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| | issue date = 03/17/2016 | | | issue date = 03/17/2016 |
| | title = IR 05000333/2016008; 2/22/2016 to 2/25/2016; James A. FitzPatrick Nuclear Power Plant; Component Design Bases Inspection (Programs) | | | title = IR 05000333/2016008; 2/22/2016 to 2/25/2016; James A. FitzPatrick Nuclear Power Plant; Component Design Bases Inspection (Programs) |
| | author name = Halter M K | | | author name = Halter M |
| | author affiliation = NRC/RGN-I/DRS/EB2 | | | author affiliation = NRC/RGN-I/DRS/EB2 |
| | addressee name = Sullivan B | | | addressee name = Sullivan B |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406 | | {{#Wiki_filter:UNITED STATES rch 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
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| SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT | | ==SUBJECT:== |
| - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)
| | JAMES A. FITZPATRICK NUCLEAR POWER PLANT - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM) INSPECTION REPORT 05000333/2016008 |
| INSPECTION REPORT 050003 33/201 6 0 08 | |
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| ==Dear Mr. Sullivan:== | | ==Dear Mr. Sullivan:== |
| On February 25, 2016 | | 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. |
| , 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. | |
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| No NRC-identified or self
| | NRC inspectors examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
| -revealing findings were identified during this inspection.
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," | | In conducting the inspection, the team examined Entergys 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. |
| 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
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| -rm/adams.html (the Public Electronic Reading Room).
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| Sincerely,
| | No NRC-identified or self-revealing findings were identified during this inspection. |
| /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
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| SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT
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| - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM)
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| INSPECTION REPORT 05000333/2016008
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| ==Dear Mr. Sullivan:==
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| On February 25, 2016
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| , the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick)
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| . The enclosed inspection report documents the inspection results, which were discussed on February 25, 2016, with you and other members of your staff.
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| | |
| 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.
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| No NRC-identified or self
| | In accordance with 10 CFR 2.390 of the NRCs 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 NRCs document system, Agencywide Documents Access and Management System (ADAMS). |
| -revealing findings were identified during this inspection.
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice,"
| | ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| 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
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| -rm/adams.html (the Public Electronic Reading Room). | |
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| Sincerely, | | Sincerely, |
| /RA/ Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety DISTRIBUTION: See Next Page DOCUMENT NAME: | | /RA/ |
| G:\DRS\Engineering Branch 2
| | Mandy K. Halter, Chief Engineering Branch 2 Division of Reactor Safety |
| \Pindale\Fitz CDBI Pilot EQ IR 2016008.docx ADAMS ACCESSION NUMBER:
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| 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
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| -3 33 License No. DPR
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| -59 Enclosure:
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| Inspection Report 050003 33/201 6 00 8 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ Letter to Brian Sullivan from Mandy Halter
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| SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT
| | ML16078A132 Non-Sensitive Publicly Available SUNSI Review Sensitive 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 |
| - COMPONENT DESIGN BASES (ENVIRONMENTAL QUALIFICATION PROGRAM) | |
| INSPECTION REPORT 05000333/2016008 DISTRIBUTION
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| : DDorman, RA (R1ORAMAIL RESOURCE)
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| DLew, DRA (R1ORAMAIL RESOURCE)
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| MScott, DRP (R1DRPMAIL RESOURCE)
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| RMcKinley, DRP (R1DRPMAIL RESOURCE)
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| RLorson, DRS (R1DRSMAIL RESOURCE)
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| BSmith, DRS (R1DRSMAIL RESOURCE)
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| 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
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| -1 Resource ROPReports Resource | |
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| i Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No: 50-3 33 License No: DPR-5 9 Report No: 05000333/201 6 0 08 Licensee: Entergy Nuclear Northeast (Entergy
| | ===Enclosure:=== |
| ) Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba , NY Inspection Period: February 22
| | Inspection Report 05000333/2016008 w/Attachment: Supplemental Information |
| - 2 5 , 201 6 Inspectors:
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| S. Pindale
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| , 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
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| | 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 i Enclosure |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 050003 33/201 6 00 8; 2/22/201 6 - 2/2 5/201 6; James A. FitzPatrick Nuclear Power Plant | | IR 05000333/2016008; 2/22/2016 - 2/25/2016; James A. FitzPatrick Nuclear Power Plant; |
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| | Component Design Bases Inspection (Programs). |
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| ; 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 report covers the Component Design Bases Inspection (Programs)conducted by a team of three U.S. Nuclear Regulatory Commission (NRC) inspectors.
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| 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. | | The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014. |
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| No findings were identified. | | No findings were identified. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
| Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity | | Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity |
| | | {{a|1R21}} |
| {{a|1R21}} | | ==1R21 Component Design Bases Inspection (Programs) (IP 71111.21N - 8 samples)== |
| ==1R21 Component Design Bases Inspection (Programs)== | |
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| (IP 71111.21N - 8 samples)
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| ===.1 Inspection=== | | ===.1 Inspection Sample Selection Process=== |
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| 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
| | The inspection team assessed the implementation of Entergys 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 Commissions (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. |
| -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 usi ng 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 Fitz Patrick. 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 ha d 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.
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| 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 | | The NRC originally verified FitzPatricks EQ program implementation through a series of onsite inspections in the 1980s. The EQ program at that time established measures to ensure EQ through the 40-year operating license period. Since that time, Entergy had renewed FitzPatricks 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. |
| -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 | |
| -compo nents , including seals and lubricants | |
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| ===.2 Results of Detailed Reviews=== | | ===.2 Results of Detailed Reviews=== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspection was a pilot inspection, conducted as outlined in NRC Inspection Procedure (IP) 71111.21N. | | The inspection was a pilot inspection, conducted as outlined in NRC Inspection Procedure (IP) 71111.21N. The team assessed Entergys 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. |
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| The team assess ed 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. | |
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| This inspection effort included review of EQ program | | 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. |
| -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
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| . The team also reviewed Entergy's evaluation of applicable operating experience t o determine whether industry EQ
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| -related issues were understood and addressed through Entergy's corrective action program. Documents reviewed for this inspection are listed in the Attachment.
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| Component samples selected for this inspection are listed below.
| | 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 Entergys evaluation of applicable operating experience to determine whether industry EQ-related issues were understood and addressed through Entergys corrective action program. Documents reviewed for this inspection are listed in the Attachment. |
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| 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. | | 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 NRCs Division of Operating Reactors (DOR) Guidelines, as indicated below. |
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| 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) | | 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 | | High Pressure Coolant Injection (HPCI) System Inboard Isolation Valve 23MOV19 Residual Heat Removal System D Torus Isolation Valve 10MOV13D (DOR) |
| -3LT-72A MSIV 'A' Position Indication Limit Switches (Open, Closed, 85% Open) | | 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 | | Residual Heat Removal System A Flow Transmitter 10-FT-109A |
| -FT-109A | |
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| ====b. Findings==== | | ====b. Findings==== |
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| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES== |
| {{a|4OA2}} | | {{a|4OA2}} |
| ==4OA2 Identification== | | ==4OA2 Identification and Resolution of Problems (IP 71152)== |
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| and Resolution of Problems (IP 71152) | |
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| ====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. T he specific corrective action documents that were sampled a nd 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. The specific corrective action documents that were sampled and reviewed by the team are listed in the Attachment. |
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| B Findings No findings were identified. | | B Findings No findings were identified. |
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| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Meetings, including Exit== | | ==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. | | 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. |
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| The team verified that no proprietary information was documented in the report. | | The team verified that no proprietary information was documented in the report. |
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| ATTACHMENT | | ATTACHMENT |
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| =SUPPLEMENTAL | | =SUPPLEMENTAL INFORMATION= |
| INFORMATION= | |
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| ==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 Engi | | : [[contact::M. Hawes]], Regulatory Compliance Engineer |
| n eer
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| : [[contact::A. Lauzon]], EQ Engineer | | : [[contact::A. Lauzon]], EQ Engineer |
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| ==LIST OF ITEMS== | | ==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED== |
| OPENED, CLOSED , DISCUSSED, AND UPDATED | | |
| None | | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| EQ Files
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| : QDR 03.01, Limitorque Model SMB
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| and SB Motor-Operated Valves, Revision 12
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| : QDR 03.02, Limitorque Model SMB Motor
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| -Operated Valves, Revision 13
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| : QDR 04.01, General Electric 4KV Series SK6339XC Motors, Revision 3
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| : QDR 08.03, Foxboro I Model
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| : N-El 0 Series I Pressure Transmitters, Revision 2
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| : QDR 08.04, Rosemount 1153 Series B Transmitters and 353C Conduit Seals, Revision 3
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| : QDR 09.01, NAMCO Limit Switches Model EA740 Series, Revision 4
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| : QDR 34.03, NAMCO EC210 Series Receptacle and Connector/Cable Assemblies, Revision 4
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| : QDR 34.05, NAMCO Model EC290 Series Connector/Cable Assemblies, Revision 0
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| : QDR 35.07, Hiller Model SA
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| -A111 MSIV Solenoid Valve Cluster Assemblies, Revision 4
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| : QDR 35.08, Target Rock Model 1/2 SMS
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| -S-02-1 Solenoid Valve, Revision 4
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| ===Procedures===
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| : EN-MA-101-02, Control of Material Outside Facility Warehouse, Revision 6
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| : EN-NF-200, Special Nuclear Material Control, Revision 13
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| : EOP-4, Primary Containment Control, Revision 8
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| : IMP-G77, Replacement of Rosemount Pressure Transmitter Model 1153, Series B, Code R, with Conduit Seal 353*, Revision 14
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| : MP-059-51, Limitorque Actuators Inspection and Lubrication, Revision 35
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| : MP-200.19, NAMCO Connectors Maintenance, Revision 10
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| : MP-200.20, MSIV Solenoid Valve Cluster Assembly Replacement, Revision 05
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| ===Drawings===
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| : FM-20A, Flow Diagram Residual Heat Removal System, Revision 72
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| : FM-20B, Flow Diagram Residual Heat Removal System, Revision 63
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| ===Design and Licensing Basis Documents===
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| : JAF-SE-96-016, Acceptability of Establishing a One Hour Post Accident Operating Time Requirement for the ADS System to Mitigate LOCA, Revision 4
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| : James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, April 2015
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| : Safety Evaluation for E
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| : Q of Safety-Related Electrical Equipment, 4/19/83
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| ===Miscellaneous===
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| : EQCL Report, 1/14/16
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| : Letter , Nutherm International, Inc. to NRC , Final Update on Potential 10
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| : CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 2/3/16 Letter , Nutherm, International, Inc. to NRC , Update on Potential 10
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| : CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, 8/31/15
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| : 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
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| : NUREG-0588, Interim Staff Position on E
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| : Q of Safety-Related Electrical Equipment, Revision 1
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| : Operability Evaluation No. CR
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| -JAF-2016-0050, 10
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| : CFR 21 Issue Regarding Incorrect Industrial Irradiation Dose, dated 02/10/16
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| : PM Template
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| : 50047998-01, Stem Lube and Gearcase Grease Check per MP
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| -0 59-51 Pre-NRC CDBI EQ Snapshot Self
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| -Assessment, 1/12/16
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| : Purchase Order S
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| -96-82818, Torque Switch Assembly, 8/19/96 Snapshot Self
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| -Assessment EQ Program, 7/20/04
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| : Vendor Documents
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| : L200-0036, SMB Installation and Maintenance ManuaI, Revision 8
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| : N007-0123, Namco Limit Switch EA740 Series, Revision D
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| : R369-0030, Rosemount 1153 Series B Alphaline Nuclear Pressure Transmitter, Revision 7
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| ===Calculations and Engineering Evaluations===
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| : EC 0000014122, Modification to Improve SRV Reliability
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| - Replace 02RV
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| -71C, -71E and -71F with Target Rock Three
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| -Stage Safety/Relief Valves (Model 0867F), Revision 0
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| : JAF-CALC-09-00016, Attachment 21
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| : JAF-RPT-MISC-04046, Environmental Qualification Service Conditions, Revision 0
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| ===Condition Reports===
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| : 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
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| ===Work Orders===
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| : 51122191
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| : 51569866
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| : 51569867
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| : 51569867
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| : 52085457
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| : 52115739
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| : 52169613
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| : 52182411
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| : 52258742
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| : 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
| |
| PR A Probabilistic
| |
| Risk Assessment
| |
| SPAR Standardized
| |
| Plant Analysis Report
| |
| : [[UFSAR]] [[Updated Final Safety Analysis Report]]
| |
| : [[WO]] [[Work Order]]
| |
| }} | | }} |
|
---|
Category:Inspection Report
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 IR 05000333/20220062023-03-0101 March 2023 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2022006) IR 05000333/20220032022-11-10010 November 2022 Integrated Inspection Report 05000333/2022003 IR 05000333/20220052022-08-31031 August 2022 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2022005) IR 05000333/20220022022-08-10010 August 2022 Integrated Inspection Report 05000333/2022002 IR 05000333/20220102022-06-27027 June 2022 Reissued Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 ML22153A2612022-06-0202 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 IR 05000333/20210142022-05-23023 May 2022 Problem Identification and Resolution Inspection Report 05000333/2021014 IR 05000333/20220012022-05-0505 May 2022 Integrated Inspection Report 05000333/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2022001 IR 05000333/20210062022-03-0202 March 2022 Annual Assessment Letter for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021006) IR 05000333/20210042022-01-27027 January 2022 Integrated Inspection Report 05000333/2021004 IR 05000333/20210402021-11-0808 November 2021 95001 Supplemental Inspection Report 05000333/2021040 and Assessment Follow-Up Letter IR 05000333/20210032021-11-0808 November 2021 Integrated Inspection Report 05000333/2021003 IR 05000333/20213012021-10-0505 October 2021 Initial Operator Licensing Examination Report 05000333/2021301 IR 05000333/20215012021-09-29029 September 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2021501 IR 05000333/20210052021-09-0101 September 2021 Updated Inspection Plan for the James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021005) IR 05000333/20210132021-08-11011 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000333/2021013 IR 05000333/20210022021-08-0303 August 2021 James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002 ML21176A0052021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20210902021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20214022021-06-0909 June 2021 Security Baseline Inspection Report 05000333/2021402 IR 05000333/20210112021-06-0303 June 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000333/2021011 IR 05000333/20210012021-05-0505 May 2021 Integrated Inspection Report 05000333/2021001 IR 05000333/20210122021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000333/2021012 IR 05000333/20214012021-04-19019 April 2021 Material Control and Accounting Program Inspection Report 05000333/2021401 (Letter Only) IR 05000333/20210102021-04-0707 April 2021 Triennial Fire Protection Inspection Report 05000333/2021010 IR 05000333/20200062021-03-0303 March 2021 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2020006) IR 05000333/20200042021-02-11011 February 2021 Integrated Inspection Report 05000333/2020004 IR 05000333/20200122021-01-21021 January 2021 Problem Identification and Resolution Report 05000333/2020012 and Preliminary White Finding and Apparent Violation IR 05000333/20204202020-12-10010 December 2020 Security Inspection Report 05000333/2020420 IR 05000333/20200032020-11-10010 November 2020 Integrated Inspection Report 05000333/2020003 IR 05000333/20204022020-09-16016 September 2020 Security Baseline Inspection Report 05000333/2020402 IR 05000333/20200052020-08-31031 August 2020 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2020005) IR 05000333/20200022020-08-10010 August 2020 Integrated Inspection Report 05000333/2020002 IR 05000333/20204012020-07-28028 July 2020 Cyber Security Inspection Report 05000333/2020401 (Letter Only) IR 05000333/20200112020-04-30030 April 2020 Problem Identification and Resolution Annual Sample Inspection Report 05000333/2020011 IR 05000333/20200012020-04-28028 April 2020 Integrated Inspection Report 05000333/2020001 2024-02-07
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
[Table view] |
Text
UNITED STATES rch 17, 2016
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 Commissions rules and regulations and with the conditions of your license.
In conducting the inspection, the team examined Entergys 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 NRCs 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 NRCs 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
ML16078A132 Non-Sensitive Publicly Available SUNSI Review Sensitive 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
Enclosure:
Inspection Report 05000333/2016008 w/Attachment: Supplemental Information
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 i Enclosure
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 NRCs 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.
ii
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 Entergys 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 Commissions (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 FitzPatricks EQ program implementation through a series of onsite inspections in the 1980s. The EQ program at that time established measures to ensure EQ through the 40-year operating license period. Since that time, Entergy had renewed FitzPatricks 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 Entergys 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 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 Entergys evaluation of applicable operating experience to determine whether industry EQ-related issues were understood and addressed through Entergys 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 NRCs Division of Operating Reactors (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. The specific corrective action documents that were sampled and 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. 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.
ATTACHMENT
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Entergy Personnel
- V. Bacanskas, Director, Chief Engineer
- J. Eckman, Senior Design Engineer
- M. Hawes, Regulatory Compliance Engineer
- A. Lauzon, EQ Engineer
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
None
LIST OF DOCUMENTS REVIEWED