ML17303B153
| ML17303B153 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/20/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17303B152 | List: |
| References | |
| NUDOCS 8806020209 | |
| Download: ML17303B153 (24) | |
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. 34 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated April 8, 1988, 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 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 comIIon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Specifi-cations 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:
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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
34, 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:
Change to the Technical Specifications Date of Issuance:
May 20, 1988 George
. Knigh
, Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
f'I
May 20, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
34 TO FACILITY OPERATING LICENSE NO.
NPF-~1 DOCKET NO.
STN 50-528 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of chanoe.
Also to be replaced is the following overleaf page to the amended page.
Amendment Pa e
5-5 Overleaf Pa e
5-6
V J
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel or by vacancies may be made if justified by a cycle specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.
Each burnable poison rod shall have a nominal active poison length of 136 inches.
The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.05 weight percent U-235.*
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.
5 4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1
'a ~
b.
c ~
The Reactor Coolant System is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, For a pressure of 2500 psia, and For a temperature of 650'F, except for the pressurizer which is 700 F
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900
+ 300/-0 cubic feet at a nominal T
of 593 F.
"No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored in a high density mode in the spent fuel storage facility.
PALO VERDE " UNIT 1 AMENDMENT NO.
34
DESIGN FEATURES
- 5. 5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown. on Figure 5.1-1.
t 5.6 FUEL STORAGE
- 5. 6. 1 CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k equivalent to less than or equal to 0.95 when flooded with unb8Gted water, which includes a conservative allowance of 2.6X delta klk for uncertainties as described in Section 9.1 of the FSAR.
b.
A nominal 9.5 inch center to-center distance between. fuel assemblies placed in the storage racks in a high density configuration.
5.6.1.2 The k ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 137 feet - 6 inches.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1329 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Tables 5.7-1 and 5.7-2.
PALO VERDE - UNIT 1
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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. 21 License No. NPF-51 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated April 8, 1988, 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 Authority (licensees),
complies with the standards arid requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I; B.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; 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 COIImission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 a change to the Technical Specifi-cations as indicated in the enclosure to this license amendment, arid paragraph 2.C.(2) of 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.
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:
Change to the Technica'1 Specifications Date of Issuance:
May 20, 1988 George W. Knighton, irector Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
I I
1 I
May 20, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
21 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Also to be replaced is the following overleaf page to the amended page.
Amendment Pa e
5-5 Overleaf Pace 5-6
l
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods con-sisting of Zircaloy-4 or stainless steel or by vacancies may be made if justi-fied by a cycle specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approxi-mately 1950 grams uranium.
Each burnable poison rod shall have a nominal active poison length of 136 inches.
The initial core loading shall have a
maximum enrichment of 3.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrich-ment of 4.05 weight percent U-235."
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4. 1 The Reactor Coolant System is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, b.
C.
For a pressure of 2500 psia, and For a temperature of 650'F, except for the pressurizer which is
/vu l.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is l3,900 + 300/-0 cubic feet at a nominal T
of 593 F.
"No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored in a high density mode in the spent fuel storage facility.
PALO VERDE - UNIT 2 5"5 AMENDMENT NO. 21
DESIGN FEATURES
- 5. 5 HETEOROLOGICAL TOWER LOCATION 5.5. 1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE
-5.6. 1 CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k equ'ivalent to less than or equal to 0.95 when flooded with unblotted water, which includes a conservative allowance of 2.6X delta klk for uncertainties as described in Section
- 9. 1 of the FSAR.
b.
A nominal 9.5 inch center-to-center distance between fuel assemblies placed in the storage racks in a high density configuration.
5.6. 1.2 The k ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 137 feet " 6 inches.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1329 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Tables 5.7-1 and 5.7-2.
PALO VERDE - UNIT 2 5-6
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UNITEDSTATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 5O-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No.
NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated April 8, 1988, 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 CoIIIIission'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 coIIIIon
"=.;--- 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 a change to the Technical Specifi-cations 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:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
8, 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:
Change to the Technical Specifications Date of Issuance:
~8v ~o~
>988 Georg
. Knighto,
Project Directorate Division of Reactor IV, V and Special Director V
Projects - III, Projects
t
> ~
'%I
May 20, 1988 FNCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
8 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.
STN 50-530 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Also to be replaced's the following overleaf page to the amended page.
Amendment Pa e
5-5 Ovet leaf Pa e
5-6
DESIGN FEATURES
- 5. 3 REACTOR *CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods con-sisting of Zircaloy-4 or stainless steel or by vacancies may be made if justi-fied by a cycle specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approxi-mately 1950 grams uranium.
Each burnable poison rod shall have a nominal active poison length of 136 inches.
The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrich-ment of 4.05 weight percent U-235."
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5,4. 1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, b.
For a pressure of 2500 psia, and c.
~~"
a t mperature of 650~F, except for the pressurizer which is 700 F
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900
+ 300/-0 cubic feet at a nominal T
of 593 F.
"No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored'in a high density mode in the spent fuel storage facility.
PALO VERDE " UNIT 3 5-5 AMENDMENT NO. 8
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5. 1-1.
5.6 FUEL STORAGE
- 5. 6. 1 CRITICALITY 5.6. l. 1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k equivalent to less than or equal to 0.95 when flooded with unb80ted water, which includes a conservative allowance of 2.6X delta k/k for uncertainties as described in Section
- 9. 1 of the FSAR.
b.
A nominal 9.5 inch center-to-center distance between fuel assemblies placed in the storage racks in a high density configuration.
5.6.1.2 The k ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE
'.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 137 feet -
- 6. inches.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1329 fuel assemblies'.
7 COMPONENT CYCLIC OR TRANSIENT LIMITS
- 5. 7. 1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Tables 5.7-1 and 5.7-2.
PALO VERDE - UNIT 3 5-6