ML17300A580
| ML17300A580 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/07/1986 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300A581 | List: |
| References | |
| NUDOCS 8610140149 | |
| Download: ML17300A580 (22) | |
Text
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gDR R<GVC'fp UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.
1 AYIENDViENT TO FACILITY OPERATING LICENSE Amendment No. l0 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application f'r amendment, dated July 23, 1986, as supplemented by letters dated August 26 and September 26,
- 1986, by the Arizona Public Service Company (APS) 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 Yexico, Los Angeles Department of 'kiater and Power, and Southern California Public Power Authority (licensees),
complies with the stariaards 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 Act, and the 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; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of the Facility Operating License No.
NPF-41 is hereby amended to read as follows:
8gipg+pi49 000528 861007 PDR ADOCK o PDR P
4 2
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
1O, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY CONYiISSION E. A. Licltra, Project Yianager PWR Project Directorate No.
7 Divis ion of PWR Licens ing-B Encl osure:
Change to the Technical Specifications Date of Issuance:
October 7, 1986
October 7
1986 3
ENCLOSURE TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Also to be replaced are the following overleaf pages to the amended pages.
A~II
~01 P
2-3 2-6 3/4 3-11 2-4 2-5 3/4 3-12
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TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT I ~
TRIP GENERATION A.
Process 1.
Pressurizer Pressure
- High 2.
Pressurizer Pressure
- Low 3.
Steam Generator Level Low 4.
Steam Generator Level High 5.
Steam Generator Pressure Low 6 ~
Containment Pressure
- High 7.
Reactor Coolant Flow -
Low a.
Rate b.
Floor c.
Band 8.
Local Power Density - High 9..
DNBR Low B.
Excore Neutron Flux 1.
Variable Overpower Trip a.
Rate b.
Cei ling c.
Band TRIP SETPOINT
< 2383 psia
> 1837 psia (2)
> 44.2X (4)
< 91.0X (9)
> 919 psia (3)
~ < 3.0 psig
< 0. 115 psi/sec (6)(7)
> 11.9 psid (6)(7)
< 10.0 psid (6)(7)
< 21.0 I<W/ft (5)
> 1;231 (5)
< 10.6X/min of RATED THERMAL POWER (8)
< 110.0X of RATED THERMAL POWER (8)
< 9.8X of RATED THERMAL POWER (8)
ALLOWABLE VALUES
< 2388 psia
> 1822 psia (2)
> 43.VX (4)
< 91.5X (9)
> 912 psia (3) 3.2 pslg
< 0.118 psi/sec (6)(7)
> 11.7 psid(6)(7)
< 10.2 psid (6)(7)
< 21.0 kW/ft (5)
> 1.231 (5)
< 11.0X/min of RATED THERMAL POWER (8)
< 111.(C of RATED THERMAL POWER (8)
< 10.0X of RATED THERMAL POWER (8)
TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT 2.
Logarithmic Power Level.- High (I) a.
Startup and Operating b.
Shutdown TRIP SETPOINT
< 0.798K of RATED THERMAL POWER
< 0. 798X of RATED THERMAL POWER ALLOWABLE VALUES
< 0.895K of RATED THERMAL POWER
< 0.895K of RATED THERMAL POWER C.
I Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators Not Applicabl e Not Applicable Not Applicable Not Applicable D.
Supplementary Protection System Pressurizer Pressure - High II.
RPS LOGIC A.
Matrix Logic B.
Initiation Logic III. RPS ACTUATION DEVICES A.
Reactor Trip Breakers B.
< 2409 psia Not Applicable Not-App1 icabl e Not Applicable Not Applicable
< 2414 psia Not Applicable Not Applicable Not Applicable Not Applicable
TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (1)
Trip may be manually bypassed above 10-~X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10-'X of RATED THERMAL POWER.
(2)
In MODES 3-6, value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.
Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.
(3)
In MODES 3-6, value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(4)
X of the distance between steam generator upper and lower level wide range instrument nozzles.
(5)
As stored within the Core Protection Calculator (CPC).
Calculation of the trip setpoint includes measurement,-calculational and processor uncer-
- tainties, and dynamic allowances.
Trip may be manually bypassed below 1X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 1X of RATED THERMAL POWER.
The approved DNBR limit is 1.231 which includes a partial rod bow penalty compensation.
If the fuel burnup exceeds that for which an increased rod bow penalty is required, the DNBR limit shall be adjusted.
In this case a
DNBR trip setpoint of 1.231 is allowed provided that the difference is com-pensated by an increase in the CPC addressable constant BERR1 as follows:
RB -
RB where BERR1 is the uncompensated value of BERRl; RB is the fuel rod old bow penalty in X DNBR; RB is the fuel rod bow penalty in X DNBR already accounted for in the DNBR limit; POL is the power operating limit; and d (/o POL)/d (I DNBR) is the absolute value of the most adverse derivative of POL with respect to DNBR.
PALO VERDE - UNIT I 2-5
TABLE 2. 2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (Continued)
(6)
RATE is the maximum rate of decrease of the trip setpoint.
There are no restrictions on the rate at which the setpoint can increase.
FLOOR is the minimum value of the trip setpoint.
BAND is the amount by which the trip setpoint is below the input signal unless limited by Rate or Fl oor.
Setpoi nts are based on steam generator differential pressure.
(7 )
The setpo int may be altered to disable trip function during testing pursuant to Spec ificati on 3. 10. 3.
(8)
RATE is the maximum rate of increase of the trip setpoi nt.
There are no restri ctions on the rate at which the setpoi nt can decrease CEILING is the maximum value of the trip setpoi nt.
BAND is the amount by which the trip setpoi nt is above the input s ignal unless limited by the rate or the ceiling.
(9)
X of the di stance between steam generator upper and lower level narrow range instrument nozz 1 es.
PALO VERDE - UNIT 1 Amendment No.
10
TABLE 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT I.
TRIP GENERATION A.
Process
RESPONSE
TIME 1.
2.
3.
4 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.
CEA Positions c.
CEA Positions:
CEAC Penalty Factor DNBR - Low
<1.15 seconds
<1.15 seconds
<1.15 seconds
<1.15 seconds
< 1.15 seconds
< 1.15 seconds
< 0'8 second
<0.75 second"
<1.35 second**
0.75 second""
ah b.
C.
d.
e.f.
g.
Neutron Flux Power from Excore Neutron Detectors CEA Positions Cold Leg Temperature Hot Leg Temperature Primary Coolant Pump Shaft Speed Reactor Coolant Pressure from Pressurizer CEA Positions:
CEAC Penalty Factor
<0.75 second~
<1.35 second"-*
<0.75 second¹¹
<0.75 second¹¹
<0.75 second¹
<0.75 second¹¹¹ 0.75 second"*
B.
Excore Neutron Flux 2.
Variable Overpower Trip 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 INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT
RESPONSE
TIME C.
Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators Supplementary Protection System Pressurizer Pressure
- High Not Applicable Not Applicable
< 1.15 second II.
RPS LOGIC B.
Matrix Logic Initiation Logic Not Applicabl e Not Applicable I II.
RPS ACTUATION DEVICES A.
Reactor Trip Breakers B.
Hanual Trip Not Applicable Not 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.
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.
¹¹Response 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 13 seconds.
Adjustments to the CPC addressable constants given in Table 3.3-2a shall be made to accomodate current values of the RTD time constants.
If the RTD time constant for a CPC channel exceeds the value corresponding to the penalties currently in
- use, the affected channel(s) shall be declared inoperable until penalties appropriate to the new time constant are installed.
¹¹¹Response 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.
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)0 y ~*4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.
2 AMIENDMIENT TO FACILITY OPERATING LICENSE Amendment No.
5 L'icense No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated July 23, 1986, as supplemented by letters dated August 26 and September 26, 1986, by the Arizona Public Service Company (APS) 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 'Rater and Power, and Southern California Public Power Authority (licensees),
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 Act, and the 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; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of the Facility Operating License No. NPF-51 is hereby amended to read as follows:
~
~ (2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
5, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Encl osure:
Change to the Technical Specifications Date of Issuance:
October 7,
1986 E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-B
October 7, 1986 ENCLOSURE TO LICENSE AMENDMENT NO.
5 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.
Also to be replaced are the following overleaf pages to the amended"'pages.
.~Ad P
2-3 2-6 3/4 3-11 Overl ea f Pages 2-4
'-5 3/4 3-12
t
~
r
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT I.
TRIP GENERATION A.
Process 1.
Pressurizer Pressure High 2.
Pressurizer Pressure
- Low 3.
Steam Generator Level Low 4.
Steam Generator Level - High 5.
Steam Generator Pressure
- Low 6.
Containment Pressure
- High 7.
Reactor Coolant Flow - Low a.
Rate b.
Floor c.
Band 8.
Local Power Density - High 9.
DNBR - Low B.
Excore Neutron Flux 1.
Variable Overpower Trip a.
Rate b.
Ceiling c.
Band TRIP SETPOINT
< 2383 psia
> 1837 psia (2)
> 44.2X (4)
< 91.0X (9)
> 919 psia (3)
< 3 0 psig
< 0.115 psi/sec (6)(7)
> 11.9 psid (6)(7)
< 10.0 psid (6)(7)
< 21.0 kW/ft (5)
> 1.231 (5)
< 10.6X/min of RATED THERMAL POWER (8)
< 110.0X of RATED THERMAL POWER (8)
< 9.8X of RATED THERMAL POWER (8)
ALLOWABLE VALUES
< 2388 psia
> 1822 psia (2)
> 43. 7X (4)
< 91.5X (9)
> 912 psia (3)
< 3.2 psig
< 0.118 psi/sec (6)(7)
> 11.7 psid(6)(7)
< 10.2 psid (6)(7)
< 21.0 kW/ft (5)
> 1.231 (5)
< 11.0X/min of RATED THERMAL POWER (8)
< 111.0X of RATED THERMAL POWER (8)
< 10.0X of RATED THERMAL POWER (8)
TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT 2.
Logarithmic Power Level - High (1) a.
Startup and Operating b.
Shutdown 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 Breakers B.
Manual Trip TRIP SETPOINT
< 0.798X of. RATED THERMAL POWER
< 0.798X of RATED THERMAL POWER Not Applicable Not Applicable
< 2409 psia Not Applicable Not Applicable Not Applicable Not Applicable ALLOWABLE VALUES
< 0.895X of RATED THERMAL POWER
< 0.895X of RATED THERMAL POWER Not Applicable Not Applicable
< 2414 psia Not Applicable Not Applicable Not Applicable Not Applicable
P TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (1)
Trip may be manually bypassed above 10-~X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10-iX of RATED THERMAL POWER.
(2)
In MODES 3-4, value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.
Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.
(3)
In MODES 3-4, value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(4)
X of the distance between steam generator upper and lower level wide range instrument nozzles.
(5)
As stored within the Core Protection Calculator (CPC).
Calculation of the trip setpoint includes measurement, calculational and processor uncer-
- tainties, and dynamic allowances.
Trip may be manually bypassed below IX of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 1X of RATED THERMAL POWER.
The approved DNBR limit is 1.231 which includes a partial rod bow penalty compensation.
If the fuel burnup exceeds that for which an increased rod bow penalty is required, the DNBR limit shall be adjusted.
In this case a
DNBR trip setpoint of 1.231 is allowed provided that the difference is com-pensated by an increase in the CPC addressable constant BERR1 as follows:
RB -
RB where BERRl is the uncompensated value of BERR1; RB is the fuel rod old bow penalty in X DNBR; RB is the fuel rod bow penalty in X DNBR already accounted for in the DNBR limit; POL is the power operating limit; and d {X POL)/d {X DNBR) is the absolute value of the most adverse derivative of POL with respect to DNBR.
PALO VERDE - UNIT 2 2-5
TABLE 2. 2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (Continued)
(6)
RATE is the maximum rate of decrease of the trip setpoint.
There are no restrictions on the rate at which the setpoint can increase.
FLOOR is the minimum value of the trip setpoint.
BAND is the amount by which the trip setpoint is below the input signai unless limited by Rate or Floor.
Setpoints are based on steam generator differential pressure.
(7)
The setpoint may be altered to disable trip function during testing pursuant to Specification 3.10.3.
(8)
RATE is the maximum rate of increase of the trip setpoint.
There are no restrictions on the rate at which the setpoint can decrease.
CEILING is the maximum value of the trip setpoint.
BAND is the amount by which the trip setpoint is above the input signal unless limited by the rate or the ceiling.
(9)
X of the distance between steam generator upper and lower level narrow range instrument nozzles.
PALO VERDE - UNIT 2 2"6 Amendment No.
5
TABLE 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT I.
TRIP GENERATION A.
Process Pressur izer Pressure High 2.
3.
5.
Pressurizer Pressure
- Low Steam Generator Level -
Low Steam Generator Level - High Steam Generator Pressure Low Containment Pressure
- High Reactor Coolant Flow Low 6.
7.
9.
b.. CEA Positions c.
CEA Positions:
CEAC Penalty Factor DNBR Low I,
8.. Local Power Density - High a.
Neutron Flux Power from Excore Neutron Detectors
RESPONSE
TIME
< 1.15
< 1.15
< 1.15
< 1.15
< 1.15
< 1.15
< 0.58 seconds seconds seconds seconds seconds seconds second
< 0.75 second"
< 1.35 second*"
< 0.75 second""
a b.
C.
d.
e.f.
g.
Neutron Flux Power from Excore Neutron Detectors CEA Positions Cold Leg Temperature Hot Leg Temperature Primary Coolant Pump Shaft Speed Reactor Coolant Pressure from Pressurizer CEA Positions:
CEAC Penalty Factor
< 0.75
< 1.35
< 0.75
-< 0.75
< 0.75
< 0.75
< 0.75 second" second""
second¹¹ second¹¹ second¹ second¹¹¹ second""
B.
Excore Neutron Flux 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 INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT C.
Core Protection Calculator:System 1.
CEA Calculators Core Protection Calculators D.
Supplementary Protection System Pressurizer Pressure - High
RESPONSE
TIME Not Applicable Not Applicable
< 1.15 second II.
RPS A.
B.
III.
A.
B.
LOOIC Matrix Logic Initiation Logic RPS ACTUATION DEVICES Reactor Trip Breakers Manual Trip Not Applicable Not Applicable Not Applicable Not 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'irst 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.
flhe pulse transmitters measuring pump speed are exempt from response time testing.
The response time shall be measured from the pulse shaper input.
NResponse 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 13 seconds.
Adjustments to the CPC addressable constants given in Table 3.3-2a shall be. made to accommodate current values 'of the RTD time constants.
If.the RTD time constant for a CPC channel.
exceeds the value corresponding to the penalties currently in use, the affected channel'(s) shall be declared inoperable until; penalties appropriate.,to the. new.time constant are installed.
8%Response time shall be measured from the output,of:the pressure transmitter.
The transmitter response time shall be leCs than or"equal to 0.7 second.