ML17305B195

Proposed Tech Specs Sections 3/4.3.1,3/4.4.2,3/4.7.1 & 3/4.7.1.2 Re Main Steam & Pressurizer Safety Valves Setpoint Tolerances

ML17305B195
Person / Time
Site:	Palo Verde
Issue date:	11/13/1990
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17305B194	List: ML17305B195
References
NUDOCS 9011210064
Download: ML17305B195 (38)

Text

ATTACHMENT 4 MARKED-UP TECHNICAL SPECIFICATION CHANGE PAGES 90tl2l0064 PDR 5'Ol l l3" -

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0 TABLE 3. -2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME I. TRIP GENERATION A. Process o.so

1. Pressurizer Pressure - High seconds

2. Pressurizer Pressure - Low < 1.15 seconds

3. Steam Generator Level - Low < 1.15 seconds Steam Generator Level - High < 1.15 seconds

5. Steam Generator Pressure - Low < 1.15 seconds

6. Containment Pressure - High < 1.15 seconds

7. Reactor Coolant Flow - Low < 0.58 second

8. Local Power Density - High

a. Neutron Flux Power from Excore Neutron Detectors < 0.75 second"

b. CEA Positions < 1.35 second""

c. CEA Positions: CEAC Penalty Factor < 0.75 second*"

9. DNBR " Low a~ Neutron Flux Power from Excore Neutron Detectors < 0.75 second"

b. CEA'Positions < 1.35 second."*

C. Cold Leg Temperature < 0.75 seconds

d. Hot Leg Temperature < 0.75 seconds

e. Primary Coolant Pump. Shaft Speed < 0.30 second//

f. Reactor Coolant Pressure from Pressurizer < 0.75 secondCH

g. CEA Positions: CEAC Penalty Factor < 0.75 second**

B. Excore Neutron Flux Variable Overpower Trip < 0.55 second*

2. Logarithmic Power Level - High

a. Startup and Operating < 0.55 second*

b. Shutdown < 0.55 second"

I CCh+3 ~ /~Q REACTOR-COOLANT SYSTEM 3/4; 4:2- -SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2.1 of pressurizer code safety valve shall with a

A lift settingminimum of 2500 on'e psia ~*.

~3i-l l~

be OPERABLE APPLICABILITY: MODE 4.

ACTION:

'a 4 With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE. shutdown cooling loop into operation.

b. The provisions of Specification 3.0.4 may be suspended for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for entering into and during operation in MODE 4 for purposes of setting the pressurizer code safety valves under ambient (HOT) conditions provided a preliminary cold setting was made prior to heatup.

SURVEILLANCE RE UIREMENTS 4.4.2.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

PALO VERDE " UNIT 1 3/4 4-7 AHENDHENT NO. 27

t I

REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall setting of 2500 psia W&".

b'e OPERABLE with a lift

+3,-l /

APPLICABII ITY: MODES 1, 2, and 3.

ACTION:

Mith one pressurizer code safety valve'inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> arid in HOT SHUTDOWN within the following 6 hours with the shutdown cooling system suction line relief valves aligned to provide overpressure protection for the Reactor Coolant System.

SURVEILLANCE RE UIREMENTS 4.4.2.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

PALO VERDE - UNIT 1 3/4 4-8 ,

AMENDMENT NO. 27

0 I

C 0

(4

0 TABLE 3. 7-1 STEAM LINE SAFETY VALVES PER LOOPS L3% MINIMUM VALYE NUMBER LIFT SETTING RATED CAPACITY""

S/G No. 1 S/G No. 2

a. SGE PSV 572 SGE PSV 554 1250 psig 941,543 lb/hr

b. SGE PSV 579 SGE PSV 561 1250 psig 941,543 lb/hi

c. SGE PSY 573 SGE PSV 555 1290 psig 971,332 lb/hr

d. SGE PSV 578 SGE PSV 560 1290 psig 971,332 lb/hr

e. SGE PSV 574 SGE PSV 556 1315 psig 989,950 lb/hr

f. SGE PSV 575 SGE PSV 557 1315 psig 989,950 lb/hr

g. SGE PSV 576 SGE PSV 558 1315 psig 989,950 lb/hr

h. SGE PSY 577 SGE PSY 559 1315 psig 989,950 lb/hr

i. SGE PSV 691 SGE PSV 694 1315 psig 989,950 lb/hr

3. SGE PSV 692 SGE PSV 695 1315 psig 989,950 lb/hr "The lift setting pressure shall correspond to ambient conditions at the valve at nominal operating temperature and pressure.

"*Capacity is rated at lift setting +3X accumulation.

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I

PLANT SYSTEHS SURVEILLANCE RE UIREHENTS Continued) b.. At least once per 18.months during shutdown by:

1. Verifying that each automatic valve in the flop path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.

2. Verifying that each pump that starts automatically upon receipt of an auxil.iary feedwater actuation test signal will start automatically upon receipt of an auxiliary feedwater actuation test signal.

c. Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, by verifying on a STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of'he steam generators through one of the essential auxiliary feedwater pumps deliver s at least 7SO gpm at 1270 psia or equivalent g5a

d. The provisions of Specification 4.0.4 are not applicable for entry into HODE 3 or HODE 4 for the turbine-driven pump.

PALO VERDE - UNIT 1 3/4 7-5

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PLANT SYSTEMS BASES SAFETY VALVES (continued) 10 total number of secondary safety valves for one steam generator.

number of inoperable main steam safety valves on the steam generator with the greater number of inoperable valves.

109.2 = ratio of main steam safety valve relieving capacity of 110K steam generator design pressure to calculated steam flow rate at 100K plant power + 2 uncertainty (see above text) 9.8 = BAND between the maximum thermal power and the variable over-power trip setpoint ceiling 3/4. 7. l. 2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions inthe event of a total loss-of-.offsite power.

f5+ g50 A Each electric-driven auxiliary feedwater pump is capable of delivering a minimum feedwater flow of ~gpm at a press re of 1270 psia ~ the entrance

~+

of the steam generators.

of delivering a minimum feedwater flow of

~ the entrance of the steam generators.

~

The steam-driven a iliary feedwater pump is capable gpm at a pressure of 1270 psia This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F when the shutdown cooling system may be placed into operation.

3/4.7. 1.3 CONDENSATE STORAGE TANK The, OPERABILITY of the condensate storage tank ensures that a minimum water volume of 300,000 gallons is available to maintain the Reactor Coolant System at HOT STANDBY for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> followed by an orderly cooldown to the shutdown cooling entry (350 F) temperature with concurrent total loss-of-site power. The con-tained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics:

PALO VERDE - UNIT 1 B 3/4 7-2 T"'Q<i+if (j

1'i 7<t

0 TABLE 3.3-2

(

m REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIl1ES C) FUNCTIONAL UNIT RESPONSE TIME m

I. TRIP GENERATION A. Process l.

2.

Pressurizer Pressure - High Pressurizer Pressure - Low

< ~

O. SO

< 1 seconds 15 seconds

3. Steam Generator Level - Low < 1. 15 seconds Steam Generator Level - High < 1. 15 seconds

5. Steam Generator Pressure - Low < 1.15 seconds Containment Pressure - High < 1.15 seconds Reactor Coolant Flow Low < 0.58 second Local Power Density High

a. Neutron Flux Power from Excore Neutron Detectors < 0.75 second"

b. CEA Positions < 1.35 second""

c. CEA Positions: CEAC Penalty Factor < 0.75 second""

9. DNBR - Low

a. Neutron Flux Power from Excore Neutron Detectors < 0.75 second"

b. CEA Positions < 1.35 second""

c. Cold Leg Temperature < 0. 75 secondly

d. Hot Leg Temperature < 0.75 secondb8

e. Primary Coolant Pump Shaft Speed < 0.30 seconds

f. Reactor Coolant Pressure from Pressurizer < 0.75 seconds'0'

g. CEA Positions: CEAC Penalty Factor 0.75 second*"

m B. Excore Neutron Flux m

Variable Overpower Trip < 0.55 second"

2. Logarithmic Power Level - High

a. Star tup and Operating < 0 55 second"

b. Shutdown < 0.55 second"

CQM7RQILLE9 B~f USER REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR .OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a'lift setting of 2500 psia ~o

+>i "<%

APPLICABILITY: MODE 4.

ACTION:

a. Mith no pressurizer code safety valve OPERABLE, immediately suspend al') operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.

b. The provisions of Specification 3.0.4 may be suspended for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for entering into and during operation in MODE 4 for purposes of setting the pressurizer code safety valves under ambient (HOT) conditions provided a preliminary cold setting was made prior to heatup; SURVEILLANCE RE UIREMENTS 4.4.2:1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressur>zer:code setting of 2500 psia ~".- safety valves shall. be OPERABLE with a lift

+3 -lo/

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to.OPERABLE status withip 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours with the shutdown cooling system suction 'line relief valves aligned to provide overpressure protection for the. Reactor. Coolant System.

SURVEILLANCE RE UIREMENTS

'. 4. 2. 2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

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TABLE 3. 7-1 STEAM LINE SAFETY.'ALVES PER LOOPS

(

m C) R3%

m MINIMUM VALVE NUMBER LIFT SETTING (~)* RATED CAPACITY~~

S/G No. 1 S/G No. 2

a. SGE PSV 572 SGE PSV 554 1250 psig 941,543 lb/hr

b. SGE PSV 579 . SGE PSV 561 1250 psig 941,543 lb/hr

c. SGE PSV 573 .. SGE PSV 555 1290 psig 971,332 lb/h1

d. SGE PSV 578 SGE PSV 560 1290 psig 971,332 lb/hr.

e. SGE PSV 574 SGE PSV 556 1315 psig 989,950 lb/hr

f. SGE PSV 575 SGE PSV 557 1315 psig 989,950 lb/hr

g. SGE PSV 576 SGE PSV 558 1315 psig 989,950 lb/hr

h. SGE PSV 577 SGE PSV 559 1315 psig 989,950 lb/hr

i. -

SGE PSV 691 SGE PSV 694 1315 psig 989,950 lb/hr

j. SGE PSV '692 SGE PSV: 695 1315 psig 989,950 lb/hr "The lift setting pressure shall correspond to ambient conditions at the valve at nominal operating temperature and pressure.

"*Capacity is rated at. lift setting +3% accumulation.

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FOR INFORMATION ONLY PLANT SYSTEHS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 18 months during shutdown by:

1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.* I

2. Verifying that each pump that starts automatically upon receipt of an auxiliary feedwater actuation test signal will start automatically upon receipt of an auxiliary feedwater actuation test signal.*

C. Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, by verifying on a STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 750 gpm at 1270 psia or equivalent t'5o The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.

A~ +Pc c h4e,~(w o4 ti gcwcv~4ov, "Deferred until cycle 3 refueling outage.

PALO VERDE - UNIT 2 3/4 7-5 AMEil0llENT NO. 30

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CGMTIRGILII.EG BY LIISIEIR PLANT SYSTEMS BASES SAFETY VALVES (continued) 10 total number of secondary safety valves for one steam generator.

number of inoperable main steam safety valves on the steam generator with the greater number of inoperable valves.

109.2 = ratio of main steam safety valve relieving capacity of 110%

steam generator design pressure to calculated steam flow rate at 100% 'plant power + 2/o'ncertainty (see above text)

.9.8 = BAND between the maximum thermal power and the variable over-power, trip setpoint ceiling 3/4. 7. 1. 2 AUXILIARY FEEDMATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions,, in the ever@ of a total loss-of-offsite power.

(,50

",Each,,el,ectric-dri-ve auxil=iary feedwat r pump is "capable'QFf delivering a minimum feedwater flow of gpm at a pre sure of 1270 psia M the entrance of the steam generators. The steam-driven auxiliary feedwater pump is capable of delivering a minimum feedwater flow of 750 gpm at a pressure of 1270 psia

~~ M the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F when the shutdown cooling system may be placed into operation.

3/4.7. 1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank ensures that a minimum water volume of 300,000 gallons is available to maintain the Reactor Coolant System at HOT STANDBY for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> followed by,. an. orderly cooldown to the shut'down cooling entry (350'F) temperature with concur rent total loss-of-site power. The con-tained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

PALOVERDE- U T B 47

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'1,

TABLE 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME 5

I. TRIP GENERATION A. Process 0.5O

1. Pressurizer Pressure - High seconds

2. Pressurizer Pressure - Low < 1 15 seconds

3. Steam Generator Level - Low < 1.15 seconds

4. Steam Generator Level - High < 1.15 seconds

5. Steam Generator Pressure - Low < 1 15 seconds

6. Containment Pressure " High < 1. 15 seconds

7. Reactor Coolant Flow - Low < 0.5S second

8. Local Power Density - High

a. Neutron Flux Power from Excore Neutron Detectors < 0.75 second"

b. CEA Positions < 1,35 second"~

c. CEA Positions: CEAC Penalty Factor < 0.75 second""

9. DNBR - Low

a. Neutron Flux Power from Excore Neutron Detectors < 0.75 second*

b. CEA Positions < 1.35 second"~

c. Cold Leg Temperature < 0.75 secondbk

d. Hot Leg Temperature < 0.75 seconds//

e. Primary Coolant Pump Shaft Speed < 0.30 seconds

f. Reactor Coolant Pressure from Pressurizer < 0.75 second&'0

g. CEA Positions: CEAC Penalty Factor < 0.75 second"*

8. Excore Neutron Flux

1. Variable Overpower Trip < 0.55 second"

2. Logarithmic Power Level - High

a. Startup and Operating < 0.55 second"

b. Shutdown < 0.55 second"

k 1

, II llx

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2.1 minimum of one pressurizer safety valve shall with of 2500 psia ~".

A code be OPERABLE a lift setting +3,-I lo APPLICABILITY: MODE 4.

ACTION:

a. with no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop- into operation.

b. The provisions of Specification 3.0.4 may be suspended for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for entering into and during operation in MODE 4 for purposes of setting the pressurizer code safety valves under ambient (HOT) conditions provided a preliminary cold setting was made prior to heatup.

SURVEILLANCE RE UIREMENTS 4.4.2.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

PALO VERDE - UNIT 3 3/4 4-7

7 C

'f

REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer setting of 2500 psia ~". code safety valves shall be OPERABLE with a lift

+38 r%

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours with the shutdown cooling system suction line relief valves aligned to provide overpressure protection for the Reactor Coolant System.

SURVEILLANCE RE UIREMENTS 4.4. 2. 2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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

PALO VEROE " UNIT 3 3/4 4"8

~' >> 4 h'

TABLE 3 ~ 7-1 STEAM LINE SAFETY VALVES PER LOOPS LIFT SETTING MINIMUM VALVE NUMBER ) RATED CAPACITY*"

S/G No. 1 S/G No. 2

a. SGE PSV 572 SGE PSV 554 1250 psig 941,543 lb/hr

b. SGE PSV 5?9 SGE PSY 561 1250 psig 941,543 lb/hr

c. SGE PSY 573 SGE PSV 555 1290 psig 971,332 lb/hr

d. SGE PSV 578 SGE PSY 560 1290 psig 971,332 lb/hr

e. SGE PSV 574 SGE PSV 556 1315's ig 989,950 lb/hr SGE PSV 575 SGE PSV 557 1315 psig 989,950 lb/hr

g. SGE PSV 576 SGE PSV 558 1315 psig 989,950 lb/hr

h. SGE PSV 577 SGE PSY 559 1315 psig ,989,950 lb/hr

i. lb/hr e

SGE PSV 691 SGE PSV 694 1315 psig 989,950

j. SGE PSY 692 SGE PSY 695 1315 psig 989,950 lb/hr "The lift setting pressure shall correspond to ambient conditions at the valve at nominal operating temperature and pressure.

"*Capacity is rated at lift setting +3Ã accumulation.

PALO VERDE - UNIT 3 3/4 7-2

1 I

~

N K

PL'ANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued)

b. At least once per 18 months during shutdown by:

1. Verifying that each automatic valve in the flow path actuates'o its correct position upon receipt of an auxiliary feedwater actuation test signal.

2. Verifying that each pump that starts automatically upon receipt of an auxiliary feedwater actuation test signal will start automatically upon receipt of an auxiliary feedwater actuation test signal.

c, Prior to startup following -any refueling shutdown or cold shutdown of 30 days or longer, by verifying on a STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 75G gpm at 1270 psia or equivalen 4,5o

d. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.

a~ ~4 e,w r ~ o0 4'ke skcsw amcva4v'ALO VERDE - UNIT 3 3/4 7-5

l

/--

i P

I 0

4 l

4 4'I

PLANT SYSTEHS BASES SAFETY VALVES (continued) 10 total number of, secondary safety valves for one steam generator.

number of inoperable main steam safety valves on the steam generator with the greater number of inoperable valves.

109.2 = ratio of main steam safety valve relieving capacity of 110K steam generator design pressure to calculated steam flow rate at 100K plant power + 2X uncertainty (see above text) 9.8 = BAND between the maximum thermal power and the variable over power trip setpoint ceiling 3/4.7. 1.2 AUXILIARY FEEDMATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating e conditions in the event of a total loss-of-offsite power.

Each electric-drive minimu'm feedwater flow of CSQ auxiliary gpm at feedw a

450 er pump is capable of delivering a pre sure of 1270 psia the entrance of the steam generators. The steam-driven uxiliary feedwater pump is capable of delivering a minimum feedwater flow of gpm at a pressure of 1270 psia

~+ te the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F when the shutdown cooling system may be placed into operation.

3/4.7. 1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank ensures that a minimum water volume of 300,000 gallons is available to maintain the Reactor Coolant System at HOT STANDBY for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> followed by an orderly cooldown to the shutdown cooling entry (350 F) temperature with concurrent total loss-of-site power. The con-tained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

PALO VERDE - UNIT 3 B 3/4 7-2

7 f~ I, "e