ML20148B197
| ML20148B197 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/09/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148B201 | List: |
| References | |
| NUDOCS 8803210379 | |
| Download: ML20148B197 (10) | |
Text
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u UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
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WASHINGTON, D. C. 20555
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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.
License No. NPF-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment, dated September 14, 1987, as revised by letter dated October 1,1987, 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 Californii Public Power Authority (licensees), complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I; 5.
The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Comission; C.
There is reasonable assurance'(1) 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 cor. ducted in compliance with the Comission'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; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requiretrents have been satisfied.
l 050005 9
2.
Accordingly, the license is amended by a change 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:
(2) Technical Specifications and_ Environmental Pg tection Plan The Technical Specifications contained in Appendix A, as revised I
through Amendment No.18, and the Envirorsental 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 NY ff George W ighton,
ector Project Directcrate V Divisien of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Change to the Technical Specifications Date of Issuance: March 9, 1988
Sfarch 9, 1938 6
ENCLOSURE TO LICENSE AMEN 0 MENT AMENDMENT NO.18 TO FACILITY OPERATING LICENSE N0. 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 rumber and contains a vertical line indicating the area of change. Also to be replaced is the following overleaf page to the amended page.
Amendment Page Overleaf Page 5-5 5-6 w
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly containing 236 fuel rods or burnable poison rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 150 inches anu 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 ccie 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 T,EMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the code requirew.ints 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.
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 f 593*F.
avg
- 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 AMEN 0 MENT NO 18
J DESIGN FEATURES 9
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. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with unb8f$tedwater,whichincludesaconservativeallowanceof2.6%
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 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.
Cf.PACITY 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.
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l PALO VERDE - UNIT 2 5-6 l
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'c, UNITED STATES NUCLEAR REGULATORY COMMISSION n
.,i WASHINC TON, D. C. 20555
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ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. NPF-74 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment, dated September 14, 1987, as revised by letter dated October 1,1987, by the Arizona Public Service Company (APS) on behalf of itself ano the Salt River Project Agricultural Improvement and Power District, El Paso Electrfc Company, Southern California Edison Company, Public Service Company of New Mexico, ios Angeles Department of Water and Power, and Southern California Public Power Authority (licensees), complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter It B.
The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities w111 be conducted in ccepliance with the Commission'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; 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.
1 e
. - - - - - - ~ - - - -
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6 2.
Accordingly, the license is amended by a change 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 arenced to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 6. 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 cf the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George [se#1 s.c 4Knightondirector g
't Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
Change to the Technical Specifications Date of Issuance: March 9, 1988 l
l l
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d March 9. 1988 ENCLOSURE TO LICENSE AMEhDMENT AMENDMENT N0. 6 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 a vertical line indicating the area of change. Also to be replaced is the following overleaf page to the amended page.
Arrendment Page Overleaf Page 5-5 5-6 l
1 4
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4 DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly containing 236 fuel rods or burnable poison rods clad with Zircaloy-4.
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.*
l 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.
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,yg of 593'F.
i l
I
- 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. 6
i DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION
'e 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.
Ak equivalent to less than or equal to 0.95 when floeded with unb8f$tedwater,whichincludesaconservativeallowanceof2.6%
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 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elavation 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 nc 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.
O PALO VERDE - UNIT 3 5-6