Text

Amends 60,47 & 33 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Min SDC Flowrate for Mode 5 and Mode 6
	ML17306A667
Person / Time
Site:	Palo Verde
Issue date:	03/31/1992
From:	Quay T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17306A668	List: ML17306A667; ML17306A669;
References
	NUDOCS 9204210330
	Download: ML17306A667 (52)
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No.

NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated November 20,

1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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.

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.

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.

NPF-41 is hereby amended to read as follows:

9204210330 92033i PDR ADOCK 05000528 P'DR j

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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

60, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

F R THE NUCLEAR REGULATORY COMMISSION heod re R. Quay, Director oj t Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance-'arch 3i, )99$

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

NPF.-41 DOCKET NO.

STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

Remove 3/4 4-5 3/4 4-6 3/4 9-8 3/4 9-9 B 3/4 4-1 B 3/4 9-2 Insert 3/4 4-5 3/4 4-6 3/4 9"8 3/4 9-9 B 3/4 4-1 B 3/4 9-2

~

REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.'1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation",

and either:

a.

One additional shutdown cooling loop shall be OPERABLE¹, or b.

The secondary side water level of at least two steam generators shall be greater than 25K indicated wide range level.

APPLICABILITY:

MODE 5 with reactor coolant loops filled¹¹.

ACTION:

b.

With less than the above required loops OPERABLE or with less than the required steam generator level, immediately initiate corrective action to return the required loops to OPERABLE status or to restore the required level as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4.1.4.1.1 The secondary side water level of both steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4. 1.4. 1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

¹One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

¹¹A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 214'F during cooldown, or 291 F during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than 100~F above each of the Reactor Coolant System cold leg temperatures.

Reactor Coolant Pump operation is limited to no more than, 2 Reactor Coolant Pumps with RCS cold leg temperature less than or equal to 200'F, 3 Reactor Coolant Pumps with RCS cold leg temperature greater than 200'F but less than or equal to 500 F.

PALO VERDE - UNIT 1 3/4 4-5

'MENDMENT NO.

SZ 60

~

I'

REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4. 1.4.2 Two shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation~.

APPLICABILITY:

MODE 5 with reactor coolant loops not filled.

ACTION:

b.

With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4. 1.4.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (j.) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below s'aturation temperature.

PALO VERDE - UNIT 1 3/4 4-6 AMENDMENT NO. g8, 60

REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be OPERABLE and in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS 4.9.8.1 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The.shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period dur ing the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE - UNIT 1 3/4 9-8 AMENDMENT NO. 27 60

REFUELING OPERATIONS LOW MATER LEVEL LIMITED CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a ~

b.

Mith less than the required shutdown cooling loops

OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel

flange, as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS 4.9.8.2 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE " UNIT 1 3/4 9-9 AMENDMENT NO. 0',

60

]

li

4.4 REACTOR COOLANT SYSTEM BASES 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.231 during all normal operations and anticipated transients.

In MODES 1 and 2

with one reactor coolant loop not in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either shutdown cooling or RCS) be OPERABLE.

Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two shutdown cooling loops be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling loops be OPERABLE.

The operation of one reactor coolant pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification, and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.

A flow rate of at least 3400 gpm (actual) will circulate one equivalent Reactor Coolant System volume of 12,097 cubic feet in approximately 27 minutes.

The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.

The 3780 gpm in the specification includes all instrument uncertainties including the 300~F calibration temperature of the flow transmitters.

The restrictions on starting a reactor coolant pump in MODES 4 and 5, with one or more RCS cold legs less than or equal to 255'F during cooldown or 2954F during heatup are provided to prevent RCS pressure transients, caused by energy additions from the secondary

system, which could exceed the limits of Appendix G

to 10 CFR Part 50.

The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100'F above each of the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve a minimum of 460,000 lb per hour of saturated steam at the valve setpoint.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

PALO VERDE - UNIT 1 B 3/4 4-1 AMENDMENT NO.

60

P t

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I I

REFUELING OPERATIONS BASES 3/4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that:

(1) the machine will be used for movement of fuel assemblies, (2) the machine has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation, and circulating reactor coolant at a flow rate equal to or greater than 3400 gpm (actual) ensures that (1) sufficient.cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135 F as required during the REFUELING MODE, (2) sufficient coolant circulation is main-tained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification, and (3) the hT across the core will be maintained at less than 75'F during the REFUELING MODE.

The required flowrate of > 3400 gpm (actual) ensures that at 288 hours0.00333 days 0.08 hours 4.761905e-4 weeks 1.09584e-4 months after reactor shutdown sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135~F as required during REFUELING MODE; this assumes a shutdown cooling heat exchanger cooling water flowrate of 14000

gpm, a cooling water inlet temperature of < 105 F at 27 1/2 hours after reactor

shutdown, and the decay heat curve of CKSSAR-F Figure 6.2.1-1 and reactor operation for two years at 4000 tQt.

The 3780 gpm in the specification includes all instrument uncertainties including the 300'F calibration temperature of the flow transmitters.

Without a shutdown cooling train in operation steam may be generated; therefore, the containment should be sealed off to prevent escape of any radioactivity, and any operations that would cause an increase in decay heat should be secured.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel

flange, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability.

Mith the reactor vessel head removed and 23 feet of water above the reactor pressure vessel

flange, a

large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

PALO VERDE " UNIT 1 B 3/4 9-2 AMENDMENT NO. 60

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No.

NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:

A ~

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated November 20,

1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Part 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.

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.

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.

NPF-51 is hereby amended to read 'as follows:

l,

2 (2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. <7, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3 ~

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION heod re R. Quay, Director roy ct Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 31, 1992

0 IV',

~

"1 1

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

47 TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

Remove 3/4 4-5 3/4 4-6 3/4 9-8 3/4 9-9 B 3/4 4-1 B 3/4 9-2 Insert 3/4 4-5 3/4 4-6 3/4 9-8 3/4 9-9 B 3/4 4-1 B 3/4 9-2

~

REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation",

and either:

a.

One additional shutdown cooling loop shall be OPERABLE¹, or b.

The secondary side water level of at least two steam generators shall be greater than 25K indicated wide range level.

APPLICABILITY:

MODE 5 with reactor coolant loops filled¹¹.

ACTION:

a e b.

With less than the above required loops OPERABLE or with less than the required steam generator level, immediately initiate corrective action to return the required loops to OPERABLE status or to restore the required level as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4. 1.4. 1. 1 The secondary side water level of both steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

¹One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

¹¹A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 214~F during cooldown, or 291 F during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than 100'F above each of the Reactor Coolant System cold leg temperatures.

Reactor Coolant Pump operation is limited to no more than, 2 Reactor Coolant Pumps with RCS cold leg temperature less than or equal to 200 F, 3 Reactor Coolant Pumps with RCS cold leg temperature greater than 200'F but less than or equal to 5000F.

PALO VERDE - UNIT 2 3/4 4"5 AMENDMENT NO. N

~

47

REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4. 1.4.2 Two shutdown cooling loops shall be OPERABLE and at least one

¹ shutdown cooling loop shall be in operation".

APPLICABILITY:

MODE 5 with reactor coolant loops not filled.

ACTION:

a 0 b.

with less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the'eactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4. 1.4.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

PALO VERDE - UNIT 2 3/4 4-6 AMENDMENT NO. 47

'I

REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION

3. 9.8. 1 At least one shutdown cooling loop shall be OPERABLE and in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS 4.9.8.1 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE - UNIT 2 3/4 9-8 AMENDMENT NO. 47

REFUELING OPERATIONS LOW MATER LEVEL LIMITING CONDITION FOR OPERATION

3. 9. 8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a 0 b.

Mith less than the required shutdown cooling loops

OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel

flange, as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS 4.9.8.2 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE - UNIT 2 3/4 9-9 AMENDMENT NO. 47

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.231 during all normal operations and anticipated transients.

In MODES 1 and 2 with one reactor coolant loop not in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either shutdown cooling or RCS) be OPERABLE.

Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two shutdown cooling loops be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling loops be OPERABLE.

The operation of one reactor coolant pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification, and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.

A flow rate of at least 3400 gpm (actual) will circulate one equivalent Reactor Coolant System volume of 12,097 cubic feet in approximately 27 minutes.

The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.

The 3780 gpm in the specification includes all instrument uncertainties including the 300 F calibration temperature of the flow transmitters.

The restrictions on starting a reactor coolant pump in MODES 4 and 5, with one or more RCS cold legs less than or equal to 255 F during cooldown or 295 F

during heatup are provided to prevent RCS pressure transients, caused by energy additions from the secondary

system, which could exceed the limits of Appendix G

to 10 CFR Part 50.

The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100 F above each of the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve a minimum of 460,000 lb per hour of saturated steam at the valve setpoint.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

PALO VERDE - UNIT 2 B 3/4 4-1 AMENDMENT NO. 47

I

REFUELING OPERATIONS BASES 3/4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that:

(1) the machine will be used for movement of fuel assemblies, (2) the machine has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release wi 11 be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation, and circulating reactor coolant at a flow rate equal to or greater than 3400 gpm (actual) ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135 F as required during the REFUELING MODE, (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification, and (3) the hT across the core will be maintained at less than 75'F during the REFUELING MODE.

The required flowrate of > 3400 gpm (actual) ensures that at 288 hours0.00333 days 0.08 hours 4.761905e-4 weeks 1.09584e-4 months after reactor shutdown suff7cient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135 F as required during REFUELING MODE; this assumes a shutdown cooling heat exchanger cooling water flowrate of 14000

gpm, a cooling water inlet temperature of < 105 F at 27 1/2 hours after reactor

shutdown, and the decay heat curve of CESSAR-F Figure 6.2. l-l and reactor operation for two years at 4000 MWt.

The 3780 gpm in the specification includes all instrument uncertainties including the 300 F

calibration temperature of the flow transmitters.

Without a shutdown cooling train in operation steam may be generated; therefore, the containment should be sealed off to prevent escape of any radioactivity, and any operations that would cause an increase in decay heat should be secured.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel

flange, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability.

With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel

flange, a

large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

PALO VERDE - UNIT 2 B 3/4 9-2 AMENDMENT NO. 47

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UNITEDSTATES NUCLEAR REGULATORY COMIVIISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No.

NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated November 20,

1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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.

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 wi 11 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.

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. NPF-74 is hereby amended to read as follows:

I (2) Technical S ecifications and Environmental Protection Plan 3.

The Technical Specifications contained in Appendix A, as revised through Amendment No.

33, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

OR THE NUCLEAR REGULATORY COMMISSION The ore R. Quay, Director Pro ect Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 31, 1992

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

33 TO FACILITY OPERATING LICENSE NO.

NPF-74 DOCKET NO.

STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

Remove 3/4 4-5 3/4 4-6 3/4 9-8 3/4 9-9 B 3/4 4-1 B 3/4 9-2 Insert 3/4 4-5 3/4 4-6 3/4 9-8 3/4 9-9 B 3/4 4-1 B 3/4 9-2

REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation*,

and either:

a.

One additional shutdown cooling loop shall be OPERABLE¹, or b.

The secondary side water level of at least two steam generators shall be greater than 25K indicated wide range level.

APPLICABILITY:

MODE 5 with reactor coolant loops filled¹¹.

ACTION:

a ~

b.

With less than the above required loops OPERABLE or with less than the required steam generator level, immediately initiate corrective action to return the required loops to OPERABLE status or to restore the required level as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4.1.4.l. 1 The secondary side water level of both steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

AMENDMENT NO. N~

3/4 4-5 "The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

¹One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

¹¹A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 214'F during cooldown, or 291~F during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than 100 F above each of the Reactor Coolant System cold leg temperatures.

Reactor Coolant Pump operation is limited to no more than, 2 Reactor Coolant Pumps with RCS cold leg temperature less than or equal to 200'F, 3 Reactor Coolant Pumps with RCS cold leg temperature greater than 200'F but less than or equal to 500'F.

PALO VERDE - UNIT 3

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REACTOR COOLANT SYSTEM COLD SHUTDOWN -

LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION

3. 4. 1.4. 2 Two shutdown cooling loops shall be OPERABLE and at least one

¹ shutdown cooling loop shall be in operation*.

APPLICABILITY:

MODE 5 with reactor coolant loops not filled.

ACTION:

a.

b.

With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE RE UIREMENTS 4.4. 1.4.2 At least one shutdown cooling loop shall be determined'o be in oper ation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

PALO VERDE - UNIT 3 3/4 4"6 AMENDMENT NO. N~

33

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REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8. 1 At least one shutdown cooling loop shall be OPERABLE and in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS

4. 9. 8. 1 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate ot greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period dur ing the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE " UNIT 3 3/4 9-8 AMENDMENT NO.

OJ

REFUELING OPERATIONS LOW MATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation".

APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a.

With less than the required shutdown cooling loops

OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel

flange, as soon as possible.

b.

With no shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate'orrective action to return the required shutdown cooling loop to operation.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE RE UIREMENTS

4. 9. 8. 2 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3780 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or during surveillance testing of ECCS pumps.

PALO VERDE " UNIT 3 3/4 9-9 AMENDHENT NO. 33

IL

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.24

'.during all normal operations and anticipated transients.

In MODES 1 and 2

with one reactor coolant loop not in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations

'equire that two loops be OPERABLE.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either shutdown cooling or RCS) be OPERABLE.

Thus, if the reactor coolant loops are not OPERABLE, this specification requires that two shutdown cooling loops be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling loops be OPERABLE.

The operation of one reactor coolant pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification, and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.

A flow rate of at least 3400 gpm (actual) will circulate one equivalent Reactor Coolant System volume of 12,097 cubic feet in approximately 27 minutes.

The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.

The 3780 gpm in the specification includes all instrument uncertainties including the 300'F calibration temperature of the flow transmitters.

The restrictions on starting a reactor coolant pump in MODES 4 and 5, with one or more RCS cold legs less than or equal to 255 F during cooldown or 295 F

during heatup are provided to prevent RCS pressure transients, caused by energy additions from the secondary

system, which could exceed the limits of Appendix G

to 10 CFR Part 50.

The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100~F above each of the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve a minimum of 460,000 lb per hour of saturated steam at the valve setpoint.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

PALO VERDE " UNIT 3 8 3/4 4-1 AMENDMENT NO. X8, 33

f I

REFUELING OPERATIONS

. ~

BASES 3/4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that:

(1) the machine will be used for movement of fuel assemblies, (2) the machine has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation, and circulating reactor coolant at a flow rate equal to or greater than 3400 gpm (actual) ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135'F as required during the REFUELING MODE, (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification, and (3) the hT across the core will be maintained at less than 75 F during the REFUELING MODE.

The required flowrate of > 3400 gpm (actual) ensures that at 288 hours0.00333 days 0.08 hours 4.761905e-4 weeks 1.09584e-4 months after reactor shutdown suff7cient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 135 F as required during REFUELING MODE; this assumes a shutdown cooling heat exchanger cooling water flowrate of 14000

gpm, a cooling water inlet temperature of < 105~F at >

27 1/2 hours after reactor

shutdown, and the decay heat curve of CESSAR-F Figure 6.2.1-1 and reactor operation for two years at 4000 MWt.

The 3780 gpm in the specification includes all instrument uncertainties including the 300 F

calibration temperature of the flow transmitters.

Without a shutdown cooling train in operation steam may be generated; therefore, the containment should be sealed off to prevent escape of any radioactivity, and any operations that would cause an increase in decay heat should be secured.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel

flange, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability.

With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel

flange, a

large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

PALO VERDE - UNIT 3 B 3/4 9"2 AMENDMENT NO. 33

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ML17306A667

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