ML17332A300

Amends 182 & 167 to Licenses DPR-58 & DPR-74,respectively, Increasing Main Steam Safety Valve Setpoint Tolerance for Both Units to 3 Percent & Revises Emergency Core Cooling Sys

ML17332A300
Person / Time
Site:	Cook
Issue date:	09/09/1994
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML17332A301	List: ML17332A300 ML17332A302
References
NUDOCS 9409160131
Download: ML17332A300 (14)

Text

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gO 4p*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. i82 License No.

DPR-58 l.

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

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated November ll, 1992, and supplemented December 17,

1993, and March 29,

1994, 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, the provisions of the Act, and the rules and regulations of the Commission; C,

D.

E.

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; 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 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.

P409160131 940909K I

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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-58 is hereby amended to read as follows:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. iB2, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

SePtember 9,

1994 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO 182 TO 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 vertical lines indicating the area of change.

REMOVE=

3/4 7-1 3/4 7-4 B 3/4 7-1 INSERT 3/4 7-1 3/4 7-4 B 3/4 7-1

3 4.7 PLANT SYSTEMS 3

4'.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: Modes 1, 2 and 3.

ACTION:

a.

With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves lnoperahle, operation in MODES l, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODE 3

may proceed

provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the reactor trip breakers are opened; otherwise, be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with liftsettings as shown in Table 4.7-1.

The safety valve shall be reset to the nominal value

~1X whenever found outside the

+1X tolerance.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-1 AMENDMENT NO ~ ~,182

TABLE 4.7-1 STEAM L NE SA ETY VA VES PER LOOP VALVE NUMBER a.

SV-1A b.

SV-1B c.

SV-2A d.

SV-2B e.

SV-3 LIFT SETTING

-3 1065 psig 1065 psig 1075 psig 1075 psig 1085 psig ORIFIC SIZE 16 in. 2 16 in. 2 16 in. 2 16 in. 2 16 in. 2

• The liftsetting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-4 AMENDMENT NO.

4QO, 182

3 4.7 PLANT SYS EMS BASES 3 4.7.1 TURBINE CYCLE 3 4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110X of its design pressure of 1085 psig during the most severe anticipated system operational transient.

The maximum relieving capacity is associated with a turbine trip from 100X RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e.,

no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure

Code, 1971 Edition.

The safety valve is OPERABLE with a lift setting of +3X about the nominal value.

However, the safety valve shall be reset to the nominal value +1X whenever found outside the +1X tolerance.

The total relieving capacity for all valves on all of the steam lines is 17,153,800 lbs/hr which is approximately 121 percent of the total secondary steam flow of 14,120,000 lbs/hr at 100X RATED THERMAL POWER.

A minimum of 2 OPERABLE safety valves per operable steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1

~

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Range Neutron Flux channels.

The reactor trip setpoint reductions are derived on the following bases:

For 4 loop operation X

Where:

SP reduced reactor trip setpoint in percent of RATED THERMAL POWER V

maximum number of inoperable safety valves per steam line 1,

2 01 3.

X Total relieving capacity of all safety valves per steam line 4,288,450 lbs/hour.

Y - Maximum relieving capacity of any one safety valve - 857,690 lbs/hour (109) - Power Range Neutron Flux-High Trip Setpoint for 4 loop operation.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-1 AMENDMENT NO.

CRT 182

gAS RE00 po Cy C

0

+~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D,.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No.

DPR-74 l.

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

A.

B.

C.

D.

E.

The application for amendment by Indiana Michigan Power Company (the licensee) dated November 11,

1992, and supplemented December 17,

1993, and March 29,

1994, 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 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 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.

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:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.

167, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 9,

1994 I5(~ h Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

167 FACILITY OPERATING 'LICENSE NO.

DPR-74 DOCKET NO. 50-316 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 vertical lines indicating the area of change.

REMOVE 3/4 5-3 3/4 7-1 3/4 7-4 B 3/4 5-1 8 3/4 7-1 INSERT 3/4 5-3 3/4 7-1 3/4 7-4 B 3/4 5-1 B 3/4 7-1

0 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T~

W 350 F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE safety injection pump c.

One OPERABLE residual heat removal heat exchanger, d.

One OPERABLE residual heat removal pump, e.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.

f.

All safety injection cross-tie valves open.

PPLICABILITY:

MODES 1, 2,

and 3.

ACTION:

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With a safety injection cross-tie valve closed, restore the cross-tie valve to the open position or reduce the core power level to less than or equal to 3250 MW within one hour. Specification 3.0.4 does not apply.

C.

Zn the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

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

167

3 4 ~ 7 PLANT SYSTEMS 3 4.7.1 TURBINE CYCLE SAFETY VALV S I

TING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

P LICABILITY: Modes 1, 2 and 3.

~CT ON:

a.

With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpointis reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODE 3 may proceed

provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the reactor trip breakers are opened; otherwise, be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0e5 and with liftsettings as shown in Table 4.7-1.

The safety valve shall be reset to the nominal value ~lXwhenever found outside the flXtolerance.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-1 AMENDMENT NO. 82,167

T BLE 4 7-N S FETY VALVES PER OOP VALVE a.

SV-1A b.

SV-1B c.

SV-2A SV-2B e.

SV-3 SETTING

+3 1065 psig 1065 psig 1075 psig 1075 psig 1085 psig ORIFICE S

E 16 in. 2 16 in. 2 16 in. 2 16 in. 2 16 in. 2

+ The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-4 ANZNDNBNT IO. f67

3 4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3 4.5.1 ACCUMULATORS The OPERABZLZTY of each RCS accumulator ensures that a sufficient volume of horated water will he immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators.

This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator infection in the safety analysis are met.

The accumulator power operated isolation valves are considered to he "operating bypasses" in the context of ZEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

Zn addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.

Zf a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a

mode where this capability is not required.

3 4.5.2 and 3 4.5.3 ECCS SUBSYSTEMS The OPERABZLZTY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a

LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sires ranging from the double ended break of the largest RCS cold leg pipe downward.

Zn addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.

Zf a safety injection cross-tie valve is closed, safety injection would he limited to two lines assuming the loss of one safety injection subsystem through a single failure consideration.

The resulting lowered flow requires a decrease in THERMAL POWER to limit the peak clad temperature within acceptable limits in the event of a postulated small break LOCA.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 5-1 AMENDMENT NO 49, 167

3 4. 7 PLANT S S

S BASES 3 4.7.

TURBINE C CLE 3 4.7.1.1 SAFETY V LV S The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1085 psig during the most severe anticipated system operational transient.

The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e.,

no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section IIIof the ASME Boiler and Pressure

Code, 1971 Edition.

The safety valve is OPERABLE with a lift setting of +3%

about the nominal value.

However, the safety valve shall be reset to the nominal value +1% whenever found outside the +1% tolerance.

The total relieving capacity of all safety valves on all of the steam lines is 17,153,800 lbs/hr which is at least 105 percent of the maximum secondary steam flow rate at 100% RATED THERMAL POWER.

A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Range Neutron Flux channels.

The reactor trip setpoint reductions are derived on the following bases:

For 4 loop operation Where:

SP

~

reduced reactor trip setpoint in percent of RATED THERMAL POWER V ~

maximum number of inoperable safety valves per steam line total relieving capacity of all safety valves per steam line in lbs./hours

~ 4,288@450 maximum relieving capacity of any one safety valve in lbs./hour

~ 857,690 109

~

Power Range Neutron Flux-High Trip Setpoint for 4

loop operation COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-1 AMENDMENT NO. 8&, 484