Text

Proposed Tech Specs Re Auxiliary Pressurizer Spray Sys
	ML20205J538
Person / Time
Site:	Waterford
Issue date:	03/26/1987
From:	; LOUISIANA POWER & LIGHT CO.
To:	;
Shared Package
ML20205J517	List: ML20205J538; W3P87-0958, Application for Amend to License NPF-38,creating New Tech Spec Re Auxiliary Pressurizer Spray Sys.Proposed Change Does Not Involve Unreviewed Safety Question or Significant Hazards Consideration.Util Safety Analysis Encl.Fee Paid;
References
	NUDOCS 8704010337
	Download: ML20205J538 (10)
	v • d • e

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INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.............................

3/4 4-1 HOT STAN08Y.............................................

3/4 4-2 HOT SHUT 00WN............................................

3/4 4-3 COLD SHUT 00WN - LOOPS FILLED............................

3/4 4-5 COLD SHUTDOWN - LOOPS NOT FILLE0........................

3/4 4-6 3/4.4.2 SAFETY VALVES SHUT 00WN.............................................

3/4 4-7 OPERATING............................................

3/4 4-8 3/4.4.3 PRESSURIZER.............................................

3/4 4-9 3/4.4.4 STEAM GENERATORS........................................

3/4 4-10 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS............................

3/4 4-17 OPERATIONAL LEAKAGE..................................

3/4 4-18 3/4.4.6 CHEMISTRY...............................................

3/4 4-21 3/4.4.7 SPECIFIC ACTIVITY.......................................

3/4 4-24 3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM...............................

3/4 4-28 PRESSURIZER HEATUP/C00LDOWN..........................

3/4 4-33 OVERPRESSURE PROTECTION SYSTEMS......................

3/4 4-34 3/4.4.9 STRUCTURAL INTEGRITY....................................

3/4 4-36 3/4.4.10 REACTOR COOLANT SYSTEM VENTS............................

3/4 4-37 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS..................................

3/4 5-1 3/4.5.2 ECCS SU8 SYSTEMS - T

> 350*F..........................

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T

< 350*F..........................

3/4 5-8 3/4.5.4 REFUELING WATER STORAGE P00L............................

3/4 5-9 0704010337 870326 I,'DR ADOCK 05000382 yg I

PDR

REACTOR COOLANT SYSTEM

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3/4.4.3 PRESSURIZER 1

LIMITING CONDITION FOR OPERATION i

3.4.3 The pressurizer shall be OPERA 8LE with:

1 i

A steady-state water volume greater than or equal to 26% indicated a.

i level (350 cubic feet) but less than or equal to 62.5% indicated j

level (900 cubic feet), and, 1

b.

At least two groups of pressurizer heaters powered from Class 1E j

buses each having a nominal capacity of 150 kW.

APPLICA8ILITY:

MODES 1, 2, ar.d 3.

l ACTION:

4 With only one group of the above required pressurizer heaters a.

OPERABLE, restore at least two groups to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i

in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1

{

b.

With the pressurizer otherwise inoperable, be in at least H0T STAN08Y i

with the reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , i

i SURVEILLANCE REQUIREMENTS i

i 4.4.3.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified to be at least 150 kW at least once per 92 days.

4 j

4.4.3.3 The emergency power supply for the pressurizer heaters shall be j

demonstrated OPERA 8LE at least once per 18 months by:

Verifying the above pressurizer heaters are automatically shed from a.

the emergency power sources upon the injection of an SIAS test signal.

b.

Verifying that the above heaters can be manually placed and energized j

on the emergency power source from the control room.

l WATERFOR0 - UNIT 3 3/4 4-9 1

e

_ _ = _ _ _ _ _.. _

REACTOR COOLANT SYSTEM 5

i BASES i

i SAFETY VALVES (Continued) i valves are OPERA 8LE, an operating shutdown cooling loop, connected to the RCS,

{

provides overpressure relief capability and will prevent RCS overpressurization.

In addition, the overpressure protection system provides a diverse means of j

protection against RCS overpressurization at low temperatures.

During operation, all pressurizer code safety valves must be OPERABLE to i

j prevent the RCS from being pressurized above it. safety limit of 2750 psia.

The combined relief capacity of these valves is sufficient to limit the system i

pressure to within its Safety Limit of 2750 psia following a complete loss of l

turbine generator load while operating at RATED THERMAL POWER and assuming no i

reactor trio until the first Reactor Protective System trip setpoint (Pressurizer

!l Pressure-High) is reached and also assuming no operation of the steam dump valves.

1 Demonstration of the safety valves' lift settings will occur only during reactor shutdown and will be performed in accordance with the provisions of i

Section XI of the ASME Boiler and Pressure Vessel Code.

t 3/4.4.3 PRESSURIZER i

An OPERA 8LE pressurizer provides pressure control for the Reactor Coolant j

System during operations with both forced reactor coolant flow and with natural circulation flow.

The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure con-trol, remain covered with water to prevent failure, which could occur if the l

heaters were energized while uncovered.

The maximum water level in the pres-surizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis.

The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble will be provided to accommodate pressure surges during operation.

The steam bubble 1

{

also protects the pressurizer code safety valves against water relief.

The i

requirement to verify that on an SIAS test signal the pressurizer heaters are automatically shed from the emergency power sources is to ensure that the non-Class IE heaters do not reduce the reliability of or overload the emergency 1

power source.

The requirement that a minimum number of pressurizer heaters be l

OPERA 8LE enhances the capability to control Reactor Coolant System pressure and establish and maintain natural circulation.

l' 3/4.4.4 STEAM GENERATORS i

l The Surveillance Requirements for inspection of the steam generator tubes j

ensure that the structural integrity of this portion of the RCS will be main-tained.

The program for inservice inspection of steam generator tubes is WATERFORD - UNIT 3 83/44-2

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INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION i

PAGE l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.............................

3/4 4-1 HOT STAN08Y.............................................

3/4 4-2 HOT SHUTD0WN............................................

3/4 4-3 COLO SHUTDOWN - LOOPS FILLED............................

3/4 4-5 COLD SHUTDOWN - LOOPS NOT FILLED........................

3/4 4-6 3/4.4.2 SAFETY VALVES SHUTD0WN.............................................

3/4 4-7 0PERATING............................................

3/4 4-8 3/4.4.3 NSEAT f PRESSURIZER. -. p.. A p. g. p. p A. 4 L M 3/4.4.4 STEAM GENERATORS........................................

3/4 4-10 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS............................

3/4 4-17 OPERATIONAL LEAKAGE..................................

3/4 4-18 3/4.4.6 CHEMISTRY...............................................

3/4 4-21 3/4.4.7 SPECIFIC ACTIVITY.......................................

3/4 4-24 3

3/.4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM...............................

3/4 4-28 PRESSURIZER HEATUP/C00LDOWN..........................

3/4 4-33 OVERPRESSURE PROTECTION SYSTEMS......................

3/4 4-34 3/4.4.9 STRUCTURAL INTEGRITY....................................

3/4 4-36

/l

, 3/4.4.10 REACTOR COOLANT SYSTEM VENTS............................

3/4 4-37 i

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TAMMS..................................

3/4 5-1 3/4.5.2 ECCS SU8 SYSTEMS - T,,, > 350*F..........................

3/4 5-3 3/4.5.3 ECCS SU8 SYSTEMS - T,,, < 350*F..........................

3/4 5-8 3/4.5.4 REFUELING WATER STORAGE P00L............................

3/4 5-9 i

WATNAF0A0 - UNIT 3 VI i

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_ INSERT 1 PRESSURIZER.................................................... 3/4 4-9 AUXIL IARY S P RAY................................................ 3 / 4 4 - 9 a

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REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION

3. 4. J. l

3. '. 3 The pressurizer shall be OPERA 8LE with:

i A steady-state water volume greater than or equal to 26% indicated a.

level (350 cubic feet) but less than or equal to 62.5% indicated level (900 cubic feet), and, b.

At least two groups of pressurizer heaters powered from Class 1E buses each having a nominal capacity of 150 kW.

1 APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

With only one group of the abcVe required pressurizer heaters a.

OPERABLE, restore at least two groups 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the pressurizer otherwise inoperable, be in at least HOT STANOBY with the reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4'4. 3.1. /

- ' 3.1 The pressurizer water volume shall be determined to be within its l

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

4. 4.1. U

' ' 2.2 The capacity of each of the above required groups of pressurizer l

heaters shall be verified to be at least 150 kW at least once per 92 days.

4 4.51.3

\\

' ' ?a The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by:

Verifying the above pressurizer heaters are automatically shed from a.

the emergency power sources upon the injection of an SIAS test signal.

b.

Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.

WATERFORD - UNIT 3 3/4 4-9

/

REACTOR COOLANT SYSTEM AUXILIARY SPRAY LIMITING CONDITIONS FOR OPERATION 3.4.3.2 Both auxiliary spray valves shall be OPERABLE.

' APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With only one of the above required auxiliary spray valves OPERABLE, restore both valves to OPERABLE status prior to startup following the next reactor shutdown.

b.

With none of the above required auxiliary spray valves OPERABLE, restore at least one valve to OPERABLE status within the next i

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The auxiliary spray valve shall be verified to have power available j

to each valve every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i 4.4.3.2.2 The auxiliary spray valves shall be cycled at least once per 18 months.

i WATERFORD - UNIT 3 3/4 4-9a NS41262

l REACTOR COOLANT SYSTEM 8ASES SAFETY VALVES (Continued) valves are OPERA 8LE, an operating shutdown cooling loop, connected to the RCS, 4

l provides overpressure relief capability and will prevent RCS overpressurization.

In addition, the overpressure protection system provides a diverse means of j

protection against RCS overpressurization at low temperatures.

)j During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.

}

The combined relief capacity of these valves is sufficient to limit the system j

pressure to within its Safety Limit of 2750 psia following a complete loss of l

turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached and also assuming no operation of the steam dump valves.

l Demonstration of the safety valves' lift settings will occur only during reactor shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.

3/4.4.3 PRESSURIZER a

An OPERABLE pressurizer provides pressure control for the Reactor Coolant System during operations with both forced reactor coolant flow and with natural l

circulation flow.

The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure con-trol, remain covered with water to prevent failure, which could occur if the heaters were energized while uncovered.

The maximum water level in the pres-surizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis.

The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble will be provided to accommodate pressure surges during operation.

The steam bubble i

also protects the pressurizer code safety valves against water relief.

The l

requirement to verify that on an SIAS test signal the pressurizer heaters are automatically shed from the emergency power sources is to ensure that the non-Class IE heaters do not reduce the reliability of or overload the emergency 4

i power source.

The requirement that a minimum number of pressurizer heaters be OPERA 8LE enhances the capability to control Reactor Coolant System pressure i

and establish and maintain natural circulation.

1

TABffr2 ~

i 3/4.4.4 STEAM GENERATORS l

The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-l tained.

The program for inservice inspection of steam generator tubes is i

I WATERFORD - UNIT 3 83/44-2

1 INSERT 2 The auxiliary pressurizer spray is used to depressurize the RCS by cooling the pressurizer steam space.

The auxiliary pressurizer spray is used during those periods when normal pressurizer spray is not available, such as during natural circulation and during the later stages of a normal RCS cooldown.

The auxiliary pressurizer spray also distributes baron to the pressurizer when nonnal pressurizer spray is not available.

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ML20205J538

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