Text

Amend 97 to License DPR-74,revising Tech Specs to Extend Interval of Certain 18-month Surveillances Until Next Refueling Outage Currently Planned to Begin in Early 1988
	ML17326B299
Person / Time
Site:	Cook
Issue date:	12/28/1987
From:	Perkins K; Office of Nuclear Reactor Regulation
To:	;
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ML17326B300	List: ML17326B299; ML17326B301;
References
	NUDOCS 8801070182
	Download: ML17326B299 (30)
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t UNITED STATES UCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POllER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT, UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

97 License No.

DPR-74 1.

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

A.

C.

D.

The application for amendment by Indiana Michigan Power Company (the licensee) dated October 28, 1987 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 endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the COIImIission'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 Commission's regulations and all applicable requirements have been satisfied.

n 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 Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2) Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

97

, 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 issuance.

The Technical Specification revisions are to be implemented within 45 days of receipt.

FOR THE NUCLEAR REGULATORY COYiMISSION

Attachment:

Changes to the Technical Specifications Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects Date of Issuance:

December 28, 1987

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

97 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET N0.50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

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

Corresponding overleaf pages are provided to maintain document completeness.

REMOVE

?hSERT 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 0-3 3-1 3-14 3-32 3-47 4-33 5-1*

5-2 5-5 6-10 6-12 6-14 7-6 7-11*

7-12 7-13 7-14*

7-16a 7-19a 8-3 8-5 9-3*

9-4 3/4 0-3 3/4 3-1 3/4 3-14 3/4 3-32 3/4 3-47 3/4 4-33 3/4 5-1*

3/4 5-2 3/4 5-5 3/4 6-10 3/4 6-12 3/4 6-14 3/4 7-6 3/4 7-11*

3/4 7-12 3/4 7-13 3/4 7-14*

3/4 7-16a 3/4 7-19a 3/4 8-3 3/4 8-5 3/4 9-3*

3/4 9-4

Overleaf pages

d, I

3I' Amos rrAzl>>TY SURVrt LLNCE REOUIRE! 1ENTS b.

Surve>llance intervals speci',ied in Section XI of the ASPE Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the AS!1E Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Techn'ical Specifications:

ASHE Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice inspection and testin cri.eria Required frequencies fcr performing inservice inspect on and tes.ina activi.ies Weekly Honthly 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 At least once per 92 days At least once per 184 days At least once per 366 days c.

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

e.

Performance of the above inservice 'inspection and esting activi ies shall be in addition to other specified Surveillance Requiremen.s.

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

4'-6 By specific reference to this section, those surveillances vhich must be performed on or before March 31, 1986, and are designated as 18-month sur-veillances (or required as outage-related surveillances under the provisions of Specification 4.0.5) may be delayed until the end of the refueling outage scheduled to begin on or before February 28, 1986.. For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 vill be determined vith the new initiation date estab-lished by the surveillance date during the Unit 2 1986 refueling outage.

4.0.7 By specific reference to this section, those surveillances which must be performed on or before July 1, 1988 and are designated as 18-month surveillances (or required as outage-related surveillances under the provisions of Specification 4.0.5) may be delayed until the end of the cycle 6-7 refueling outage (currently scheduled to begin during the latter part of the second quarter of 1988).

For these specific surveillances under this section, the specified 'dime intervals required by Specification 4.0.2 will be determined with the new initiation'.date=edtahliahed'.5y"the surveillance date during the Unit 2 1988 refueling outage.

D C

COOK - UNIT 2 3/4 0-3 Amendment No. IS, 97

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INSTRUMENTATION 3/4. 3. 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INS7RUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.

1 The Engineered Safety Feature Actuation System (ESFAS) instrumenta-tion 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 Set-point 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 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*"..

The provisions of Specification 4.0.6 are applicable.

- The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 3-14 Amendment No. 7g, 97

Co ti ued)

J 0

S STEM INS UMEN ATIO U

E ENTS 4 ~

STEAM LINE ISOLATION CHANNEL

~KQL.

CHANNEL C

Io CHANNEL FUNCTIONAL MODES IN HHICH SURVEILLANCE a.

Manual b.

Automatic Actuation Logic N.A.

N.A.

c.

Containment Pressure-S High-High d.

Steam Flow in Taro Steam LinesS High Coincident with T Low-Low e.

Steam Line Pressure-Low 5 ~

TURBINE TRIP AND FEEMATER ISOLATION a.

Steam Generator Mater LevelHigh-High 6 ~

MOTOR DRIVEN AUXILIARYFEEDHATER PUMPS a.

Steam Generator Mater S

Level Low-Low b.

4 kv Bus S

Loss of Voltage c.

Safety In)ection N.A.

d.

Loss of Main Feed Pumps N.A.

+ The provisions of Specification 4.0.7 are applicable.

N.A.

M (1)

M(2)

M(3)

M M(2) 1, 2, 3

1, 2, 3

1; 2, 3

1, 2) 3 1, 2, 3

1, 2, 3and$

1$ 2, 3

1, 2

TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK CHANNEL 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 - TC()Lp (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 R(1)

R(3)+

R R

(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 Exi~

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;rbHow. P-.l'2.in MODE l3.

The core exit thermocouples will not be installed until the 1988 refueling outage; therefore, surveil-lances 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.

+ The provisions of Specification 4.0.7 are applicable.

I Amendment No. N, 9$

(Am. 95 effective before startup following refueling outage currently scheduled in early 1988)

I'l

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.

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 or (2) close and de-energize the Apply the portions of ACTION a.2 OPERATIONAL MODE, as appropriate unavailable.

the valves to OPERABLE status other valve in each line.

or a.3 above, relating to for two or three lines 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 3.4.1l.a or 3.4.ll.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.

- The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK UNIT 2 3/4 4-33 Amendment No. gg, 97

3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system accumulator shall be OPERABLE with:

~

The isolation valve open, b.

A contained borated water volume of between 929 and 971 cubic feet, c.

A boron concentration between 2400 ppm and 2600 ppm, and d.

A nitrogen cover-pressure of between 599 and 644 psig.

APPLICABILITY:

MODES 1, 2 and 3*.

ACTION:

b.

With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With one accumulator inoperable due to the isolation valve being closed, either inmediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS 4.5.1 Each accumulator 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:

l.

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.

Verifying that each accumulator isolation valve is open.

+Pressurizer Pressure above 1000 psig.

D.

C.

COOK - UNIT 2 3/4 5-1 Amendment No. 94 0 ]987

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 >

1Ã 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.

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

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 5-2 Amendment No.

97

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.

At least once per 18 months by:

l.

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:*

l.

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 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:

Centrifugal charging pump 2405 psig 2.

Safety Injection pump 1445 psig 3.

Residual heat removal pump 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.

"The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 5-5 Amendment No.

97

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:

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

a ~

b.

Co d.

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.

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

discharge pressure of > 255 psig at a flow of > 700 gpm, when tested pursuant to Specification 4.0.5.

At least once per lS months during shutdown, by:*

l.

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.

"The provisions of Specification 4. 0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 6-10 Amendment No.

97

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.*

d.

At least once per 5 years by verifying a water, flow rate of at least 20 gpm (> 20 gpm) but not to exceed 50 gpm (< 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

> 255 psig.

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 6-12 Amendment No. Q, 97

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 test 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.

The provisions of Specification 4.0.7 are applicable.

D. C.

COOK ~ UNIT 2 3/4 6-14 Amendment No.

97

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 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 10K 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:*

l.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engi-neered 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 fe'atures actuation test signal required by Specification 3/4.3.2.

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 7-6 Amendment No. 77, 97

PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the steam generators shall be

> 70'F when the pressure of either coolant in the steam generator is

> 200 psig.

APPLICABILITY: At all times.

ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam generator pressure of the applicable side to

< 200 psig within 30 minutes, and b.

Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator.

Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200'F.

SURVEILLANCE RE UIREMENTS 4.7.2.1 The pressure in each side of the steam generator shall be determined to be

< 200 psig at least once per hour when the temperature of either the primary or secondary coolant is

< 70'F.

D.

C.

COOK - UNIT 2 3/4 7-11

0 I

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 follow-ing 3Q hours.

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 equip-ment 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.*

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 7-12 Amendment No. 97

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 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:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equip-ment 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.*

The provisions of Specification 4.0.7 are applicable.

D. C.

COOK UNIT 2 3/4 7-13 Amendment No.

g7

PLANT SYSTEMS 3 4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system shall be OPERABLE with:

a.

Two independent heating and cooling systems, b.

Two independent pressurization

fans, and c.

One charcoal adsorber and HEPA filter train.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

b.

C.

With one heating and cooling system inoperable, restore the inoperable system to OPERABLE status within 7 days 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 ....

With one pressurization fan, inoperable, restore the inoperable fan to OPERABL'E status within 7 days 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 .

With the filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 follow-ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.7.5.1 The control room emergency ventilation system shall be demon-strated 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 control room air temperature is ( 120'F.

b.

At least once per 31 days on a

STAGGERED TEST BASIS by initiat-ing flow through the HEPA filter and charcoal adsorber train and verifying that the system operates for at least 15 minutes.

D.

C.

COOK UNIT 2 3/4 7-14

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PLANT SYSTEMS SURVEILLANCE RE UIRENENTS Continued e.

3.

Verifying that the standby fan starts automatically on a

Containment Pressure--High-High Signal and diverts its exhaust flow through the HEPA filters and charcoal adsorber.'anks on a Containment Pressure--High-High Signal.*

After each complete or partial replacement of HEPA filter bank by verifying that the HEPA filter banks remove 99K 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 25,000 cfm + 10Ã.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers.

remove

> 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 25,000 cfm +

10%%d.

"The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 7-19a Amendment No.

97

t ~

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.

Verifying the fuel transfer pump can be started and

~ transfers fuel from the storage system to the day tank.

4.

Verifying the diesel starts from ambient condition and accelerates to at least 514 rpm in < 10 seconds.

5.

Verifying the generator is loaded to

> 1750 kw, and operates for > 60 minutes and verifying that the generator output breaker to the emergency bus is OPERABLE.

b.

6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits specified in Table 1 of ASTM-D975-74 when checked for viscosity, water and sediment.

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

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recomnendations for this class of standby service.

2.

Verifying that the automatic sequence timing relays are OPERABLE with each load sequence time within + 5X of its required value and that each load is sequenced on within the design allowable time limit.

3.

Verifying the generator capability to reject a load of >

600 kw while maintaining voltage at 4160 + 420 volts and frequency at 60 + 1.2 Hz.

4.

Verifying the generator capability to reject a load of 3500 kw without exceeding 75K of the difference between nominal speed and the overspeed trip setpoint.

5.

Simulating a loss of offsite power by itself, and:

a)

Verifying de-energization of the emergency busses and load shedding from the emergency busses.

"The provisions of Specification 4.0.7 are applicable.

D. C.

COOK - UNIT 2 3/4 8-3 Amendment No.

97

ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b.

One diesel generator with:

l.

- A day fuel tank containing a minimum volume of 70 gallons of fuel, 2.

A fuel storage system containing a minimum volume of 42,000 gallons of fuel, and 3.

A fuel transfer pump.

APPLICABILITY:

MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Require-ments of 4.8.1.1.1 and 4.8.1.1.2 except for Requirement 4.8.1.1.2.a.5.*

The provisions of Specifications 4.0.6 and 4.0.7 are applicable.

D. C.

COOK - UNIT 2 3/4 8-5 Amendment No. 7g, 97

REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

ACTION:

With the reactor subcritical for less than 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , suspend all opera-tions involving movement of irradiated fuel in the reactor pressure vessel..

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

D.

C.

COOK UNIT 2 3/4 9-3

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, iranediately 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 condi-tion, or b.

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

The provisions of Specification 4.0.7 are applicable.

D.

C.

COOK - UNIT 2 3/4 9-4 Amendment No.

97

ML17326B299

Text

Attachment:

RESPONSE

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