ML17306A554
| ML17306A554 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/02/1992 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17306A555 | List: |
| References | |
| NUDOCS 9203190120 | |
| Download: ML17306A554 (48) | |
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UNITEDSTATES NUCLEAR REGLILATORYCOMMISSION 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.
57 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 28,
- 1991, as supplemented November 27,
- 1991, 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; CD 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 ED 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-41 is hereby amended to read as follows:
9203190120 920302 l t PDR ADOCK 05000528 P
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l (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, 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 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:
March 2, 1992
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
57 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 Insert XXII 3/4 7-21 3/4 7-22 XXII 3/4 7-21 3/4 7-22 3/4 7-25a 3/4 7-25b
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LIST OF TABLES INDEX
- 3. 7-2 4.7-1
- 4. 7-2
- 4. 8-1
- 3. 8-1
- 4. 8-2
- 3. 8-2
- 3. 8"3 MAXIMUM ALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES...........
SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.............................
SNUBBER VISUAL INSPECTION INTERVAL......
DIESEL GENERATOR TEST SCHEDULE..........................
D.C.
ELECTRICAL SOURCES.................
BATTERY SURVEILLANCE RE(UIREMENTS CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES,.............
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES.......................
PAGE 3/4 7-3 3/4 7"8 3/4 7-25a 3/4 8-7 3/4 8"11 3/4 8"12 3/4 8-19 3/4 8-41
- 4. 11-1 RADIOACTIVE LI(UID WASTE SAMPLING AND ANALYSIS PROGRAM..
3/4 11-2 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS ROGRAM..............................
P 3/4 11-8
- 3. 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........
3/4 12-3
- 3. 12"2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES...........
3/4 12-7 4.12"1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS ~
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B 3/4.4-1 REACTOR VESSEL TOUGHNESS..............
3/4 12-8 B 3/4 4-8
- 5. 7-1
- 5. 7-2
- 6. 2-1 PRESSURIZER SPRAY NOZZLE USAGE FACTOR...................
MINIMUM SHIFT CREW COMPOSITION..........................
5-9 6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS...,.................
5-7 PALO VERDE - UNIT 1 XXII AMENDMENT NO.
57
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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.
APPLICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
Mith 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.
~Stb 7
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 PALO VERDE - UNIT 1 3/4 7-21 AMENDMENT NO. 57
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued c.
Visual Ins ection Acce tance Criteria Visual inspections, shall verify that:
(1) there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclas-sified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specifications 4.7.9f.
When a fluid port of a hydraulic snubber is found to be.
uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing unless the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direction.
d.
Transient Event Ins ection An inspection shall be performed of all hydraulic and mechanical snub-bers attached to sections of systems that have experienced unexpec-ted, potentially damaging transients as determined from a review of operational data.
A visual inspection of the systems shall be made within 6 months following such an event.
In addition to satisfying PALO VERDE - UNIT 1 3/4 7"22 AMENDMENT NO.
57
I-
TABLE 4.7-2 SNUBBER VISE~ESP IIN INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2) o umn Extend Interval Notes 3 and 6) o umn Repeat Interval (Notes 4 and 6
o umn Reduce Interval (Notes 5 and 6) 80 100 150 200 300 12 13 25 400 500 750 12 20 18 40
'36 48 78 1000 or greater 29 56 109 Note 1:
Note 2:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, and C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
PALO VERDE - UNIT 1 3/4 7-25a AMENDMENT NO. 57
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TABLE 4.7-2 (Continued)
SNUBBE ERVAL Note 3:
Note 4:
Note 5:
Note 6:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval, but not greater than 48 months.
If the number of unacceptable snubbers is equal to or less than the number in Column B, but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C, but greater than the number in Column B,'he next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable,snubbers found during the previous interval and the number in Column B to the difference in the number in Columns B and C.
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
PALO VERDE - UNIT 1 3/4 7-25b AMENDMENT NO.
57
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UNITEDSTATES 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. 44 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 May 28,
- 1991, as supplemented November 27,
- 1991, 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 wi 11 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 ED 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-51 is hereby amended to read as follows:
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'l (2) Technical S ecifications and Environmental Protection Plan 3.
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 and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 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:
March 2, 199P
4 3
1'
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
44 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 Insert XXII 3/4 7-21 3/4 7-22 XXII 3/4 7-21 3/4 7-22 3/4 7-25a 3/4 7-25b
I" Yi 4 t
LIST OF TABLES INDEX 3.7 2 4.7-1
- 4. 7-2
- 4. 8-1
- 3. 8-1
- 4. 8-2
- 3. 8-2 3.8-3 MAXIMUM ALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES......................................
SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.............................
SNUBBER VISUAL INSPECTION INTERVAL......................
DIESEL GENERATOR TEST SCHEDULE..........................
D.C.
ELECTRICAL SOURCES.................................
BATTERY SURVEILLANCE RE(UIREMENTS.......................
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES......................................
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES...................................
PAGE 3/4 7-3 3/4 7-8 3/4 7"25a 3/4 8-7 3/4 8-11 3/4 8-12 3/4 8-19 3/4 8-41
- 4. 11-1
- 4. 11-2 RADIOACTIVE LI(UID WASTE SAMPLING AND ANALYSIS PROGRAM..
3/4 ll"2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM..............................
3/4 11-8
- 3. 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........
3/4 12-3
- 3. 12-2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES..........
3/4 12-7 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS...............................
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B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................
3/4 12"8 B 3/4 4-8 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.....................
5"7
- 5. 7"2
- 6. 2"1 PRESSURIZER SPRAY NOZZLE USAGE FACTOR...................
MINIMUM SHIFT CREW COMPOSITION..........................
5-9 6-5 PALO VERDE - UNIT 2 XXII AMENDMENT NO.
44
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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.
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 the requirements of Specification 4.0.5.
~Stl 7
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 criter ia shall be based upon the previous inspection as interval established by the requirements in effect before Amendment No. 44.
PALO VERDE - UNIT 2 3/4 7-21 AMENDMENT NO". 44
I A,'V
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) c.
Visual Ins ection Acce tance Criteria Visual inspections shall verify that:
(1) there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically suspectible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specifications 4.7.9f.
Mhen a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing unless the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direction.
d.
Transient Event Ins ection An inspection shall be performed of all hydraulic and mechanical snub-bers attached to sections of systems that have experienced unexpec-ted, potentially damaging transients as determined from a review of operational data.
A visual inspection of the systems shall be made within 6 months following such an event.
In addition to satisfying PALO VERDE - UNIT 2 3/4 7-22 AMENDMENT NO.
44
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TABLE 4.7-2 SNUBBER VISEAALENS EC ENTI INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2
Co umn A Extend Interval (Notes 3 and 6
Column B
Repeat Interval Notes 4 and 6) o umn Reduce Interval (Notes 5 and 6) 80 100 150 200 300 12 13 25 400 500 750 12 20 18 24 40 36 78 1000 or greater 29 56 109 Note 1:
Note 2:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, and C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
PALO VERDE - UNIT 2 3/4 7"25a AMENDMENT NO. 44
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TABLE 4.7-2 (Continued)
SNUBBE ERVAL Note 3:
Note 4:
Note 5:
Note 6.
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval, but not greater than 48 months.
If the number of unacceptable snubbers is equal to or less than the number in Column B, but greater than the number in Column A, the next inspection interval shall be same as the previous interval.
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C, but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the number in Columns B and C.
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
PALO VERDE - UNIT 2 3/4 7-25b AMENDMENT NO. 44
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL...p.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERAT NG STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
30 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 May 28,
- 1991, as supplemented November 27,
- 1991, 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:
~
I (2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 30 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.
3.
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 Theodore R.
Quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance:
March 2, 1992
ATTACHMENT TO LICENSE AMENDHENT AMENDMENT NO.
3 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 Insert XXII 3/4 7-21 3/4 7-22 XXII 3/4 7-21 3/4 7-22 3/4 7-25a 3/4 7-25b
~
LIST OF TABLES INDEX 3.7-2
- 4. 7-1
- 4. 7-2
- 4. 8-1
- 3. 8-1
- 4. 8-2
- 3. 8-2
- 3. 8-3 MAXIMUM ALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM......................
SNUBBER VISUAL INSPECTION INTERVAL......................
DIESEL GENERATOR TEST SCHEDULE....................
D. C.
ELECTRICAL SOURCES........................
BATTERY SURVEILLANCE REQUIREMENTS.......................
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES..........................
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES PAGE 3/4 7-3 3/4 7-8 3/4 7-25a 3/4 8-7 3/4 8-11 3/4 8-12
'/4 8-19 3/4 8-41 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM..
3/4 11-2 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS ROGRAM.................................................
P 3/4 11-8
- 3. 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........
3/4 12-3
- 3. 12-2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES......................
3/4 12-7 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS..
B 3/4.4-1 REACTOR VESSEL TOUGHNESS................................
3/4 12"8 B 3/4 4-8
- 5. 7-1
- 5. 7-2
- 6. 2"1 PRESSURIZER SPRAY NOZZLE USAGE FACTOR...................
MINIMUM SHIFT CREW COMPOSITION........
5-9 6-5 COMPONENT CYCLIC OR TRANSIENT LIMITS...................
5-7 PALO VERDE - UNIT 3 XXII AMENDMENT NO. 30
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II
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.
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 the requirements of Specification 4.0.5.
~Sbt 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 established by the requirements in effect before Amendment No.
30.
PALO VERDE " UNIT 3 3/4 7-21 AMENDMENT NO.
30
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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued c.
Visual Ins ection Acce tance Criteria Visual inspections shall verify that:
(1) there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is function-ally tested in the as-found condition and determined OPERABLE per Specifications 4.7.9f.
When a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing unless the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direction.
d.
Transient Event Ins ection An inspection shall be performed of all hydraulic and mechanical snub-bers attached to sections of systems that have experienced unexpec-ted, potentially damaging transients as determined from a review of operational data.
A visual inspection of the systems shall be made within 6 months following such an event.
In addition to satisfying PALO VERDE - UNIT 3 3/4 7-22 AMENDMENT NO.
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TABLE 4.7-2 SNUBBER V!SU TBEUEEEEUN INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2) o umn Extend Interval (Notes 3 and 6
o umn Repeat Interval (Notes 4 and 6
o umn Reduce Interval (Notes 5 and 6) 80 100 150 200 13 300 12 25 400 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
Note 2:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, and C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
PALO VERDE - UNIT 3 3/4 7-25a AMENDMENT NO.
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TABLE 4.7-.2 (Continued)
SNUBBE ERVAL Note 3:
Note 4:
Note 5:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval, but not greater than 48 months.
If the number of unacceptable snubbers is equal to or less than the'umber in Column B, but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C, but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the number in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
PALO VERDE - UNIT 3 3/4 7-25b AMENDMENT NO.
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