ML16004A013
| ML16004A013 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/19/2016 |
| From: | Watford M Plant Licensing Branch IV |
| To: | Edington R Arizona Public Service Co |
| Watford M | |
| References | |
| CAC MF5810, CAC MF5811, CAC MF5812 | |
| Download: ML16004A013 (27) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 19, 2016 Mr. Randall K. Edington Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - ISSUANCE OF AMENDMENTS RE: ADOPTION OF TSTF-439-A, "ELIMINATE SECOND COMPLETION TIMES LIMITING TIME FROM DISCOVERY OF FAILURE TO MEET AN LCO [LIMITING CONDITION OF OPERATION]" (CAC NOS. MF5810, MF5811, AND MF5812)
Dear Mr. Edington:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 197 to Renewed Facility Operating License No. NPF-41, Amendment No. 197 to Renewed Facility Operating License No. NPF-51, and Amendment No. 197 to Renewed Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 27, 2015, as supplemented by letter dated January 19, 2016.
The amendments revise TS 1.3, "Completion Times, TS 3.7.5, "Auxiliary Feedwater (AFW)
System," TS 3.8.1, "AC [Alternating Current] Sources - Operating," and TS 3.8.9, "Distribution Systems - Operating," by eliminating the second Completion Time in accordance with TS Task Force (TSTF)-439-A, Revision 2, "Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO [Limiting Condition for Operation]."
R. Edington A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
~~a:/t{Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 197 to NPF-41
- 2. Amendment No. 197 to NPF-51
- 3. Amendment No. 197 to NPF-74
- 4. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 197 License No. NPF-41
- 1. 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 February 27, 2015, as supplemented by letter dated January 19, 2016, 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.
Enclosure 1
- 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 Renewed Facility Operating License No. NPF-41 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, 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 shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. NPF-41 and Technical Specifications Date of Issuance: February 19, 2016
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 197 License No. NPF-51
- 1. 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 February 27, 2015, as supplemented by letter dated January 19, 2016, 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.
Enclosure 2
- 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 Renewed Facility Operating License No. NPF-51 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, 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 shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. NPF-51 and Technical Specifications Date of Issuance: February 19, 2016
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 197 License No. NPF-74
- 1. 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 February 27, 2015, as supplemented by letter dated January 19, 2016, 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.
Enclosure 3
- 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 Renewed Facility Operating License No. NPF-74 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, 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 shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. NPF-74 and Technical Specifications Date of Issuance: February 19, 201 6
ATTACHMENT TO LICENSE AMENDMENT NOS. 197, 197 AND 197 RENEWED FACILITY OPERATING LICENSE NOS. NPF-41. NPF-51. AND NPF-74 DOCKET NOS. STN 50-528. STN 50-529. AND STN 50-530 Replace the following pages of the Renewed Facility Operating Licenses Nos. NPF-41, NPF-51, and NPF-74, and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License No. NPF-41 REMOVE INSERT 5 5 Renewed Facility Operating License No. NPF-51 REMOVE INSERT 6 6 Renewed Facility Operating License No. NPF-74 REMOVE INSERT 4 4 Technical Specifications REMOVE INSERT 1.3-2 1.3-2 1.3-6 1.3-6 1.3-7 1.3-7 3.7.5-1 3.7.5-1 3.8.1-2 3.8.1-2 3.8.1-3 3.8.1-3 3.8.9-1 3.8.9-1 3.8.9-2 3.8.9-2
(1) Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power), in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed operating 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) Antitrust Conditions This renewed operating license is subject to the antitrust conditions delineated in Appendix C to this renewed license.
(4) Operating Staff Experience Requirements Deleted (5) Post-Fuel-Loading Initial Test Program (Section 14, SER and SSER 2)*
Deleted (6) Environmental Qualification Deleted (7) Fire Protection Program APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed Facility Operating License No. NPF-41 Amendment No. 197
(1) Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed operating 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) Antitrust Conditions This renewed operating license is subject to the antitrust conditions delineated in Appendix C to this renewed operating license.
(4) Operating Staff Experience Requirements (Section 13.1.2, SSER 9)*
Deleted (5) Initial Test Program (Section 14. SER and SSER 2)
Deleted (6) Fire Protection Program APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(7) lnservice Inspection Program (Sections 5.2.4 and 6.6, SER and SSER 9)
Deleted
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed Facility Operating License No. NPF-51 Amendment No. 197
(4) Pursuant to the Act and 10 CFR Part 30, 40, and 70, APS to receive, possess, and use in amounts required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, APS to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power), in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed operating 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) Antitrust Conditions This renewed operating license is subject to the antitrust conditions delineated in Appendix C to this renewed operating license.
(4) Initial Test Program (Section 14, SER and SSER 2)
Deleted (5) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 171, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Additional Conditions.
Renewed Facility Operating License No. NPF-74 Amendment No. 197
Completion Times 1.3 1.3 Completion Times DESCRIPTION However. when a subsequent train. subsystem. component. or (continued) variable expressed in the Condition is discovered to be inoperable or not within limits. the Completion Time(s) may be extended. To apply this Completion Time extension. two criteria must first be met. The subsequent inoperability:
- a. Must exist concurrent with the first inoperability:
and
- b. Must remain inoperable or not within limits after the first inoperability is resolved.
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:
- a. The stated Completion Time. as measured from the initial entry into the Condition. plus an additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: or
- b. The stated Completion Time as measured from discovery of the subsequent inoperability.
The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train.
subsystem. component. or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e ..
"once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />." where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . . " I (continued)
PALO VERDE UNITS 1.2.3 1. 3-2 AMENDMENT NO. -+/-+7197
Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1. 3-3 (continued)
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X train train to OPERABLE inoperable. status.
B. One 8.1 Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function Y Function Y train train to OPERABLE inoperable. status.
C. One C. l Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function X Function X train train to OPERABLE inoperable. status.
-AND -OR One C.2 Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function Y Function Y train train to OPERABLE inoperable. status.
(continued)
PALO VERDE UNITS 1.2.3 1. 3-6 AMENDMENT NO. W 197
Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)
When one Function X train and one Function Y train are inoperable. Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e .. the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time. Conditions B and C are exited. If the Completion Time for Required Action A.l has not expired.
operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e ..
initial entry into Condition A).
It is possible to alternate between Conditions A. B. and c in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However.
doing so would be inconsistent with the basis of the Completion Times. Therefore. there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
(continued)
PALO VERDE UNITS 1.2.3 1.3-7 AMENDMENT NO. ++/--7197
AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCD 3.7.5 Three AFW trains shall be OPERABLE.
NOTE----------------------------
Only one AFW train. which includes a motor driven pump, is required to be OPERABLE in MODE 4.
APPLICABILITY: MODES 1. 2. and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS
NOTE-------------------------------------
LCO 3.0.4.b is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore affected 7 days turbine driven AFW equipment to OPERABLE pump inoperable. status.
-OR
NOTE---------
Only applicable if MODE 2 has not been entered following refueling.
One turbine driven AFW pump inoperable in MODE 3 following refueling.
B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable for reasons OPERABLE status.
other than Condition A in MODE 1. 2. or 3.
(continued)
PALO VERDE UNITS 1.2.3 3.7.5-1 AMENDMENT NO. ~. 197
AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> offsite circuit to OPERABLE status.
B. One DG inoperable. B.1 Perform SR 3.8.1.l 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for the OPERABLE required offsite -AND circuit(s). Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter
-AND B.2 Declare required 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from feature(s) supported discovery of by the inoperable DG Condition B inoperable when its* concurrent with redundant required inoperability of feature(s) is redundant inoperable. required feature(s)
AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DG is not inoperable due to common cause failure.
-OR B.3.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for OPERABLE DG.
-AND (continued)
PALO VERDE UNITS 1'.2.3 3.8.1-2 AMENDMENT NO. +/-64. 197
AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 Restore DG 10 days to OPERABLE status.
C. Two required offsite C.l Declare required 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from circuits inoperable. featureCs) inoperable discovery of when its redundant Condition C required feature(s) concurrent with is inoperable. inoperability of redundant required feature(s)
-AND C.2 Restore one required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> offsite circuit to OPERABLE status.
(continued)
PALO VERDE UNITS 1.2.3 3.8.1-3 AMENDMENT NO. +/-64. 197
Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Train A and Train B AC. DC. and AC vital instrument bus electrical power distribution subsystems shall be OPERABLE.
APPLICABILITY: MODES 1. 2. 3. and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical A.I Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution power distribution subsystem inoperable. subsystem to OPERABLE status.
B. One AC vital B.l Restore AC vital 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> instrument bus instrument bus electrical power electrical power distribution subsystem distribution inoperable. subsystem to OPERABLE status.
(continued)
PALO VERDE UNITS 1.2.3 3.8.9-1 AMENDMENT NO. +/-+/-+ 197
Distribution Systems - Operating 3.8.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. One DC electrical C.1 Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> power distribution power distribution subsystems inoperable. subsystem to OPERABLE status.
D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. -AND D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Two or more inoperable E.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of safety function.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY.
SR 3.8.9.1 Verify correct breaker alignments and In accordance voltage to required AC. DC. and AC vital with the instrument bus electrical power Surveillance distribution subsystems_ Frequency Control Program PALO VERDE UNITS 1.2.3 3.8.9-2 AMENDMENT NO. ~. 197
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 197, 197, AND 197 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-41, NPF-51, AND NPF-74 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530
1.0 INTRODUCTION
By application dated February 27, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15065A031), as supplemented by letter dated January 19, 2016 (ADAMS Accession No. ML16019A368), Arizona Public Service Company (the licensee) requested changes to the Technical Specifications (TSs) for Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. The supplemental letter dated January 19, 2016, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on May 12, 2015 (80 FR 27195).
The proposed changes revise TS 1.3, "Completion Times," TS 3.7.5, "Auxiliary Feedwater (AFW) System," TS 3.8.1, "AC [Alternating Current] Sources - Operating," and TS 3.8.9, "Distribution Systems - Operating," by eliminating the second Completion Time in accordance with TS Task Force (TSTF)-439-A, Revision 2, "Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO [Limiting Condition for Operation]."
2.0 REGULATORY EVALUATION
2.1 System Description 2.1.1 Auxiliary Feedwater System The licensee's TS 3.7.5, "Auxiliary Feedwater (AFW) System," Condition A has a 7-day Completion Time for Required Action A.1 for one inoperable steam supply to a turbine-driven AFW pump in the applicable Mode or one inoperable turbine-driven AFW pump in Mode 3 following refueling. Condition B lists a 72-hour Completion Time for Required Action B.1 for one AFW train inoperable for reasons other than Condition A in Modes 1, 2, or 3. Conditions A and B have a second Completion Time of 10 days from discovery of failure to meet the LCO.
Enclosure 4
Condition C states that if the Required Actions and associated Completion Time of Condition A or B are not met or two AFW trains are inoperable, the plant must be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Condition D has an immediate Completion Time for three AFW trains inoperable in Modes 1, 2, or 3. Condition E has an immediate Completion Time for required AFW train inoperable in Mode 4.
2.1.2 AC Sources - Operating The licensee's TS 3.8.1, "AC Sources - Operating," Condition A has a 72-hour Completion Time for Required Action A.3 for one required offsite circuit inoperable. Condition B has a 10-day Completion Time for Required Action B.4 for one diesel generator inoperable. Both Condition A and Condition B have a second Completion Time of 13 days from discovery of failure to meet the LCO. In order for the second Completion Time to be limiting, entry into and out of Conditions A and B must occur. Condition H Required Actions H.1 and H.2 applies when the Required Actions and associated Completion Time of Conditions A, B, C, D, E, F, or Gare not met and, as a result, the plant must be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
2.1.3 Distribution Systems - Operating The licensee's TS 3.8.9, "Distribution Systems - Operating," Condition A has an 8-hour Completion Time for Required Action A.1 for one AC electrical power distribution subsystem inoperable. Conditions B and C have 2-hour Completion Times for respective Required Actions B.1 and C.1 for one AC vital bus instrument bus electrical power distribution subsystem inoperable (Condition B) or one direct current (DC) electrical power distribution subsystem (Condition C) inoperable. Conditions A, B, and C have a second Completion Time of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet the LCO. Condition E applies if two or more electrical power distribution subsystems are inoperable that result in a loss of safety function thus the corresponding Required Action E.1 specifies LCO 3.0.3 must be entered immediately.
2.2 Proposed TS Changes The amendments revise TS 1.3, "Completion Times," TS 3.7.5, "Auxiliary Feedwater (AFW)
System," TS 3.8.1, "AC Sources - Operating," and TS 3.8.9, "Distribution Systems - Operating."
- TS 1.3: Revision of Example 1.3-3 to eliminate the second Completion Time for Required Actions A.1 and B.1 and to add a discussion that requires administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO.
- TS 3.7.5: Deletion of the second Completion Times from Required Actions A.1, and 8.1, which states, "AND 10 days from discovery of failure to meet the LCO."
- TS 3.8.1: Deletion of the second Completion Time from Required Action A.3 and 8.4 which states, "AND 13 days from discovery of failure to meet LCO.
- TS 3.8.9: Deletion of the second Completion Times from Required Actions A.1, B.1, and C.1 which states, "AND 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO."
2.3 Regulatory Requirements and Guidance Documents The NRC staff reviewed the proposed changes to eliminate TS second Completion Times against the criteria in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 and the precedent established in NUREG-1432, Revision 4, "Standard Technical Specifications, Combustion Engineering Plants," April 2012 (ADAMS Accession No. ML12102A165). Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the license. These TS are derived from the plant safety analyses. In 10 CFR 50.36, the NRC established its regulatory requirements related to the content of the TS, which include (1) safety limits, limiting safety systems settings and control settings, (2) LCOs, (3) surveillance requirements, (4) design features, and (5) administrative controls.
In NUREG-1432, a second Completion Time was included in the STS for certain Required Actions to establish a limit on the maximum time allowed for any combination of Conditions that would result in a single continuous failure to meet the LCO. These Completion Times (henceforth referred to as "second Completion Times") are joined by an "AND" logical connector to the Condition-specific Completion Time and state "X days from discovery of failure to meet the LCO" (where "X" varies by specification). The intent of the second Completion Time was to preclude entry into and out of the Actions for an indefinite period of time without meeting the LCO. The second Completion Time provides a limit on the amount of time that the LCO would not be met for various combinations of Conditions. The TSTF-439, Revision 2, deletes these second Completion Times from the affected Required Actions from the STS.
Section 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and, specifically, 10 CFR 50.65(a)(1), the Maintenance Rule, requires each licensee to monitor the performance or condition of structures, systems, and components (SSCs) against licensee-established goals in a manner sufficient to provide reasonable assurance that the SSCs are capable of fulfilling their intended functions. These goals shall be established commensurate with safety and, where practical, take into account industrywide operating experience. When the performance or condition of an SSC does not meet established goals, appropriate corrective action shall be taken. The effectiveness of these performance and condition monitoring activities, and associated goals and preventive maintenance activities, are evaluated at least every refueling cycle, not to exceed 24 months, per 10 CFR 50.65(a)(3). The goals shall be established commensurate with safety and, where practical, take into account industry-wide operating experience.
By letter dated June 20, 2005 (ADAMS Accession No. ML051860296), the TSTF submitted a proposed change, TSTF-439, Revision 2, to the improved Standard Technical Specifications (STS). The proposed TSTF-439, Revision 2, was approved by the U.S. Nuclear Regulatory Commission (NRC) in a letter dated January 11, 2006 (ADAMS Accession No. ML060120272).
3.0 TECHNICAL EVALUATION
As discussed in Section 2.2 of the safety evaluation, the proposed changes revise Example 1.3-3 to eliminate the second Completion Time and to add a discussion that requires administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. The proposed changes also delete the second Competition Times from TS 3.7.5, 3.8.1, and 3.8.9.
Additional secondary completion times, such as limits on the period of time from discovery of the failure to meet the LCOs discussed above, were specified to prevent repeated entry and exit from alternating TS Required Actions. In its submittal dated February 27, 2015, the licensee stated that it has incorporated an administrative control into the Operations Department procedure 40DP-90P02, "Conduct of Shift Operations," which states, "Alternating between LCO Conditions, in order to allow indefinite continued operation while not meeting the LCO, is not allowed." This administrative control fulfills the requirement of TS Example 1.3-3 to adopt administrative controls to not allow entry into and out of the Required Actions for an indefinite period of time without meeting the LCO.
The NRC staff is not concerned that the deletion of the second Completion Times could result in indefinite operation without restoration of the systems because the 10 CFR 50.65 Maintenance Rule requires licensees to monitor the performance or conditions of SSCs in a manner sufficient to provide reasonable assurances that SSCs are capable of fulfilling their intended functions.
The Maintenance Rule provides a strong disincentive for the licensee's continuing to operate without restoring systems.
The licensee's application stated the following regarding the 10 CFR 50.65 Maintenance Rule:
Under 10 CFR 50.65(a)(4), the risk impact of all inoperable risk-significant equipment is assessed and managed when performing preventative or corrective maintenance. The risk assessments are conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants. Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. The guidance recommends actions to determine that proposed maintenance and activities are acceptable and to plan and conduct them in a manner that controls overall risk by reducing the duration of the conditions that increase risk and minimizing the magnitude of risk increases (establishment of backup success paths or compensatory measures).
This comprehensive program provides greater assurance of safe plant operation than the second Completion Time in the TSs.
NRC staff notes that Regulatory Guide (RG) 1.182 was withdrawn since it was determined that the document (RG 1.182) was redundant due to the inclusion of its subject matter in Revision 3 of RG 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," May 2012.
Withdrawal of RG 1.182 was published in the Federal Register on November 27, 2012
(77 FR 70846). The Federal Register notice also stated that withdrawal of RG 1.182 neither altered any prior or existing licensing commitments based on its use, nor constituted backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and was not otherwise inconsistent with the issue finality provisions in 10 CFR Part 52. In its letter dated January 19, 2016, the licensee clarified that prior references to RG 1.182 in the license amendment request should be assumed to refer to RG 1.160, Revision 3, and NUMARC 93-01, Revision 4A.
In addition, the licensee's application stated the following regarding performance indicators:
Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Petiormance Indicator Guideline, describes the tracking and reporting of performance indicators to support the NRC Reactor Oversight Process (ROP). The NEI document is endorsed by Regulatory Issue Summary 2001-11, Voluntary Submission of Petiormance Indicator Data. Section 2.2 of NEI 99-02 describes the Mitigating Systems Cornerstone including emergency AC Sources and the AFW system. Extended unavailability of these systems due to multiple entries into the Required Actions would affect the NRC evaluation of licensee performance under the ROP.
Prior to the promulgation of 10 CFR 50.65, TSs were the primary rules governing operations, including what equipment must normally be in service, how long equipment can be out of service, compensatory actions, and surveillance testing to demonstrate equipment readiness.
The goal of TSs is to provide adequate assurance of the availability and reliability of equipment needed to prevent, and if necessary mitigate, accidents and transients. The Maintenance Rule supports this same goal by requiring a comprehensive process for performance and condition monitoring activities.
As required by 10 CFR 50.65, the licensee assesses and manages the inoperable equipment; however, the rule also considers all inoperable risk-significant equipment. Under the TSs, the Completion Time for one system within an LCO is not generally affected by inoperable equipment in another LCO. However, the second Completion Time influenced the Completion Time for one system based on the condition of another system, but only if the two systems were required by the same LCO.
Plant Maintenance Rule programs implement risk-based configuration management programs that augment the deterministic Completion Times in the TSs. The performance and condition monitoring activities required by 10 CFR 50.65 identify poor maintenance practices that would result from multiple entries into the Actions of the TSs which would contribute to unacceptable unavailability of these SSCs.
Based on the above, the NRC staff concludes that multiple continuous entries into TS Conditions, without meeting the LCO, will be adequately controlled by (1) the licensee's administrative controls (operation procedures, etc.), (2) the configuration risk management programs, as implemented to meet the requirements of the Maintenance Rule to assess and manage risk and performance indicators, and (3) the requirements of Section 1.3 of the TS, "Completion Times." In addition, the NRC staff concludes the Maintenance Rule provides adequate assurance against inappropriate use of combinations of TS Conditions that result in a single contiguous occurrence of failing to meet the LCO. Accordingly, consistent with
TSTF-439-A, the NRC staff concludes that the proposed changes to the Palo Verde TS to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on May 12, 2015 (80 FR 27195). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Caroline E. Tilton Date: February 19, 2016
R. Edington A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRA/
Margaret M. Watford, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 197 to NPF-41
- 2. Amendment No. 197 to NPF-51
- 3. Amendment No. 197 to NPF-74
- 4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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