ML17328A443

Errata to Amend 144 to License DPR-58 & Amends 134 & 131 to License DPR-74,correcting Typos Re ESFAS Instrumentation Trip Setpoints

ML17328A443
Person / Time
Site:	Cook
Issue date:	09/11/1990
From:	NRC
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ML17328A444	List: ML17328A443
References
NUDOCS 9009190243
Download: ML17328A443 (15)

Text

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 6.

MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.

Steam Generator Water Level--Low-Low b.

4 kV Bus Loss of Voltage Greater than or equal to 21$ of narrow range instrument span each steam generator 3280 volts with a 2 second delay Greater than or equal to 19.2% of narrow range instrument span each steam generator 3280 + 120 volts with a 2 +/- 0.2 second delay

c. Safety Injection

d. Loss of Main Feedwater Pumps Not Applicable Not Applicable Not Applicable Not Applicable 7.

TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.

Steam Generator Water Level--Low-Low Greater than or equal to 21% of narrow range instrument span each steam generator Greater than or equal to 19.2% of narrow range instrument span each steam generator

b. Reactor Coolant Pump Bus Undervoltage Greater than or equal Greater than or equal to 2750 Volts--each bus 2725 Volts--each bus 8;

LOSS OF POWER a.

4 kV Bus Loss of Voltage 3280 volts with a 2

second delay 3280 + 120 volts with a 2 +/- 0.2 second delay b.

4 kV Bus Degraded Voltage 3638 volts with a 2.0 minute time delay 3638 + 60 volts with a 2.0 minute +/-

6 second time delay COOK NUCLEAR PLANT - UNIT 2 3/4 3-25a AMENDMENT NO. 82, iN,

134, 9009190243 900911 PDR ADOCK 05000315 P

PDC

)

II

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.

At least once per 18 months by:

1.

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are,not restricted by debris and that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or corrosion.

e.

At least once per 18 months, during shutdown, by:

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

2.

Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:

a)

Centrifugal charging pump b)

Safety injection pump c)

Residual heat removal pump f.

By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1.

Centrifugal charging pump Greater than or equal to 2405 psig 2.

Safety Injection pump Greater than or equal to 1409 psig 3.

Residual heat removal pump Greater than or equal to 190 psig g.

By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

COOK NUCLEAR PLANT - UNIT 2 3/4 5-5 AMENDMENT N0.97'~, 99>>

/gal, 134

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURED ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 4.STEAM LINE ISOLATION CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST mL" a.Manual b.Automatic Actuation Logic c.Containment Press-ure--High-High d.Steam Flow in Two Steam Lines--

High Coincident with Tavg--Low-Low Pressure--Low N.A.

N.A.

N.A.

N.A.

M(1)

M(2)

M(3) 1 2

3 1,2,3 1

2 3

1,2,3 5.TURBINE TRIP & FEEDWATER ISOLATION a.Steam Generator Water Level--High-High 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS 1,2,3 a.Steam Generator Water Level--Low-Low 1

2 3

b.4 kv Bus Loss of Voltage c.Safety Injection d.Loss of Main Feed Pumps N.A.

N.A.

N.A.

N.A.

M(2) 123 1 2 3

1 2

COOK NUCLEAR PLANT - UNIT 1 3/4 3-33 AHENDMENT NO. g(,

egg, Qf,

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued shall be constituted of one basket each from Radial Rows 1, 2, 4, 6,

8 and 9 (or from the same row of an adjacent bay if a basket from a designated row cannot be obtained for weighing) within each bay. If any basket is found to contain less than 1220 pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed.

The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1220 pounds/basket at a 958 level of confidence.

The ice condenser shall also be subdivided into 3 groups of

baskets, as follows:

Group 1 - bays 1 through 8, Group 2-bays 9 through 16, and Group 3 - bays 17 through 24.

The minimum average ice weight of the sample baskets from Radial Rows 1, 2, 4, 6, 8 and 9 in each group shall not be less than 1220 pounds/basket at a 958 level of confidence.

The minimum total ice condenser ice weight at a 95% level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,371,450 pounds.

3.

Verifying, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on the top deck floor grating, on the intermediate deck and on flow passages between ice baskets and past lattice frames is restricted to a nominal thickness of 3/8 inches.

If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall'e visually inspected. If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.

More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.

C.

At least once per 18 months by verifying, by a visual inspection, each ice condenser bay, that the accumulation of frost or ice on the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of 3/8 inches.

An accumulation of frost and ice greater than this thickness is evidence of abnormal degradation of the ice condenser.

d.

COOK NUCLEAR PLANT - UNIT 1 At least once per 40 months by lifting and visually inspecting the accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear, cracks, corrosion or other damage.

The ice baskets shall be raised at least 12 feet for this inspection.

3/4 6-27 AMENDMENT NO.

108, Nf, 08, 144

CONTAINMENT SYSTEMS ICE CONDENSER DOORS I

LIMITING CONDITION FOR OPERATION 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPERABLE.

1 APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more ice condenser doors open or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the maximum ice bed temperature is maintained less than or equal to 27 F; otherwise, restore the doors to their closed positions or OPERABLE status (as applicable) 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.6.5.3.1 Inlet Doors

- Ice condenser inlet doors shall be:

a.

Continuously monitored and determined closed by the inlet door position monitoring system, and b.

Demonstrated OPERABLE during shutdown at least once per 18 months by:

1.

Verifying that the torque required to initially open each door is less than or equal to 675 inch pounds.

2.

Verifying that opening of each door is not impaired by ice, frost or debris.

3.

Testing each one of the doors and verifying that the torque required to open each door is less than 195 inch-pournds when the door is 40 degrees open.

This torque is defined as the "door opening torque" and is equal to the nominal door torque plus a frictional torque component.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-30 AMENDMENT NO.f/g, Pg, 144

PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7 '.1 a.

At least two independent component cooling water loops shall be OPERABLE.

b.

At least one component cooling water flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.1.a.

- MODES 1, 2, 3, 4.

Specification 3.7.3.l.b.

- At all times when Unit 2 is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.?.3.l.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

When Specification 3.7.3.1.b is applicable:

With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in 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 /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE' a

~

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not

locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

C.

At least once per 31 days on a STAGGERED TEST BASIS, by verifying that each pump develops at least 93% of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve.

d.

At least once per 18 months during shutdown, by verifying that the cross-tie valves can cycle full travel.

Following cycling, the valves will be verified to be in their closed positions.

DE C.

COOK - UNIT 1 3/4 7-15 Amendment No.$07, gf, 144

PLANT SYSTEMS 3 4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION

'.7.4.1 a.

At least two independent essential service water loops shall be OPERABLE.

b.

At least one essential service water flowpath associated with support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.l.a.

MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b.

- At all times when Unit 2 is in MODES 1, 2, 3 or 4.

ACTION:

When Specification 3.7.4.l.a is applicable:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

When Specification 3.7.4.l.b is applicable:

With no essential service water flow path available in support of Unit 2 shutdown functions, return at least one flow path available status within 7 days or provide equivalent shutdown capability in Unit 2 and return the equipment to available status within the next 60 days, or have Unit 2 in 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 /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE'

~

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not

locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test. signal.

C.

At least once per 31 days on a STAGGERED TEST BASIS, by verifying that each pump develops at least 93% of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve.

D.

C.

COOK - UNIT 1 3/4 7-17 Amendment No.fg7, /gal, 144

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

a.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel as provided by Technical Specification 4.7.9.l.l.d.

b.

At least once per 18 months:

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2.

By visual inspection of deluge and preaction system piping (this is not required for systems supervised by air) to verify their integrity.

3.

By visual inspection of each open head deluge nozzle to verify that there is no blockage.

At least once per 3 years by performing an air flow test through the piping of each open head deluge system and verifying each open head deluge nozzle is unobstructed.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-45 AMENDMENT NO. egg, f/0, 144

PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 a.

At least two independent component cooling water loops shall be OPERABLE.

b.

At least one component cooling water flow path in support of Unit 1 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.l.a.

MODES 1, 2, 3, 4.

Specification 3.7.3.l.b.

- At all times when Unit 1 is in MODES 1, 2,

3, or 4.

ACTION:

When Specification 3.7.3.1.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

When Specification 3.7.3.l.b is applicable:

With no flowpath in Unit 1 available, return at least one flowpath to available status within 7 days, or provide equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in 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 /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked,

sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

t 4.7.3.2 At least once per 18 months during shutdown, verify that the unit cross-tie valves can cycle full travel.

Following cycling, the valves will be verified to be in their closed positions.

D.

C.

COOK - UNIT 2 3/4 7-12 15 Amendment No. P, fN, 131

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued 2.

With two or more block valves inoperable, Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either (1) restore a total of at least two block valves to OPERABLE status, or (2) close the block valves and remove power from the block valves, or (3) close the associated PORVs and remove power from their associated solenoid valves; and apply the portions of ACTION a.2 or a.3 above for inoperable PORVs, relating to OPERATIONAL MODE, as appropriate.

c.

With PORVs and block valves not in the same line inoperable,*

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either (1) restore the valves to OPERABLE status or (2) close and de-energize the other valve in each line.

Apply the portions of ACTION a.2 or a.3 above, relating to OPERATIONAL MODE, as appropriate for two or three lines unavailable.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE:

a.

At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.

At least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

The block valve(s) do not have to be tested when ACTION 3.4.11.a or 3.4.11.c is applied.

4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries.

This testing can be performed in conjunction with the requirements of Specifications 4.8.1.1.2.c and 4.8.2.3.2.d.

• PORVs isolated to limit RCS leakage through their seats and the block valves shut to isolate this leakage are not considered inoperable'OOK NUCLEAR PLANT - UNIT 2 3/4 4-33 AMENDMENT NO gg, g, 131

0

3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 a.

At least two independent essential service water loops shall be OPERABLE.

b.

At least one essential service water flowpath associated with support of Unit 1 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.1.a.

MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b.

- At all times when Unit 1 is in MODES 1, 2, 3 or 4.

ACTION:

When Specification 3.7.4.1.a is applicable:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

When specification 3.7.4.1.b is applicable:

With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one flow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in 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 /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The requirements of Specifications 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked,

sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

D.

C.

COOK - UNIT 2 3/4 7-13 Amendment No.97, Ag, 131

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel as provided by Technical Specification 4.7.9.1.1.d.

b.

At least once per 18 months:

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, 2.

By visual inspection of deluge and preaction system piping (this is not required for systems supervised by air) to verify their integrity.

3.

By visual inspection of each open head deluge nozzle to verify that there is no blockage.

c

~

At least once per 3 years by performing an air flow test through the piping of each open head deluge system and verifying each open head deluge nozzle is unobstructed.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-40 AMENDMENT NO. $0, fg, f3[

't Y

E