ML17329A223

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Proposed Tech Spec Pages 3.4 3-10 & 3/4 3-9,consisting of Table 3.3-2, Reactor Trip Sys Instrumentation Response Times.
ML17329A223
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/23/1991
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17329A222 List:
References
NUDOCS 9110300062
Download: ML17329A223 (21)
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Text

Attachment 1 to AEP:NRC:1167 Corrected Technical Specifications Pages for Donald C. Cook Nuclear Plant Units 1 and Unit 2 9ii0300062 9ii023 PDR. AOOCK 050003i5 P , PDR

TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

1. Manual Reactor Trip NOT APPLICABLE
2. Power Range, Neutron Flux Less than or equal to (High and Low Setpoint) 0.5 seconds*
3. Power Range, Neutron Flux, NOT APPLICABLE High Positive Rate
4. Power Range, Neutron Flux, Less than or equal to High Negative Rate 0.5 seconds*
5. Intermediate Range, Neutron Flux NOT APPLICABLE
6. Source Range, Neutron Flux NOT APPLICABLE
7. Overtemperature delta T Less than or equal to 6.0 seconds*

8, Overpower delta T NOT APPLICABLE

9. Pressurizer Pressure--Low Less than or equal to 1.0 seconds 10.Pressurizer Pressure--High Less than or equal to 1.0 seconds 11.Pressurizer Mater Level--High Less than or equal to 2.0 seconds Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-10 AMENDMENT NO. gP, ggP, 139

TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

1. Manual Reactor Trip NOT APPLICABLE
2. Power Range, Neutron Flux Less than or equal to 0.5 (High and Low Setpoint) seconds*
3. Power Range, Neutron Flux, NOT APPLICABLE High Positive Rate
4. Power Range, Neutron Flux Less than or equal to 0.5 High Negative Rate seconds*
5. Intermediate Range, Neutron Flux NOT APPLICABLE
6. Source Range, Neutron Flux NOT APPLICABLE
7. Overtemperature Delta T Less than or equal to 6.0 seconds*
8. Overpower Delta T NOT APPLICABLE
9. Pressurizer Pressure--Low Less than or equal to 2.0 seconds
10. Pressurizer Pressure--High Less than or equal to 2.0 seconds ll. Pressurizer Water Level--High Less than seconds or equal to 2.0
  • Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

3/4 3-9 AMENDMENT NO. Pg, ggP, 134

Attachment 2 to'EP:NRC:1167 Corrected Technical Specifications Pages Associated with our Submittal AEP:NRC:1140

TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

1. Manual Reactor Trip NOT APPLICABLE
2. Power Range, Neutron Flux Less than or equal to (High and Low Setpoint) 0.5 seconds*
3. Power Range, Neutron Flux, NOT APPLICABLE High Positive Rate
4. Power Range, Neutron Flux, Less than or equal to High Negative Rate 0.5 seconds*
5. Intermediate Range, Neutron Flux NOT APPLICABLE
6. Source Range, Neutron Flux NOT APPLICABLE
7. Overtemperature. delta T Less than or equal to 6.0 seconds*
8. Overpower delta T Less than or equal to 6.0 seconds*
9. Pressurizer Pressure--Low Less than or equal to 1.0 seconds 10.Pressurizer Pressure--High Less than or equal to 1.0 seconds 11.Pressurizer Water Level--High Less than or equal to 2.0 seconds
  • Neutron detectors are exempt from response time testing. Response'time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-10 AMENDMENT NO. W, XN, XN

TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

1. Manual Reactor Trip NOT APPLICABLE
2. Power Range, Neutron Flux Less than or equal to 0.5 (High and Low Setpoint) seconds*
3. Power Range, Neutron Flux, NOT APPLICABLE High Positive Rate
4. Power Range, Neutron Flux, Less than or equal to 0.5 High Negative Rate seconds*
5. Intermediate Range, Neutron Flux NOT APPLICABLE
6. Source Range, Neutron Flux NOT APPLICABLE
7. Overtemperature Delta T Less than or equal to 6.0 seconds*
8. Overpower Delta T Less than 'or equal to 6.0 seconds*
9. Pressurizer Pressure--Low Less than or equal to 2.0 seconds
10. Pressurizer Pressure--High Less than or equal to 2 '

seconds

11. Pressurizer Water Level--High Less than or equal to 2.0 seconds
  • Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-9 AMENDMENT NO.

pg pe,

Attachment 3 to AEP:NRC:1167 Additional Corrected Technical Specifications Pages Associated with AEP:NRC:1140

~IE)(

BASES

~SR ION ~PG 3 4.0 APPLICABILITY.o..o. ..... ~ .o ~ .................. ~ ~ ~ .. B 3/4 O-l 3 4 1 REACTIVITY CONTROL SYSTEMS 3/4 ~ 1 ~ 1 BORATZON CONTROL. B 3/4 1-1 3/4.1 2 BORATION SYSTEMS ~ ~ ~ ~ ~ ~ ~ ~ ~........ ~ .~. ~... ~... ~ ~ . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . ~ . . . o ...... . ~ ~ o B 3/4 1-3 3 4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE. ~ . ~ ........ ..... .... ...

~ ~ ~ ~ ~ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTORS ~ ~ ~ ~ .~. ~ ~ ~ ~ .. ~ ~ ~ ~ ~ o ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ B 3/4 2-5 3/4.2.5 DNB PARAMETERS' ~ ~ ~ ~ o ~ ~ ~ ~ , ~ ~ ~ ~ ~ ~ ~ ~ ,~, ~ oooo' B 3/4 2-6 3/4.2.6 ALLOWABLE POWER LEVELo ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o.. ~ ~ ~ ~ ~ B 3/4 2-6 3 4,3 INSTRUMENTATION 3/4 3 ~ 1 AND 3/4 ' 2 PROTECTIVE

~ AND ENGINEERED SAFETY FEATURE INSTRUMENTATZONo o ~ ~ ~ ~ . ~ ~ ~ ~ ......... ~ ~ ~ ~ B 3/4 3-1 3/4 3 ' MONITORING INSTRUMENTATZON . ... ~ ~ ~ . ~ ~ o ~ ~ ~ ~ ~ ~ B 3/4 3-2 3 4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS. ~ .. .. ...

~ ~ ........... ~ ~ ~ ~ B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES......................... B 3/4 4-1 3/4 ' ' PRESSURIZER, ~ o.oo.ooooooooooo ~ oooo ~ ~ ~ . ~ ~ ~ ~ ~ . ~ ~ ~ ~ o ~ B 3/4 4-2 3/4 ' ' STEAM GENERATOR TUBE ZNTEGRZTY ~ oo ~ ~ ~ ~ o ~ ~ oo.... ... ~ B 3/4 4-2a 3/4 ' 6 REACTOR COOLANT SYSTEM LEAKAGE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ..

~ ~ B 3/4 4-3 3/4o4o7 CHEMISTRY......................................... B 3/4 4-4 3/4.4 ' SPECIFIC ACTIVITY . . .... ...

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . .

~ ~ B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 1 XZI AMENDMENT NOo SSi

TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1. Manual a ~ Safety Injection (ECCS) Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Essential Service Water System Not Applicable
b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Containment Air Recirculation Fan Not Applicable
c. Containment Isolation-Phase "A" Not Applicable Containment Purge and Exhaust Isolation Not Applicable
d. Steam Line Isolation Not Applicable
2. Containment Pressure-Hi h
a. Safety Injection (ECCS) Less than or equal to 27.0QQ/27.0++
b. Reactor Trip (from SI) Less than or equal to 3.0 C. Feedwater Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Less than or equal to l8 Off/28 ON/
e. Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Essential Service Water System Less than or equal to l3 Wf/48 OIH/

COOK NUCLEAR PLANT - UNIT 1 3/4 3-27

3 4.3.3 MONITORING INSTRUMENTATION 3 4.3.3.1 RADIATION MONITORING INSTRUMENTATION Noble gas effluent monitors provide information, during and following an accident, which is considered helpful to the operator in assessing the plant condition. It is desired that these monitors be OPERABLE at all times during plant operation, but they are not required for safe shutdown of the plant.

In addition, a minimum of two in containment radiation-level monitors with a maximum range of 10 R/hr for photon only should be OPERABLE at all times except for cold shutdown and refueling outages. In case of failure of the monitor, appropriate actions should be taken to restore its operational capability as soon as possible.

Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed. For the unit vent noble gas monitors, it should be noted that there is an automatic switchover from the low/mid-range channels to the high-range channel when the upper limits of the low- and mid-range channel measurement ranges are reached. In this case there is no flow to the low- and mid-range channels from the unit vent sample line.

This is considered to represent proper operation of the monitor. Therefore, if automaticdetectors are switchover to the high-range of should functioning occur, flow and the low- and is re-established, mid-range capable when the low- and mid-range channels should not be declared inoperable and the ACTION statement in the Technical Specification does not apply. This is also true while purging the low- and mid-range chambers following a large activity excursion prior to resumption of low-level monitoring and establishment of a new background.

'I ALARM/TRIP INSTRUMENT SETPOINT MEASUREMENT RANGE*

1) Area Monitor- The monitor trip setpoint 10 R/hr to 10R/hr.

Upper Containment is based on 10 CFR 20 (VRS 1101/1201) limits. A homogeneous mixture of the containment atmosphere is assumed. The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.

  • This is the minimum required sensitivity of the instrument. Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-2 AMENDMENT NO. Ni lN

INSTRUMENTATION BASES Radiation Monitorin Instrumentation Continued ALARM/TRIP INSTRUMENT SETPOINT MEASUREMENT RANGE*

7

2) Area Monitor The monitor setpoint was 1R/hr to 1 x 10 R/hr Containment High selected to reflect the Photons.

Range (VRA 1310/ guidance provided in Generic 1410) Letter 83-37 for NUREG-0737 Technical Specifications

3) Process Monitor The monitor trip setpoint 1.5 x 10 uCi to Particulate is based on 10 CFR 20 7.5 uCi (ERS 1301/1401) The setpoint was determined using the Noble gas setpoint and historical monitor data of the ratio of particulates to Noble gases.

-7

4) Process Monitor The monitor trip setpoint 5.8 x 10 2 uCi/cc to Noble Gas is based on 10 CFR 20 2.7 x 10 uCi/cc (ERS 1305/1405) limits' homogeneous mixture of the containment atmosphere is assumed.

The setpoint value is defined as the monitor reading when .

the purge is operating at the maximum flow rate.

5) Steam Generator Not Applicable.** O.luCi/cc to 1.0x10 2 PORV (MRA 1601) uCi/cc.

(MRA 1602)

(MRA 1701)

(MRA 1702)

  • This is the minimum sensitivity of the instrument for normal operation, to follow the course of an accident, and/or take protective actions. Values of the instrument above or below this minimum sensitivity range are acceptable.
    • These monitors are used to provide data to assist in post-accident off-site dose assessment.

COOK NUCLEAR PLANT - UNIT 1 "

B 3/4 3-3 AMENDMENT NO. W. lN

INSTRUMENTATION BASES Radiation Monitorin Instrumentation Continued ALARM/TRIP INSTRUMENT SETPOINT MEASUKBKNT RANGE*

6) Noble Gas Unit Vent Monitors -7 a) Low Range See Bases Section 5.&x10 uCi/cc to (VRS 1505) 3/4.3.3.10 2.7x10 uCi/cc b) Mid Range Not Applicable~ 1.3x102 uCi/cc to (VRS 1507) 7.5x10 yCi/CC c) High Range Not Applicable~ 2.9x104 uCi/cc to (VRS 1509) 1.6x10 uCi/cc
7) Gland Steam Condenser Vent Noble Gas Monitor a) Low Range See Bases Section 5.8x10 uCi/cc to (SRA 1805) 3/4.3.3.10 2.7x10 uCi/cc

&) Steam Jet Air Ejector Vent Noble Gas Monitor a) Low Range See Bases Section 5.8x10 uCi/cc to 2.7xlO uCi/

(SRA 1905) 3/4.3.3.10 cc.

-3 b) Mid Range Not applicable.~ 1.3xl0 uCi/cc to 7.5x10 2 uCi/

(SRA 1907) cc ~

-2 4 c) High Range Not Applicable.~ 2.9x10 uCi/cc to 1.6xlO uCi/

(SRA 1909) cc.

-1

9) Spent Fuel Storage The monitor setpoint is lxlO mR/hr to lx10 mR/hr (RRC-330) selected to alarm and trip consistent with 10 CFR 70.24(a) (2)
  • This is minimum sensitivity of the instrument for normal operation, to follow the course of an accident, and/or take protective actions. Values of the instrument above or below this minimum sensitivity range are acceptable.

~ These monitors are used'o provide data to assist in post-accident off-site dose assessment.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-4 AMENDMENT NO. yg Zgg

BASES 3 4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

3 4.3.3.5.1 APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the Appendix R remote shutdown instrumentation ensures that sufficient instrumentation is available to permit shutdown of the facility to COLD SHUTDOWN conditions at the local shutdown indication (LSI) panel. In the event of a fire, normal power to the LSI panels may be lost.

As a result, capability to repair the LSI panels from Unit 2 has been provided. If the alternate power supply is not available, fire watches will be established in those fire areas where loss of normal power to the LSI panels could occur in the event of fire. This will consist of either establishing continuous fire watches or verifying OPERABILITY of fire detectors per Specification 4.3.3.7 and establishing hourly fire watches.

The details of how these fire watches are to be implemented are included in a plant procedure.

3 4.3.3.7 FIRE DETECTION INSTRUMENTATION SYSTEMS DETECTORS OPERABILITY of the fire detection systems/detectors ensures that adequate detection capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of the fires will reduce the potential for damage to safety related systems or components in the areas of the specified systems and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection systems is inoperable, the ACTION statements provided maintain the facility's fire protection program and allows for continued operation of the facility until the inoperable system(s)/detector(s) are restored to OPERABILITY. However, it is not our intent to rely upon the compensatory action for an extended period of time and action will be taken to restore the minimum number of detectors to OPERABLE status within a reasonable period.

3 4.3.3.8 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.

The containment water level and containment sump level transmitters will be modified or replaced and OPERABLE by the end of the refueling outage to begin in February 1989.

+Amendment 112 (Effective before startup following refueling outage currently scheduled in 2/89).

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-6 AMENDMENT NO.

EMERGENCY CORE COOLING SYSTEMS BASES 3 4.5.5 REFUELING WATER STORAGE TANK The OPERABILITY of the RWST as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown, and ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. Reactor coolant system cooldown can be caused by inadvertent depressurization, a loss of coolant accident or a steam line rupture. The limits on RWST minimum volume and boron concentration ensure that

1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

The limits on contained'ater volume and boron concentration of the RWST also ensure a pH value of between 7.6 and 9.5 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The ECCS analyses to determine F limits 0

in Specifications 3.2.2 and 3.2.6 assumed a RWST water temperature of 70 F. This temperature value of the RWST water determines that of the spray water initially delivered to the containment following LOCA. It is one of the factors which determines the containment back-pressure in the ECCS analyses, performed in accordance with the provisions of 10 CFR 50.46 and Appendix K to 10 CFR 50. The value of the minimum RWST temperature in Technical Specification 3.5.5 has been conservatively changed to 80 0 F to increase the consistency between Units 1 and 2. The lower RWST temperature results in lower containment pressure from containment spray and safeguards flow assumed to exit the break. Lower containment pressure results in increased flow resistance of steam exiting the core thereby slowing reflood and increasing PCT.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 5-3 AMENDMENT NO. P jf, ggP

LHEK

/USES

~CT~IO ~AG 3 4 0 PP ICAB LITY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 O 1 3 4 1 EACT VITY CO OL SYSTEMS 3/4.1.1 BORATION CONTROL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 1 1 3/4.1.2 BORATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-4 3 4 2 POWER DISTRIBUTION LIMITS 3/4. 2 1 AXIAL FLUX DIFFERENCE

~ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR EFQQLPY HOT CHANNEL FACTOR B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-5 3/4.2.5 DNB PAiUQCETERS B 3/4 2-5 3/4.2.6 ALLOWABLE POWER LEVEL B 3/4 2-5 3 4 3 INS UMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-la 3/4.3,4 TURBINE OVERSPEED PROTECTION B 3/4 3-4 3 4 4 REACTOR COOLANT SYST 3/4.4. 1 REACTOR COOLANT LOOPS B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES B 3/4 4-2 3.4.4.4 PRESSURIZER B 3/4 4-2 3/4 '.5 STEAM GENERATOR TUBE INTEGRITY B 3/4 4-2a 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3,4.4.7 CHEMISTRY B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XII AMENDMENT NO. QO, +K.

TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1. Manual
a. Safety Injection (ECCS) Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps ~ Not Applicable Essential Service Water System Not Applicable
b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Purge and Exhaust Isolation Not Applicable Containment Air Recirculation Fan Not Applicable C. Containment Isolation-Phase "A" Not Applicable Containment Purge and Exhaust Isolation Not Applicable
d. Steam Line Isolation Not Applicable
2. Containment Pressure-Hi h
a. Safety Injection (ECCS) Less than or equal to 27.0QQ/27.0++
b. Reactor Trip (from SI) Less than or equal to 3.0 C. Feedwater Isolation Less than or equal to 8.0
d. Containment Isolation-Phase "A" Not Applicable
e. Containment Purge and Exhaust Isolation Not Applicable
f. Auxiliary Feedwater Pumps Not Applicable, g Essential Service Water System Not Applicable COOK NUCLEAR PLANT - UNIT 2 3/4 3-26 AMENDMENT NO. gyes, Z/7

INSTRUMENTATION Continued BASES ESF response times specified in Table 3.3-5 which include sequential operation of the RWST and VCT valves (Notes Q and QQ) are based on values assumed in the,non-LOCA safety analyses. These analyses take credit for injection of borated water from the RWST. Injection of borated water is assumed not to occur until the VCT charging pump suction valves are closed following opening of the RWST charging pump suction valves. When sequential operation of the RWST and VCT valves is not included in the response times (Note ++); the values specified are based on the LOCA analyses. The LOCA analyses take credit for injection flow regardless of the source.

Verification of the response times specified in Table 3.3-5 will assure that the assumption used for VCT and RWST valves are valid.

3 4.3.3 MONITORING INSTRUMENTATION 3 4.3.3.1 RADIATION MONITORING INSTRUMENTATION Noble gas effluent monitors provide information, during and following an accident, which is considered helpful to the op'erator in assessing the plant condition. It is desired that these monitors be OPERABLE at all times during plant operation, but they are not required for safe shutdown of the plant.

In addition, a minimum of two in containment radiation-level monitors with a maximum range of 107 R/hr for photon only should be OPERABLE at all times except for cold shutdown and refueling outages. In case of failure of the monitor, appropriate actions should be taken to restore its operational capability as soon as possible.

Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed. For the unit vent noble gas monitors, it should be noted that there is an automatic switchover from the low/mid-range channels to the high-range channel when the upper limits of the low- and mid-range channel measurement ranges are reached. In this case there is no flow.to the low- and mid-range channels from the unit vent sample line. This is considered to represent proper operation of this monitor.

Therefore, if automatic switchover to the high-range should occur, and the low- and mid-range detectors are capable of functioning when flow is re-established, the low- and mid-range channels should not be declared inoperable and the ACTION statement in the Technical Specification does not apply. This is also true while purging the low- and mid-range chambers following a large activity excursion prior to resumption of low-level monitoring and establishment of a new background.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-la AMENDMENT NO.HP

INSTRUMENTATION BASES Radiation Monitorin Instrumentation Continued ALARM/TRIP INSTRUMENT SETPOINT MEASUREMENT RANGE*

1) Area Monitor- The monitor trip setpoint 10 R/hr to 10R/hr.

Upper Containment is based on 10 CFR 20 (VRS 2101/2201) limits. A homogenous mixture of the containment atmosphere is assumed. The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.

7

2) Area Monitor- The monitor setpoint was 1R/hr to 1 x 10 R/hr Containment High selected to reflect the guidance Photons.

Range (VRA 2310/ provided in Generic Letter 83-37 2410) for NUREG-0737 Technical Specifications.

3) Process Monitor The monitor trip setpoint is 1.5x10 uCi to 7.5 Particulate based on 10 CFR 20 Uci.

(ERS 2301/2401) The setpoint was detemined using the Noble gas setpoint and historical monitor data of the ratio of particulate to Noble gases.

-7

4) Process Monitor The monitor trip setpoint 5.8xlO uCi/cc to Noble Gas is based on 10 CFR 20 2.7xlO uCi/cc (ERS 2305/2405) limits. A homogenous mixture of the containment atmosphere is assumed. The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.
5) Steam Generator PORV Not Applicable.** O.luCi/cc to 1.0x10 2 (MRA 2601) uCi/cc.

(MRA 2602)

(MRA 2701)

(MRA 2702)

  • This is the minimum required sensitivity of the instrument. Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
    • These monitors are used to provide data to assist in post-accident off-site dose assessment.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-lb AMENDMENT NO. Ni XX9

INSTRUMENTATION BASES Radiation Monitorin Instrumentation Continued ALARM/TRIP INSTRUMENT SETPOINT MEASUREMENT RANGE*

6) Noble Gas Unit Vent Monitors a) Low Range See Bases Section 5.8x10 uCi/cc to 2.7x10 (VRS 2505) 3/4.3.3.10 uCi/cc.

b) Mid Range Not Applicable** 1.3x102 uCi/cc to (VRS 2507) 7.5x10 yCi/cc c) High Range Not Applicable** 2.9x104 uCi/cc to (VRS 2509) 1.6xl0 uCi/cc

7) Gland Steam Condenser Vent Noble Gas Monitor a) Low Range See Bases Section 5.8xl0 2uCi/cc to (SRA 2805) 3/4.3.3.10 2.7x10 uCi/cc.
8) Steam Jet Air Ejector Vent Noble Gas Monitor a) Low Range See Bases Section 5.8x10 uCi/cc to 2.7xl0 uCi/

(SRA 2905) 3/4.3.3.10 CC.

-3 b) Mid Range Not applicable.** 1.3x10 uCi/cc to 7.5x10 2 uCi/

(SRA 2907) CC.

-2 4 c) High Range Not Applicable.** 2.9x10 uCi/cc to 1.6x10 uCi/

(SRA 2909) CC.

9) Spent Fuel Storage The monitor setpoint is lxl0-1 mR/hr to lxl04 mR/hr (RRC-330) selected to alarm and trip consistent with 10 CFR 70.24(a) (2)
  • This is minimum sensitivity of the instrument for normal operation, to folio~ the course of an accident, and/or take protective actions. Values of the instrument above or below this minimum sensitivity range are acceptable.
    • These monitors are used to provide data to assist in pose-accident off-site dose assessment.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-lc AMENDMENT NO.pp, ZZp

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