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{{Adams
#REDIRECT [[IR 05000529/2016009]]
| number = ML17004A044
| issue date = 01/03/2017
| title = NRC Team Inspection Report 05000528/2016009; 05000529/2016009; and 05000530/2016009
| author name = Alexander R D
| author affiliation = NRC/RGN-IV/DRP/RPB-A
| addressee name = Bement R S
| addressee affiliation = Arizona Public Service Co
| docket = 05000528, 05000529, 05000530
| license number = NPF-041, NPF-051, NPF-074
| contact person = Miller G B
| document report number = IR 2016009
| document type = Inspection Report, Letter
| page count = 15
}}
 
{{IR-Nav| site = 05000528 | year = 2016 | report number = 009 }}
 
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD.
 
ARLINGTON, TX 76011-4511 January 3, 2017
 
Mr. Robert 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 - NRC TEAM INSPECTION REPORT 05000528/2016009
; 05000529/2016009; AND 05000530/2016009
 
==Dear Mr. Bement:==
On November 18, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Palo Verde Nuclear Generating Station, Units 1, 2, and 3. On December 30, 2016, the NRC inspectors discussed the results of this inspection with Mr. George Andrews, Director, Nuclear Regulatory Affairs, and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
 
The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA
-12-049 and EA-12-051) and Emergency Preparedness Communication , Staffing, and Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.
 
The NRC inspectors did not identify any findings or violations of more than minor significance associated with this inspection.
 
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
 
Sincerely,/RA/
Geoffrey B. Miller
, Branch Chief Project Branch D Division of Reactor Projects Docket Nos. 50
-528, 50-529, 50-530 License Nos. NPF
-41, NPF-51, NPF-74
 
===Enclosure:===
Inspection Report 05000 528/2016009 05000529/2016009, 05000530/2016009 w/
 
===Attachment:===
Supplemental Information
 
ML17004A04 4 SUNSI Review By: JRG ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE SPE:DRP/A PE:RIII/DRP PE:DRS/IPAT RI:DRP/PV BC:DRP/D NAME RAlexander BBartlett EUribe DReinert GMiller SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ DATE 12/16/16 12/19/16 12/16 /16 12/16/16 12/30/16 Letter to Robert Bement from Geoffrey Miller dated January 3, 2017
 
SUBJECT: PALO VERDE NUCLEAR GENERATING STATION
- NRC TEAM INSPECTION REPORT 05000528/2016009
; 05000529/2016009; AND 05000530/2016009 DISTRIBUTION
: Regional Administrator (Kriss.Kennedy@nrc.gov)
Deputy Regional Administrator (Scott.Morris@nrc.gov)
DRP Director (Troy.Pruett@nrc.gov)
DRP Deputy Director (Ryan.Lantz@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
DRS Deputy Director (Jeff.Clark@nrc.gov)
Senior Resident Inspector (Charles.Peabody@nrc.gov)
Resident Inspector (David.You@nrc.gov)
Resident Inspector (Dustin.Reinert@nrc.gov)
PV Administrative Assistant (Yvonne.Dubay@nrc.gov)
Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov)
Senior Project Engineer, DRP/D (John.Dixon@nrc.gov)
Project Engineer, DRP/D (Brian.Parks@nrc.gov)
Project Engineer, DRP/D (Jan.Tice@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Project Manager (Siva.Lingam@nrc.gov)
Team Leader, DRS/IPAT (Thomas.Hipschman@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
ACES (R4Enforcement.Resource@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Project Engineer, DRS/IPAT (Eduardo.Uribe@nrc.gov)
Senior Congressional Affairs Officer (Jenny.Weil@nrc.gov)
RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)
RIV/ETA: OEDO (Jeremy.Bowen@nrc.gov)
RIV RSLO (Bill.Maier@nrc.gov
) ROPreports Electronic Distribution for Palo Verde Nuclear Generating Station Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000528, 05000529; 05000530 License: NPF-41, NPF-51, NPF-74 Report: 05000528/2016009
; 05000529/2016009; and 05000530/2016009 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Location: 5801 South Wintersburg Road Tonopah, AZ 85354 Dates: November 14
- 18, 2016 Inspectors:
R. Alexander, Sr. Project Engineer (Team Leader)
B. Bartlett, Project Engineer, Region III D. Reinert, PhD, Resident Inspector E. Uribe, Project Engineer Approved By: Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Enclosure
 
=SUMMARY=
IR 05000 528/2016009, 05000529/2016009, and 05000 530/2016009; 11/14/2016 - 11/18/2016; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Temporary Instruction 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi
 
-Unit Dose Assessment Plans issued December 23, 2015.
 
The inspection covered a one week inspection by two inspectors from the Region IV office, one inspector from the Region III office, and one of the assigned resident inspectors. No findings were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process," Revision 5.
 
===A. NRC-Identified and Self-Revealing Findings===
None 
 
===B. Licensee-Identified Violations===
 
None
 
=REPORT DETAILS=
 
4. Other Activities
 
{{a|4OA5}}
==4OA5 Other Activities==
 
(TI 2515/191)
The objective of Temporary Instruction (TI) 2015/191 "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi
-Unit Dose Assessment Plans" is to verify that licensees have adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan (ADAMS Accession No.
 
ML15364A034) and the NRC's plant safety evaluation (ADAMS Accession No. ML16088A261) and to verify that the licensee installed reliable water
-level measurement instrumentation in their spent fuel pools. The purpose of this TI is also to verify the licensees have implemented Emergency Preparedness (EP) enhancements as described in their site
-specific submittals and NRC safety assessments, including multi
-unit dose assessment capability and enhancements to ensure that staffing is sufficient and communications can be maintained during such an event.
 
The inspection verifies that plans for complying with NRC Orders EA 049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond
-Design-Basis External Events (ADAMS Accession No. ML12229A174) and EA 051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12056A044) are in place and are being implemented by the licensee. Additionally, the inspection verifies implementation of staffing and communications information provided in response to the March 12, 2012 request for information letter and multiunit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013 (ADAMS Accession No. ML12339A262).
 
The team discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walk downs to verify that the strategies could be implemented as stated in the licensee's submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the team's inspection activities are described in the following sections.
 
1. Mitigation Strategies for Beyond
-Design-Basis External Events
 
====a. Inspection Scope====
The team examined the licensee's established guidelines and implementing procedures for the beyond
-design-basis mitigation strategies. The team assessed how the licensee coordinated and documented the interface/transition between existing off
-normal and Emergency Operating Procedures with the newly developed mitigation strategies. The team selected a number of mitigation strategies and conducted plant walk downs with licensed operators and responsible plant staff to assess: the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment; and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios.
 
The team verified that a preventive maintenance program had been established for the FLEX portable equipment and that periodic equipment inventories were in place and being conducted. Additionally, the team examined the introductory and planned periodic/refresher training provided to the Operations and Fire Protection staffs most likely to be tasked with implementation of the FLEX mitigation strategies.
 
The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel. Documents reviewed are listed in the attachment.
 
b. Assessment Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA 049. The inspectors verified that the licensee satisfactorily:
Developed and issued FLEX Support Guidelines (FSG) to implement the FLEX strategies for postulated external events
;  Integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs are clear when using existing plant procedures
;  Protected FLEX equipment from site
-specific hazards
;  Developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability
;  Trained their staff to assure personnel proficiency in the mitigation of beyond-design-basis events; and  Developed means to ensure that the necessary off
-site FLEX equipment will be available from off
-site locations
. The inspectors verified that non
-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
 
====c. Findings====
No findings identified.
 
. Spent Fuel Pool (SFP) Instrumentation
 
====a. Inspection Scope====
The team examined the licensee's newly installed spent fuel pool instrumentation. Specifically, the inspectors verified the sensors were installed as described in the plant specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel are physically and electrically separated. Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the attachment.
 
b. Assessment Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the SFP instrumentation as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA 051. The inspectors verified that the licensee satisfactorily:
Installed the SFP instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant specific submittal and safety evaluation
;    Installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittals; and  Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.
 
The inspectors verified that non
-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
 
====c. Findings====
No findings identified.
 
3. Staffing and Communication Request for Information
 
====a. Inspection Scope====
Through discussions with plant staff, review of documentation and plant walk downs, the team verified that the licensee has implemented required changes to staffing, communications equipment and facilities to support an Extended Loss of All AC Power (ELAP) scenario as described in the licensee's staffing assessment and the NRC safety assessment. The team also verified that the licensee has implemented dose assessment (including releases from spent fuel pools) capability using the licensee's site-specific dose assessment software and approach as described in the licensee's dose assessment submittal. Documents reviewed are listed in the attachment.
 
b. Assessment The inspectors reviewed information provided in the licensee's multi
-unit dose submittal and in response to the NRC's March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near
-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that results in an extended loss of all ac power to the site and impedes access to the site.
 
The inspectors verified the following:
Licensee satisfactorily implemented required staffing change(s) to support an ELAP scenario;    Emergency preparedness communications equipment and facilities are sufficient for dealing with an ELAP scenario; and  Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensee's site
-specific dose assessment software and approach.
 
The inspectors verified that non
-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective
 
action program.
 
====c. Findings====
No findings identified.
 
{{a|4OA6}}
==4OA6 Exit Exit Meeting Summary==
 
On November 17, 2016, the inspectors presented the on-site inspection results in a management debrief to Mr. B. Rash, Vice President, Nuclear Engineering, and other members of the site staff. The inspectors completed an exit meeting with                    Mr. G. Andrews, Director, Nuclear Regulatory Affairs, and other members of the site staff, via telephone on December 30 , 2016, who acknowledged the final results of the inspection.
 
The inspectors confirmed that proprietary information was not provided or examined during the inspection.
 
=SUPPLEMENTAL INFORMATION=
 
==KEY POINTS OF CONTACT==
 
===Licensee Personnel===
: [[contact::G. Andrews. Director]], Nuclear Regulatory Affairs
: [[contact::J. Barnes]], Auxiliary Operator
: [[contact::J. Chon]], Manager, Information Technology
: [[contact::S. Dornseif]], Compliance Consultant, Nuclear Regulatory Affairs
: [[contact::G. Eimar]], Manager, Fukushima Initiatives Project
: [[contact::D. Elkinton]], Acting Section Leader, Nuclear Regulatory
Affairs
: [[contact::J. Fearn]], Manager, Emergency Preparedness
: [[contact::K. Foster]], Department Leader, Fire Protection
: [[contact::C. Holland]], Fire Protection Maintenance
: [[contact::P. Hom]], Senior Consultant, Nuclear Regulatory Affairs
: [[contact::D. Horton]], D
epartment Leader, Fire Department
: [[contact::M. Kura]], S
enior Reactor Operator, Operations
: [[contact::A. Martin ]], Auxiliary Operator
: [[contact::M. Powell]], Director, Fukushima Initiatives Project
: [[contact::B. Rash]], Vice President, Nuclear Engineering
: [[contact::C. Siefert ]], Auxiliary Operator
: [[contact::T. Weber]], Department Leader, Nuclear Regulatory Affairs
 
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
 
===Opened and Closed===
 
None     
 
Attachment
 
==LIST OF DOCUMENTS REVIEWED==
Section 4OA5
:
: Other Activities
===Condition Reports===
: 15-11586 16-00512 16-02176 16-05306 16-05637 16-07956 16-07998 16-08135 16-12146 16-12339 16-12892 16-13233 16-13321 16-13600 16-13722 16-14235 16-14780 16-15379 16-15532 16-15535 16-15642 16-17580 16-17768
: 16-18558* 16-18587 16-18588 16-18593* 16-18636* 16-18630* 16-18638* 16-18656* 16-18666* 16-18637* 16-18669* 16-18688* 16-18694* 16-18690* 16-18697* 16-18702* 16-18722* * - indicates condition report written by the licensee as a result of the NRC inspection
===Drawings===
: Number Title Revision 01-P-PCF-0505 Fuel Building Isometric Spent Fuel Pool Make Up Flex
: 02-J-PCE-055 Instrument Loop Wiring Diagram Beyond Design Basis, Spent Fuel Pool
===Procedures===
: Number Title Revision 14DP-0BD01 PVNGS Portable FLEX Equipment Administrative Deployment Strategy
: 81DP-0CC05 Design and Technical Document Control
: 81DP-0EE10 Design Change Process
: 14DP-0BD02 PVNGS FLEX Equipment Status Control
: 14MT-9BD11 FLEX 800kW Diesel Generator Inspections and Tests
: 14MT-9BD51 FLEX RCS Injection Pump (Modes 1
-4) Inspections and Tests 5 14MT-9BD81 FLEX Stored Consumables Items Inspection
: 14MT-9BD99 FLEX Equipment Storage Monthly Walkdown
: 36MT-9FH01 Spent Fuel Pool Instrumentation System Level and Temperature Calibration Check
- Primary 1 36MT-9FH02 Spent Fuel Pool Instrumentation System Level and Temperature Calibration Check
- Alternate 1 
: Attachment
===Drawings===
: Number Title Revision 40EP-9EO01 Standard Post Trip Actions
: 40EP-9EO08 Blackout 23 40ST-9ZZM1 Operations Mode 1 Surveillance Logs
: 73DP-9XI01 Pump and Valve Inservice Testing Program
: 79IS-9ZZ07 PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 5 79IS-9ZZ07 PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 6 79IS-9ZZ07, Appendix A
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - DC Load Shed
: 79IS-9ZZ07 ,
: Appendix C PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Secondary Side Walkdown 6 79IS-9ZZ07 ,
: Appendix D PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Control Room Status of Walkdowns
: 79IS-9ZZ07 ,
: Appendix F PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Temporary Communications Strategy
: 79IS-9ZZ07,
: Appendix H
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Open Door List
: 79IS-9ZZ07,
: Appendix J
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - CST Refill Strategy
: 79IS-9ZZ07,
: Appendix K
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Diesel Fuel Oil Supply
: 79IS-9ZZ07 ,
: Appendix M PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Resetting AFA
-P01 6 79IS-9ZZ07 ,
: Appendix N PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Local Operation of
: AFA-P01 Using Main Steam
: 79IS-9ZZ07 ,
: Appendix O PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - RCS Inventory Addition
: 79IS-9ZZ07 ,
: Appendix P PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - Satellite Phone Use
: 79IS-9ZZ07,
: Appendix Q
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - FLEX AC Power
- 480V, 800kW
: 79IS-9ZZ07,
: Appendix R
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - FLEX Deployment
: 79IS-9ZZ07,
: Appendix S
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - FLEX SG Fill
: Attachment
===Drawings===
: Number Title Revision 79IS-9ZZ07,
: Appendix T
: PVNGS Extended Loss of All Site AC Guideline Modes 1
-4 - SFP Makeup
: 79IS-9ZZ08 PVNGS Extended Loss of All Site AC Guideline Modes 5, 6, and Defueled
: 79IS-9ZZ08,
: Appendix L
: PVNGS Extended Loss of All Site AC Guideline Modes 5, 6, and Defueled
- SFP Makeup
: 13-NS-A116 Engineering Guide to NRC Post Fukushima Requirements
===Work Orders===
: 4567169
: 4674260
===Calculations===
: Number Title Revision JN350-A00080 Spent Fuel Pool Instrumentation System Channel Accuracy Analysis
: NM1000-A00008 Spent Fuel Pool Cooling FLEX Pump Discharge Piping Pressure Drop
: NM1000-A00048 FLEX Project Study Report For The Battery Discharge Capacity During Extended Loss of AC Power (ELAP)
: NM10 00-A00149 Witness Test Results for FLEX SG Injection Pumps
===Miscellaneous===
: Documents/Reports Number Title Revision / Date
: PVNGS Diverse and Flexible Coping Strategies (FLEX) Program Plan
: 16DP-0EP25 Emergency Preparedness Training Program Description Engineering Study 13-MS-B116 Essential Electrical Rooms Temperature after Extended Loss of AC Power (ELAP)
: LTR 102-06615 Emergency Preparedness Communications Objective 2
: November 9, 2012
: LTR 102-06664 Response to NRC Tier 1 Near
-term Task Force Recommendation 9.3 Communications Technical Issues for Resolution February 22, 2013 
: Attachment
===Miscellaneous===
: Documents/Reports Number Title Revision / Date
: LTR 102-06885 Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50
-528, 50-529, and 50
-530 Submittal of Phase 2 Staffing Assessment Report June 11, 2014
: NKASYC017200
: Licensed Operator Initial Training Classroom Lesson - In Plant Communications July 1, 2013 NLR14S050501
: Licensed Operator Continuing Training
- Licensed Operator Continuing Training August 19, 2014 NLR16C0501
: Licensed Operator Continuing Training
- Fukushima and Flex, Modes 5, 6 and Defueled August 16, 2016 NM1000-A00187 Strategic Alliance for FLEX Emergency Response (SAFER) Plan for Palo Verde Nuclear Generating Station
: NM1000-A00191 National SAFER Response Center (NSRC) Equipment Technical Requirements
: NNI02C0184
: Non Licensed Operator Initial Training Classroom Lesson
- In Plant Communications/Remote Multiplex System July 2, 2015
: 4580242-13 Validation Plan for the Manual Operation of ADV ISO FLEX Phase 1
: 4580242-21 Validation Plan for the Restoration of the SG Makeup with the FLEX Pump
: VTD-A915-00169 ABB Installation & Maintenance Instructions for Low
-Voltage Power Circuit Breakers Type K
-225 Thru 2000 &
: K-600S Thru 2000S
: VTD-S188-00030 Siemens Instruction Manual for Multiranger 100/200
: 1
}}

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