ML17306A874
| ML17306A874 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/05/1992 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17306A875 | List: |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9208130039 | |
| Download: ML17306A874 (30) | |
Text
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+n )f~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555
+208i30039 920805 PDR ADDCK 05000528 P
PDR 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.
63 License No.
NPF-41 The Nuclear Regulatory Commission (the Commission) has found that; A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated June 7,
- 1991, supplemented by letters dated November 20,
- 1991, and April 13,
- 1992, 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; 2.
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-41 is hereby amended to read as follows:
~
~
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 63, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated into this license.
APS shall'perate the facility in accordance with the Technical Specifications and the Environmental Protection. Plan, except where otherwise stated in specific license conditions.
This license amendment is effective as of the date of issuance and must be fully implemented no later -than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, igg2
, Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
0
AMENDMENT NO.
TTACHMENT TO LICENSE AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove 3/4 4-32 3/4 4-33 Insert 3/4 4-32 3/4 4-33
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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.8.3 Both shutdown cooling system (SCS) suction line relief valves with lift settings of less than or equal to 467 psig shall be OPERABLE and aligned to provide overpressure protection for the Reactor Coolant System.
APPLICABILITY:
When the reactor vessel head is installed and the temperature gt t tt ttt td 1
g t
1 tt t
1 t:
a.
214'F during cool down b.
291~F dur ing heatup ACTION:
a ~
b.
C.
With one SCS relief valve inoperable in MODE 4, restore the inoperable valve to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 16 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Do not start a reactor coolant pump if the steam generator water temperature is greater than 100'F above any RCS cold leg temperature.
With one SCS relief valve inoperable in MODES 5 or 6, either (1) restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or (2) reduce T
ld to less than 200'F and, complete depressurization and venting of the RCS through at least a 16 square inch vent(s) within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100'F above any RCS cold leg temperature.
With both SCS relief valves inoperable, reduce T
ld to less than 200 F
- and, depressurize and vent the RCS through a greater than or equal to 16 square inch vent(s) within eight hours.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100 F above any RCS cold leg temperature.
d.
With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
e.
In the event either the SCS suction line relief valves or an RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the SCS suction line relief valves or RCS vent(s) on the transient and any corrective action necessary to prevent recurrence.
f.
The provisions of Specification 3.0.4 are not applicable.
PALO VERDE - UNIT 1 3/4 4"32 AMENDMENT NO.
SP 63
II
!I
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS 4.4.8. 3. 1 Each SCS suction line relief valve shall be verified to be aligned to provide overpressure protection for the RCS at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise verify alignment every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during a.
Cooldown with the RCS temperature less than or equal to 214'F.
b.
Heatup wi.th the RCS temperature less than or equal to 291'F.
4.4.8.3.2 The SCS suction line relief valves shall be verified OPERABLE with the required setpoint at least once per 18 months.
PALO VERDE - UNIT 1 3/4 4-33 AMENDMENT NO.
gg 63
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Vl0ll r+l7 W~*g4 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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No.
NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated June 7,
- 1991, supplemented by letters dated November 20,
- 1991, and April 13,
- 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Part I; B.
The facility will operate in conformity, with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 2.
D.
The issuance of this -amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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:
Ik
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into. this license.
APS shall operate the facility in,accordance with the Technical Specifications and the Environmental Protection
- Plan, except where otherwise stated in specific license, conditions.
This license amendment is effective as of the date of issuance and must-be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, 1992 Theodore R. quay, Director Project Directorate V
Division of Reactor Proj'ects III/IV/V Office of Nuclear Reactor Regulation
41
TTACHMENT TO LICENSE AMENDMENT MENDMENT NO.
4 TO FACILITY OPERATING LICENSE NO.
NPF-51 DOCKET NO.
STN 50-529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove 3/4 4-32 3/4 4-33 Insert 3/4 4-32 3/4 4-33
0 Il
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.8.3 Both shutdown cooling system (SCS) suction line relief valves with lift settings of less than or equal to 467 psig shall be OPERABLE and aligned to provide overpressure protection for the Reactor Coolant System.
APPLICABILITY:
When the reactor vessel head is installed and the temperature R
fth RCS idlg i 1
th 0 1t:
a.
b.
ACTION:
214 F during cooldown 2914F during heatup a.
b.
C.
d.
e.
With one SCS relief valve inoperable in MODE 4, restore the inoperable valve to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 16 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Do not start a reactor coolant pump if the steam generator water temperature is greater than 100 F above any RCS cold leg temperature.
With one SCS relief valve inoperable in MODES 5 or 6, either (1) restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or (2) reduce T
ld to less than 200'F and, complete depressurization and venting of the RCS through at least a 16 square inch vent(s) within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100'F above any RCS cold leg temperature.
With both SCS relief valves inoperable, reduce T
ld to less than 200 F
I and, depressurize and vent the RCS through a greater than or equal to 16 square inch vent(s) within eight hours.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100 F above any RCS cold leg temperature.
With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In the event either the SCS suction line relief valves or an RCS I
vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the SCS suction line relief valves or RCS vent(s) on the transient and any corrective action necessary to prevent recurrence.
The provisions of Specification
- 3. 0.4 are not applicable.
PALO VERDE - UNIT 2 3/4 4-32 AMENDMENT NO.
N, 49
4l
0 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS SURVEILLANCE RE UIREMENTS 4.4.8.3.1 Each SCS suction line relief valve shall be verified. to be aligned to provide overpressure protection for the RCS at least once per 31-days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise verify alignment every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during a.
Cooldown with the RCS temperature less than or equal to 214 F.
b.
Heatup with the RCS temperature less than or equal to 2910F.
4.4. 8.3.2 The SCS suction line relief valves shall be verified OPERABLE with the required setpoint at least once per 18 months.
PALO VERDE - UNIT 2 3/4 4-33 AMENDMENT NO.
N~ 49
II 0
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O Cy Cy ip +y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No.
NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated June 7,
- 1991, supplemented by letters dated November 20,
- 1991, and April 13,
- 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-74 is hereby amended to read as follows:
Ik Ik
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 36, and the Environmental Protection Plan contained'n Appendix B, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection
- Plan, except where otherwise stated in specific'license conditions.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days. from the date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION g.Q ~~
Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, 1992
0
TTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
3 TO FACILITY OPERATING LICENSE NO. NPF-74 OCKET NO.
STN 50-530
'Replace the following pages of the Appendix A Technical Specifications wi,th the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove 3/4 4-32 3/4 4-33 Inser.t 3/4 4-32 3/4 4-33
Ik 1
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.8.3 Both shutdown cooling system (SCS) suction line relief valves with liftsettings of less than or eeual to 467 psig shall be OPERABLE and aligned to provide overpressure protection for the Reactor Coolant System.
APPLICABIL'ITY:
When the reactor vessel head is installed and the temperature 1tg Rtg 1dl g
1 1
tg 1 1t:
a.
214'F during cool down b.
2910F dur ing heatup ACTION:
a.
b.
C.
d.
e.
With one SCS relief valve inoperable in MODE 4, restore the inoperable valve to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 16 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Do not start a reactor coolant pump if the steam enerator water temperature is greater than 100'F above any RCS cold eg temperature.
With one SCS relief valve inoperable in MODES 5 or 6, either (1) restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or (2) reduce Tcold to less than 200'F and, complete depressurization and venting of the RCS through at least a 16 square inch vent(s) within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100 F
above any RCS cold leg temperature.
With both SCS relief valves inoperable, reduce T
ld to less than 200'F and, depressurize and vent the RCS through a greater than or equal to 16 square inch vent(s) within eight hours.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 100'F above any RCS cold leg temperature.
With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, ver>fy the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In the event either the SCS suction line relief valves or an RCS I
vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the SCS suction line relief valves or RCS vent(s) on the transient and any corrective action necessary to prevent recurrence.
f.
The provisions of Specification 3.0.4 are not applicable.
PALO VERDE - UNIT 3 3/4 4-32 AMENDMENT NO.
N, 36
0 l
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS SURVEILLANCE RE UIREMENTS
- 4. 4.8. 3. 1 Each SCS suction line relief valve shall be verified to be aligned to provide overpressure protection for the RCS at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise verify alignment every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during a.
Cooldown with the RCS temperature less than or equal to 214'F.
b.
Heatup with the RCS temperature less than or equal to 291'F.
4.4.8.3.2 The SCS suction line relief valves shall be verified OPERABLE with the required setpoint at least once per 18 months.
PALO VERDE - UNIT 3 3/4 4-33 AMENDMENT NO.
gg 36
0