ML17310A370
| ML17310A370 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/21/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML17310A371 | List: |
| References | |
| NUDOCS 9306300069 | |
| Download: ML17310A370 (24) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 R
ONA PUBLIC S RV C COMPANY T
OCKET NO.
STN 50-5 8 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.71 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 May 20,
- 1993, 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:
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3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, 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, ex'cept where otherwise stated in specific license conditions.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifi.cations Date of Issuance:
brune 21, 1993 Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Offi'ce of Nuclear Reactor Regulation
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TTACHMENT 0
'ICENS D
AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528'eplace 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 7-21 nsert 3/4 7-21
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PLANT SYSTEMS 3 4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
APPLY ABILITY:
EOOEE I, E,
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d systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9g.
on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.*
bb As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment No. 57.
- For functional testing performed during the third refueling outage, the selection of the snubber test samples was not performed in accordance with the requirements of the Specification.
The methodology described in licensee correspondence dated Hay 20, 1993 was used for the sample selections for this testing and adequately demonstrated the operability of the snubber population.
PALO VERDE UNIT 1 3/4 7-21 AMENDMENT NO.~ 71
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UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON. D.C. 20555.0001 RIZONA'.'PUBLIC SERVICE COMPANY T AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
2 AMENDMENT'O FACILITY OPERATING ICENSE Amendment No. 57 License No. NPF-51 1
The Nuclear Regulatory Commission (the Commi'ssion) has found that:
A.
The applicati.on for amendment by the Arizona Public Service Company (APS or the licensee) on behal'f of itself and the Salt River Project Agricultural Improvement and:Power District, El Paso Electric Company, Souther n California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated May 20,
- 1993, 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 regul'ations; 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:
II I
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 57, 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, ex'cept where otherwise stated in specific license conditions.
This license amendment is effective as of the date of issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
brune 2i, igg3 FOR THE NUCLEAR 'REGUL'ATORY COMMISSION
~~ g.2~
Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor.Regulation
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TT CHMENT TO LICENSE AMENDMENT M
DM NT NO. 57'O FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace
.the fol.lowing pages of the Appendix,A Technical Specifications with the enclosed pages.
The revised pages are identified, by amendment number and contain vertical l,ines indicating the areas of change.
'remove 3/4 7-21 Insert 3/4 7-'21
'PLANT SYSTEMS ENUBBER LIMITING CONDITION FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are in-
- stalled, would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9g.
on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and'he requirements of Specifica-tion 4.0.5.*
t As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection as interval established by the requirements in effect before Amendment No. 44.
- For functional testing performed during the fourth refueling outage, the selec-tion of the snubber test samples was not performed in accordance with the requirements of the Specification.
The methodology described in licensee correspondence dated May 20, 1993 was used for the sample selections for this testing and adequately demonstrated the operability of the snubber population.
PALO VERDE UNIT 2 3/4 7-21 AMENDMENT NO. ~ 57
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20555.0001 R ZONA PUBLIC S RVIC COMPANY E
AL'.
OCKET NO.
STN 50-530 A 0 V RDE NUCLEAR GENE TING STATION UNIT NO.
3 AMENDMENT TO. FACILITY OPERATING LICENSE Amendment No; 44 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 Mater and
- Power, and Southern:California Public Power Authority dated May 20,
- 1993, complies with the standards and, requirements of the Atomic Energy Act of 1954,
'as amended (the Act) and the Commission's regula'tions 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'afety 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-74 is hereby amended to read as follows:
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3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
3une 21, 1993 FOR THE. NUCLEAR REGULATORY COMMISSION
~i' g.~
Theodore R. quay, Director Project Directorate V
Divisi'on of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
4l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
44 0
F CILITY 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 3/4 7-21 nsert 3/4 7-21
Ii 0
~TE I6 3 4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7,.9 All hydraulic and mechanical snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only i',their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES I, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9g.
on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.*
As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of. capacity.
b.
Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be.inspected independently according to the schedule determined by Table 4.7-2.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection as established by the requirements in effect before Amendment No. 30.
- For functional testing performed during the third refueling outage, the selection of the snubber test samples was not performed in accordance with the requirements of the Specification.
The methodology described in licensee correspondence dated.
May 20, 1993 was used for the sample selections for this testing and adequately demonstrated the operability of the snubber population.
PALO VERDE UNIT 3 3/4 7-21 AMENDMENT NO. ~
44
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