ML18047A300

Proposed Tech Spec Changes Re Instrumentation & Control Sys

ML18047A300
Person / Time
Site:	Palisades
Issue date:	04/21/1982
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18047A299	List: ML18047A298 ML18047A300
References
NUDOCS 8204290338
Download: ML18047A300 (11)

Text

CONSUMERS POWER COMPANY PROPOSED TECHNICAL SPECIFICATION CHANGE.REQUEST PALISADES PLANT

. 3~17 J?r~TRV:*:2ff~A'ff ON AND CONTROL SYSTEMS Anplicabili ty Applies to plant instrumentation systems.

Objective To delineate the conditions of the plant instrumentation and control systems nece~sary to assure reactor safety.

Suec i ficat ions 3.17.1 The operability of the plant instrument and control system shall be in accordance with, Tables 3.17.1 through 3.17.3.

3.17.2 As a minimum, the Reactor Protection System instrumentation channels and bypasses shall be OPERABLE as defined in Table 3.17.1.

3.17.3 P~ a minimum, the Engineered Safety Features instrumentation channels and bypasses shall be OPERABLE as defined in Table 3.17.2.

3.i7.4 In the event that the number of channels of a particular system listed in Table 3.17; 3 "Other Safety Features Functions Instrumentation" falls below the limits given in the colwims entitled Minimum Operable Channels" or "Minimum. Degree of Redundancy", except as ccmdi tioned by the.column entitled "?ermissible Bypass Conditions", the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the re~ctor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Easis During plant operations, the complete instrumentation systems will normally be in service.

Reactor safety is provided by the reactor pro-tection system, which. automatically initiates appropriate action to prevent exceeding established limits.

Safety is not compromised, however, by continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design.

This specification outlines limiting conditions for operation necessary to preserve the effectiveness of the reactor control and protection system when any one or more of the channels are out of service.

Al:nost_ all rea~t9.r.prote9tiQ.n a.nd engineered safeguards channels are st:pplied with sufficient redundancy to provide the capability for channel test at power.

Exceptions are back-up channels such as loss-of-load trip.

i~11en one of the four channels is taken out of service for maintenance, the protective system logic can be changed to a two-out-of-three coin-cidence by bypa~sing the removed channel for a limited time.

3-76 PROPOSED

3.1_7 INSTRUMENTATION AND CONTROL SYSTEMS (Continued)

If the bypass is not affected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-change of power, high power level and high pressurizer pressure),(l)which results in a one-out-of-three channel logic. If, in the 2 of 4 logic system of either the reactor protectiye system or the engineered safe-guards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2.

At rated power, the minimum operable high-power level channels is 3 in order to provide adequate flux tilt detection.

If only two channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts and from exceeding dropped rod peaking factors in the event that a turbine runback signal is required from the power range channels.

The engineered safeguaras system provides a 2 of 4 logic on the.signal used to actuate the equipment connected to each of the two emergency diesel generator units.

Two start-up channels are*available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the log-range nuclear instrumentation or above lo-43 of rated power.

This ensures that redundant start-up instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the start-up channels.

In the event only one start-up range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of log-range instrumentation, a start-up can be performed in accordance with footnote (d) of Table 3.17.4.

References (1)

FSAR, Section 7.2.7.

3-77 PROPOSED

• v

~

TABLE 3.lJ.l

. t-1

{JJ

(;

REAC'l'OH PROTECTIVE INS'rRUMENTATION l;-l MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE f'IJllG'l'l ONAL UNIT*

OF CHANNELS TO TRIP OPERABLE NOTES MODES (f)

ACTION

1.

M1.111ual Reactor Trip 2

1 2

1, 2 1

2.

Power I~vel - High 4

2 3

(e) 1, 2 2

3.

Primary Coolant Flov - Lov 4

2 3

(a), (d )

1, 2 2

Pressurizer Pre*asure - High 4

2 3

1, 2 2

5.

Co11tainment Pressure - High 4

2 3

1, 2 2

w I

6.

Steam Generator Pressure - Lov 4/SG 2/SG 3/SG (a), (d )

1, 2 2

-.:i CP

1.

Steam Generator Water Level - Lov 4/SG 2/SG 3/SG 1, 2 2

8.

'l'la<!rmal Margin/Lev Pressure 11 2

3 Ja), ( d) 1, 2 2

9.

Lo:;s of Load--Hydraulic ft'luid Pressure - Lov 1

1 1

(b) 1 2

10.

Lo~ Runge Channels 2

1 2

(c),(d) 1, 2 1

e*

(a)

TABLE '.3.17.1 (Continued)

TABLE NOTATION Trip may be bypassed belo~ lo-4% of RATED POWER: bypass shall be automatically removed when POWER is greater than or equal to lo-4%

of RATED POWER.

(b)

Trip may be bypassed below 15% of RATED POWER.

Trip bypass is auto-matically removed above 15% RATED POWER.

(c)

Trip is automatically bypassed below 10-4% and above 15% of RATED POWER.

Two channels required if TM/LP, low steam generator or primary coolant flow channels are bypassed.

(d)

For low power physics testing, lo-4% may be increased to lo-1%.

(e) If only two channels are operable (see Action 2.C), load shall be reduced to 70% or less of RATED POWER.

(f) Definition of Operational Modes:

MODE

1.

POWER OPERATION

,J

2.

HOT STANDBY

3.

HOT SHUTDOWN

4.

COLD SHUTDOWN

5.

REFUELING 3-78a PROPOSED

TABLE 3.17.1 (Continued)

• • TABLE NOTATION ACTION STATEMENTS ACTION l ACTION 2 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoper-able channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER*OPERATION may proceed provided the following conditions are satisfied:

I

a.

The inoperable channel is placed in either the bY!Jassed or tripped condition.

For. the purposes of testing and maintenance, the inoperatle channel may be bypassed for up to seven days (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) from time of initial loss of OPERABILI~'!'.; ho\\.:eY~r, the* inoperable channel shall then be either restored to OPERl\\BLE status or. placed.in the tripped condition.

'b.

The Ninimum Channels OPE::ffiBLE requirement is ;net; however,*

one additional channel may be bypassed for '..lP to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> while performing tests and mainte:J.ance on that channel provided the other inoperable cha~nel is placed in the tripped *condition.

3-78b PROPOSED

TABLE 3.17.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO CHANNELS CHANNELS APPLICABLE FUUCTI0:iAL UNIT OF CHANNEIS TO TRIP OPERABLE NOI'ES MODES (d)

ACTION

1.

S/SETY INJECTION

a. Manual (Trip Buttons) 2 1

2 1,2 3

b.* Containment Pressure - High 4

2 3

(a) 1,2 4

c. Pressurizer Pressure -

Low 4

2 3

(b) 1,2 4

2.

cc:iTAINMENT SPRAY

a. Manual (Control Switches) 2 1

2 1,2,3 3

b. Containment* Pressure - High 4

2 3

(a) 1,2,3 4

w I

---.J

3.

CO:ITAINMENT ISOLATION

\\0.

a. f*1anual (Hand Switches) 2 1

2 1,2,3 3

b. Containment Pressu,re - High 4*

2 3

(a) 1,2,3 4

c. Containment Radiation - High 4

2 3

1,2,3 4

4.

HAIN STEAM LINE ISOLATION

a. Manual (Control Switches) 1/steam 1/steam I/steam 1,2,3 3

generator generator generator

b. Steam Generator Pressure -

4/steam 2/steam 3/steam (c) 1,2,3 4

Low generator generator generator

5.

RECIRCULATION ACTUATION SYSTEM

a. f.!anual (Hand Switches) 2 1

2 1,2,3 3

b. SIRW Tank -

Low 4

~

3 1,2,3 4

'"d

~

0

'"d 0

(j}

t:x:l t:1

TABLE 3.17.2 (Continued)

TABLE NOTATION (a)

Bypass of containment high pressure channels is permissible during containment leak tests.

(b)

Trip function may be bypassed in this MODE when pressurizer pressure is less than 1700 psia; bypass shall be automatically removed prior to pressurizer pressure exceeding 1700 psia.

( c)

Trip function may be bypassed in this MODE below 55*0 psia; bypass shall be automatically removed prior to exceeding 550 psia.

(d)

Definition of Operational Modes:

MODE

1.

POWER OPERATION

2.

HOT STANDBY

3.

HOT SfilJTDOWN

4.

COLD SHUTDOWN

~.

REFUELING 3-79 a PROPOSED

TABLE 3.17.2 (Continued)

TABLE NOTATION.

ACTION STATEMENTS ACTION 3 ACTION 4 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status vithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With the number* of OPERABLE channels one less than the Total Number cf Channels, operation may proceed provided the following conditions a.re satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition.

For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to seven days (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) from time of initial loss of OPERABILITY; ho~ever, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

'b.

The Minimum Channels OPERABLE requirer.ient is met; however, one additional channel may be bypassed for up to 48 hou.rs while performing tests and maintenance on that ~hannel provided the other inoperable channel is placed in the*

tripped condition.

3-79 b PROPOSED

NO 1

2 3

4 5

TABLE 3.17.3

-OTHER SAFETY FEATURE FUNCTIONS INSTRUMENTATION MINIMUM OPERABLE FUNCTIONAL UNIT CHANNELS 6T - Power 3(b)

Comparator Air Cooler Service 1

Water Flow Instr Primary and Secondary 1

Rod Insertion and Out-of-Sequence Monitors Fuel Pool Bldg 1

Crane Interlocks Start-up Channels 2

MINIMUM DEGREE OF REDUNDANCY 1

None None None l(c)

PERMISSIBLE BYPASS CONDITIONS None None N/A As Requested Under Admini-strati ve Control (a)

Not Reauired Above 10-4% ~f _Rated Po-w-er (a)

Crane shall not be used to move material past the fuel storage pool unless the interlocks are available.

(b) If only two channels are operable, load shall be reduced to 70% or less of rated power.

(c)

Minimum operable channels shall be one (i) and minimum degree of redundancy is zero (0) if shutdown neutron power levels indicated on the log-range channels *are greater than three times the lowest decade in which neutron visibility can be confirmed.

Neutron visibility will be confirmed through observation of reactivity changes on neutron pc-wer level (including a l/M plot during reactor start-up} and comparing the observed changes to the changes noted on previous similar start-ups.

Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.

3-80 PROPOSED

DELETED 3-81 PROPOSED