ML17305A531
| ML17305A531 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  (NPF-41-A-046, NPF-41-A-46, NPF-51-A-033, NPF-51-A-33, NPF-74-A-021, NPF-74-A-21) |
| Issue date: | 02/13/1990 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17305A532 | List: |
| References | |
| NUDOCS 9002220588 | |
| Download: ML17305A531 (36) | |
Text
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UNITEDSTATES 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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated October 24, 1989 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 Water 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 the 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 Facility Operating License No.
NPF-41 is hereby amended to read as follows:
90Q22205SB 9002'1'3 PDR ADOCK 0500052S P
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. q6, 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.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Charles M. Trammell, Acting Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation Date of Issuance:
February 13, 1990
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ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 46 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 Pa es 3/4 3-3 3/4 3-4 3/4 3-8 Insert Pa es 3/4 3-3 3/4 3-4 3/4 3-8
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FUNCTIONAL UNIT 1.
TRIP GENERATION TABLE 3.3-1 RFACTOR PROTFCTI Vf:. If!STRUfiENTATION MIN IMUt~
TOfAL NO.
CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES ACTION A.
f'rocess 1.
Pressurizer Pressure
- High 2.
Pressurizer Pressure
- Low 3.
Steam Generator Level - Low 4.
Steam Generator Level - leigh 5.
Steam Generator Pressure
- Low 6.
Containment Pressure
- Higl 7.
Reactor Coolant Flow - Low 8.
Local Power Density - fligh 9.
DNBR - Low B.
Excore Neutron Flux 4/SG 4/SG 4/SG 4/SG 4
4 2
? (b) 2/SG 2/SG 2/SG 2
2/SC 2 (c)(d)
" (c)(d) 3/SG 3/SG 3/SG 3
3/SG 3
1, 2
1, 2
1, 2
1, 2
]
2 3*
1,?
1, 2
1, 2
1,?
3¹ 2¹ 3¹ 2¹ 3¹ 2¹ 3¹ 4*
?¹
~¹ 2¹ 3¹
.¹
¹ P ~C ~
Variable Overpower Trip Logarithmic Power Level - Hioh a.
Startup and Operating b.
Shutdown 2 (a)(d) 2 3
C 1,
2 1,
2 3*
4*
5*
3, 4, 5
2¹
~¹ 9
4 C.
Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators 1
? (e) 2 (c)(d) 3 1,
2 I,
2 6~
7 2", 3',
7
(
Pl C7m FUNICTIOKAL UNIT TOPI.F.'.3-1 (Continued)
REACTOR PPOTECTJVE INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS Ck'.AKKELS OF CHANNELS TO TRIP OPERABLE APPLICABLE MODES ACTION D.
Supplementary Protection S>>stem Pressurizer Pressure
- High II.
RPS LOGIC A.
Matrix Logic B.
Initiation Logic III. RPS ACTUATION DEVICES A.
Reactor Trip Breaker 8.
Manual Trip 4 (f) 4 (f) 4 (f) 4 (f) 4 (f)
,2 2
1, 2
1, 2
1 3*
4*
5*
9 1,
2 5
3*
4*
5*
Q 1 j 2
5 3*
4*
5*
Q 1,
2 5
3*
4*
5*
m C7 Pl C)
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TABLE 3.3-1 Continued ACTION STATEMENTS 2.
Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
a)
All full-length and part-length CEA groups are withdrawn to and subsequently maintained at the "Full Out" position, except during surveillance testing pursuant to the requirements of Specifica-tion 4.1.3.1.2 or for control when CEA group 5
may be inserted no further than 127.5 inches withdrawn.
b) c)
The "RSPT/CEAC Inoperable" addressable constant in the CPCs is set to be indicated that both CEAC's are inoperable.
The Control Element Drive Mechanism Control System (CEDMCS) is placed in and subsequently maintained in the "Standby" mode except during CEA group 5 motion permitted by a) above, when the CEDMCS may be operated in either the "Manual Group" or "Manual Individual" mode.
ACTION 7 ACTION 8 ACTION 9 3.
At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all full-length and part-length CEAs are verified fully withdrawn except during surveillance testing pursuant to Specification
- 4. 1.3. 1.2 or during insertion of CEA group 5 as permitted by 2.a) above, then verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the inserted CEAs are aligned within 6.6 inches (indicated position) of all other CEAs in its group.
With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a
CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
PALO VERDE - UNIT 1
3/4 3-8 AMENDMENT NO. 46
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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.
33 License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated October 24, 1989 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 ItIexico, Los Angeles Department of Water and Power, and Southern Cal,ifornia 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 the 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 Facility Operating License No.
NPF-51 is hereby amended to read as follows:
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~
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shall operate the faci lity 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
Enclosure:
Changes to the Technical Specifications Charles M. Trammell, Acting Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation Date of Issuance:
February 13, 1990
~
~
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
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 Pa es 3/4 3-3 3/4 3-4 3/4 3-8 Insert Pa es 3/4 3-3 3/4 3-4 3/4 3-8
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TABLE 3.3-1 FUNCTIONAL UNIT I.
TRIP GENERATION A.
Process 1.
Pressurizer Pressure
- High 4
2.
Pressurizer Pressure
- Low 4
3.
Steam Generator Level - Low 4/SG 4.
Steam Generator Level - High 4/SG 5.
Steam Generator Pressure
- Low 4/SG 6.
Containment Pressure - High 4
7.
Reactor Coolant Flow - Low 4/SG 8.
Local Power Density - High 4
9.
DNBR - Low 4
B.
Excore Neut'ron Flux 2
3 2 (b) 2/SG 3/SG 2/SG 3/SG 2/SG 3/SG 2
3 2/SG 3/SG 2 (c)(d) 3 2 (c)(d) 3 1,
2 1,. 2 1,
2 1,
2
]
2 3*
4*
1 $
2 1,
2 1;
2 1,
2 REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES ACTION 2¹ 3¹ 2¹ 3¹ 2¹ 3¹ 2¹ 2¹ 2¹ l.
Variable Overpower Trip 2.
Logarithmic Power Level - High a.
Startup and Operating b.
Shutdown-2 (a)(d) 3 2
3 0
2 1,
2 1 $
2 3*
4*
5*
3, 4, 5
2¹ 3¹ 2¹ 9
4 C.
Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators 1
2 (c)(d) 2 (e) 3 1,
2 1,
2 6~
7 2', 3¹,
7
TABLE 3.3-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION FUNCTIONAL UNIT D.
Supplementary Protection System Pressurizer Pressure
- High II. RPS LOGIC TOTAL NO.
OF CHANNELS 4 (f)
CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES 1,
2 ACTION A.
Matrix Logic B.
Initi ation Logic 1,
2 1
3*
4*
5*
9 1,
2 5
3*
4*
5*
B III.
RPS ACTUATION DEVICES A.
Reactor Trip Breaker B.
Manual Trip 4 (f) 4 (f) 4 (f) 4 (f) 1, 2
5 3*
4*
5*
Q 1,
2 5
3*
4*
5*
Q m
C7
0
ACTION 7 ACTION 8 ACTION 9 TABLE 3.3-1 (Continued REACTOR PROTECTIVE INSTRUMENTATION ACTION STATEMENTS 2.
Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
a)
All full-length and part-length CEA groups are withdrawn to and subsequently maintained at the "Full Out" position, except during surveillance testing pursuant to the requirements of Specifica-tion 4.1.3.1.2 or for control when CEA group 5
may be inserted no further than 127.5 inches withdrawn.
b)
The "RSPT/CEAC Inoperable" addressable constant in the CPCs is set to indicate that both CEACs are inoperable.
c)
The Control Element Drive Mechanism Control System (CEDMCS) is placed in and subsequently maintained in the "Standby" mode except during CEA group 5 motion permitted by a) above, when the CEDMCS may be operated in either the Manual Group" or "Manual Individual" mode.
3.
At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all full-length and part-length CEAs are verified fully withdrawn except during surveillance testing pursuant to Specification
- 4. 1.3.1.2 or during insertion of CEA group 5 as permitted by 2.a)
- above, then verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the inserted CEAs are aligned within 6.6 inches (indicated position) of all other CEAs in its group.
With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a
CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the number of OPERABLE channels one less than the Yiinimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
PALO VERDE - UNIT 2 3/4 3-8 AMENDMENT NO.
33
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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.
21 License No. NPF-74 1.
The Nuclear Regulatory Commission (the Commission),has found that:
A.
The application for amendment, dated October 24, 1989 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 Mater and Power, and Southern California Public Power Author ity
( 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 the 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 Facility Operating License No.
NPF-74 is hereby amended to read as follows:
1 I
~i
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 21, 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.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications M4 ap. ~~~)M~
Charles M. Trammell, Acting Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation Date of Issuance:
Febr uary 13, 1990
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- ~
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 21 TO FACILITY OPERATING LICENSE NO.
NPF-74 DOCKET 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.
Remove Pa es 3/4 3-3 3/4 3-4 3/4 3-8 Insert Pa es 3/4 3-3 3/4 3-4 3/4 3-8
4
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.TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION O
C7m FUNCTIONAL UNIT I.
TRIP GENERATION c
A.
Process TOTAL NO.
OF CHANNELS 3.
Steam Generator Level - Low 4.
Steam Generator Level - High 5.
Steam Generator Pressure
- Low 6.
Containment Pressure
- High 7.
Reactor Coolant Flow - Low 8.
Local Power Density - High 9.
DNBR - Low B.
Excore Neutron Flux 4/SG 4/SG 4/SG 4
4/SG 4
4 1.
Pressurizer Pressure
- High 4
2.
Pressurizer Pressure - Low 4
CHANNELS TO TRIP 2
3 2 (b) 2/SG 3/SG 2/SG 3/SG 2/SG 3/SG 2
3 2/SG 3/SG 2 (c)(d) 3 2 (c)(d) 3 1,
2 1,. 2 1,
2 1,
2 3*
4*
1, 2
1, 2
1, 2
1, 2
2¹ 3¹ 2¹ 3¹ 2¹ 3¹ 2¹ 3¹ 2¹ 2¹ 3¹ 3¹ MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION lTl C7 fTI 2.
Variable Overpower Trip Logarithmic Power Level - High a.
Startup and Operating b.
Shutdown C.
Core Protection Calculator System 1.
CEA Calculators 2.
Core Protection Calculators 2 (a)(d) 3 2
3 0
2' 2 (e) 2 (c)(d) 3 1,
2 1,
2 3*
4*
5*
3, 4, 5
1, 2
1, 2
2¹ 2¹ 9
4 6,
7 3¹
r ( y t'
TABLE 3.3-1 (Continued)
(
CTl Pl FUNCTIONAL UNIT REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES ACTION D.
Supplementary Protection System Pressurizer Pressure
- High II. RPS LOGIC.
A.
Matrix Logic B.
Initiation Logic III.
RPS ACTUATION DEVICES A.
Reactor Trip Breaker B.
Manual Trip 4 (f) 4 (~)
4 (f) 4 (V) 4 (Z) 1, 2
1, 2
1 3*
4*
5*
9 1 j 2 5
3*
4*
5*
Q 1,
2 5
3*
4*
5*
B 1,
2 5
3*
4*
5*
B m
CD m
C CD
I
ACTION 7 ACTION 8 TABLE 3.3-1 Continued REACTOR PROTECTIVE INSTRUMENTATION ACTION STATEMENTS 1.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the DNBR margin required by Specifica-tion 3.2.4b (COLSS in service) or 3.2.4d (COLSS out of service) is satisfied and the Reactor Power Cutback System is disabled, and 2.
Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
a)
All full-length and part-length CEA groups must be withdrawn within the limits of Specifica-tions 3. 1.3.5, 3.1.3.6b, and 3. 1.3.7b, except during surveillance testing pursuant to the requirements of Specification 4. 1.3. 1.2.
Specifi-cation 3.1.3.6b allows CEA Group 5 insertion to no further than 127.5 inches withdrawn.
b)
The "RSPT/CEAC Inoperable" addressable constant in the CPCs is set to indicate that both CEAC's are inoperable.
c)
The Control Element Drive Mechanism Control System (CEDMCS) is placed in and subsequently maintained in the "Standby" mode except during CEA motion permitted by Specifications
- 3. 1.3.5,
- 3. 1.3.6b and 3. 1.3.7b, when the CEDMCS may be operated in either the "Manual Group" or "Manual Individual" mode.
3.
CEA position surveillance must meet the requirements of Specifications 4.1.3.1. 1, 4. 1.3.5, 4.1.3.6 and 4.1.3.7 except during surveillance testing pursuant to Specification 4.1.3.1.2.
With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a
CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.
ACTION 9 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to=OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
PALO VERDE - UNIT 3 3/4 3-8 AMENDMENT NO.
21
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