ML17310B294
| ML17310B294 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/16/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17310B291 | List: |
| References | |
| NUDOCS 9405250240 | |
| Download: ML17310B294 (48) | |
Text
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%%*f4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055~1 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.75 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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 Hexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated November 13,
- 1990, supplemented by letters dated Hay 27,
- 1992, Hay 13,
- 1993, and November 12,
- 1993, 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 wil3 not be inimical to the common defense and security or to the health and safety of the public; and 2.
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.
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.'PF-41 is hereby amended to read as follows:
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Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.75 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 December 1,
1994.
FOR THE NUCLEAR REGULATORY COMMISSION g/'. 4~2~p Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
75 TO FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the fo]lowing 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 8 3/4 7-2 Insert 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 B 3/4 7-2
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TABLE 3.3-REACTOR PROTECTIV INSTRUMENTATION RESPONSE TINES EUUMCTIGNA IINIT I.
TRIP GENERATION RESPONSE TIN A.
Process 1.
Pressurizer Pressure - High 2.
Pressurizer Pressure Low 3.
Steam Generator Level - Low 4.
Steam Generator Level High i 5.
Steam Generator Pressure Low 6.
Containment Pressure High 7.
Reactor Coolant Flow - Low 8.
Local Power Density High a.
Neutron Flux Power from Excore Neutron Detectors b.
CEA Positions c.
CEA Positions:
CEAC Penalty Factor 9.
DNBR - Low
< 0.50 seconds
< 1. 15 seconds
< 1.15 seconds
< 1.15 seconds
< 1.15 seconds
< 1.15 seconds
< 0.58 second
< 0.75 second*
< 1.35 second**
< 0.75 second**
a.
Neutron Flux Power from Excore Neutron Oetectors b.
CEA Positions c.
Cold Leg Temperature d:,-
Hot Leg Temperature e.'rimary Coolant Pump Shaft Speed f.
Reactor Coolant Pressure from Pressurizer g.
CEA Positions:
CEAC Penalty Factor B.
Excore Neutron Flux
< 0.75
< 1.35
< 0.75
< 0.75
< 0.30
< 0.75
< 0.75 second*
second**
second¹¹ second¹¹ second¹ second¹¹¹ second**
~ 1.
Variable Overpower Trip 2.
Logarithmic Power Level High a.
Startup and Operating b.
Shutdown
< 0.55 second*
< 0.55 second*
< 0.55 second*
TABLE 3.3-2 (Continued)
REACTOR PROTECTIVE INSTRlNENTATION RESPONSE TINES m
FUNCTIONAL UNIT
RESPONSE
TINE C.
Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators D.
Supplementary Protection System Pressurizer Pressure - High II.
RPS LOGIC A.
Matrix Logic B.
Initiation Logic III. 'RPS ACTUATION DEVICES A.
Reactor Trip 8reakers 8.. Manual Trip-Not Applicable Not Applicable
< 1.15 second Not Applicable Not Applicable Not Applicable Not Applicable m
~
C7 Neutron detectors are exempt from response time testing.
The response time of the neutron flux signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel.
Ak
Response
time shall be measured from the output of the sensor.
Acceptable CEA sensor response shall be demonstrated by compliance with Specification 3.1.3.4.
IThe pulse transmitters measuring pump speed are exempt from response time testing.
The response time shall be measured from the pulse shaper input.
NNResponse time shall be measured from the output of the resistance temperature detector (sensor).
RTD response time shall be measured at least once per 18 months.
The measured response time of the slmrest RTD shall be less than or equal to 8 seconds.
HNResponse time shall be measured from the output of the pressure transmitter.
The transmitter response time shall be less than or equal to 0.7 second.
LB REACTOR COO ANT SYSTEM 3 4.4.2 SAFETY VA V S 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 +3, -IX*.
~OPPLTOPBIL TT:
IIOOT 4.
~CT ON:
'a ~
b.
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop'-into operation.
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 AMENDMENT NO. 47-,
75
R ACTOR CO ANT YS M
OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 psia +3, -1X*.
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~AT ON:
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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 liftsetting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
PALD iVERDE - UNIT I 3/4 4-8 AMENDMENT NO.~
75
3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves shall be OPERABLE with liftsettings as specified in Table 3.7-1.
APPLICABILITY:
MODES 1, 2, 3, and 4*.
ACTION:
a ~
C.
With both reactor coolant loops and associated steam generators in operation and with one or more~" main steam safety valves inoperable per steam generator, operation in MODES 1 and 2 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 all the inoperable valves are restored to OPERABLE status or the maximum variable overpower trip setpoint and the maximum Allowable Steady State Power Level are reduced per Table 3.7-2; 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 />.
Operation in MODES 3 and 4* may proceed with at least one reactor coolant loop and associated steam generator in operation, provided that there are no more than four inoperable main steam safety valves associated with the operating steam generator; otherwise, be 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 />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.1.
1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
Until the steam generators are no longer required for heat removal.
- 0 The maximum number of inoperable safety valves on any operating steam.
generator-is four (4).
~ y PALD VERDE - UNIT 1 3/4 7-1 AMENDMENT NO. 27
TABLE 3.7-1 STEAH LINE SAFETY VALVES PER LOOPS S
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~PATRI RRIIB R
I
~SG No.
1 SGE PSV ~72 b.
SGE PSV 579
~SG No.
SGE PSV 554 SGE PSV 561 d.
SGE PSV 578 SGE e;
SGE PSV 574 SGE f.
SGE PSV 575 SGE 9.
SGE PSV 576 SGE SGE PSV 577 SGE SGE PSV 691 SGE SGE PSV 692 SGE I
PSV 560 PSV 556 PSV 557 PSV 558 PSV 559 PSV 694 PSV 695 c.
SGE PSV 573 SGE PSV 555 L~IFT TT RR LRR 1250 psig 1250 psig 1290 psig 1290 psig 1315 psig 1315 psig 1315 psig 1315 psig 1315 psig 1315 psig HINIHUH
~RATIB AAPA ITT 941,543 lb/hr 941,543 lb/hr 971,332 lb/hr 971,332 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 Rlb/hr 989,950 lb/hr 989,950 lb/hr m
- The liftsetting pressure shall correspond to ambient conditions at the valve at nominal operating temperature and pressure.
- Capacity is rated at lift setting
+3X accumulation.
P ANT SYSTEMS SURVEILLANCE RE UIREMENTS 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.
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 650 gpm at 1270 psia or equivalent at the entrance of the steam generator d.
The provisions of Specification 4.0.4 are not applicable for entry into NODE 3 or NODE 4 for the turbine-driven pump.
PALO VERDE UNIT 1 3/4 7-5 ANE'NONENT NO.
75
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION fOR OPERATION
- 3. 7.1.3 The condensate storage tank (CST) shall be OPERABLE with an indicated level of at least 25 feet (300,000 gallons).
APPLICABILITY:
MODES 1, 2, 3f, and 4*$.
ACTION:
With the condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
Restore the CST to OPERABLE status or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or b.
Demonstrate the OPERABILITY of the reactor makeup water tank as a
backup supply to the essential auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or 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 HOT SHUTDOWN with a
OPERABLE shutdown cooling loop in operation within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.7.1.3. 1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the level (contained water volume) is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The reactor makeup water tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the reactor makeup water tank is the supply source for the essential auxiliary feedwater pumps by verifying:
a.
b.
That the reactor makeup water tank supply line to the auxiliary fee&
water system isolation valve is open, and That the reactor makeup water tank contains a water level of at. least 26 feet (300,000 gallons).
- Until the steam generators are no longer required for heat removed.
Not applicable when cooldown is in progress.
PALO VERDE - UNIT 1 3/4 7-6 AMENDMENT NO.
27
3/4.7 PLANT SYSTEMS BASES 3/4.7. 1 TURBINE CYCLE 3/4.7. 1. 1 SAFETY VALVES The OPERABILITY of the main steam safety valves (HSSVs) limit secondary system pressure to within llOX (1397 psia) of the design pressure (1270 psia) during the most severe anticipated operational transient.
For design purposes the valves are sized to pass a minimum of 102'f the RATED THERMAL POWER at 102K of design power.
The adequacy of this relieving capacity is demonstrated by maintaining the Reactor Coolant System pressure below NRC acceptance criteria (120K of design pressure for large feedwater line breaks, CEA ejection and 110X of design pressure for all overpressurization events).
The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASME Boiler and Pressure Vessel
- Code, 1974 Edition including the Summer 1975 Addenda.
The total relieving capacity for all twenty HSSVs at llOX of system design pressure (adjusted for 50 psi pressure drop to valves inlet) is 19.44 x 106 ibm/hr.
This capacity is less than the total rated capacity as the HSSVs are operating at an inlet pres-sure below rated conditions.
At these same secondary pressure conditions, the total steam flow at 02K (2X uncertainty) of 3817 HWt (RATED THERMAL POWER plus 17 MWt pump heat input) is 17.83 x 10 ibm/hr.
The ratio of this total steam flow to the total capacity is 109.2X.
STARTUP and/or POWER OPERATION is allowable with HSSVs inoperable if the maximum allowable power level is reduced to a value equal to the product of the ratio of the number of HSSVs available per steam generator to the total number of MSSVs per steam generator with the ratio of the total steam flow to available relieving capacity.
Allowable Power Level. = (
) x 109.2 10-N 10
-The ceiling on.the variable over power reactor trip is also reduced to an amount over the allowable power level equal to the BAND given for this trip in Table 2.2-1.
SP = Allowable Power Level + 9. 8 where:
SP reduced reactor trip setpoint in pe."."ent of RATED THERMAL
'POWER.
This is a ratio of the available relieving capacity over the..total steam flow at rated power.
PALO VERDE - UNIT 1 B 3/4 7-1
ANT SYST HS BASES 10 N
109.2 9.8 d) 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.
ratio of main steam safety valve relieving capacity of 110X steam generator design pressure to calculated steam flow rate at 100X plant power + 2X uncertainty (see above text)
BAND between the maximum thermal power and the variable over power trip setpoint ceiling 3 4.7.
.2 AU IAR FEEDWATER SY The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coo1ant System can be cooled down to less than 350'F from normal operating
.conditions in the event of a total loss-of-offsite power.
Each electric-driven auxiliary feedwater pump is capable of delivering a
minimum feedwater flow of 650 gpm at a pressure of 1270 psia at the entrance of the steam generators.
The steam-driven auxiliary feedwater pump is capable of delivering a minimum feedwater flow of 650 gpm at a pressure of 1270 psia at 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 COND NSAT STORAGE TAN
-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 concurrent total loss-of-site power.
The contained 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 AMENDMENT NO. 75
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%y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.O. 2055&4001 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. 6i License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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 13, 1990, supplemented by letters dated May 27,
- 1992, May 13,
- 1993, and November 12,
- 1993, 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.
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.
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 I
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~ 4 0'
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. <<,
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 December 1,
1994.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1994 Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
6" 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 B 3/4 7-2 Insert 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 B 3/4 7-2
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TABLE 3.3-2 EACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONA UHIT
'- I.
TRIP GENERATION A.
Pro>ess
RESPONSE
TIME 1.
2.
3.
5.
6.
7.
8.
9 Pressurizer Pressure - High Pressurizer Pressure Low Steam Generator Level Low Steam Generator Level High Steam Generator Pressure - Low Containment Pressure High Reactor Coolant Flow Low Local Power. Density - High a.
Neutron Flux Power from Excore Neutron Detectors b.
CKA Positions c.
CEA Positions:
CEAC Penalty Factor ONBR - Low
< 0.50 seconds g 1.15 seconds
< 1.15 seconds g 1.15 seconds
< 1.15 seconds g 1.15 seconds
< 0.58 second g 0.75 second*
g 1.35 second**
~
- g 0.75 second~~
a.
Neutron Flux Power from Excore Neutron Detectors b.
CEA Positions c.
Cold Leg Temperature d.
Hot Leg Temperature e.
Primary Coolant Pump Shaft Speed f.
- Reactor Coolant Pressure from Pressurizer g.
CEA Positions:
CEAC Penalty Factor B.
Excore Neutron Flux g 0.75 second*
g 1.35 second**
~ 0.75 secondff g 0.75 secondff g 0.30 secondf g 0.75 secondfff
< 0.75 second**
1.
2.
Variable Overpower Trip Logarithmic Power Level High a.
Startup and Operating b.
Shutdown g 0.55 second*
~ 0.55 second*
g 0.55 second*
TABLE 3.3-2 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES
,I FUNCTIONAL UNIT C.
Core Protection Calculator System 1.
CEA'.Calculators 2.
Core Protection Calculators D.
Supplementary Protection System Pressurizer Pressure - High II. RPS LOGIC A.
Hatrix Logic:
B.
Initiation Logic III.
RPS ACTUATION DEVICES A.
Reactor Trip Breakers B.
Hanual Trip
RESPONSE
TIME Hot Applicable Hot Appli cable
< 1 15 second Hot Applicable Hot Applicable Hot Applicable Hot Applicable Neutron detectors are exempt from response time testing.
The response time of the neutron
.flux signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel.
A*
Response
time shall be measured from the output of the sensor.
Acceptable CEA sensor response shall be demonstrated by compliance with Specification 3.1.3.4.
NThe pulse transmitters measuring pump speed are exempt from response time testing.
The response time shall be measured from the pulse shape~ input.
NNResponse time shall be measured from the output of the resistance temperature detector (sensor).
RTD response time shall be measured at least once per 18 months.
The measured response time of the slowest RTD shall be less than or equal to 8 seconds.
l NNNResponse time shall be measured from the output of the pressure transmitter.
The transmitter response time shall be less than or equal to 0.7 second.
ACTO COOL S ST 3 4.4.
SAF T
~SHUT OWH 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 +3, -1X*.
~PAB BABE 4.
~CT OH:
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 fn 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 additiona1 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 2 3/4 4-7 AMENDMENT NO. 61
REACTOR COOLANT SYST OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 psia +3, -1X*.
I
~II IT:
2 222 l. 2.
2 2.
~CTI ON:
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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with the shutdown cooling system suction line relief valves aligned to provide overpressure protection for the Reactor Coolant System.
SURVEILLANCE RE UIREHENTS 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 2 3/4 4-8 AMENDMENT NO. 61
3/4.7 PLANT SYSTEHS 3/4.7. 1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves shall be OPERABLE with liftsettings as specified in Table 3.7-1.
APPLICABILITY:
MODES 1, 2, 3, and 4".
ACTION:
a.
b.
With both reactor coolant loops and associated steam generators in operation and with one or more"* main steam safety valves inoperable per steam generator, operation in MODES 1 and 2 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 all the inoperable valves are restored to OPERABLE status or the Haximum Variable Overpower trip setpoint and the Maximum Allowable Steady State Power Level are reduced per Table 3.7-2; 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 />.
Operation in MODES 3 and 4" may proceed with at least one reactor coolant loop and associated steam generator in operation, provided that there are no more than four inoperable main steam safety valves associated with the operating steam generator; otherwise, be 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 />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7. l. 1 No additional Surveillance Requirements other than those required by Specification
- 4. 0.5.
Until the steam generators are no longer required for heat removal.
The maximum number of inoperable safety valves oq.any operating steam generator is-four (4).
PALO VERDE - UNIT 2 3/4 7-1
T B
3.7-S EAM N
SAF Y VA V S
P 0
VA V NUM ER
~SG No.
S G No.
LIFT SETTING MINIMUM a 0 b.
c d.,
e.
g.
SGE PSV 572 SGE PSV 579 SGE PSV 573 SGE PSV 578 SGE PSV 574 SGE PSV 575 SGE PSV 576 SGE PSV 577 SGE PSV 691 SGE PSV 692 SGE PSV 554 SGE PSV 561 SGE PSV 555 SGE PSV 560 SGE PSV 556 SGE PSV 557 SGE PSV 558 SGE PSV 559 SGE PSV 694 SGE PSV 695 1250 psig 1250 psig 1290 psig 1290 psig
- .1315 psig 1315 psig 1315 psig 1315 psig 1315 psig 1315 psig 941,543 lb/hr 941,543 lb/hr 971,332 lb/hr 971,332 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/hr 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 liftsetting
+3X accumulation.
PALO VERDE - VNIT 2 3/4 7-2 AMENDMENT NO-61
P ANT SYSTEMS SURVEILLANCE RE UIREMENTS 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.*-
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 650 gpm at 1270 psia or equivalent at the entrance of the steam generator.
d.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.
~Deferred until cycle 3 refueling outage.
PALO VERDE - UNIT 2 3/4 7-5 AMENDMENT NO. %h~,
61
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 0
3.7. 1.3 The condensate storage tank (CST) shall be OPERABLE with an indicated level of at least 25 feet (300,000 gallons).
APPLICABILITY:
NODES 1, 2, 3,f and 4.<<N ACTION:
Mith the condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the CST to OPERABLE status or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or b.
Demonstrate'the OPERABILITY of the reactor makeup water tank as a
backup supply to the auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or 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 HOT SHUTDOWN with a OPERABLE shutdown cooling loop in operation within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4'.1.3. 1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the level (contained water volume) is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The reactor makeup water tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the reactor makeup ~ater tank is the supply source for the auxiliary feedwater pumps by verifying:
a.
b.
That the reactor makeup water tank supply line to the auxiliary feed system isolation valve is open, and That the reactor makeup ~ater tank contains a ~ater level of at least 26 feet (300,000 gallons).
<<Until the steam generators are no longer required for heat removed.
Not applicable when cooldown is in progress.
. ~
'ALO VERDE - UNIT 2 3/4 7-6 NENDHENT NO. l
3/4.7 PLANT SYSTEMS BASES 3/4. 7. 1 TURBINE CYCLE 3/4. 7. 1. 1 SAFETY VALVES The OPERABILITY of the main steam safety valves (HSSVs) limit secondary system pressure to within 110K (1397 psia) of the design pressure (1270 psia) during the most severe anticipated operational transient.
For design purposes the valves are sized to pass a minimum of 102K of the RATED THERMAL POWER at 102K of design power.
The adequacy of this relieving capacity is demonstrated by maintaining the Reactor Coolant System pressure below NRC acceptance criteria (120X of design pressure for large feedwater line breaks, CEA ejection and 110X of design pressure for all overpressurization events).
The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASHE Boiler and Pressure Vessel
- Code, 1974 Edition including the Summer 1975 Addenda.
The total relieving capacity for all twenty HSSVs at 110K of system design pressure (adjusted for 50 psi pressure drop to valves inlet) is 19.44 x 106 ibm/hr.
This capacity is
= less-than the total rated capacity as the HSSVs are operating at an inlet pres-sure below rated conditions.
At these same secondary pressure conditions, the total steam flow at 102K (2X uncertainty) of 3817 HWt (RATED THERMAL POWER plus 17 HWt pump heat input) is 17.83 x 10 ibm/hr.
The ratio of this total steam flow to the total capacity is 109.2X.
STARTUP and/or POWER OPERATION is allowable with HSSVs inoperable if the maximum allowable power level is reduced to a value equal to the product of the ratio of the number of HSSVs available per steam generator to the total number of HSSVs per steam generator with the ratio of the total steam flow to available relieving capacity.
Allowable Power Level = (
) x 109.2 10-N 10 The ceiling on the variable over power reactor trip is also reduced to an amount over the allowable power level equal to the BAND given for this trip in Table 2.2-1.
SP = Allowable Power Level + 9.8 where:
SP reduced reactor trip setpoint in per. ent of RATED THERMAL POWER.
This is a ratio of the available relieving capacity over the,+otal steam flow at rated power.
. PALO VERDE - UNIT 2 B 3/4 7-1
ANT S S
BASES AF TY V V
10 N
109.2 9.8 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.
ratio of main steam safety valve relieving capacity of 110X steam generator design pressure to calculated steam flow rate at 100X plant power + 2X uncertainty (see above text)
BAND between the maximum thermal power and the variable over power trip setpoint ceiling 3 4.7.1.2 AUXILIARY F EDWATER SYST 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 event of a total loss-of-offsite power.
Each electric-driven auxiliary feedwater pump is capable of delivering a
minimum feedwater flow of 650 gpm at a pressure of 1270 psia at the entrance of the steam generators.
The steam-driven auxiliary feedwater pump is capable of delivering a minimum feedwater flow of 650 gpm at a pressure of 1270 psia at 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 STORAG AN 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 concurrent total loss-of-site power.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
PALO VERDE - UNIT 2 B 3/4 7-2 ANENDNENT NO.
61
ggf', IIEQg 0
~E c
I )<
I og Vl 4y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 00555-000I 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.47 License No.
NPF-74 1.
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 13,
- 1990, supplemented by letters dated May 27,
- 1992, May 13,
- 1993, and November 12,
- 1993, 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'll 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 l
1 4
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 47, 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 December 1,
1994.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1994 3" -~- < ~:
Theodore R, quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
~
L I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
47 TO FACILITY'ERATING LICENSE NO.
NPF-74 POCKET 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 B 3/4 7-2 Insert 3/4 3-11 3/4 4-7 3/4 4-8 3/4 7-2 3/4 7-5 B 3/4 7-2
g
\\
/
'1 la e
~ ~
ps'>
+4+
g CENT tv' I
C Ob 3
3
~
3 3
l I'
PN f f 3
IT "3
~NNII UNCTION I.
TRIP GENERATION A.
Process I
1.
Pressurizer Pressure - High 2.
Pressurizer Pressure Low 3.
Steam Generator Level Low 5.; Steam Generator Level - High 5.
Steam Generator Pressure Low 6.
Containment Pressure - High 7.
Reactor Coolant Flow Low 8.
Local Power Density - High
~ 0.50 seconds g 1.15 seconds 5 1.15 seconds 6 1.15 seconds 5 1.15 seconds 5 1.15 seconds 6 0.58 second I~NB I 3.3-3 REACTOR PROTECTIV INSTRUMENTATION RESPONSE TIN S 33 TONBN TINT II fj I '3 9 ~
a.
Neutron Flux Power from Excore Neutron Detectors b.
CEA Positions c.
CEA Positions:
CEAC Penalty Factor DNBR - Low 5 0.75 second*
6 1.35 second*~
5 0.75 second**
C7 ED a.
Neutron Flux Power from Excore Neutron Detectors b..
CEA Positions
- c. 'old Leg Temperature d.
Hot Leg Temperature e.
Primary Coolant Pump Shaft Speed f.
Reactor Coolant Pressure from Pressurizer g.
CEA Positions:
CEAC Penalty Factor B.
Excore Neutron Flux I
1.
Variable Overpower Trip 2.
Logarithmic Power Level'- High
- a. 'tartup and Operating b.
Shutdown g 0.75 second*
g 1.35 second**
g 0.75 secondff g 0.75 secondff g 0.30 secondt 5 0.75 secondfff 6 0.75 second**
8 0.55 second*
6 0.55 second*
6 0.55 second*
IC7 C7m I,
Cal 4P I
TABLE 3.3-2 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT C.
Core Protection Calculator System 1.
CEA'alculators 2.
Core Protection Calculators 0.
Supplementary Protection System I
'Pressurizer Pressure - High II. RPS LOGIC A.
Hatrix Logic 8.
Initiation Logic III.
RPS ACTUATIOH DEVICES A.
Reactor Trip Breakers 8.
Hanual Trip
RESPONSE
TIME Not Applicab1e Not Applicable
< 1.15 second Hot Applicable Not Appl icab le Not Applicable Not Applicable m
C7 m
4 Cl I
Neutron dete(-tors are exempt from response time testing.
The response time of the neutron flux'signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel.
Response
time shall be measured from the output of the sensor.
Acceptable CEA sensor response shall be demonstrated by compliance with Specification
- 3. 1.3.4.
OThe pulse transmitters measuring pump speed are exempt from response time testing.
The response time shall be measured from the pulse shaper input.
I HResponse time shall be measured from the output of the resistance temperature detector (sensor).
RTD response time shall be measured at least once per 18 months.
The measured response time of the slowest RTD shall be less than or equal to 8 seconds.
HNResponse time shall be measured from the output of the pressure transmitter.
The transmitter response time shall be less than or equal to 0.7 second.
e
Y1 REACTOR COOLANT SYSTEM 3 4.4.
SAFETY V VES SHUTDOWN Y
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 +3, -1X*.
APPLY ABILITY:
IIBAE A.
~CT ON:
a 4 b.
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop. into operation.
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 AMENDMENT ND. 47
REACTOR COOLANT SYSTE OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift sett'ing of 2500 psia +3, -1X*.
I d:
ddddd d, d, d
~CTI ON:
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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 3 3/4 4-8 AMENDMENT NO. 47 ~
3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE SAFETY VALVES L'IMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves. shall be OPERABLE with liftsettings as specified in Table 3.7-1.
APPLICABILITY:
MODES 1, 2, 3, and 4*.
ACTION:
With both reactor coolant l'oops and associated steam generators in operation and with one or more** main steam safety valves inoperable per steam generator, operation in MODES 1 and 2 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 all the inoperable valves are restored to OPERABLE status or the Variable Overpower trip setpoint ceiling and the Maximum Allowable Steady State Power Level are reduced per Table 3.7-2; 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.
Operation in MODES 3 and 4* may proceed with at least one reactor coolant loop and associated steam generator in operation, provided that there are no more than four inoperable main steam safety valves associated with the operating steam generator; otherwise, be 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 />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.1.1 No additional. Surveillance Requirements other than those required by Specification 4.0.5.
"Until the steam generators are no longer required for heat removal.
""The maximum number of inoperable safety valves on any operating steam generator is four g).
PALO VERDE " UNIT 3 3/4 7-1
SAF TY VALV P
R OP LIFT SETTING HINIHUH
~INT 0 APAC " ~I a ~
C e.
g.
~SG l~
SGE PSV 554 1250 psig SGE PSV 572 SGE PSV 579 SGE PSV 573 SGE PSV 578 SGE PSV 574 SGE PSV 575 SGE PSV.576 SGE PSV 577 SGE PSV 561 SGE PSV 555 SGE PSV 560 SGE PSV 556 SGE PSV 557 SGE PSV 558 SGE PSV 559 1250 psig 1290 psig 1290 psig 1315 psig 1315 psig 1315 psig 1315 psig 1315 psig.
1315 psig SGE PSV 695 SGE PSV 692 SGE PSV 691...SGE PSV 694 941,543 lb/hr 941,543 lb/hr 971,332 lb/hr 971,332 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/hr 989,950 lb/h1 989,950 lb/hr 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.
PALO VERDE - UNIT 3 3/4 7-2 AMENDMENT NO. 47 0
PLANT SYSTEMS SURVEILLANCE RE UIREHENTS b.
At least once per 18 months during shutdown by:
I.
Verifying that each automatic valve in the flow 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 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 essentia')
auxiliary feedwater pumps delivers at least 650 gpm at 1270 psia or equivalent at the entrance of the steam generator.
d.
The provisions of Specification 4.0.4 are not applicable for entry into NODE 3 or MODE 4 for the turbine-driven pump.
PALO VERDE - UNIT 3 3/4 7-5 AMENDHENT NO. 47
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be OPERABLE with a level of at least 25 feet (300,000 gallons).
APPLICABILITY:
MODES 1, 2, 3,8 and 4"8.
ACTION:
With the condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the CST to OPERABLE status or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or b.
Demonstrate the OPERABILITY of the reactor makeup water tank as a
backup supply to the essential auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or 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 HOT SHUTDOWN with a OPERABLE shutdown cooling loop in operation within the follow-ing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS 0
4.7. 1.3.1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the level (contained water volume) is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7. 1.3.2 The reactor makeup water tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the reactor makeup water tank is the supply source for the essential auxiliary feedwater pumps by verifying:
a.
b.
That the reactor makeup water tank supply line to the auxiliary feedwater system isolation valve is open, and That the reactor makeup water tank contains a water level of at least 26 feet (300,000 gallons).
"Until the steam generators are no longer required for heat removed.
Not applicable when cooldown is in progress.
PALO VERDE - UNIT 3 3(4 7-6
3/4.7 PLANT SYSTEMS BASES 3/4. 7. 1 TURBINE CYCLE 3/4. 7. 1. 1 SAFETY VALVES The OPERABILITY of the main steam safety valves (HSSVs) limit secondary system pressure to within llOX (1397 psia) of the design pressure (1270 psia) during the most severe anticipated operational transient.
For design purposes the valves are sized to pass a minimum of 102K of the RATED THERMAL POWER at 102X of design power.
The adequacy of this relieving capacity is demonstrated by maintaining the Reactor Coolant System pressure below NRC acceptance criteria (120K of design pressure for large feedwater line breaks, CEA ejection and 110K of design pressure for all overpressurization events).
The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASHE Boiler and Pressure Vessel
- Code, 1974 Edition including the Summer 1975 Addenda.
The total relieving capacity for all twenty HSSVs at llOX of system design pressure (adjusted for 50 psi pressure drop to valves inlet) is 19.44 x 10 ibm/hr.
This capacity is less than the total'ated capacity as the MSSVs are operating at an inlet pres-sure below rated conditions.
At these same secondary pressure conditions, the total steam flow at 102'2X uncertainty) of 3817 HWt (RATED THERYAL POWER plus 17 MWt pump heat input) is-17.83 x 10 ibm/hr, The ratio of this total steam flow to the total capacity is 109.2L.
STARTUP and/or POWER OPERATION is allowable with MSSVs inoperable if the maximum allowable power level is reduced to a value equal to the product of the ratio of the number of MSSVs available per steam generator to the total number of MSSVs per steam generator with the ratio of the total steam flow to available relieving capacity.
Allowable Power Level = (
) x 109.2 10-N 10 The ceiling on the variable over power reactor trip is also reduced to an amount over the allowable power level equal to the BAND given for this trip in Table 2.2-1.
SP = Allowable Power Level + 9.8 where:
=. SP I
reduced reactor trip setpoint in percent of RATED THERMAL POWER.
This is a ratio of the available relieving capacity over the total steam flow at rated power.
PALO *VERDE - UNIT 3 B 3/4 7-1
AN YST M
BASES I0 a
N 109.2 9.8 tl d) total number of secondary safety valves for one steaa generator.
number of inoperable main steam safety valves on the steam generator with the greater number of inoperable valves.
ratio of main steam safety valve relieving capacity of 110X steam generator design pressure to calculated steam flow rate at 100X plant power + 2X uncertainty (see above text)
BAND between the maximum thermal power.
and the variable over power trip setpoint ceiling 3 4.7.1.2 AUXILIARY FEEDWATER SYST H
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 event of-a total loss-of-offsite power.
Each electric-driven auxiliary feedwater pump is capable of delivering a
minimum feedwater flow of 650 gpm at a pressure of 1270 psia at the entrance of the steam generators.
The steam-driven auxiliary feedwater pump is capable of delivering a minimum feedwater flow of 650 gpm at a pressure of 1270 psia at 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.
.3 CON NSATE STORAG T
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 concurrent total loss-of-site power.
The contained 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 AMENNENT NO. 47