per Trip Function requirement, place the inoperable channel (s) in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l ACTION 34 -

Deleted.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPEPABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the associated ADS valve or ECCS l

inoperable.

ACTION 36 -

With the number of OPEPABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPEPABLE or are in the tripped condition to maintain automatic HPCS actuation capability, and place the inoperable channel (s) in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *. Otherwise, declare the HPCS system inoperable.

ACTION 37 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that the HPCS pump suction is either aligned or is capable of automatically realigning to the suppression pool, and place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *. Otherwise, declare the HPCS system inoperable.

i

The provisions of Specification 3.0.4 are not applicable.

CLINTON - UNIT I 3/4 3-38 Amendment No. 71

l TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 38 -

With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator l

inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 39 -

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped i

condition within I hour *; operation may then continue until 1

performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 40 -

With the number of OPERABLE channels less than required by the l

Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain i

a OPERABLE or are in the tripped condition to maintain automatic actuation capability of either Division I or Division II ECCS, and restore the inoperable channel (s) to OPERABLE status within 7 days.

Otherwise, declare the associated system (s) inoperable.

l ACTION 41 -

With the number of OPERABLE channels less that required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel (s) to OPERABLE status within 7 days. Otherwise, declare the HPCS system inoperable.

l i

i

The provisions of Specification 3.0.4 are not applicable.

CLINTON - UNIT 1 3/4 3-38a Amendment No. 71

,l f

b i

TABLE 3.3.3-3 EMERGENCY CORE COOLING SYSTEM' RESPONSE TIMES ECCS RESPONSE TIME (Seconds) i 1.

LOW PRESSURE CORE SPRAY SYSTEM

$ 37 l

i 2.

LOW PRESSURE COOLANT INJECTION MODE 0F RHR SYSTEM a.

Loops A, B and C

< 37 l

.)

3.

AUTOMATIC DEPRESSURIZATION SYSTEM NA 4.

HIGH PRESSURE CORE SPRAY SYSTEM i 27 i

5.

LOSS OF POWER NA 1

i

.i I

i I

I I

I i

t

-1 f

l

?

I 1

i CLINTON - UNIT 1 3/4 3-43

.l i

l

6 TABLE 4.3.3.1-1 PG EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RfQUIREMENTS

=

CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CllANNEL CONDITIONS FOR WHICll Z

TRIP FUNCTION CllECK TEST CALIBRATION SURVEILLANCE REQUIRED w

A.

DIVISION I TRIP SYSTEM 1.

RHR-A (LPCI MODE) AND LPCS SYSTEM a.

Reactor Vessel Water Level -

Low Low Low, level 1 5

Q R(a) 1, 2, 3, 4*,

5*

b.

Drywell Pressure - High 5

Q R(a) 1, 2, 3 c.

Reactor Vessel Pressure-Low (LPCI and LPCS Injection Valve Permissive)

S Q

R(")

1, 2, 3, 4*, 5*

d.

LPCI Pump A Start Time Delay Logic Card NA Q

R 1, 2, 3, 4*, 5*

g) e.

LPCS Pump Discharge Flow-low 5

Q R

1,2,3,4*,5*

f.

LPCI Pump (A) Discharge Flow w

8)

}

-Low S

Q R

1, 2, 3, 4 *, 5

g.

Manual Initiation NA R

NA 1, 2, 3, 4*,

5*

A 2.

AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSIEM "1"#

ADS LOGIC "A" AND "E" a.

Reactor Vessel Water Level -

Low Low Low, level 1 S

Q R(a) 1, 2, 3 b.

Drywell Pressure-High 5

Q R(a) 1, 2, 3 g

3 c.

ADS Timer NA Q

R 1,2,3 g-d.

Reactor Vessel Water Level -

g Low, Level 3 S

Q R(,)

1,2,3 e+

e.

LPCS Pump Discharge g

Pressure-High '

S Q

R(,)

1,2,3 f.

LPCI Pump A Discharge Pressure-liigh S

Q R(,)

1,2,3 w

g.

ADS Drywell Pressure Bypass Timer NA Q

R 1,2,3 h.

Manual Inhibit ADS Switch NA Q

NA 1, 2, 3 1.

Manual Initiation NA R

NA 1,2,3

TABLE 4.3.3.1-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS z

CilANNEL OPERATIONAL c

CilANNEL FUNCTIONAL CilANNEL CONDITIONS FOR WilICil TRIP FUNCTION CilECK TEST CALIBRATION SURVEILLANCE REQUIRED B.

DIVISION II TRIP SYSTEM 1.

RHR B AND C (LPCI MODE) a.

Reactor Vessel Water Level -

Low Low Low, level 1 S

Q R(")

1, 2, 3, 4*,

5*

b.

Drywell Pressure - liigh 5

Q R(a) 1, 2, 3 c.

Reactor Vessel Pressure-Low (LPCI Injection Valve Permissive)

S Q

R(a) 1, 2, 3, 4*, 5*

d.

LPCI Pump B Start Time Delay Logic Card NA Q

R 1, 2, 3, 4*, 5*

R e.

LPCI Pump (B) Discharge Flow R,)

-Low S

Q 1, 2, 3, 4*, 5*

Y f.

LPCI Pump (c) Discharge Flow C.

-Low S

Q R$a) 1, 2, 3, 4", 5*

g.

Manual Initiation NA R

NA 1, 2, 3, 4*, 5*

2.

AUTOMATIC DEPRESSURIZATION SYSTEM

_ TRIP SYSTEM "2"#

ADS LOGIC "B" AND "F" p

Eih 8

a.

Reactor Vessel Water Level -

E Low Low Low, Level 1 S

Q R(a) y, p, 3 2

b.

Drywell Pressure-High S

Q R(a) 1, 2, 3 c.

A05 Timer NA Q

R 1, 2, 3 d.

Reactor Vessel Water Level -

2 P

Low, level 3 5

Q R(,)

1, 2, 3 u

e.

LPCI Pump (B and C) Discharge Pressure-High S

Q R(")

1, 2, 3 f.

ADS Drywell Pressure Bypass Timer NA Q

R 1, 2, 3 g.

Manual Inhibit ADS Switch NA Q

NA 1, 2, 3 h.

Manual Initiation NA R

NA 1,2,3

_ TABLE 4.3.3.1-1 (Continued) h EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRdMI NTAll0N SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL E

CHANNEL FUNCTIONAL CilANNEL CONDITIONS FOR WillCil TRIP FUNCTION CllECK TES1 CALIBRATION SURVEILLANCE REQUIRED e-4 C.

DIVISION III TRIP SYSTEM 1.

HPCS SYSTEM a.

Reactor Vessel Water Level -

Low Low, level 2 5

Q R(a) 1, 2, 3, 4*, 5*

5 R *)

1, 2, 3 b.

Drywell Pressure-High S

Q c.

Reactor Vessel Water Level-High, level 8 5

Q R(a) 1, 2, 3, 4*, 5*

d.

RCIC Storage Tank Level -

IR ")

1, 2, 3, 4*, 5*

Low S

Q e.

Suppression Pool Water w}

Level - High S

Q R(,)

1, 2, 3, 4*,

5*

f.

HPCS Pump Discharge Pressure 4

-High S

Q R(3) 1, 2, 3, 4*, 5*

g.

HPCS System Flow Rate-Low S

Q R(a) 1, 2, 3, 4*, 5*

m h.

Manual Initiation NA R

NA 1, 2, 3, 4 *, 5*

D.

LOSS OF POWER 1.

4.16 kV Emergency Bus Under-NA NA R

1, 2, 3, 4**, 5**

p voltage (Loss of Voltage)

M 2.

4.16 kV Emergency Bus Under-S H

R 1, 2, 3, 4**, 5**

8.

voltage (Degraded Voltage)

S a

E.

~. - -

i I

3 TABLE 4.3.3.1-1 (Continued) i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENI l

TABLE NOTATIONS Not required to be OPERABLE when reactor steam dome pressure is < 100 psig.

f l

When the system is required to be OPERABLE per Specification 3.5.2.

l Required when ESF equipment is required to be OPERABLE.

(a) Calibrate the analog trip module at least once per 92 days.

j i

T l

1 t

I i

'l 1

i

?

l

?

f i

t F

i i

CLINTON - UNIT 1 3/4 3-47 Amendment No. 71

INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.1-2.

APPLICABitITY: OPERATIONAL CONDITION 1.

ACTION:

a.

With an ATWS-RPT system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.4.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With the number ef OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, pisce at least one inoperable channel in the tripped condition within one hour, and place the second inoperable channel in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Otherwise, be'in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With both trip systems otherwise incperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.3.4.1.1 Each ATWS-RPi system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1.

4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

CLINTON'- UNIT 1 3/4 3-48 Amendment No. 64

p g

1Antt A L4.t_

E AESdllCI8CULAll0N_(' UMP IRIP SYSilH IN51RUMJ NTAll0N EU TRIP FUNCTION HINIMUM OPERABLE CIIANN[ts ElR TRIP SYSTEM '*'

l.

Reactor Vessel Water level -

low low Level 2 2

2.

Reactor Vessel Pressure - liigh 2

(a)

One trip system may be placed in an inoperable status for up t R.

^

a.

A

.EF

T ABLE 3.3.4.1-2 b

ATWS RECIRCULATION PUMP 1 RIP SYSTEM INSTRUMENTA110N SETPOINTS 5E-TRIP ALLOWABLE SETPOINT VALUE TRIP FUNCTION e

> -45.5 in.*

> -50.0 in.

5*

1.

Reactor Vessel, Water level -

~

H Low low, level 2 2.

Reactor Vessel Pressure - liigh i 1127 psig 1 1150 psig

See Bases Figure 83/4 3-1.

M.

Y E

9 9

i...

TABLE 4.3.4.1-1 9y ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEN 8

z CilANNEL CilANNEL FUNCTIONAL CilANNEL g

TRIP FUNCTION C11ECK TEST CAllBRATION Z

1.

Reactor Vessel Water Level -

S Q

R*

l g

Low Low, level 2 2.

Reactor Vessel Pressure - liigh S

Q R8 l

Calibrate trip unit at least once per 92 days.

R.

Y F

a i

i INSTRUMENTATION 1

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumen-l tation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip i

setpoints set consistent with the values shown in the Trip Setpoint column of i

Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM i

RESPONSE TIME as shown in Table 3.3.4.2-3.

]

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

I ACTION:

I a.

With an end-of-cycle recirculation pump trip function instrumentation j

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 l

until the channel is restored to OPEPABLE 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The provisions of Specification 3.0.4 are not applicable.

c.

With two of the f our channels required for. any Trip Function inoperable,-

place one channel in the tripped condition within six hours provided no.

l l

tripped channel.for that Trip Function already exists. The provisions of-i Specification 3.0.4 are not applicable.

i d.

With three of the four channels required for any Trip Function inoperable, reduce THERMAL POWER to less than 40% of RATED THERMAL POWER l

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

j t

SURVEILLANCE RE0VIREMENTS 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 CALIBRATION operations at the frequencies shown in Table 4.3.4.2-1.

[

4.3.4.2.2~ LOGIC SYSTEM FUNCTIONAL TESTS shall be perfonned at least once per.

1 18 months. Divisional logic and portions of the channel coincident logic-i shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage such that all trip functions are tested at least once every j

four fuel. cycles.

I i

i l

CLINTON'- UNIT I 3/4 3-52 Amendment No. 71

i 1

i INSTRUMENTATION 4

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION t

SURVEILLANCE REQUIREMENTS (Continued) i 4.3.4.2.3 The END-OF-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 l

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 l

at least once per 36 months.

i f

d f

P r

I

?

l i

b CLINTON - UNIT 1 3/4 3-53 l

TABLE 3.3.4.2-1 P;;

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 8

z MINIMUM OPERABLE E

CHANNELS {ggTRIP tj TRIP FUNCTION FUNCTION 1.

Turbine Stop Valve - Closure 4(b) 2.

Turbine Control Valve-Fast Closure 4(b)

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required survelliance l

provided at least two OPERABLE channels are monitoring that parameter.

(b) This function shall be automatically bypassed when turbine first stage pressure is less than the value of turbine first stage pressure corresponding to 40% of RATED THERMAL POWER.

R Y

T l

a R

a*

I Ei 1

U l

l 1

.TADLE 4.3.4.2-1

?

E END-OF-CYCLE RECIRCULATION PUMP 1 RIP SYSTEM SURVEILLANCE REQUIREMENTS z

CilANNEL E

FUNCTIONAL CHANNEL q

TRIP FUNCTION TEST CALIBRATION 1.

Turbine-Stop Valve-Closure Q

R 2.

Turbine Control alve-Fast Closure Q

R R.

Y

!G W

a R-a*

INSTRUMENTATION 1

3/a.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTAT10M llMITING 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 RE0UIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL l

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 performed at least once per 18 l

months. All RCIC actuation system logic shall be manually tested independent of the SELF TEST SYSTEM such that all trip functions are tested at least once every four fuel cycles.

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

n TABLE 3.3.5-1 5

E REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION

-c5.

MINIMUM FUNCTIONAL UNITS OPERABLE CHANNELS 9

PER TRIP SYSTEM ACTION Reactor Vessel Water level - Low Low, level 2 2(b)(a) a.

50

~ b.

Reactor Vessel Water Level - Hfgh, level 8 IC) 2 51 RCIC Storage Tank Water Level - Low 2(d)(a) c.

52 d.

Suppression Pool Water Level - Hfgh 2(d)(a) 52 e.

Manual Initfation I '}

I 53 M.

i

... - - ~

I TABLE 3.3.5-1 (Continued)

REACTOR CORE ISOLATION C0C ING SYSTEM ACTUATION INSTRUMENTATION TABLE NOTATIONS (a) A channel may be p Med in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for l

required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Two trip systems with two channels per trip system.

i (c) One trip sys.em with two-out-of-two logic, (d) One trip system with one-out-of-two logic.

(e) One trip system with one channel.

ACTION t

ACTION 50 -

With the number of OPERABLE channels less than required by the Minimum OPEPABLE Channels per Trip System requirement, verify within one hour that a sufficient number of low reactor vessel water level channels remain OPERABLE or are in the tripped condition to maintain automatic RCIC system actuation capability, and place the inoperable channel (s) in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement, declare the RCIC system inoperable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l ACTION 52 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, verify within one hour that the RCIC pump suction is aligned or will automatically realign to the suppression pool, and place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare the RCIC system inoperable.

ACTION 53 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or l

declare the RCIC system inoperable.

CLINTON - UNIT 1 3/4 3-60 Amendment No. 71 l

o c.,

TABLE 3.3.5-2 C".

E

. REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS e

g FUNCTIONAL UNITS

. ALLOWABLE TRIP SETPOINT VALUE N

Reactor Vessel Water Level - Low Low, level 2

> -45.5 in.*

> -47.7 in, a.

b.

Reactor Vessel Water Level:- High. Level 8 5 52.0 in.*

$ 52.6 in.

c.

RCIC Storage _ Tank Level - Low

> 3\\ in.**

1 0 in.**

d.

Suppression Pool Water Level - High-5 -8 in.t 1 -3 in.t l

e.

Manual Initiation NA NA R.

.e

See Bases Figure 8 3/4 3-1.

- Instrument zero is:739' 10-3/4" as1.

t Instrument zero is 732' 8" as1.

l 5

&g r

o m-.

. -m---

4-,,

.-w-w

-,w

+4 w

n w

TABLE 4.3.5._-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

$z CllANNEL c

CllANNEL FUNCTIONAL CilANNEL h

FUNCT10NAL UNITS CliECK TEST CAllDRATION a.

Reactor Vessel Water Level -

Low Low, level 2 S

Q R(,)

b.

Reactor Vessel Water Level - High, level 8 5

Q R(3) c.

RCIC Storage Tank Level - Low 5

Q R(a) d.

Suppression Pool Water Level -

liigh S

Q R(3)

R e.

Manual Initiation NA R

NA Y

E (a) Calibrate the analog trip module at least once per 92 days.

E R

Br 4

INSTRUMENTATION 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6 The control rod block instrumentation channels shown in Table 3.3.F-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

With a control rod block instrumentation channel trip setpoint less a.

conservative than the value shown in the Allowable Value column of Table 3.3.6-2, declare the channel inoperable'until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

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

SURVEILLANCE REOUIREMENTS 4.3.6 Each of the above required control rod block trip systems and instru-mentation channels 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 4.3.6-1.

1 CLINTON - UNIT 1 3/4 3-63

TABLE 3.3.6-I P

$2 CONTROL ROD BLOCK INSTRIIMENTA110N 8

MINIMUM APPLICABLE OPERABLE CHANNELS (")OPERATIONAL E

TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION 4

1.

ROD PATTERN CONTROL SYSTEM g

a.

Low Power Setpoint 2

1, 2 60 b.

RWL High Power Setpoint 2

1 60 2.

APP.M a.

Flow Biased Neutron Flux - Upscale 3

1 61 b.

Inoperative 3

1, 2, 5 61 c.

Downscale 3

1 61 d.

Neutron Flux - Upscale, Startup 3

2, 5 61 3.

SOURCE RANGE MONITORS Detector not full in(a) 3 2

61 a.

R 2**

5 62 b.

Upscale (b) 3 2

61 w

2**

5 62 Inoperative ( )

3 2

61 h

c.

2**

5 62 d.

Downscale(c) 3 2

61 2**

5 62 4.

INTERMEDIATE RANGE MONITORS a.

Detector not full in 6

2, 5 61 g

b.

Upscale 6

2, 5 61 y

c.

Inoperative 6

2, 5 61 k

d.

Downscale(d) 6 2, 5 61 5

5.

SCRAM DISCHARGE VOLUME f

a.

Water Level-High 2

1, 2, 5*

64 l

3 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale 3

1 64 7.

REACTOR MODE SWITCH a.

Shutdown Mode 2

3, 4 63 b.

Refuel Mode 2

5 63 m

~ _.. _ _

._2 c

i TABLE 3.3.6-1 (Continued) l CONTROL ROD BLOCK INSTRUMENTATION TABLE NOTATIONS i

I With more than one control rod withdrawn. Not applicable to control l

rods removed per Specification 3.0.10.1 or 3.9.10.2.

OPERABLE channels must be associated with SRMs required OPERABLE per

{

Specification 3.9.2.

(a)

This function shall be automatically bypassed if detector count rate.is

> 100 cps or the IRM channels are on' range 3 or higher.

(b)

This function shall be automatically bypassed when the associated IRM l

channels are on range 8 or higher.

(c)

This function shall be automatically bypassed when the IRM channels are on range'3 or higher.

(d)

This function shall be autotuatically bypassed when the IRM channels-are

[

on range 1.

i (e)

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for l-required surveillance provided at least one other OPERABLE channel in the same trip function is monitoring that parameter.

a ACTION ACTION 60 - Declare the RPCS inoperable and take the ACTION required by.

Specification 3.1.4.2.-

i)

ACTION 61 - With the number of OPERABLE Channels:

i One less than required by the Minimum OPERABLE Channels per a.

Trip Function requirement, restore the inoperable channel to i

OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.

j b.

Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least.one i

inoperable channel in the tripped condition within I hour.

ACTION 62 - With the number of OPERABLE channels less than required by the Minimum'0PERABLE Channels per Trip Function requirement, place the-inoperable _ channel in the tripped condition within I hour.

i ACTION 63 - With the number of OPERABLE channels less than required by the

~

Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

ACTION 64 - With the number of OPERABLE Channels'.less than required by the

~ Minimum OPERABLE Channels per Trip function requirement,; verify l

within one hour that a sufficient number of channels remain i

OPERABLE to initiate'a rod block by the associated Trip Function, and place at least one inoperable channel in the tripped condition j

within'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, initiate a rod block CLINTON - UNIT I 3/4'3-65

' Amendment No.,71-

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-N f4 et CLINTON - UNIT 1 3/4'3-66 Amendment No. 18 m

m

.-- - m.

.m

l i

TABLE 3.3.6-2 (Continued)

CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS i

TABLE NOTATIONS i

To be determined during startup test program. The actual setpoints are the corresponding values of the turbine first stage pressure for these power levels.

l The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W). The trip setting of this function must be maintained in accordance with note (a) of Table 2.2.1-1.

l

{

Instrument zero is 758' 5" as1.

1. Instrument zero is 758' 4 1/2" as1.

1 k

t l

i l

~

i i

CLINTON - UNIT 1 3/4 3-67 Amendment No.18 I

TABLE 4.3.6-1 O

5 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS c

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WillCil TRIP FUNCTION CHECK TEST CALIBRATION (a)

SURVEILLANCE REQUIRER W

l.

ROD PATTERN CONTROL SYSTEM b

a.

Low Power Setpoint NA S/

c g)

{)

b b.

RWL High PJwer Setpoint NA S/

c

)

{)

2.

APRM l

a.

Flow Biased Neutron Flux -

Upscale NA S/U(b) Q SA 1

b.

Inoperative NA S/U

,Q NA 1, 2, 5 c.

Downscale NA S/U(b),Q SA 1

d.

Neutron Flux - Upscale, Startup NA S/U

,Q SA 2, 5 3.

SOURCE RANGE MONITORS S/U(b)

NA 2, 5 a.

Detector not full in NA S/U(b),W I,W SA 2, 5 b.

Upscale NA W

NA 2, 5 c.

Inoperative NA S/U d.

Downscale NA S/UI I,W SA 2, 5 4.

JLTEftMEDIATE RANGE MONITORS a.

Detector not full in NA S/U

,W NA 2, 5 SA 2, 5 b.

Upscale NA S/U(b),W c.

Inoperative NA S/U(b),W NA 2, 5 g

d.

Downscale NA S/U

,W SA 2, 5 3

5.

SCRAM DISCHARGE VOLUME a.

Water Level-High S

Q R(7) 1, 2, 5*

l Y

6.

REACTOR-COOLANT SYSTEM RECIRCULATION FLOW P

a.

Upscale NA S/UIb) Q SA 1

l 0

7.

REACTOR MODE SWITCH a.

Shutdown Mode NA R

NA 3, 4 b.

Refuel Mode NA R

NA 5

9

TABLE 4.3.6-1 (Continued)

CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE RE0VIREMENTS TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

'(b) Within 7 days prior to startup.

(c) Within one hour prior to control rod movement, unless performed within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and as each power range above the RPCS low power setpoint is entered for the first time during any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period during power increase or decrease.

(d) Deleted.

(e)

Includes reactor manual control multiplexing system input.

(f) Calibrate the analog trip module at leest once per 92 days.

With any control rod withdrawn.

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

?

CLINTON - UNIT I 3/4 3-69 Amendment No. 71 r

i INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE, with their alarm / trip setpoints within the specified limits.

t APPLICABILITY:

As shown in Table 3.3.7.1-1.

ACTION:

With a radiation monitoring instrumentation channel alarm / trip setpoint a.

exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE RE0VIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the l

conditions and at the frequencies shown in Table 4.3.7.1-1.

1

?

\\

CLINTON - UNIT 1 3/4 3-70 Amendment No.40

n TABLE 3.3.7.1-1 R

E RADIATION MONITORING INSTRUMENTATION E

MINIMUM CHANNELS APPLICABLE ALARM / TRIP g

INSTRUMENTATION OPERABLE CONDITIONS SETPOINT ACTION 1.

Main Control Room 2/ intake (a) 1, 2, 3, 5, and

1 10 mR/hr 70 Air Intake Radiation Monitor 2.

Area Monitors a.

New Fuel 1

< 2.5 mR/hr**

71 Storage Vault b.

Spent-Fuel 1

$ 2.5 mR/hr**

71 Storage Pool D

c.

Control Room 1

At all times

-< 2.5 mR/hr**

71 w

Direct Radiation 4

Monitor w

a Br s

TABLE 3.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS t

When irradiated fuel is being handled in the secondary containment.

Alarm only.

i With fuel in the new fuel storage vault.

1. With irradiated fuel in the spent fuel storage pool.

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for re-quired surveillance without placing the trip system in the tripped condi-tion provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

ACTION ACTION 70 -

a.

With one of the required monitors inoperable, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable channel to OPERABLE status i

within 7 days, or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the control room emergency filtra-tion system in the high radiation mode of operation.

b.

With both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the high radiation mode of operation within I hour.

ACTION 71 -

With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

CLINTON - UNIT 1 3/4 3-72 Amendment-No. If, AD. 71

, s.-

TABLE 4.3.7.1-1 Eg RADIATION MON 110 RING INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

.x CilANNEL

.g CllANNEL '

FUNCTIONAL CilANNEL

.p INSTRUMENTATION CllECK TEST

-CAllBRATION APPLICABILITY H

1.

Main Control Room Air S

Q R

1, 2, 3, 5, and

I Intake Radiation

-l Monitor 2.

Area Monitors i

-a.

New Fuel Storage S

M

.R Vault

. b.' Spent Fuel Storage 5

M R

Pool w

c.

Control Room Direct S

M R

At all times 1

Radiation Monitor

'YE ili

ai ar

'O IR 4

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

=

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

TABLE 4.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

)

TABLE NOTATION

When irradiated fuel is being handled in the secondary containment.

1

With fuel in the new fuel storage vault.

1. With irradiated fuel in the spent fuel storage pool.

I i

t i

l CLINTON - UNIT 1 3/4 3-74 Amendment NoJ0. 40

=

INSTRUMENTATION-

'I l

3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION-

.i 3.3.9 The plant systems actuation instrumentation channels shown in I

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.

l I

APPLICABILITY: As shown in Table 3.3.9-1.

-l i

ACTION:

j 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'

-l OPERABLE status with its trip setpoint adjusted. consistent with the Trip i

Setpoint value.

'j f

b.

With one or more plant systems actuation instrumentation channels l

l inoperable, take the ~ ACTION required by Table 3.3.9-1.

1 1

i k

i

.. I

'I i

L f

I CLINTON,- UNIT 1 3/4 3-97 Amendment No. (9. 71

[

t i

i.

I INSTRUMENTATION PLANT SYSTEMS ACTUATION INSTRUMENTATION f

SURVEILLANCE REQUIREMENTS l

4.3.9.1 Each plant system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL i

TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.1-1.

i 4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.

Each trip system or division of the plant system actuation logic associated with the Nuclear System Protection System shall be manually tested independent of the SELF TEST SYSTEM during separate refueling outages such that all divisions and all trip functions are tested at least once every four fuel cycles.

l j

l CLINTON - UNIT 1 3/4 3-98 Amendment No. 10 71 l

a TABLE 3.3.9-1 n

C5 PLANT SYSTEMS ACTUATION INSTRUMENTATION E

MINIMUM OPERABLE e

CHANNELS PER APPLICABLE 5

CONTAINMENT OPERATIONAL TRIP FUNCTION SPRAY LOOP CONDITIONS ACTION 1.

CONTAINMENT SPRAY SYSTEM

~

a.

Drywell Pressure-High 2*

1, 2, 3 52 b.

Containment Pressure-High 2,

1, 2, 3 52 c.

Reactor Vessel Water Level-Low low Low, level 1 2

1, 2, 3 52 d.

Timers (1) Loop A, Loop B (10 minutes) 1 1, 2, 3 53 (2)

Loop B only (90 seconds).

I 1, 2, 3 53 e.

Manual Initiation 1

1, 2, 3 53 M

MINIMUM OPERABLE Y

2.

FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM CHANNELS a.

Reactor Vessel Water Level-High, level 8 3*

1 54 MINIMUM OPERABLE 3.

EUPPRESSION POOL _ MAKEUP SYSTEM CHANNELS;PER TRIP SYSTEM a.

Drywell Pressure-High 2

1, 2, 3 50 b.

Reactor Vessel Water Level-Low Low Low, level 1 2,

1, 2, 3 50 c.

Suppression Pool Water Level-Low Low 2,

1, 2, 3 50 l

d.

Suppression Pool Makeup Timer 1

1, 2, 3 51 e.

SPMS Manual Initiation 2

1, 2, 3 51 k

f.

SPMS Mode Switch Permissive 1

1, 2, 3 51 h

E

[

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance without P

placing the channel in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

w?

4--a

TABLE 3.3.9-1 (Continued)

PLANT SYSTEMS ACTUATION INSTRUMENTATION ACTION ACTION 50 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the SPMS inoperable and take the ACTION of Specification 3.6.3.4.

b.

With more than one channel inoperable, declare the SPMS inoperable and take the ACTION of Specification 3.6.3.4.

F ACTION 51 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement, declare the SPMS system inoperable and take the ACTION of l

Specification 3.6.3.4.

ACTION 52 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per containment spray loop requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the associated loop inoperable and take the ACTION of Specification 3.6.3.2.

b.

With more than one channel inoperable, declare the associated loop inoperable and take the ACTION of Specification 3.6.3.2.

ACTION 53 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per containment spray loop requirement, declare the associated loop inoperable and take the ACTION of Specification 3.6.3.2.

ACTION 54 -

For the feedwater system / main turbine trip system:

a.

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

b.

With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

CLINTON - UNIT I 3/4 3-100 Amendment No JD, 71 1

o TABLE 3.3.9-2 C

- PLANT SYSTEMS ACTUATION INSTRUMENTATION SETPOINTS i

c-ALLOWABLE j TRIP FUNCTION TRIP SETPOINT VALUE 1.

CONTAINMENT SPRAY SYSTEM a.

Drywell Pressure-High

< 1.68 psig

< 1.88 psig b.

Containment Pressure-High 7 22.3 psia 7 22.4 psia c.

Reactor Vessel Water Level-Low Low Low, level 1 d.

Timers

-F-145.5 in.*

I-147.7 in, 1.

Loop A, Loop B 10.17 min.

> 10.10 < 10.23 min.

2.

Loop B'only

$ 90 sec.

_7 90.6 s~c.

w ' 2.

FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM k

w a.

Reactor Vessel Water level-High, level 8 5 52.0 in.*

5 52.6 in.

N 3.

SUPPRESSION POOL MAKEUP SYSTEM a.

Drywell Pressure-High 5 1.68 psig

'$ 1.88 psig b.

Reactor Vessel Water Level-Low Low Low, Level 1

> -145.5 in.*

> -147.7 in.

c.

Suppression Pool Water level-Low Low

> 37 9/16 in.**

> 29 in.**

d.

-Suppression Pool Makeup Timer 1 25 minutes 5 30 minutes k

e.

SPMS Manual Initiation NA NA f.

SPMS Mode Switch Permissive-NA NA a

F

See Bases Figure 8 3/4 3-1.

8 ** Instrument zero is 727'-0" as1.

______,m

_m.,

.,.vo..

4, -.

-....e.

.-~

....-m e...

.w-.--

,,-,... _,.r_.-.....

,_..-,+..r-

.-_..,..--s,.

-,.w.

,m_.,,,,

m

TABLE 4.3.9.1-1 0

{

PLANT SYSTEMS ACiUATION INSTRilMENTATION SURVEILLANCE REQUIREMENTS E

^

CilANNEL OPERAT10NAL E-CilANNEL IUNCT10NAL CilANNEL CONDITIONS IN WillCH TRIP FUNCTION CNECK IEST CALIBRATION SURVEILLANCE REQUIRED w

1.

, CONTAINMENT SPRAY SYSTEM Rfa" a.

Drvwell Pressure-liigh S

Q 1,2,3 b.

Containment Pressure-liigh 5

Q R

1,2,3 c.

Reactor Vessel Water Level-Low Low Low, level 1 5

Q R(a) 1, 2, 3 d.

Timers NA Q

R 1,2,3 e.

Manual Initiation NA R

NA 1, 2, 3 2.

FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM a.

Reactor Vessel Water Level-High, m)

Level 8 5

Q R

1 l

Y 3.

SUPPRESSION POOL MAKEUP g

a.

Drywell Pressure-High S

Q R(a) 1, 2, 3 b.

Reactor Vessel Water Level -

Low Low Low, Level 1 5

Q R(a) 1, 2, 3 c.

Suppression Pool Water Level-Low Low S Q

R(b) 1, 2, 3 d.

Suppression Pool Makeup Timer NA Q

Q 1,2,3 g

e.

SPMS Manual Initiation NA R

NA 1,2,3 5

f.

SPMS Mode Switch Permissive NA R

NA 1,2,3 5

p (a) Calibrate the analog trip module at least once every 92 days.

3 (b) Calibrate the analog comparator unit at least once every 92 days.

.y

t REACTOR COOLANT SYSTEM

+

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 satisfying 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** (psia) 7 Safety 1165 i 11.6 psi 5

Safety 1180 1 11.8 psi 4

Safety 1190 1 11.9 psi 1

Relief 1103 1 15.0 psi 8

Relief 1113 15.0 psi 7

Relief 1123 1 15.0 psi APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the safety and/nr relief valve function of one or more of the above a.

required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 safety / relief valve (s); if suppression pool average water tempera-ture is 110'F or greater, place the reactor mode switch in the Shutdown ensition.

",n one or more safety / relief valve acoustic monitor (s) inoperable, restore c.

t.

inoperable monitor (s) to OPERABLE status within 7 days or be in at i

les t HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for the l

purpose of performing surveillance testing in accordance with Specifica-tions 4.4.2.1.1 and 4.4.2.1.2.

- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressstres.

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

REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES SURVEILLANCE REQUIREMENTS 4.4.2.1.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE by performance of a:

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a a.

b.

CHANNEL 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:

CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least a.

once per 92 days.

I b.

CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18 Each of the two trip systems or divisions of the relief valve months.

function actuation logic associated with the Nuclear System Protection System shall be manually tested independent of the SELF TEST SYSTEM during i

separate refueling outages such that both divisions and all channel trips are tested at least once every four fuel cycles.

l i

i "The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

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

71 1.

REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION 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 Setaoint* (psig) 15 psi Valve No.

Open Close F051D 1033 926 F051C 1073 936 F047F 1113 946 F051B 1113 946 F051G 1113 946 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the low-low set function of one of the above required reactor coolant a.

system safety / relief valves inoperaole, 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the low-low set function of more than one of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With either low-low set function pressure actuation trip system "A" or c.

"B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least a.

once per 92 days.

l b.

CHANNEL CALIBRATI0tl and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18 i

months.

Each of the two trip systems or divisions of the low-low set function actuation logic associated with the Nuclear System Protection System shall be manually tested independent of the SELF TEST SYSTEM during L

separate refueling outages such that both divisions and all channel trips are tested at least once every four fuel cycles.

l "One channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for the pur-l pose of performing surveillance testing in accordance with Specification 4.4.2.2.

- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

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

Person / Time
ML20035F642
Site:	Clinton (NPF-62-A-071, NPF-62-A-71)
Issue date:	04/09/1993
From:	Dyer J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20035F643	List: ML20035F642 ML20035F646
References
NUDOCS 9304220122
Download: ML20035F642 (63)
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