IR 05000333/2016008: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406
[[Issue date::March 17, 2016]]
-2713 March 17, 2016 Mr. Brian Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093


Mr. Brian Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)
INSPECTION REPORT 05000333/2016008


SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM) INSPECTION REPORT 05000333/2016008
==Dear Mr. Sullivan:==
On February 25, 2016
, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)
. The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016
, with you and other members of your staff. NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team examined Entergy's implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.
 
No NRC-identified or self
-revealing findings were identified during this inspection.
 
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice,"
a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC's document system, 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/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety Mr. Brian Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
 
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)
INSPECTION REPORT 05000333/2016008


==Dear Mr. Sullivan:==
==Dear Mr. Sullivan:==
On February 25, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016, with you and other members of your staff. NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team examined Entergy's implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel. No NRC-identified or self-revealing findings were identified during this inspection. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC's document system, 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).
On February 25, 2016
, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)
. The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016, with you and other members of your staff.
 
NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team examined Entergy's implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.
 
No NRC-identified or self
-revealing findings were identified during this inspection.


Sincerely,/RA/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice,"
a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC's document system, 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).


ML16078A132 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME SPindale ABurritt MHalter DATE 3/15/16 3/15/16 3/17/16 Docket No. 50-333 License No. DPR-59  
Sincerely,/RA/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety DISTRIBUTION: See Next Page DOCUMENT NAME:
G:\DRS\Engineering Branch 2
\Pindale\Fitz CDBI Pilot EQ IR 2016008.docx ADAMS ACCESSION NUMBER:
ML16078A132 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME SPindale ABurritt MHalter DATE 3/15/16 3/15/16 3/17/16 OFFICIAL RECORD CO PY Docket No. 50
-333 License No. DPR
-59  


===Enclosure:===
===Enclosure:===
Inspection Report 05000333/2016008  
Inspection Report 050003 33/2016008  


===w/Attachment:===
===w/Attachment:===
Supplemental Information cc w/encl: Distribution via ListServ Letter to Brian Sullivan from Mandy Halter
Supplemental Information cc w/encl: Distribution via ListServ Letter to Brian Sullivan from Mandy Halter


SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM) INSPECTION REPORT 05000333/2016008 DISTRIBUTION: DDorman, RA (R1ORAMAIL RESOURCE) DLew, DRA (R1ORAMAIL RESOURCE) MScott, DRP (R1DRPMAIL RESOURCE) RMcKinley, DRP (R1DRPMAIL RESOURCE) RLorson, DRS (R1DRSMAIL RESOURCE) BSmith, DRS (R1DRSMAIL RESOURCE) M. Halter, DRS S. Pindale, DRS ABurritt, DRP CBickett, DRP LCline, DRP BLin, DRP EKnutson, DRP, SRI BSienel, DRP, RI KMcKenzie, DRP, AA TClark, RI OEDO RidsNrrPMFitzPatrick Resource RidsNrrDorlLpl1-1 Resource ROPReports Resource i    Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No: 50-333 License No: DPR-59 Report No: 05000333/2016008 Licensee: Entergy Nuclear Northeast (Entergy) Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba, NY Inspection Period: February 22 - 25, 2016 Inspectors: S. Pindale, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader D. Orr, Senior Reactor Inspector, DRS J. Ayala, Reactor Inspector, DRS Approved By: Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety ii  
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)
INSPECTION REPORT 05000333/2016008 DISTRIBUTION
: DDorman, RA (R1ORAMAIL RESOURCE)
DLew, DRA (R1ORAMAIL RESOURCE)
MScott, DRP (R1DRPMAIL RESOURCE)
RMcKinley, DRP (R1DRPMAIL RESOURCE)
RLorson, DRS (R1DRSMAIL RESOURCE)
BSmith, DRS (R1DRSMAIL RESOURCE)
M. Halter, DRS S. Pindale, DRS ABurritt, DRP CBickett, DRP LCline, DRP BLin, DRP EKnutson, DRP, SRI BSienel, DRP, RI KMcKenzie, DRP, AA TClark, RI OEDO RidsNrrPMFitzPatrick Resource RidsNrrDorlLpl1
-1 Resource ROPReports Resource  
 
i    Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No: 50-333 License No: DPR-59 Report No: 05000333/2016008 Licensee:
Entergy Nuclear Northeast (Entergy
) Facility:
James A. FitzPatrick Nuclear Power Plant Location:
Scriba, NY Inspection Period: February 22
- 25, 2016 Inspectors:
S. Pindale
, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader D. Orr, Senior Reactor Inspector, DRS J. Ayala, Reactor Inspector, DRS Approved By: Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety  
 
ii  


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
IR 05000333/2016008; 2/22/2016 - 2/25/2016; James A. FitzPatrick Nuclear Power Plant; Component Design Bases Inspection (Programs). The report covers the Component Design Bases Inspection (Programs) conducted by a team of three U.S. Nuclear Regulatory Commission (NRC) inspectors. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process." Cross-cutting aspects associated with findings are determined using IMC 0310, "Components Within the Cross-Cutting Areas." The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014. No findings were identified.
IR 05000333/2016008; 2/22/2016 - 2/25/2016; James A. FitzPatrick Nuclear Power Plant
 
; Component Design Bases Inspection (Programs)
. The report covers the Component Design Bases Inspection (Programs)conducted by a team of three U.S. Nuclear Regulatory Commission (NRC) inspectors.
 
The significance of most findings is indicated by their color (Green,
White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process."
 
Cross-cutting aspects associated with findings are determined using IMC 0310, "Components Within the Cross-Cutting Areas." The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014.
 
No findings were identified.


=REPORT DETAILS=
=REPORT DETAILS=


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity 1R21  Component Design Bases Inspection (Programs) (IP 71111.21N - 8 samples)
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity


===.1 Inspection Sample Selection Process===
{{a|1R21}}
The inspection team assessed the implementation of Entergy's Environmental Qualification (EQ) program, established to meet the requirements of Title 10, Code of Federal Regulations (CFR) 50.49, "Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants."  The scope of this rule includes safety-related equipment relied upon to remain functional during and following design basis events, non-safety-related equipment whose failure under postulated environmental conditions could prevent safety-related equipment from performing design functions, and certain post-accident monitoring equipment. The team selected risk significant components for review using information contained in the James A. FitzPatrick Nuclear Power Plant (FitzPatrick) Probabilistic Risk Assessment (PRA) and the U.S. Nuclear Regulatory Commission's (NRC) Standardized Plant Analysis Risk (SPAR) model for FitzPatrick. Additionally, the team referenced the FitzPatrick Risk-Informed Inspection Notebook in the selection of potential components for review. The NRC originally verified FitzPatrick's EQ program implementation through a series of onsite inspections in the 1980's. The EQ program at that time established measures to ensure EQ through the 40-year operating license period. Since that time, Entergy had renewed FitzPatrick's operating licenses for an additional 20 years. The team initially compiled a list of components based on the risk factors previously mentioned. The team then interviewed plant staff, and reviewed procurement, maintenance, and design records. Based on these additional reviews, the team focused the inspection on eight EQ program elements and components. The components that were selected included pump motors, motor-operated valves (MOV), solenoid valves, limit switches and flow/level transmitters located both inside and outside of containment. The team also evaluated the EQ of selected supporting sub-components, including seals and lubricants.
==1R21 Component==
 
Design Bases Inspection (Programs)
(IP 71111.21N
- 8 samples)
 
===.1 Inspection===
 
Sample Selection Process  The inspection team assessed the implementation of Entergy's Environmental Qualification (EQ) program, established to meet the requirements of Title 10, Code of Federal Regulations (CFR) 50.49, "Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants."  The scope of this rule includes safety-related equipment relied upon to remain functional during and following design basis events, non
-safety-related equipment whose failure under postulated environmental conditions could prevent safety
-related equipment from performing design functions, and certain post
-accident monitoring equipment. The team selected risk significant components for review using information contained in the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)
Probabilistic Risk Assessment (PRA) and the U.S. Nuclear Regulatory Commission's (NRC) Standardized Plant Analysis Risk (SPAR) model for FitzPatrick. Additionally, the team referenced the FitzPatrick Risk-Informed Inspection Notebook in the selection of potential components for review. The NRC originally verified FitzPatrick's EQ program implementation through a series of onsite inspections in the 1980's
. The EQ program at that time established measures to ensure EQ through the 40
-year operating license period. Since that time, Entergy had renewed FitzPatrick's operating licenses for an additional 20 years
. The team initially compiled a list of components based on the risk factors previously mentioned.
 
The team then interviewed plant staff, and reviewed procurement, maintenance, and design records. Based on these additional reviews, the team focused the inspection on eight EQ program elements and components
. The components that were selected included pump motors, motor
-operated valves (MOV), solenoid valves, limit switches and flow/level transmitters located both inside and outside of containment
. The team also evaluated the EQ of selected supporting sub
-components, including seals and lubricants
.


===.2 Results of Detailed Reviews===
===.2 Results of Detailed Reviews===


====a. Inspection Scope====
====a. Inspection Scope====
The inspection was a pilot inspection, conducted as outlined in NRC Inspection Procedure (IP) 71111.21N. The team assessed Entergy's implementation of the EQ program as required by 10 CFR 50.49. The team evaluated whether Entergy staff properly maintained the EQ of electrical equipment important to safety through plant life (repair, replacement, modification, and plant life extension), established and maintained required EQ documentation records, and implemented an effective corrective action program to identify and correct EQ-related deficiencies and evaluate EQ-related industry operating experience.
The inspection was a pilot inspection, conducted as outlined in NRC Inspection Procedure (IP) 71111.21N.


This inspection effort included review of EQ program-related procedures, component EQ files, EQ test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team also interviewed plant staff knowledgeable with the design, maintenance, and operation of the selected components. Additionally, the team performed physical in-plant walkdowns (where accessible) to verify the installed equipment 1) was consistent with the EQ component documentation files, 2) was installed in their tested configuration, and 3) could be impacted by the failure of surrounding equipment. The team reviewed procurement records and inspected a sample of replacement parts stored in the warehouse to verify EQ parts approved for installation in the plant were properly identified and controlled; and that storage time and environmental conditions did not adversely affect the components' qualified life or service life. The team also reviewed Entergy's evaluation of applicable operating experience to determine whether industry EQ-related issues were understood and addressed through Entergy's corrective action program. Documents reviewed for this inspection are listed in the Attachment. Component samples selected for this inspection are listed below. Six of the eight components were qualified in accordance with 10 CFR 50.49; and two components, which are original plant equipment, were qualified in accordance with the NRC's Division of Operating Reactors (DOR) Guidelines, as indicated below.
The team assessed Entergy's implementation of the EQ program as required by 10 CFR 50.49. The team evaluated whether Entergy staff properly maintained the EQ of electrical equipment important to safety through plant life (repair, replacement, modification, and plant life extension)
, established and maintained required EQ documentation records, and implemented an effective corrective action program to identify and correct EQ
-related deficiencies and evaluate EQ
-related industry operating experience.


Main Steam Isolation Valve (MSIV) 'A' Inboard Solenoid Valve Cluster Assembly Safety/Relief Valve 'A' Pilot Solenoid Valve   Residual Heat Removal System 'A' Pump Motor (DOR)
This inspection effort included review of EQ program
High Pressure Coolant Injection (HPCI) System Inboard Isolation Valve 23MOV19   Residual Heat Removal System 'D' Torus Isolation Valve 10MOV13D (DOR)  HPCI/Reactor Core Isolation Cooling System Level Transmitter 02-3LT-72A MSIV 'A' Position Indication Limit Switches (Open, Closed, 85% Open)   Residual Heat Removal System 'A' Flow Transmitter 10-FT-109A
-related procedures, component EQ files, EQ test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations
. The team also interview ed plant staff knowledgeable with the design, maintenance, and operation of the selected components. Additionally
, the team performed physical in-plant walkdowns (where accessible)to verify the installed equipment 1) was consistent with the EQ component documentation files, 2) was installed in their tested configuration, and 3) could be impacted by the failure of surrounding equipment. The team reviewed procurement records and inspected a sample of replacement parts stored in the warehouse to verify EQ parts approved for installation in the plant were properly identified and controlled; and that storage time and environmental conditions did not adversely affect the components' qualified life or service life
. The team also reviewed Entergy's evaluation of applicable operating experience to determine whether industry EQ
-related issues were understood and addressed through Entergy's corrective action program. Documents reviewed for this inspection are listed in the Attachment.
 
Component samples selected for this inspection are listed below.
 
Six of the eight components were qualified in accordance with 10 CFR 50.49; and two components, which are original plant equipment, were qualified in accordance with the NRC's Division of Operating Reactor s (DOR) Guidelines, as indicated below.
 
Main Steam Isolation Valve (MSIV) 'A' Inboard Solenoid Valve Cluster Assembly Safety/Relief Valve 'A' Pilot Solenoid Valve Residual Heat Removal System 'A' Pump Motor (DOR)
High Pressure Coolant Injection (HPCI) System Inboard Isolation Valve 23MOV19 Residual Heat Removal System 'D' Torus Isolation Valve 10MOV13D (DOR)  HPCI/Reactor Core Isolation Cooling System Level Transmitter 02
-3LT-72A MSIV 'A' Position Indication Limit Switches (Open, Closed, 85% Open)
Residual Heat Removal System 'A' Flow Transmitter 10
-FT-109A


====b. Findings====
====b. Findings====
Line 66: Line 169:
==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
{{a|4OA2}}
{{a|4OA2}}
==4OA2 Identification and Resolution of Problems (IP 71152)==
==4OA2 Identification==
 
and Resolution of Problems (IP 71152)


====a. Inspection Scope====
====a. Inspection Scope====
The team reviewed a sample of problems that Entergy had previously identified and entered into the corrective action program. The team reviewed a sample of these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. The specific corrective action documents that were sampled and reviewed by the team are listed in the Attachment.
The team reviewed a sample of problems that Entergy had previously identified and entered into the corrective action program. The team reviewed a sample of these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. T he specific corrective action documents that were sampled a nd reviewed by the team are listed in the Attachment.
 
B Findings  No findings were identified.


B Findings  No findings were identified.
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, including Exit==
==4OA6 Meetings,==
On February 25, 2016, the team presented the inspection results to Mr. Brian Sullivan, Site Vice President, and other members of Entergy staff. The team reviewed proprietary information, which was returned to Entergy at the end of the inspection. The team verified that no proprietary information was documented in the report.
 
including Exit  On February 25, 2016
, the team presented the inspection results to Mr. Brian Sullivan, Site Vice President, and other members of Entergy staff. T he team reviewed proprietary information, which was returned to Entergy at the end of the inspection.
 
The team verified that no proprietary information was documented in the report.


ATTACHMENT  
ATTACHMENT


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL
INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
Entergy Personnel  
Entergy Personnel
: [[contact::V. Bacanskas]], Director, Chief Engineer  
: [[contact::V. Bacanskas]], Director, Chief Engineer
: [[contact::J. Eckman]], Senior Design Engineer  
: [[contact::J. Eckman]], Senior Design Engineer  
: [[contact::M. Hawes]], Regulatory Compliance Engineer
: [[contact::M. Hawes]], Regulatory Compliance Engi
: [[contact::A. Lauzon]], EQ Engineer
neer
: [[contact::A. Lauzon]], EQ Engineer
 
==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED==
==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED==
None   
None   
==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS==
EQ Files
REVIEWED
: QDR 03.01, Limitorque Model SMB and SB Motor-Operated Valves, Revision 12
: EQ Files
: QDR 03.02, Limitorque Model SMB Motor-Operated Valves, Revision 13
: QDR 03.01, Limitorque Model SMB
and SB Motor-Operated Valves, Revision 12
: QDR 03.02, Limitorque Model SMB Motor
-Operated Valves, Revision 13
: QDR 04.01, General Electric 4KV Series SK6339XC Motors, Revision 3
: QDR 04.01, General Electric 4KV Series SK6339XC Motors, Revision 3
: QDR 08.03, Foxboro I Model N-El 0 Series I Pressure Transmitters, Revision 2
: QDR 08.03, Foxboro I Model  
: N-El 0 Series I Pressure Transmitters, Revision 2
: QDR 08.04, Rosemount 1153 Series B Transmitters and 353C Conduit Seals, Revision 3
: QDR 08.04, Rosemount 1153 Series B Transmitters and 353C Conduit Seals, Revision 3
: QDR 09.01, NAMCO Limit Switches Model EA740 Series, Revision 4
: QDR 09.01, NAMCO Limit Switches Model EA740 Series, Revision 4
: QDR 34.03, NAMCO EC210 Series Receptacle and Connector/Cable Assemblies, Revision 4
: QDR 34.03, NAMCO EC210 Series Receptacle and Connector/Cable Assemblies, Revision 4
: QDR 34.05, NAMCO Model EC290 Series Connector/Cable Assemblies, Revision 0
: QDR 34.05, NAMCO Model EC290 Series Connector/Cable Assemblies, Revision 0
: QDR 35.07, Hiller Model
: QDR 35.07, Hiller Model SA
: SA-A111 MSIV Solenoid Valve Cluster Assemblies, Revision 4
-A111 MSIV Solenoid Valve Cluster Assemblies, Revision 4
: QDR 35.08, Target Rock Model 1/2
: QDR 35.08, Target Rock Model 1/2 SMS
: SMS-S-02-1 Solenoid Valve, Revision 4  
-S-02-1 Solenoid Valve, Revision 4  
===Procedures===
===Procedures===
: EN-MA-101-02, Control of Material Outside Facility Warehouse, Revision 6
: EN-MA-101-02, Control of Material Outside Facility Warehouse, Revision 6
Line 114: Line 232:
: FM-20B, Flow Diagram Residual Heat Removal System, Revision 63  
: FM-20B, Flow Diagram Residual Heat Removal System, Revision 63  
===Design and Licensing Basis Documents===
===Design and Licensing Basis Documents===
: JAF-SE-96-016, Acceptability of Establishing a One Hour Post Accident Operating Time Requirement for the ADS System to Mitigate LOCA, Revision 4 James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, April 2015 Safety Evaluation for EQ of Safety-Related Electrical Equipment, 4/19/83  
: JAF-SE-96-016, Acceptability of Establishing a One Hour Post Accident Operating Time Requirement for the ADS System to Mitigate LOCA, Revision 4
: James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, April 2015
: Safety Evaluation for E
: Q of Safety
-Related Electrical Equipment, 4/19/83  
===Miscellaneous===
===Miscellaneous===
: EQCL Report, 1/14/16 Letter, Nutherm International, Inc. to NRC, Final Update on Potential 10
: EQCL Report, 1/14/16
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 2/3/16 Letter, Nutherm, International, Inc. to NRC, Update on Potential 10
: Letter, Nutherm International, Inc. to NRC
, Final Update on Potential 10
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 2/3/16 Letter, Nutherm, International, Inc. to NRC
, Update on Potential 10
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 8/31/15
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 8/31/15
: NRC 10 CFR Part 21 Report from Nutherm International, 8/1/14 Nuclear Utility Group on Equipment Qualification, Clarification of Information Related to the EQ of Limitorque MOV, August 1989
: NRC 10 CFR Part 21 Report from Nutherm International,  
: NUREG-0588, Interim Staff Position on EQ of Safety-Related Electrical Equipment, Revision 1 Operability Evaluation No.
: 8/1/14 Nuclear Utility Group on Equipment Qualification, Clarification of Information Related to the EQ of Limitorque MOV, August 1989
: CR-JAF-2016-0050, 10
: NUREG-0588, Interim Staff Position on E
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, dated 02/10/16 PM Template
: Q of Safety
: 50047998-01, Stem Lube and Gearcase Grease Check per
-Related Electrical Equipment, Revision 1
: MP-0 59-51 Pre-NRC CDBI EQ Snapshot Self-Assessment, 1/12/16 Purchase Order S-96-82818, Torque Switch Assembly, 8/19/96 Snapshot Self-Assessment EQ Program, 7/20/04
: Operability Evaluation No. CR
: Vendor Documents L200-0036, SMB Installation and Maintenance ManuaI, Revision 8 N007-0123, Namco Limit Switch EA740 Series, Revision D R369-0030, Rosemount 1153 Series B Alphaline Nuclear Pressure Transmitter, Revision 7  
-JAF-2016-0050, 10
: CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, dated 02/10/16
: PM Template
: 50047998-01, Stem Lube and Gearcase Grease Check per MP
-0 59-51 Pre-NRC CDBI EQ Snapshot Self
-Assessment, 1/12/16
: Purchase Order S
-96-82818, Torque Switch Assembly, 8/19/96 Snapshot Self
-Assessment EQ Program, 7/20/04
: Vendor Documents
: L200-0036, SMB Installation and Maintenance ManuaI, Revision 8
: N007-0123, Namco Limit Switch EA740 Series, Revision D
: R369-0030, Rosemount 1153 Series B Alphaline Nuclear Pressure Transmitter, Revision 7  
===Calculations and Engineering Evaluations===
===Calculations and Engineering Evaluations===
: EC 0000014122, Modification to Improve SRV Reliability - Replace 02RV-71C, -71E and -71F with Target Rock Three-Stage Safety/Relief Valves (Model 0867F), Revision 0
: EC 0000014122, Modification to Improve SRV Reliability  
- Replace 02RV
-71C, -71E and -71F with Target Rock Three
-Stage Safety/Relief Valves (Model 0867F), Revision 0
: JAF-CALC-09-00016, Attachment 21
: JAF-CALC-09-00016, Attachment 21
: JAF-RPT-MISC-04046, Environmental Qualification Service Conditions, Revision 0  
: JAF-RPT-MISC-04046, Environmental Qualification Service Conditions, Revision 0  
Line 144: Line 284:
: 52467939 52475718
: 52467939 52475718
==LIST OF ACRONYMS==
==LIST OF ACRONYMS==
: [[ADAMS]] [[Agencywide Documents Access and Management System]]
ADAMS Agencywide
Documents
Access and Management
System
: [[CFR]] [[Code of Federal Regulations]]
: [[CFR]] [[Code of Federal Regulations]]
: [[CR]] [[Condition Report]]
CR Condition Report
: [[DOR]] [[Division of Operating Reactors]]
DOR Division of Operating
Reactors
: [[DRS]] [[Division of Reactor Safety]]
: [[DRS]] [[Division of Reactor Safety]]
: [[EQ]] [[Environmental Qualification]]
: [[EQ]] [[Environmental Qualification]]
: [[HPCI]] [[High Pressure Coolant Injection]]
: [[HPCI]] [[High Pressure Coolant Injection]]
: [[IMC]] [[Inspection Manual Chapter]]
IMC Inspection
: [[IP]] [[Inspection Procedure]]
Manual Chapter IP Inspection
Procedure
: [[MOV]] [[Motor-Operated Valve]]
: [[MOV]] [[Motor-Operated Valve]]
: [[MSIV]] [[Main Steam Isolation Valve]]
MSIV Main Steam Isolation Valve
: [[NRC]] [[Nuclear Regulatory Commission]]
NRC Nuclear Regulatory
: [[PRA]] [[Probabilistic Risk Assessment]]
Commission
: [[SPAR]] [[Standardized Plant Analysis Report]]
PRA Probabilistic
Risk Assessment
SPAR Standardized
Plant Analysis Report
: [[UFSAR]] [[Updated Final Safety Analysis Report]]
: [[UFSAR]] [[Updated Final Safety Analysis Report]]
: [[WO]] [[Work Order]]
: [[WO]] [[Work Order]]
}}
}}

Revision as of 11:50, 30 June 2018

IR 05000333/2016008; 2/22/2016 to 2/25/2016; James A. FitzPatrick Nuclear Power Plant; Component Design Bases Inspection (Programs)
ML16078A132
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/17/2016
From: Halter M K
Engineering Region 1 Branch 2
To: Brian Sullivan
Entergy Nuclear Northeast
References
IR 2016008
Download: ML16078A132 (12)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406

-2713 March 17, 2016 Mr. Brian Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT

- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)

INSPECTION REPORT 05000333/2016008

Dear Mr. Sullivan:

On February 25, 2016

, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)

. The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016

, with you and other members of your staff. NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team examined Entergy's implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.

No NRC-identified or self

-revealing findings were identified during this inspection.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice,"

a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC's document system, 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/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety Mr. Brian Sullivan Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT

- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)

INSPECTION REPORT 05000333/2016008

Dear Mr. Sullivan:

On February 25, 2016

, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)

. The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016, with you and other members of your staff.

NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team examined Entergy's implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.

No NRC-identified or self

-revealing findings were identified during this inspection.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice,"

a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC's document system, 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/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety DISTRIBUTION: See Next Page DOCUMENT NAME:

G:\DRS\Engineering Branch 2

\Pindale\Fitz CDBI Pilot EQ IR 2016008.docx ADAMS ACCESSION NUMBER:

ML16078A132 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME SPindale ABurritt MHalter DATE 3/15/16 3/15/16 3/17/16 OFFICIAL RECORD CO PY Docket No. 50

-333 License No. DPR

-59

Enclosure:

Inspection Report 050003 33/2016008

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Letter to Brian Sullivan from Mandy Halter

SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT

- COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)

INSPECTION REPORT 05000333/2016008 DISTRIBUTION

DDorman, RA (R1ORAMAIL RESOURCE)

DLew, DRA (R1ORAMAIL RESOURCE)

MScott, DRP (R1DRPMAIL RESOURCE)

RMcKinley, DRP (R1DRPMAIL RESOURCE)

RLorson, DRS (R1DRSMAIL RESOURCE)

BSmith, DRS (R1DRSMAIL RESOURCE)

M. Halter, DRS S. Pindale, DRS ABurritt, DRP CBickett, DRP LCline, DRP BLin, DRP EKnutson, DRP, SRI BSienel, DRP, RI KMcKenzie, DRP, AA TClark, RI OEDO RidsNrrPMFitzPatrick Resource RidsNrrDorlLpl1

-1 Resource ROPReports Resource

i Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No: 50-333 License No: DPR-59 Report No: 05000333/2016008 Licensee:

Entergy Nuclear Northeast (Entergy

) Facility:

James A. FitzPatrick Nuclear Power Plant Location:

Scriba, NY Inspection Period: February 22

- 25, 2016 Inspectors:

S. Pindale

, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader D. Orr, Senior Reactor Inspector, DRS J. Ayala, Reactor Inspector, DRS Approved By: Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety

ii

SUMMARY OF FINDINGS

IR 05000333/2016008; 2/22/2016 - 2/25/2016; James A. FitzPatrick Nuclear Power Plant

Component Design Bases Inspection (Programs)

. The report covers the Component Design Bases Inspection (Programs)conducted by a team of three U.S. Nuclear Regulatory Commission (NRC) inspectors.

The significance of most findings is indicated by their color (Green,

White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process."

Cross-cutting aspects associated with findings are determined using IMC 0310, "Components Within the Cross-Cutting Areas." The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014.

No findings were identified.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R21 Component

Design Bases Inspection (Programs)

(IP 71111.21N

- 8 samples)

.1 Inspection

Sample Selection Process The inspection team assessed the implementation of Entergy's Environmental Qualification (EQ) program, established to meet the requirements of Title 10, Code of Federal Regulations (CFR) 50.49, "Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants." The scope of this rule includes safety-related equipment relied upon to remain functional during and following design basis events, non

-safety-related equipment whose failure under postulated environmental conditions could prevent safety

-related equipment from performing design functions, and certain post

-accident monitoring equipment. The team selected risk significant components for review using information contained in the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)

Probabilistic Risk Assessment (PRA) and the U.S. Nuclear Regulatory Commission's (NRC) Standardized Plant Analysis Risk (SPAR) model for FitzPatrick. Additionally, the team referenced the FitzPatrick Risk-Informed Inspection Notebook in the selection of potential components for review. The NRC originally verified FitzPatrick's EQ program implementation through a series of onsite inspections in the 1980's

. The EQ program at that time established measures to ensure EQ through the 40

-year operating license period. Since that time, Entergy had renewed FitzPatrick's operating licenses for an additional 20 years

. The team initially compiled a list of components based on the risk factors previously mentioned.

The team then interviewed plant staff, and reviewed procurement, maintenance, and design records. Based on these additional reviews, the team focused the inspection on eight EQ program elements and components

. The components that were selected included pump motors, motor

-operated valves (MOV), solenoid valves, limit switches and flow/level transmitters located both inside and outside of containment

. The team also evaluated the EQ of selected supporting sub

-components, including seals and lubricants

.

.2 Results of Detailed Reviews

a. Inspection Scope

The inspection was a pilot inspection, conducted as outlined in NRC Inspection Procedure (IP) 71111.21N.

The team assessed Entergy's implementation of the EQ program as required by 10 CFR 50.49. The team evaluated whether Entergy staff properly maintained the EQ of electrical equipment important to safety through plant life (repair, replacement, modification, and plant life extension)

, established and maintained required EQ documentation records, and implemented an effective corrective action program to identify and correct EQ

-related deficiencies and evaluate EQ

-related industry operating experience.

This inspection effort included review of EQ program

-related procedures, component EQ files, EQ test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations

. The team also interview ed plant staff knowledgeable with the design, maintenance, and operation of the selected components. Additionally

, the team performed physical in-plant walkdowns (where accessible)to verify the installed equipment 1) was consistent with the EQ component documentation files, 2) was installed in their tested configuration, and 3) could be impacted by the failure of surrounding equipment. The team reviewed procurement records and inspected a sample of replacement parts stored in the warehouse to verify EQ parts approved for installation in the plant were properly identified and controlled; and that storage time and environmental conditions did not adversely affect the components' qualified life or service life

. The team also reviewed Entergy's evaluation of applicable operating experience to determine whether industry EQ

-related issues were understood and addressed through Entergy's corrective action program. Documents reviewed for this inspection are listed in the Attachment.

Component samples selected for this inspection are listed below.

Six of the eight components were qualified in accordance with 10 CFR 50.49; and two components, which are original plant equipment, were qualified in accordance with the NRC's Division of Operating Reactor s (DOR) Guidelines, as indicated below.

Main Steam Isolation Valve (MSIV) 'A' Inboard Solenoid Valve Cluster Assembly Safety/Relief Valve 'A' Pilot Solenoid Valve Residual Heat Removal System 'A' Pump Motor (DOR)

High Pressure Coolant Injection (HPCI) System Inboard Isolation Valve 23MOV19 Residual Heat Removal System 'D' Torus Isolation Valve 10MOV13D (DOR) HPCI/Reactor Core Isolation Cooling System Level Transmitter 02

-3LT-72A MSIV 'A' Position Indication Limit Switches (Open, Closed, 85% Open)

Residual Heat Removal System 'A' Flow Transmitter 10

-FT-109A

b. Findings

No findings were identified.

OTHER ACTIVITIES

4OA2 Identification

and Resolution of Problems (IP 71152)

a. Inspection Scope

The team reviewed a sample of problems that Entergy had previously identified and entered into the corrective action program. The team reviewed a sample of these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. T he specific corrective action documents that were sampled a nd reviewed by the team are listed in the Attachment.

B Findings No findings were identified.

4OA6 Meetings,

including Exit On February 25, 2016

, the team presented the inspection results to Mr. Brian Sullivan, Site Vice President, and other members of Entergy staff. T he team reviewed proprietary information, which was returned to Entergy at the end of the inspection.

The team verified that no proprietary information was documented in the report.

ATTACHMENT

=SUPPLEMENTAL

INFORMATION=

KEY POINTS OF CONTACT

Entergy Personnel

V. Bacanskas, Director, Chief Engineer
J. Eckman, Senior Design Engineer
M. Hawes, Regulatory Compliance Engi

neer

A. Lauzon, EQ Engineer

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

None

LIST OF DOCUMENTS

REVIEWED

EQ Files
QDR 03.01, Limitorque Model SMB

and SB Motor-Operated Valves, Revision 12

QDR 03.02, Limitorque Model SMB Motor

-Operated Valves, Revision 13

QDR 04.01, General Electric 4KV Series SK6339XC Motors, Revision 3
QDR 08.03, Foxboro I Model
N-El 0 Series I Pressure Transmitters, Revision 2
QDR 08.04, Rosemount 1153 Series B Transmitters and 353C Conduit Seals, Revision 3
QDR 09.01, NAMCO Limit Switches Model EA740 Series, Revision 4
QDR 34.03, NAMCO EC210 Series Receptacle and Connector/Cable Assemblies, Revision 4
QDR 34.05, NAMCO Model EC290 Series Connector/Cable Assemblies, Revision 0
QDR 35.07, Hiller Model SA

-A111 MSIV Solenoid Valve Cluster Assemblies, Revision 4

QDR 35.08, Target Rock Model 1/2 SMS

-S-02-1 Solenoid Valve, Revision 4

Procedures

EN-MA-101-02, Control of Material Outside Facility Warehouse, Revision 6
EN-NF-200, Special Nuclear Material Control, Revision 13
EOP-4, Primary Containment Control, Revision 8
IMP-G77, Replacement of Rosemount Pressure Transmitter Model 1153, Series B, Code R, with Conduit Seal 353*, Revision 14
MP-059-51, Limitorque Actuators Inspection and Lubrication, Revision 35
MP-200.19, NAMCO Connectors Maintenance, Revision 10
MP-200.20, MSIV Solenoid Valve Cluster Assembly Replacement, Revision 05

Drawings

FM-20A, Flow Diagram Residual Heat Removal System, Revision 72
FM-20B, Flow Diagram Residual Heat Removal System, Revision 63

Design and Licensing Basis Documents

JAF-SE-96-016, Acceptability of Establishing a One Hour Post Accident Operating Time Requirement for the ADS System to Mitigate LOCA, Revision 4
James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, April 2015
Safety Evaluation for E
Q of Safety

-Related Electrical Equipment, 4/19/83

Miscellaneous

EQCL Report, 1/14/16
Letter, Nutherm International, Inc. to NRC

, Final Update on Potential 10

CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 2/3/16 Letter, Nutherm, International, Inc. to NRC

, Update on Potential 10

CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 8/31/15
NRC 10 CFR Part 21 Report from Nutherm International,
8/1/14 Nuclear Utility Group on Equipment Qualification, Clarification of Information Related to the EQ of Limitorque MOV, August 1989
NUREG-0588, Interim Staff Position on E
Q of Safety

-Related Electrical Equipment, Revision 1

Operability Evaluation No. CR

-JAF-2016-0050, 10

CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, dated 02/10/16
PM Template
50047998-01, Stem Lube and Gearcase Grease Check per MP

-0 59-51 Pre-NRC CDBI EQ Snapshot Self

-Assessment, 1/12/16

Purchase Order S

-96-82818, Torque Switch Assembly, 8/19/96 Snapshot Self

-Assessment EQ Program, 7/20/04

Vendor Documents
L200-0036, SMB Installation and Maintenance ManuaI, Revision 8
N007-0123, Namco Limit Switch EA740 Series, Revision D
R369-0030, Rosemount 1153 Series B Alphaline Nuclear Pressure Transmitter, Revision 7

Calculations and Engineering Evaluations

EC 0000014122, Modification to Improve SRV Reliability

- Replace 02RV

-71C, -71E and -71F with Target Rock Three

-Stage Safety/Relief Valves (Model 0867F), Revision 0

JAF-CALC-09-00016, Attachment 21
JAF-RPT-MISC-04046, Environmental Qualification Service Conditions, Revision 0

Condition Reports

2003-03954 2011-04208 2011-05195 2011-05328 2012-00962 2012-01002 2012-01459 2012-01913 2012-01971 2012-02399 2012-02399 2013-03234 2013-03235 2014-01191 2015-03954 2016-00431 2016-00501 2016-00764* *Written as a result of this inspection

Work Orders

51122191
51569866
51569867
51569867
52085457
52115739
52169613
52182411
52258742
52467939 52475718

LIST OF ACRONYMS

ADAMS Agencywide

Documents

Access and Management

System

CFR Code of Federal Regulations

CR Condition Report

DOR Division of Operating

Reactors

DRS Division of Reactor Safety
EQ Environmental Qualification
HPCI High Pressure Coolant Injection

IMC Inspection

Manual Chapter IP Inspection

Procedure

MOV Motor-Operated Valve

MSIV Main Steam Isolation Valve

NRC Nuclear Regulatory

Commission

PRA Probabilistic

Risk Assessment

SPAR Standardized

Plant Analysis Report

UFSAR Updated Final Safety Analysis Report
WO Work Order
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