ML18047A417

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Proposed Tech Spec Change Re Requirements for Operation W/Inoperable Reactor Protection Sys & ESF Actuation Sys Channel
ML18047A417
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/25/1982
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18047A415 List:
References
NUDOCS 8207070450
Download: ML18047A417 (14)
v • d • e


Text

CONSUMERS POWER COMPANY PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST PALISADES PLANT 8207070450 820625 PDR ADOCK 05000255 P __ r:>n~--

l'i 3.17 INSTRill'fENTATION AND CONTROL SYSTEMS Applicability Applies to plant instrumentation systems.

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

Specifications 3.17.1 The operability of the plant instrument and control system shall be in accordance with Tables 3.17.1 through 3.17.4.

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

3.17.4 As a minimum, the channels and bypasses in "Other Safety Features Functions Instrumentation" shall be operable as defined in Table 3.17.3.

3.17.5 In the event that the number of channels of a particular system listed in Table 3.17.4 "Accident Monitoring Instrumentation" falls below the limits given in the columns entitled "Minimum Operable Channels" or "Minimum Degree Of Redundancy", except as conditioned by the column entitled "Permissible Bypass Conditions", either restore the number of operable channels to the "Minimum Operable Channels" within seven days, or place the reactor in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Basis During plant operations, the complete instrumentation systems will normally be in service. Reactor safety is provided by the reactor protection 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.

Almost all xeactor protection and engineer~d safeguards cfiannels are supplied with sufficient redundancy to provide the capability for channel test at power. Exceptions are backup channels such as loss-of-load trip.

ts0682-0017a-89-93 3-76 PROPOSED

3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Continued)

When 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 coincidence by bypassing the removed channel for a limited time.

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

The engineered safeguards system provides a 2 or 4 logic on the signal used to actuate the equipment connected to each of the two emergency*

diesel generator units.

Two startup channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron powef5 is not visible on the log-range nuclear instrumentation or above 10 %

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

In the event only one startup 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 startup can be performed in accordance with footnote (b) of Table 3.17.3.

Since the instrumentation of Table 3.17.4 used for accident monitoring does not provide protective actions or initiate engineered safety features, their operability requirements are less restrictive than for Tables 3.17.1, *3.17.2 and 3.17.3.

References (1) FSAR, Section 7.2.7.

I ts068~-0017a-89-93 3-77 PROPOSED

~-

TABLE 3 . 17 . 1 REACTOR PROTECTIVE INSTRUMENTATION MIMIMUM TOTAL NO CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE NOTES MODES (e) ACTION

1. Manual Reactor Trip 2 1 2 1, 2 1
2. Power Level - High 4 2 3 1, 2 2
3. Primary Coolant Flow - Low 4 2 3 (a)' (d) 1, 2 2 e
4. Pressurizer Pressure - High 4 2 3 1, 2 2
s. Containment Pressure - High 4 2 3 1, 2 2
6. Steam Generator Pressure - Low 4/SG 2/SG 3/SG (a), (d) 1, 2 2
7. Steam Generator Water Level - Low 4/SG 2/SG 3/SG 1, 2 2
8. Thermal Margin/Low Pressure 4 2 3 (a), (d) 1, 2 2
9. Loss of Load--Hydraulic Fluid Pressure - ,Low (Iii
10. Log Range Channels 2 2 ( c), (cl) I,  :*

e 3-78 PROPOSED ts0682-0017b-89-93

TABLE 3.17.1 (continued)

TABLE NOTATION Trip may be bypassed below 10- % of RATED POWER: bypass shall ~~

4 (a)

  • automatically removed when POWER is greater than or equal to 10 % of RATED POWER.

(b) Trip may be bypassed below 15 +/- 2% of RATED POWER. Trip bypass is automatically removed above 15 +/- 2% RATED POWER.

(c) -4 Trip is automatically bypassed below 10 % and above 15 +/- 2% of RATED POWER. Two channels required if TM/LP, Low Steam Generator pressure or Primary Coolant flow channels are bypassed.

(d) For low power physics testing, 10- 4% may be increased to 10- 1%.

(e) Definition of Operational Modes:

MODE

1. POWER OPERATION
2. HOT STANDBY
3. HOT SHUTDOWN
4. COLD SHUTDOWN
5. REFUELING SHUTDOWN ts0682-0017c-89-93 3-78a PROPOSED

TABLE 3.17.1 (continued)

TABLE NOTATION ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the

  • 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 />.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, HOT STANDBY and/or POWER OPERATION may proceed provided the following conditions are 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 initi~l loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.
b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up 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 maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

If additional channel is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> be in 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 />.

ts0682-0017c-89-93 3-78b PROPOSED

TABLE 3 . I 7 . 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MIMI MUM TOTAL NO CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE NOTES MODES (d) ACTION

1. SAFETY INJECTION
a. Manual (Trip Buttons) 2 I 2 I, 2, 3 3
b. Containment Pressure - High 4 2 3 I, 2, 3 4
c. Pressurizer Pressure - Low 4 2 3 (a) I, 2, 3 4
2. CONTAINMENT SPRAY
a. Manual (Control Switches) 2 I 2 1, 2, 3 3
b. Containment Pressure - High 4 2 3 I, 2, 3 4
3. CONTAINMENT ISOLATION
a. Manual (Hand Switches) 2 I 2 I, 2, 3 3
b. Containment Pressure - High 4 2 3 I, 2, 3 4
c. Containment Radiation - High 4 2 3 I, 2, 3 4
4. MAIN STEAM LINE ISOLATION
a. Manual (Control Switches) I/Steam I/Steam I/Steam I, 2, 3 3 Generator Generator Generator
b. Steam Generator Pressure - 4/Steam 2/Steam 3/Steam (b) I, 2, 3 4 Low Generator Generator Generator
c. Containment High Pressure 4 2 3 I, 2, 3 4
5. RECIRCULATION ACTUATION SYSTEM

. a. Manual (Hand Switches) 2 I 2 I, 2, 3 3

b. SIRW Tank - Low 4 2 3 I, 2, 3 4
6. AUXILIARY FEEDPUMP
a. Manual (Control Switches) I per I per I per Required 3 pump pump pump above 325°F
b. Auto Initiation Circuitry I per I per I per (c) Required 3 pump pump pump above 325°F ts0682-00I7d-89-93 3-79 PROPOSED

TABLE 3.17.2 (Continued)

TABLE NOTATION (a) Trip function may be bypassed when pressurizer pressure is less than 1700 psia; bypass shall be automatically removed prior to pressurizer pressure exceeding 1700 psia.

(b) Trip function may be bypassed below 550 psia; bypass shall be automatically removed prior to exceeding 550 psia.

(c) With one Auxili~ry Feed Pump automatic initiation circuit inoperable, in lieu of the actiOn* statement, provide a second licensed operator in the control room within two hours. With both inoperable, in lieu of following of action statement, start and maintain in operation the turbine driven Auxiliary Feed Pump.

(d) Definition of Operational Modes:

MODE

1. POWER OPERATION
2. HOT STANDBY
3. HOT SHUTDOWN
4. COLD SHUTDOWN
5. REFUELING SHUTDOWN ts0682-0017e-89-93 3-79a PROPOSED

TABLE 3.17.2 (Continued)

TABLE NOTATION ACTION STATEMENTS ACTION 3 - With the number of OPERABLE channels one 1ess than required by the Minimum Channels Operable Requirement, restore the inoperable 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 /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 4 - With the number of OPERABLE channels one less than the Total Number of Channels, Hot Standby and/or Power Operation may proceed provided the following conditions are 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; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.
b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up 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 maintenance on that channel, provided the other inoperable channel is placed in the tripped condition.

If additional channel is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ts0682-0017e-89-93 3-79b PROPOSED

  • \' .

TABLE 3 . 17 . 3 OTHER SAFETY FEATURE FUNCTIONS INSTRUMENTATION MIMH.fill1 MIMIMUM PERMISSIBLE OPERABLE DEGREE OF BYPASS NO FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS ACTION

1. /J.T - Power 3 1 None 5 Comparator
2. Air Cooler Service 1 None None N/A Water Flow Instr
3. Primary or Secondary 1 None None 7 Rod Insertion Monitors
4. Fuel Pool Building 1 None As Requested N/A Crane Interlock~ Under Adminis-trative Con-trol (a)
s. Startup Channels 2 l(b) Not Requf 5ed N/A Above 10 % of Rated Power
6. Excore Detector 1 None None 6 Deviation Alarms (a) Crane shall not be used to move material past the fuel storage pool unless the interlocks are available.

(b) Minimum operable channels shall be one (1) 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 power level (including a 1/M plot during reactor startup) and comparing the observed changes to the changes noted on previous similar startups. Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.

ts0682-0017f-89-93 3-80 PROPOSED

... . ' ,(

e.

TABLE 3.17.3 (Continued)

OTHER SAFETY FEATURE FUNCTIONS INSTRUMENTATION ACTION STATEMENT ACTION 5 - With the number of channels less than the.limits of "Minimum Operable Channels" or "Minimum degree of Redundancy" except as*

conditioned by "Permissible Bypass Condition", the reactor shall be.

placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 6 - Calculate the Quadrant Power Tilt using the excore readings at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the excore detectors deviation alarms are inoperable.

ACTION 7 - With the number of channels less than the "Minimum Operable Channels", operation may continue for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided control rods are not moved, and rod positions are determined twice a shift to assure power dependent insertion limits are satisfied. If "Minimum Operable Channels" is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in 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 />.

ts0682-0017f-89-93 3-80a PROPOSED

' .I TABLE 3. 17. 4 ACCIDENT MONITORING INSTRUMENTATION Minimum Minimum Permissible Operable Degree of Bypass No Functional Unit Channels Redundancy Conditions

1. Containment Pressure None None (wide range) (a)
2. Containment Sump 1 None None Water Level (b)
3. Containment Floor 1 None None Water Level (c)
4. Pressurizer Water 2 1 None Level (LI-0102)
5. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve Below 325°F Position Indication (Acoustic Monitor or Temperature Indication)
6. Power Operated Relief 1 per None Not Required When Valves (Acoustic Valve PORV Isolation Valve Monitor or Temperature Is Closed and its Indication) Indication System is operable
7. PORV Isolation Valves 1 per None Not Required When*

Position Indication Valve Reactor is Depressurized and Vented Through a Vent ~1. 3 sq in

8. _ Subcooling Margin 1 None Not Required Monitor Below 515°F
9. Auxiliary Feed Flow 1 per None Not Required Indication Steam Below 325°F Generator (a) Applies to PT-1805A and PT-1812A only.

(b) Applies to LT-0382 and LT-0383 only.

(c) Applies to LE-0446A and LE-0446B only.

ts0682-0017g-89-93 3-81 pROPOSED

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<A TABLE 4.1.3 Minimum Frequencies for*Checks, Calibrations and Testing of Mi see I laneous Instrumentation and Controls (Contd)

Su rve i I I a nee Channel Description Function Frequency Surveillance Method

15. Auxi I iary Feed Pump a. Check M(5) a. Comparison of Channels Flow Indication b. Ca I i bra te R b. Known Differential Pressure Applied to Sensors
16. Aux i I i a ry Feed Pump a. Test M( 3), (5) a. Internal Test Signal Auto Initiation b. Ca I i bra te R b. Known Differential Pressure Applied to Sensors
17. Power-Operated Relief Valves and Pressurizer Code Safety Relief Valves Position Indication
a. Temperature a. Ca I i bra te R a. Known Resistance Substitute for RTD
b. Check s b. Comparison of Channels
b. Acoustic Monitor a. Ca I i bra te R a. Inject Ca I ibrated Test Signa I
18. Subcoo I i ng Marg in a. Check s a. Comparison of Channels Monitor b. Ca I i bra te R b. Known Resistance Substituted for RTD Coincident With Known Pressure lnput(4)
19. Containment Pressure a. Check s a. Comparison of Channels Wide Range b. Ca I i bra te R b. Known Pressure Applied to Sensors
20. Containment Sump a. Check s a. Comparison of Channels Water Level Instrument b. Ca I i bra te R b. Known Differential Pressure Applied to Sensors
21. Containment Floor a. Check s a. Comparison of Channels Water Level Instrument b. Ca Ii brate R b. Known Level Applied to Transducer (3)Test method to be alternated to include starting auxi I iary feedwater pump from the control room hand switch, from the breaker and from the automatic start in a three-month period.

(4)1n conjunction with Item 4(b), Table 4.1.1.

(5)1t is not necessary to perform the specified testing during the cold shutdown condition.

nu1081-0228a-46-48 4-11a Proposed

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