Text

Amends 144 & 131 to Licenses DPR-58 & DPR-74,respectively, Removing Refs to Obsolete Surveillance Interval Extensions from Tech Specs
	ML17328A403
Person / Time
Site:	Cook
Issue date:	08/06/1990
From:	Pierson R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17328A404	List: ML17328A403; ML17328A405;
References
	NUDOCS 9008310078
	Download: ML17328A403 (93)
	v • d • e

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t UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

144 License No. DPR-58 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated September 15, 1988, 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; B..

The facility will operate in conformity with the application,'he provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

9008310078 900806 PDR ADOCN, 05000315 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Faci lity Operating License No.

DPR-58 is hereby amended to read as follows:

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.

144

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 6, 1990 Robert Pierson, Director Project Directorate III-1~

Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation

ATTACIIMENT TO LICENSE AMENDMENT NO. gag

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FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain marginal 1ines indicating the area of change.

REMOVE 3/4 0-3 3/4 3-1 3/4 3-12 3/4 3-13 3/4 3-15 3/4 3-31 through 3-33a 3/4 3-42 3/4 3-48 3/4 3-54 3/4 3-56 3/4 4-14 3/4 4-36 3/4 5-2 3/4 5-5 3/4 5-8 3/4 6-10 3/4 6-13 3/4 6-15 3/4 6-27 3/4 6-30 3/4 6-33 3/4 6-34 3/4 6-38 3/4 7-6 3/4 7-15 3/4 7-17 3/4 7-22 3/4 7-25 3/4 7-28 3/4 7-45 INSERT 3/4 0-3 3/4 3-1 3/4 3-12 3/4 3-13 3/4 3-15 3/4 3-31 3/4 3-42 3/4 3-48 3/4 3-54 3/4 3-56 3/4 4-14 3/4 4-36 3/4 5-2 3/4 5-5 3/4 5-8 3/4 6-10 3/4 6-13 3/4 6-15 3/4 6-27 3/4 6-30 3/4 6-33 3/4 6-34 3/4 6-38 3/4 7-6 3/4 7-15 3/4 7-17 3/4 7-22 3/4 7-25 3/4 7-28 3/4 7-45 through 3-33a

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3 4. 0 APPLICABILITY SURVEILLANCE RE UIREMENTS b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler And Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspec-inspection and testing criteria tion and testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per At least once per At least once per At least once per At least once per 7 days 31 days 92 days 184 days 366 days C.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 Amendments

100, 107 and 108 granted extensions for certain surveillances required to be performed on or before July 31,

1987, and until the end of the Cycle 9-10 refueling outage.

For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1987 refueling outage.

4.0.7 Amendment 121 granted extensions for certain surveillances required to be performed on or before April 1, 1989, until the end of the Cycle 10-11 refueling outage.

For these specific surveillances under this extension, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during'the Unit 1 1989 refueling outage.

COOK NUCLEAR PLANT - UNIT 1 3/4 0-3 AMENDMENT NO.g Pg, ggf,144

3 4.3 INSTRUMENTATION 3 4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION

3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE RE UIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each, channel affected by interlock operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per 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 reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-1 AMENDMENT NO. )gal,gg),144

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TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT

1. Manual Reactor Trip CHANNEL CHECK CHANNEL MODE IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE CALIBRATION TEST A. Shunt Trip Function B. Undervoltage Trip Function N.A.

N.A.

S/U(l)(10) 1, 2, 3*, 4 5

S/U(1)(10) 1, 2, 3*,

4

, 5*

2.

Power Range, Neutron Flux 3.

Power Range, Neutron Flux, High Positive Rate 4.

Power Range, Neutron Flux, High Negative Rate

5. Intermediate

Range, Neutron Flux N.A.

N.A.

D(2,8),

M(3,8) and Q(6,8)

R(6)

R(6,8)

M and S/U(1)

S/U(1) 1, 2 and

1 2

1 2

1, 2,

and

6.

Source

Range, Neutron S

Flux

7. Overtemperature delta T S

8. Overpower delta T

S

9. Pressurizer Pressure--

S Low R(6,14)

R(9)

M(14) and 2(7), 3(7),

4 S/U(1) and 5

1, 2

10.Pressurizer Pressure--

S High 11.Pressurizer Water Level--

S High 12.Loss of Flow-Single Loop S

R(8) 1 2

1, 2

COOK NUCLEAR PLANT - UNIT 1 3/4 3-12 AMENDMENT NO.gPP,)gg,ggg,gg4,

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TABLE 4.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 13.Loss of Flow-Two Loops 14.Steam Generator Water Level--Low-Low S

R(8)

N.A.

1 2

CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST m"

15.Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level 1,

2 16.Undervoltage-Reactor Coolant Pumps 17.Underfrequency-Reactor Coolant Pumps 18.Turbine Trip N.A.

N.A.

A.Low Fluid Oil Pressure N.A.

N.A.

S/U(1) 1 2

B.Turbine Stop Valve Closure 19.Safety Injection Input from ESF N.A.

N.A.

S/U(1)

M(4) 1, 2

1 2

20.Reactor Coolant Pump Breaker Position Trip 21.Reactor Trip Breaker A. Shunt Trip Function B. Undervoltage Trip Function 22.Automatic Trip Logic 23.Reactor Trip Bypass Breaker N.A.

N.A.

- N.A.

N.A.

M(5)(11) 1, 2, 3*, 4

, 5*

and S/U(1)(11)

M(5)(11) 1, 2, 3*, 4

, 5*

and S/U(1)(11)

M(5) 1 2

3*

4*

M(12) and 1, 2, 3*, 4*, 5*

S/U(1)(13)

COOK NUCLEAR PLANT - UNIT 1 3/4 3-13 AMENDMENT NO./PE" ggp,]44

INSTRUMENTATION 3 4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4'-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3.3-3.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-15 AMENDMENT NO.ggP,egg,] 44

TABLE 4.3-2 ENGINEERED SAFETY FEATURED ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 1.SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARYFEEDWATER PUMPS CHANNEL.

MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST a.Manual Initiation b.Automatic Actuation Logic c.Containment Press-ure-High d.Pressurizer Press-ure-Low e.Differential Press-ure Between Steam Lines--High f.Steam Flow in Two Steam Lines--High Coincident with Tavg

--Low or Steam Line Pressure--Low N.A.

N.A.

S N.A.

N.A.

M(1)

M(2)

M(3) 1,2,3,4 1,2,3,4 1,2,3 1,2,3 1

2 3

123 2.CONTAINMENT SPRAY a.Manual Initiation b.Automatic Actuation Logic c.Containment Press-ure-High-High N.A.

N.A.

M(1)

M(2)

M(3) 1,2,3,4 1,2,3,4 1,2,3 COOK NUCLEAR PLANT - UNIT 1 3/4 3-31 AMENDMENT NO.'gPP,ggg,ggf,j.44

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TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURED ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST 3.CONTAINMENT ISOLATION a.Phase "A" Isolation l)Manual 2)From Safety Injection Automatic Actuation Logic b.Phase "B" Isolation 1)Manual 2)Automatic Actua-tion Logic 3)Containment Press-ure-High-High c.Purge and Exhaust Isolation N.A.

N.A.

M(1)

M(2)

M(1)

M(2)

M(3) 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3 1)Manual 2)Containment Radio-activity-High N.A.

S N.A.

R M(1)

M 1,2,3,4 1,2,3,4 COOK NUCLEAR PLANT -, UNIT 1 3/4 3-32 AMENDMENT NO. )PP,144 I

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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 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.

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 123 a.Steam Generator Water Level--Low-Low b.4 kv Bus Loss of Voltage c.Safety Injection d.Loss of Main Feed Pumps N.A.'.A.

N.A.

M(2) 123 123 123 123 COOK NUCLEAR PLANT - UNIT 1 3/4 3-33 AMENDMENT NO. g Pg, g g P, g gf,144

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURED ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST REQUIRED 7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low b.Reactor Coolant Pump Bus Undervoltage S.LOSS OF POWER N.A.

123 1,2.3 a.4 kv Bus Loss of Voltage b.4 kv Bus Loss of Voltage 1,2,3,4 1,2,3,4 COOK NUCLEAR PLANT - UNIT 1 3/4 3-33a AMENDMENT NO.))P,)PPy144

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TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL 1.

STRONG MOTION TRIAXIALACCEL-EROGRAPHS CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST

a. Reactor Pit Floor

1. Time History Recorder M

2. Seismic Trigger NA b.

Top of Crane Wall

1. Time History Recorder M

c. Free Field R

R M

NA 1 ~ Time History Recorder M

2. Seismic Trigger NA 2.

PEAK RECORDING ACCELEROGRAPHS M

NA a.

Containment Spring Line NA

b. Diesel Generator Room Floor NA NA NA

c. Spent Fuel Pool NA COOK NUCLEAR PLANT - UNIT 1 3/4 3-42 AMENDMENT NO /$7,144.

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT

1. Reactor Trip Breaker Indication CHANNEL CHECK N.A.

CHANNEL CALIBRATION N.A.

2. Pressurizer Pressure

3. Pressurizer Level 4.

Steam Generator Level 5.

Steam Generator Pressure COOK NUCLEAR PLANT - UNIT 1 3/4 3-48 AMENDMENT NO.)PP,)gal,144

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INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING'CONDITIONFOR OPERATION 3.3.3.8 The post-accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2,

and 3.

ACTION:

a.

With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-11, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.8 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-54 AMENDMENT NO.Q NgPg',] Q4

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TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHANNEL CHECK CALIBRATION

1. Containment Pressure

2. Reactor Coolant Outlet Temperature-THOT (Wide Range )

3. Reactor Coolant Inlet Temperature-T Wide Range) 4.

ReaMc or Coolant Pressure-Wide Range

5. Pressurizer Water Level 6

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Steam Line Pressure 7.

Steam Generator Water Level-Narrow Range 8.

RWST Water Level

9. Boric Acid Tank Solution Level 10.Auxiliary Feedwater Flow Rate 11.Reactor Coolant System Subcooling Margin Monitor 12.PORV Position Indicator

- Limit Switches 13.PORV Block Valve Position Indicator-Limit Switches 14.Safety Valve Position Indicator-Acoustic Monitor 15.Incore Thermocouples (Core Exit Thermocoup 16.Reactor Coolant Inventory Tracking System (Reactor Vessel Level ggdication) 17.Containment Sump Level 18.Containment Water Level**

M M

M les)M M(2)

M M

R R

R R(1)

R(3)

R R

(1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3

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(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

(3) completion of channel claibration for sensors to be performed halos p-l2 in MODE 3.

- The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.

The schedule for modification or replacement of the transmitters is described in the Bases.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-56 AMENDMENT NO.)g,144

REACTOR COOLANT SYSTEM 3 4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a.

One of the containment atmosphere particulate radioactivity monitoring channels (ERS-1301 or ERS-1401),

b.

The containment sump level and flow monitoring system, and c.

Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivty monitoring channels (ERS-1305 or ERS-1405).

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only two of the above required leakage detection systems

OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a.

Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months, c.

Containment humidity monitor (if being used)

- performance of CHANNEL CALIBRATION at least once per 18 months.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-14 AMENDMENT NO ~ )PAL,144

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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued 2.

With two or more block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

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

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.b 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.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-36 AMENDMENT NO. )Pg,f/',144

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution.

c.

At least once per 31 days when the RCS pressure is above 2000 psig, by verifying that power to the isolation valve operator is disconnected by removal of the breaker from the circuit.

d.

Verifying at least once per 18 months that each accumulator isolation valve opens automatically upon'eceipt of a safety injection test signal.

COOK NUCLEAR PLANT - UNIT 1 3/4 5-2 AMENDMENT NO.A/7,3,4$

I 1

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued 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 abnormal corrosion.

e.

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

1.

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 automatically upon receipt of a safety injection 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 at least once per 31 days on a STAGGERED TEST BASIS.

1.

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

Safety Injection pump Greater than or equal to 1345 psig 3.

Residual heat removal pump Greater than or equal to 165 psfg 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.

COOK NUCLEAR PLANT - UNIT 1 3/4 5-5 AMENDMENT NO. A/7,/PE,144

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 170 F as determined at least once per hour when any RCS cold leg temperature is between 170 F and 200 F.

COOK NUCLEAR PLANT - UNIT 1 3/4 5-8 AMENDMENT NO./gal,3.44

CONTAINMENT SYSTEMS 3 4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION'ith one containment spray system inoperable, restore the inoperable spray system 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restor'e the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

'a ~

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked,

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

b.

By verifying, that on recirculation flow, each pump develops a

discharge pressure of greater than or equal to 255 psig at a flow of greater than or equal to 700 gpm, when tested pursuant to Specification 4.0.5 at least once per 31 days on a STAGGERED TEST BASIS.

c.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure

-- High-High test signal.

2.

Verifying that each spray pump starts automatically on a Containment Pressure

-- High-High test signal.

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-10 AMENDMENT NO.)P7,/$ 4

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued c

At least once per 18 months during shutdown, by:

1.

Cycling each power operated (excluding automatic) valve in the flow path that is not testable during plant operation, through at least one complete cycle of full travel.

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure

-- High-High signal.

At least once per 5 years by verifying a water flow rate of at least 20 gpm (greater than or equal to 20 gpm) but not to exceed 50 gpm (less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255 psig.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-13 AMENDMENT NO. )P7,$ 44

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued valve or its associated

actuator, control or power circuit by performance of the cycling test,

above, and verification of isolation time.

4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demon-strated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b.

Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

c.

Verifying that on a Containment Purge and Exhaust isolation

signal, each Purge and Exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-15 AMENDMENT NO )P7,144

I I

r IOP*

~

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 95% 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 95% 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 flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes 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 be 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, 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.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-27 AMENDMENT N0.$'PP,)Pg,gj3g,144 0

l g'4

'F Fl

CONTAINMENT SYSTEMS ICE CONDENSER DOORS 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.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 montioring system, and b.

Demonstrated OPERABLE during shutdown at least once per 9 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'y ice, frost or debris.

3.

Testing a sample of at least 50% of the doors and verifying that the torque required to open each door is less than 195 inch-pounds 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 COOK NUCLEAR PLANT - UNIT 1 3/4 6-30 AMENDMENT NO.)gg,f/', 144

I

CONTAINMENT SYSTEMS INLET DOOR POSITION MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.4 The inlet door position monitoring system shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the inlet door position monitoring system inoperable, POWER OPERATION may continue for up to 14 days, provided the ice bed temperature monitoring system is OPERABLE and the maximum ice bed temperature is less than or o

equal to 27 F when monitored at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, restore the inlet door position monitoring system to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6.5.4 The inlet door position monitoring system shall be determined OPERABLE by:

a.

Performing a

CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Performing a

CHANNEL FUNCTIONAL TEST at least once per 18 months, and C.

Verifying that the monitoring system correctly indicates the status of each inlet door as the door is opened and reclosed during its testing per Specification 4.6.5.3.1.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-33 AMENDMENT NO gg,l44-

I

CONTAINMENT SYSTEMS DIVIDER BARRIER PERSONNEL ACCESS DOORS AND E UIPMENT HATCHES LIMITING CONDITION FOR OPERATION 3.6.5.5 The personnel access doors and equipment hatches be'tween the containment's upper and lower compartments shall be OPERABLE and closed.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With a personnel access door or equipment hatch inoperable or open except for personnel transit entry and T greater than 200 F, restore the door 0

or hatch to OPERABLE status or to Yfs closed position (as applicable) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6.5.5.1 The personnel access doors and equipment hatches between the con-tainment's upper and lower compartments shall be determined closed by a visual inspection prior to increasing the Reactor Coolant System T

above 0

ave 200 F and after each personnel transit entry when the Reactor Coolant System T

is above 200 F.

avg 4.6.5.5.2 The personnel access doors and equipment hatches between the containment.'s upper and lower compartments shall be determined OPERABLE by visually inspecting the seals and sealing surfaces of these penetrations and verifying no detrimental misalignments, cracks or defects in the sealing

surfaces, or apparent deterioration of the seal material:

a Prior to final closure of the penetration each time it has been

opened, and At least once per 10 years for penetrations containing seals fabricated from resilient materials.

COOK NUCLEAR PLANT -. UNIT 1 3/4 6-34 AMENDMENT NO;)pal ]qg

I l

SX V 1

CONTAINMENT SYSTEMS DIVIDER BARRIER SEAL LIMITING CONDITION FOR OPERATION 3.6.5.9 The divider barrier seal shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE RE UIREMENTS 4.6.5.9 The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:

a.

Removing two divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.

b.

Visually inspecting at least 95 percent of the seal's entire length and:

1.

Verifying that the seal and seal mounting bolts are properly installed, and 2.

Verifying that the seal material shows no visual evidence of deterioration due to holes,

ruptures, chemical attack,

abrasion, radiation damage, or changes in physical appearances.

COOK NUCLEAR PLANT - UNIT 1 3/4 6-38 AMENDMENT NO.)PP,1/4

I 4.

s ly

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.1.2 Each auxiliary feedwater pump sha11 be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that each motor driven pump develops an equivalent discharge pressure of k 1375 psig at 60'F on recirculation flow.

2.

Verifying that the steam turbine driven pump develops a 'discharge pressure of > 1285 psig at 60 F and at a flow of > 700 gpm when the secondary steam supply pressure is greater than 310 psig.

The provisions of Specification '4.0.4 are not applicable for entry into MODE 3.

Verifying that each non-automatic valve in the flow path that is not locked,

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

4.

Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 108 RATED THERMAL POWER.

This requirement is not applicable for those portions of the auxiliary feedwater system being used intermittently to maintain steam generator water level.

b.

At least once per 18 months during shutdown by:

2.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

3.

Verifying that the unit cross-tie valves can cycle full travel.

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

COOK NUCLEAR PLANT - UNIT 1 3/4 7-6 AMENDMENT NO. )PP,)P),144

J

PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

I'CTION:

With only one component cooling water loop OPERABLE, restore at least two loops 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

At least once per 31 days 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 938 of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-15 AMENDMENT NO. EP7,787,144

PLANT SYSTEMS 3 4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent essential service water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION'ith only one service water loop OPERABLE, restore at least two loops 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-17 AMENDMENT NO.)P7,$ )$,144

IIX'f

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10$.

2.

Verifying that on a Safety Injection Signal from either Unit 1 or Unit 2, or on a containment phase A isolation signal, the system automatically diverts its inlet flow through the HEPA filters and charcoal adsorber bank and that either fan can then be manually started in the recirculation mode.

3.

Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W.

G.

relative to the outside atmosphere at a system flow rate of 6000 cfm plus or minus 10%.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal J

to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

f g

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 10%.

t COOK NUCLEAR PLANT - UNIT 1 3/4 7-22 AMENDMENT NO.)P7,].gg.

\\I Q

PLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued b)

Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtain-ing the carbon sample, the system shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove less than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in,accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 108:

d.

At least once per 18 months by:

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Mater Gauge while operating the ventilation system at a

flow rate of 25,000 cfm plus or minus 10%.

2.

Deleted.

3.

Verifying that the standby fan starts automatically on a Containment Pressure--High-High Signal and dire"ts its exhaust flow through the HEPA filters and charcoal adsorber banks on a Containment Pressure--High-High Signal.

e.

After each complete or partial replacement of HEPA filter band by verifying that the HEPA filter banks remove greater than or equal to 99%'f the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10%.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal f

to 99% of a halogenated hydrocarbon refrigerant test gas when they are l tested in-place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10%.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-25 AMENDMENT NO. gg,gg$,144

0 I

I I

ll I

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers listed in Table 3.7-4 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREHENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Ins ections The first inservice visual inspection of snubbers shall be per-formed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-4. If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months plus or minus 258 from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers er Ins ection Period Subsequent Visual Ins ection PeriodM 0

1 2

3,4 5,6,7 8 or more 18 months 12 months 6 months 124 days 62 days 31 days plus or minus 25%

plus or minus 25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

The inspection interval shall not be lengthened more than one step at a time.

¹ The provisions of Specification 4.0.2 are not applicable.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-28 AMENDMENT No.)gal,ging,144

~,

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.2 Each of the above requi.red 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 4.7.9.1.1.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 inspection of deluge and preaction type system spray headers to verify their integrity.

3.

By inspection of each open head deluge nozzle to verify no blockage.

c ~

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

COOK NUCLEAR PLANT - UNIT 1 3/4 7-45 AMENDMENT.-NO. )gP,g)$,1/4

1 J

~h l1EQ(g e,l 0

1y A0 pl( g

+w*w+

UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

131 License No. DPR-74 l.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

The application for amendment by Indiana Michigan Power Company (the licensee) dated September 15, 1988, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endanger ing the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the COII@Iission's regulations and all applicable requirements have been satisfied.

I 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2 AC.(2) of Facility Operating License No.

DPR-74 is hereby amended to read as fol,lows:

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 131, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 6, 199Q Robert Pierson, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO. 131 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below arid inserting the attached pages.

The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

RENOVE 3/4 0-3 3/4 1-22 3/4 3-1 3/4 3-14 3/4 3-32 3/4 3-47 3/4 4-14 3/4 4-33 3/4 5-2 3/4 5-4 3/4 5-5 3/4 5-8 3/4 6-10 3/4 6-12 3/4 6-14 3/4 6-47 3/4 7-6 3/4 7-12 3/4 7-13 3/4 7-16a 3/4 7-19a through 21 3/4 7-40 3/4 9-4 INSERT 3/4 0-3 3/4 1-22 3/4 3-1 3/4 3-14 3/4 3-32 3/4 3-47 3/4 4-14 3/4 4-33 3/4 5-2 3/4 5-4 3/4 5-5 3/4 5-8 3/4 6-10 3/4 6-12 3/4 6-14 3/4 6-47 3/4 7-6 3/4 7-12 3/4 7-13 3/4 7-16a 3/4 7-19a 3/4 7-40 3/4 9-4 through 21

3 4.0 APPLICABILITY SURVEILLANCE RE UIREMENTS b.

Surveillance Intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required'y the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler And Pressure Vessel Code and applicable Addenda terminology-for inservice ins ection and testin criteria Required frequencies for performing inservice inspec-tion and testin activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days.'t least 'once per 92 days

" At least once per 184 days At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in, the ASME Boiler and Pressure Vessel Code shall be con-strued to supersede the requirements of any Technical Specification.

4.0.6 Amendment 78 granted extensions for certain surveillances required to be performed on or before March 31, 1986, until the end of the Cycle 5-6 refueling outage.

For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1986 refueling outage.

4.0.7 Amendments 97 and 99 granted extensions for certain surveillances required to be performed on or before July 1, 1988, until the end of the Cycle 6-7 refueling outage.

For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1988 refueling outage.

COOK NUCLEAR PLANT - UNIT 2 3/4 0-3 AMENDMENT NO.7g,g),131

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 At least one rod position indicator channel (excluding demand position indication) shall be OPERABLE for each shutdown or control rod not fully inserted.

APPLICABILITY:

MODES 3*¹, 4*¹ and 5M ACTION:

With less than the above required position indicator channel(s)

OPERABLE, immediately open the reactor trip system breakers.

SURVEILLANCE RE UIREMENTS 4.1.3.3 Each of the above required rod position indicator channel(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.

With the reactor trip system breakers in the closed position.

¹See Special Test Exception 3.10.5.

COOK NUCLEAR PLANT - UNIT 2 3/4 1-22 AMENDMENT NO.JP, PP,131

3 4.3 INSTRUMENTATION 3 4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1

~

SURVEILLANCE RE UIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channe" affected by interlock operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per 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 reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-1 AMENDMENT NO.7$,$7,131

C.

4

INSTRUMENTATION 3 4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3, The ENGINEERED SAFETY FEATURES

RESPONSE

TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" column of Table 3.3-3.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-14 AMENDMENT NO."7$,$ 7,3.33,

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 4.

STEAM LINE ISOLATION

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 e.

Steam Line Pressure--

Low CHANNEL CHECK N.A.

N.A.

CHANNEL CALIBRATION N.A.

N.A.

R R

CHANNEL FUNCTIONAL TEST M(1)

M(2)

M(3)

M MODES IN WHICH SURVEILLANCE RE UIRED 123 1,2,3 123 1,2,3 1,2,3 5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water Level--High-High 6.

MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.

Steam Generator Water Level--Low-Low b.

4 kV Bus Loss of Voltage

c. Safety Injection

d. Loss of Main Feed Pumps N.A.

N.A.

M(2)

R 1,2,3 and 123 1,2,3 123 1,2 COOK NUCLEAR PLANT - UNIT 2 3/4 3-32 AMENDMENT NO.g,g7,191

TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHANNEL CHECK CALIBRATION l.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

Containment Pressure Reactor Coolant Outlet Temperature THOT (Wide Range)

Reactor Coolant Inlet Temperature TCOLD (Wide Range)

Reactor Coolant Pressure

- Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level

- Narrow Range RWST Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator - Limit Switches PORV Block Valve Position Indicator

- Limit Switches Safety Valve Position Indicator - Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)(4)

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

Containment Sump Level*

Containment Water Level*

M M

M M(2)

R R

R(1)

R(3)

(1)

(2)

(3)

(4)

Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

The core exit thermocouples will not be installed until the 1988 refueling outage; therefore, surveillances will not be required until that time.

See license amendment dated April 10, 1987.

The requirements for these instruments will become effective after the level transmitters are modified or replaced and-become operational.

The schedule for modification or replacement of the transmitters is described in the Bases.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-47 AMENDMENT N0.9g,gg,131

REACTOR COOLANT SYSTEM 3 4.4.6 REACTOR COOLANT SYSTEM LEAKAGE lh LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a.

One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or ERS-2401),

b.

The containment sump level and flow monitoring system, and c.

Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).

APPLICABILITY:

MODES 1, 2,

3 and 4 ACTION:

With only two of the above required leakage detection systems

OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months, C.

Containment humidity monitor (if being used)

- performance of CHANNEL CALIBRATION at least once per 18 months.

R COOK NUCLEAR PLANT - UNIT 2 3/4 4-14 AMENDMENT N0.7$,131

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued 2.

With two or more block inoperable, Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore a total of at least two block valves to OPERABLE status, or (2) close the block valves to OPERABLE status, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 tuo or three lines unavailable.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE'REQUIREMENTS 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 '.d.

PORVs isolated to limit RCS leakage through their seats and the block valves shut to isolate this leakage are not considered inoperable.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-33 AMENDMENT NO.g,)7,131

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase greater than or equal to lS of tank volume by verifying the boron concentration of the accumulator solution.

C.

At least once per 31 days when the RCS pressure is above 2000 psig by verifying that power to the isolation valve operator is disconnected by removal of the breaker from the circuit.

At lease once per 18 months by verifying that each accumulator isolation valve opens automatically upon receipt of a safety injection test signal.

COOK NUCLEAR PLANT - UNIT 2 3/4 5-2 AMENDMENT NO.P pe

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position a.

IMO-390 b.

IMO-315 c.

IMO-325

d. IMP-262*

e.

IMO-263*

f. IMO-261*

g.

ICM-305*

h.

ICM-306*

a.

RWST to RHR b.

Low head SI to Hot Leg c.

Low head SI to Hot Leg d.

Mini flow line e.

Mini flow line f.

SI Suction g.

Sump Line h.

Sump Line a.

Open

b. Closed

c. Closed d.

Open e.

Open

f. Open

g. Closed

h. Closed b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked,

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

C.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

These valves must change position during the switchover from injection to recirculation flow following LOCA.

COOK NUCLEAR PLANT - UNIT 2 3/4 5-4 AMENDMENT NO.7$,3,33,

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.

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

1.

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 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 3.

Residual heat removal pump Greater than or equal to 1445 psig Greater than or equal to 195 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 NO.)7,)P,] 3]

II%

~l

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 152 F as determined at least once 0

per hour when any RCS cold leg temperature is between 152 F and 200 F.

COOK NUCLEAR PLANT - UNIT 2 3/4 5-8 AMENDMENT NO. PP,P),3,33,

CONTAINMENT SYSTEMS 3 4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM h

LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction,to the containment sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked

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

b.

By verifying, that on recirculation flow, each pump develops a

discharge pressure of greater than or equal to 255 psig at a flow of greater than or equal to 700 gpm, when tested pursuant to Specification 4.0.5.

C.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure--High-High test signal.

2.

Verifying that each spray pump starts automatically on a Containment Pressure--High-High test signal.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

COOK NUCLEAR PLANT - UNIT 2 3/4 6-10 AMENDMENT NO. $$,131

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued c,

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 Containment Pressure--High-High test signal.

At least once per 5 years by verifying a water flow-rate of at least 20 gpm (greater than or equal to 20 g'pm) but not to exceed 50 gpm f

(less than or equal to 50 gpm) from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure greater than or equal to 255 psig.

COOK NUCLEAR PLANT - UNIT 2 3/4 6-12 AMENDMENT NO. P P,, g7, 13$

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b.

Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

C.

Verifying that on a Containment Purge and Exhaust isolation

signal, each Purge and Exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5 COOK NUCLEAR PLANT - UNIT 2 3/4 6-14 AMENDMENT NO $7,131

CONTAINMENT SYSTEMS DIVIDER BARRIER SEAL LIMITING CONDITION FOR OPERATION 3.6.5.9 The divider barrier seal shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE RE UIREMENTS 4.6.5.9 The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:

a.

Removing two divider barrier seal test coupons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.

Visually inspecting at least 95 percent of the seal's entire length and:

1.

Verifying that the seal and seal mounting bolts are pro-perly installed, and 2.

Verifying that the seal material shows no visual evidence of deterioration due to holes,

ruptures, chemical attack,

abrasion, radiation damage, or changes in physical appearances.

COOK NUCLEAR PLANT - UNIT 2 3/4 6-47 AMENDMENT NO.gP,)3$

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that each motor driven pump develops an equivalent discharge pressure of <<1240 psig at 60 F. on recirculation Q.ow.

2.

Verifying that the steam turbine driven pump develops an equivalent discharge pressure of <<1180 psig at 60 F and at a flow of <<700 gpm when 0

the secondary steam supply pressure is greater than 310 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

3.

Verifying that each non-automatic valve in the flow path that is not locked,

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

4.

Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.

This requirement is not applicable for those portions of the Auxiliary Feedwater System being used intermittently to maintain steam generator level.

b.

At least once per 18 months during shutdown by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

2.

Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

3.

Verifying that the unit cross-tie valves can cycle full travel.

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

COOK NUCLEAR PLANT - UNIT 2 3/4 7-6 AMENDMENT NO ~ 77yg7yggf 131

PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

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

sealed, or otherwise secured in its 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.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-12 AMENDMENT NO. $7,))P,131

PLANT SYSTEMS 3 4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent essential service water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION With only one service water loop OPERABLE, restore at least two loops 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 HOT STANDBY within the next 6

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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) sevicing safety related equipment that is not locked,

sealed, or otherwise secured in its 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.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-13 AMENDMENT NO.)7, lpga/,131

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm plus or minus 108.

2.

Verifying that on a Safety Injection Signal from either Unit 1 or Unit 2, or on a containment phase A isolation

signal, the system automatically diverts its inlet flow through the HEPA filters and charcoal adsorber bank and that either fan can then be manually started in the re-circulation mode Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/16 inch W.

G.

relative to the outside atmosphere at a system flow rate of 6000 cfm plus or minus 108.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 998 of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 108.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 998 of"a halogenated hydrocarbon refrigerant

test, gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm plus or minus 108.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-16a AMENDMENT NO )$,131

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b)

Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10%.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 108.

2.

Deleted.

Verifying that the standby fan starts automatically on a Containment Pressure--High-High Signal and directs its exhaust flow through the HEPA filters and charcoal adsorber banks on a Containment Pressure--High-High Signal.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10$.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-19 AMENDMENT NO. )g),131

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.7.1 All snubbers listed in Table 3.7-9 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREMENTS 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Ins ection The first inservice visual inspection of snubbers shall be per-formed after four months but with 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-9.

If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months plus or minus 258 from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers er Ins ection Period Subsequent Visual Ins ection Period*¹ 0

1 2

3,4 5,6,7 8 or more 18 months plus or minus 258 12 months plus or minus 258 6 months plus or minus 258 124 days plus or minus 258 62 days plus or minus 258 31 days plus or minus 258 The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

The inspection interval shall not be lengthened more than one step at a time.

¹ The provisions of Specification 4.0.2 are not applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-20 AMENDMENT No.p7,gpg,f3(

)

0

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.

Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without dis-connecting the snubber, that the snubber has freedom of movement and is not frozen up.

Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of esta-blishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.7.1.d as applicable.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c.

Functional Tests At least once per 24 months during shutdown, a representative sample (14%) of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.

For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.7.1.d an additional 10% of that type of snubber shall be functionally tested.

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

At least 25% of the snubbers in the represent-ative sample shall include snubbers from the following three categories:

l.

2.

The first snubber away from each reactor vessel nozzle Snubbers within 5 feet of heavy equipment (valve,

pump, turbine, motor, etc.)

Snubbers within 10 feet of the discharge from "a safety relief valve Snubbers identified in Table 3.7-9 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.*

Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-21 AMENDMENT NO.P),ging, 131

E

~

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.2 Each of the above re h lib equired water spray and/or sprinkler systems s

a be demonstrated to be OPERABLE:

a.

b.

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

At least once per 18 months:

l.

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

a) Verifying that the'utomatic 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 inspection of deluge and preaction type system spray headers to verify their integrity.

By inspection of each open'head deluge nozzle to verify no blockage.

c ~

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

COOK NUCLEAR PLANT - UNIT 2 3/4 7-40 AMENDMENT NO. gg,1$ $,131

REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a.,

The equipment door closed and held in place by a minimum of four bolts, b.

A minimum of one door in each airlock is closed, and c.

Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either; 1.

Closed by an isolation valve, blind flange, or manual valve, or 2.

Be capable of being closed by an OPERABLE automatic Con-tainment Purge and Exhaust isolation valve.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable of being closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

a.

Verifying the penetrations are in their closed/isolated condition, or b.

Testing the Containment Purge and Exhaust isolation valves per the applicable portions of Specification 4.6.3.1.2.

COOK NUCLEAR PLANT - UNIT 2 3/4 9-4 AMENDMENT N0.97,131

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