IR 05000219/2018010: Difference between revisions

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I-20 18-0 10-0055 Licensee: Exelon Generation Company, LLC Facility: Oyster Creek Nuclear Generating Station Location: Forked River, NJ Inspection Dates: January 29, 2018 to February 14, 2018 Inspectors:
I-20 18-0 10-0055 Licensee: Exelon Generation Company, LLC Facility: Oyster Creek Nuclear Generating Station Location: Forked River, NJ Inspection Dates: January 29, 2018 to February 14, 2018 Inspectors:
C. Bickett, Senior Reactor Inspector J. Kulp, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector Approved By:
C. Bickett, Senior Reactor Inspector J. Kulp, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector Approved By:
G. Dentel , Chief Engineering Branch 2 Division of Reactor Safety 2 SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelon's performance at Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Proces The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactor Refer to https://www.nrc.gov/reactors/operating/oversight.html for more informatio No findings or more
G. Dentel , Chief Engineering Branch 2 Division of Reactor Safety 2  
-than-minor violations were identifie INSPECTION SCOPE This inspection w as conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise note Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading
 
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring
 
Exelon's performance at Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
 
No findings or more-than-minor violations were identified.
 
=INSPECTION SCOPE=
 
This inspection w as conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading
-rm/doc-collections/insp
-rm/doc-collections/insp
-manual/inspection
-manual/inspection
-procedure/index.htm Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light
-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light
-Water Reactor Inspection Program - Operations Phase."
-Water Reactor Inspection Program - Operations Phase."


The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standard REACTOR SAFETY 71111.21 N - Design Bas e s Assurance Inspection (Program s) Programs (Environmental Qualification)
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
  (7 Samples) The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018: 1) Electromatic relief valve NR
 
-108-A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors
==REACTOR SAFETY==
] 2) Main steam isolation valve V
71111.21 N - Design Bas e s Assurance Inspection (Program s) Programs (Environmental Qualification)
-1-007 [solenoid valve coil and elastomers
  (7 Samples) The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018: 1) Electromatic relief valve NR A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors
] 3) Core spray pump NZ01
] 2) Main steam isolation valve V 007 [solenoid valve coil and elastomers
] 3) Core spray pump NZ01
-B [motor and motor lubrication]
-B [motor and motor lubrication]
4) Narrow range drywell pressure instrument PT
4) Narrow range drywell pressure instrument PT 9A [pressure transmitter, operational amplifier, and O-ring] 5) Primary containment electrical penetration X
-642-9A [pressure transmitter, operational amplifier, and O-ring] 5) Primary containment electrical penetration X
-31A [epoxy sealant and thermocouple cables
-31A [epoxy sealant and thermocouple cables
] 6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring] 7) Reactor fuel zone level temperature element TE
] 6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring] 7) Reactor fuel zone level temperature element TE 1A [thermocouple, head gasket and silicone sealant
-56-1A [thermocouple, head gasket and silicone sealant
]  
]
 
3 EXIT MEETING S AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this repor On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staf DOCUMENTS REVIEWED 71111.21 N Procedures 2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation, Revision 25 610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In
==EXIT MEETING S AND DEBRIEFS==
-Service Test, Revision 72 665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15 EMG-3200.01A-FC, RPV Control  
The inspectors verified no proprietary information was retained or documented in this report.
- No ATWS EOP Flowchart, Revision 10 MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5 PES-S-002, Shelf Life, Revision 8 SM-AA-102, Warehouse Operations, Revision 24 Issue Reports (*initiated in response to inspection)
 
280415 354622 354637 554544 756924 844027 847413 862399 875631 880917 893317 911682 983859 1008809 1147890 1426157 1518358 1568796 1680592 2394239 2397876 2424903 2532305 2567167 2640145 3946707 3975833 3998185 3998203 3998203 4065078 4074271 4074273 4075139 4080517 4086301 4099394 4098406* 4099776* 4099904* 4103093* 4103107* Equipment Qualification Files OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8 OC-302, Dresser Controllers, Model 1539VX, Revision 6 OC-303, General Electric Electrical Penetrations, Model F01, Revision 5 OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5 OC-306, General Electric Motor Control Center (MCC), Model IC
On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staff. 
-7700, Revision 5 OC-307, General Electric Pump Motor, Revision 9 OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6 OC-323, Barksdale Pressure Switches, Revision 7 OC-353, Solenoid Valves, Revision 4 OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6 OC-365, PYCO Temperature Elements, Revision 6 OC-392, Patel Electrical Connectors, Revision 7 OC-396, Raychem Cable Splice, Revision 7 Test Reports EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical Connectors Model 841203
 
-7-12, dated 9/15/00 EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06
=DOCUMENTS REVIEWED=
 
71111.21 N Procedures
2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation, Revision 25
610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In
-Service Test, Revision 72
665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15
EMG-3200.01A-FC, RPV Control  
- No ATWS EOP Flowchart, Revision 10
MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5
PES-S-002, Shelf Life, Revision 8
SM-AA-102, Warehouse Operations, Revision 24
Issue Reports (*initiated in response to inspection)
280415 354622 354637 554544 756924 844027 847413 862399 875631 880917 893317 911682 983859 1008809 1147890 1426157 1518358 1568796 1680592 2394239 2397876 2424903 2532305 2567167 2640145 3946707 3975833 3998185 3998203 3998203 4065078 4074271 4074273 4075139 4080517 4086301 4099394 4098406* 4099776* 4099904* 4103093* 4103107*     Equipment Qualification Files
OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8
OC-302, Dresser Controllers, Model 1539VX, Revision 6
OC-303, General Electric Electrical Penetrations, Model F01, Revision 5
OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5
OC-306, General Electric Motor Control Center (MCC), Model IC
-7700, Revision 5
OC-307, General Electric Pump Motor, Revision 9
OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6
OC-323, Barksdale Pressure Switches, Revision 7
OC-353, Solenoid Valves, Revision 4
OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6
OC-365, PYCO Temperature Elements, Revision 6
OC-392, Patel Electrical Connectors, Revision 7
OC-396, Raychem Cable Splice, Revision 7
Test Reports
EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical Connectors Model 841203
-7-12, dated 9/15/00
EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06


4 EPRI Report 1016272, Turbine Oil Compatibility  
EPRI Report 1016272, Turbine Oil Compatibility  
- Mobil DTE 372: Addition of New Generation Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008 EPRI Report 1019593, Radiation Stability of Modern Turbine Oils  
- Mobil DTE 372: Addition of New Generation Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008
EPRI Report 1019593, Radiation Stability of Modern Turbine Oils  
- Group II Turbine Oils Exposed to Loss
- Group II Turbine Oils Exposed to Loss
-of-Coolant Accident Radiation, September 2009 GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation, November 1991 PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by Patel Engineers for use in Nuclear Power Plants, dated 5/5/86 PEP No. 42963, Project Engineer Program Test  
-of-Coolant Accident Radiation, September 2009 GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation, November 1991 PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by Patel Engineers for use in Nuclear Power Plants, dated 5/5/86
- Dresser Relief Valve Actuator, dated 6/11/68 R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A, 581A, and 583A Differential Pressure Switches, dated 12/22/83 Report No. 45592
PEP No. 42963, Project Engineer Program Test  
-3, Nuclear Environmental Qualification Test Program on Rosemount 1153 Series D Pressure Transmitters, dated 5/4/83 Report No. 46882
- Dresser Relief Valve Actuator, dated 6/11/68
R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A, 581A, and 583A Differential Pressure Switches, dated 12/22/83
Report No. 45592
-3, Nuclear Environmental Qualification Test Program on Rosemount 1153 Series D Pressure Transmitters, dated 5/4/83
Report No. 46882
-0, Performance and Recertification Testing of Dresser Electromatic relief Valve (Type 1525VX
-0, Performance and Recertification Testing of Dresser Electromatic relief Valve (Type 1525VX
-3) for GPU Nuclear, Inc., dated 2/11/99 Report No. 58442
-3) for GPU Nuclear, Inc., dated 2/11/99
Report No. 58442
-1, Environmental Qualification Test Report of Raychem WCSF
-1, Environmental Qualification Test Report of Raychem WCSF
-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80 Report No. 58722
-N Nuclear
In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80
Report No. 58722
-2, Environmental Qualification Test Report of Raychem WCSF
-2, Environmental Qualification Test Report of Raychem WCSF
-N Nuclear In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82 Work Orders 00028865 00028866 04348666 04357851 04584366 04682332 04688852 04700696 04712762 057890 510614 C0551610 C2013622 R2027147 R2060096 R2068283 R2094168 R2094317 R2119989 R2128488 R2132376 R2133635 R2134243 R2139132 R2145456 R2158529 R2173050 R2211760 R2215539 R2246426 Calculations C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1 C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy Calculation, Revision 0 C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study, Revision 3 C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0 GENE-0000-0027-3965, Similarity Analysis  
-N Nuclear
In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82
Work Orders
00028865 00028866 04348666 04357851 04584366 04682332 04688852 04700696 04712762 057890 510614 C0551610 C2013622 R2027147 R2060096 R2068283 R2094168 R2094317 R2119989 R2128488 R2132376 R2133635 R2134243 R2139132 R2145456 R2158529 R2173050 R2211760 R2215539 R2246426 Calculations
C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1
C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy Calculation, Revision 0
C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study, Revision 3
C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0
GENE-0000-0027-3965, Similarity Analysis  
- DD233A3620P001 vs. CR9503
- DD233A3620P001 vs. CR9503
-213CAT55 Solenoids, dated 3/26/04 Report No. 02
-213CAT55 Solenoids, dated 3/26/04
-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks, Revision 0 Drawings 102-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84 846D986, Sheet 1, Penetration Seal 'TH', Revision 5 GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35 GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout  
Report No. 02
- RB 51', Revision 0 GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2 GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4 Operating Experience NRC Bulletin 90
-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks, Revision 0
Drawings 102-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84 846D986, Sheet 1, Penetration Seal 'TH', Revision 5
GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35
GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout  
- RB 51', Revision 0
GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2
GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4
Operating Experience
NRC Bulletin 90
-01, Supplement 1, Loss of Fill
-01, Supplement 1, Loss of Fill
-Oil in Transmitter Manufactured by Rosemount, dated 12/22/92 NRC Information Notice 89
-Oil in Transmitter Manufactured by Rosemount, dated 12/22/92
-42, Failure of Rosemount Models 1153 and 1154 Transmitters, dated 4/21/89 5 Vendor Manuals VM-OC-0002, 24" Main Steam Isolation Valve, Revision 10 VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4 VM-OC-0039, PYCO Temperature Elements, Revision 2 VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11 VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6 VM-OC-0285, ITT Barton Model 580 A
NRC Information Notice 89
-0 DPIS, Revision 5 VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with Model 224C DPU, Revision 5 VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical Connector, Revision 1 VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3 VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2 VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH
-42, Failure of Rosemount Models 1153 and 1154 Transmitters, dated 4/21/89
-3160), Revision 8 VM-OC-6379, GEK-13903 Penetration Seals, Revision 0 Miscellaneous 1021067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1 21A5477, Relief Valve Specification, Revision 0 619.3.005, High Flow in the Main Steam Line Test and Calibration, performed 10/2/17 DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor Evaluation, dated 12/4/98 ECR ECP 15
Vendor Manuals
VM-OC-0002, 24" Main Steam Isolation Valve, Revision 10
VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4
VM-OC-0039, PYCO Temperature Elements, Revision 2
VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11
VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6
VM-OC-0285, ITT Barton Model 580 A
-0 DPIS, Revision 5
VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with Model 224C DPU, Revision 5
VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical Connector, Revision 1
VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3
VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2
VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH
-3160), Revision 8 VM-OC-6379, GEK-13903 Penetration Seals, Revision 0
Miscellaneous
21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1
21A5477, Relief Valve Specification, Revision 0
619.3.005, High
Flow in the Main Steam Line Test and Calibration, performed 10/2/17
DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor Evaluation, dated 12/4/98
ECR ECP 15
-00376, Core Spray Motor P
-00376, Core Spray Motor P
-20-1B As-Is Acceptance of Vibration ECR IEC 10-00401, Canadian Core Spray Pump Motor EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87, and 3/30/88 ES-027, Environmental Parameters  
-20-1B As-Is Acceptance of Vibration
- Oyster Creek NGS, Revision 4 Five-Year Vibration Trend Plots  
ECR IEC 10-00401, Canadian Core Spray Pump Motor
EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87, and 3/30/88 ES-027, Environmental Parameters  
- Oyster Creek NGS, Revision 4
Five-Year Vibration Trend Plots  
- NZ01B Core Spray Main Motor P
- NZ01B Core Spray Main Motor P
-20-1B LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical Equipment Important to Safety  
-20-1B LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical Equipment Important to Safety  
- Oyster Creek Nuclear Generating Station, dated 5/28/85 OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray Pump NZ01-B Maintenance Strategy NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of Limited Life Items, dated May 1992 NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990 NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications NRC Inspection Report 05000219/86
- Oyster Creek Nuclear Generating Station, dated 5/28/85 OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray
-08 (EQ Program Implementation), dated 8/8/86 OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain Installation, Revision 0 OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17 OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS
Pump NZ01-B Maintenance Strategy
-RE0022A Maintenance Strategy, dated 6/7/17 OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17 Oyster Creek EQ Master List, dated 1/8/14 Pre-NRC EQ DBA Self
NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of Limited Life Items, dated May 1992
NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990
NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications
NRC Inspection Report 05000219/86
-08 (EQ Program Implementation), dated 8/8/86
OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain Installation, Revision 0
OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17
OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS
-RE0022A Maintenance Strategy, dated 6/7/17
OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17
Oyster Creek EQ Master List, dated 1/8/14
Pre-NRC EQ DBA Self
-Assessment, dated 11/13/17 (AR 03966720)
-Assessment, dated 11/13/17 (AR 03966720)
SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System, Revision 3 SE No. 000210
SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System, Revision 3
-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13 Level Transmitters Safety Evaluation, Revision 0 SE No. 315403
SE No. 000210
-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13 Level Transmitters Safety Evaluation, Revision 0
SE No. 315403
-019, Drywell Design Pressure Reduction  
-019, Drywell Design Pressure Reduction  
- Tech Spec Change, Revision 1 SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0 TDR 1003, Environmental Qualification 'Sound Reasons to the Contrary' Guidelines, Revision 0
- Tech Spec Change, Revision 1
SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0
TDR 1003, Environmental Qualification 'Sound Reasons to the Contrary' Guidelines, Revision 0
}}
}}

Revision as of 03:01, 9 September 2018

Oyster Creek Design Bases Assurance Inspection (Programs) Report 05000219/2018010
ML18059A201
Person / Time
Site: Oyster Creek
Issue date: 02/28/2018
From: Dentel G T
NRC Region 1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Dentel G T
References
IR 2018010
Download: ML18059A201 (7)
v • d • e


Text

Addressee (First Init UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406

-2713 February 28, 2018 Mr. Bryan C. Hanson Senior Vice President, Exelon Generation Co., LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: OYSTER CREEK

- DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000 219/2018010 Dear Mr. Hanson

On February 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the Environmental Qualification Program implementation at Oyster Creek Nuclear Generating Statio The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staf The results of this inspection are documented in the enclosed repor The NRC inspectors did not identify any finding s or violation s of more-than-minor significanc This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading

-rm/adams.html and the NRC

's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/ Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects Docket Number:

50-219 License Number:

DPR-16

Enclosure:

Inspection Report 05000219/2018010 cc w/encl:

Distribution via ListServ B.Hanson2

SUBJECT: OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000 219/2018010 DATED FEBRUARY 28, 2018 Distribution: (e

-mail) DCollins, RA DLew, DRA MGray, DRP DPelton, DRP BWelling, DRS JYerokun, DRS MYoung, BC SShaffer, DRP CSafouri, DRP APatel, SRI EAndrews, DRP, RI GDentel, DRS CBickett, DRS KMcKenzie, DRP JBowen, RI, OEDO RidsNrrPMOysterCreek Resource RidsNrrDorlLpl1 Resource

ROPreports Resource DOCUMENT NAME:

G:\DRS\Engineering Branch 2

\Environmental Qualification (EQ)

\EQ Insp Reports (Region 1 only)\Oyster Creek EQ IR 2018010.docx ADAMS ACCESSION N UMBER: ML18059A201 SUNSI ReviewNon-SensitiveSensitivePublicly AvailableNon-Publicly AvailableOFFICE RI/DRS RI/DR P RI/DRS NAME CBickett MYoung GDentel DATE 02/22/18 02/22/18 02/28 18 OFFICIAL RECORD COPY

1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 50-219 License Number: DPR-16 Report Number: 05000 219/20 18010 Enterprise Identifier:

I-20 18-0 10-0055 Licensee: Exelon Generation Company, LLC Facility: Oyster Creek Nuclear Generating Station Location: Forked River, NJ Inspection Dates: January 29, 2018 to February 14, 2018 Inspectors:

C. Bickett, Senior Reactor Inspector J. Kulp, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector Approved By:

G. Dentel , Chief Engineering Branch 2 Division of Reactor Safety 2

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring

Exelon's performance at Oyster Creek Nuclear Generating Station by conducting an engineering programs design bases assurance inspection of environmental qualification program implementation in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

No findings or more-than-minor violations were identified.

INSPECTION SCOPE

This inspection w as conducted using the appropriate portions of the inspection procedure (IP) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading

-rm/doc-collections/insp

-manual/inspection

-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light

-Water Reactor Inspection Program - Operations Phase."

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21 N - Design Bas e s Assurance Inspection (Program s) Programs (Environmental Qualification)

(7 Samples) The inspectors evaluated environmental qualification program implementation by reviewing the licensed environmental qualification requirements for the following components and a sample of their associated subcomponents from January 29, 2018 to February 14, 2018: 1) Electromatic relief valve NR A [electromatic actuator, controller, pressure switch, Raychem cable splice, and electrical connectors

] 2) Main steam isolation valve V 007 [solenoid valve coil and elastomers

] 3) Core spray pump NZ01

-B [motor and motor lubrication]

4) Narrow range drywell pressure instrument PT 9A [pressure transmitter, operational amplifier, and O-ring] 5) Primary containment electrical penetration X

-31A [epoxy sealant and thermocouple cables

] 6) Main steam high flow sensor switch DPIS-RE0022A [differential pressure indicating switch, wire insulation, and O-ring] 7) Reactor fuel zone level temperature element TE 1A [thermocouple, head gasket and silicone sealant

]

EXIT MEETING S AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On February 14, 2018, the inspector presented the design bases assurance inspection results to Mr. Timothy Moore, Site Vice President, and other members of Exelon staff.

DOCUMENTS REVIEWED

71111.21 N Procedures

2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation, Revision 25

610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In

-Service Test, Revision 72

665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15

EMG-3200.01A-FC, RPV Control

- No ATWS EOP Flowchart, Revision 10

MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5

PES-S-002, Shelf Life, Revision 8

SM-AA-102, Warehouse Operations, Revision 24

Issue Reports (*initiated in response to inspection)

280415 354622 354637 554544 756924 844027 847413 862399 875631 880917 893317 911682 983859 1008809 1147890 1426157 1518358 1568796 1680592 2394239 2397876 2424903 2532305 2567167 2640145 3946707 3975833 3998185 3998203 3998203 4065078 4074271 4074273 4075139 4080517 4086301 4099394 4098406* 4099776* 4099904* 4103093* 4103107* Equipment Qualification Files

OC-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8

OC-302, Dresser Controllers, Model 1539VX, Revision 6

OC-303, General Electric Electrical Penetrations, Model F01, Revision 5

OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5

OC-306, General Electric Motor Control Center (MCC), Model IC

-7700, Revision 5

OC-307, General Electric Pump Motor, Revision 9

OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6

OC-323, Barksdale Pressure Switches, Revision 7

OC-353, Solenoid Valves, Revision 4

OC-360, Rosemount Pressure Transmitters, Models 1153 Series B and 1154, Revision 6

OC-365, PYCO Temperature Elements, Revision 6

OC-392, Patel Electrical Connectors, Revision 7

OC-396, Raychem Cable Splice, Revision 7

Test Reports

EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical Connectors Model 841203

-7-12, dated 9/15/00

EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06

EPRI Report 1016272, Turbine Oil Compatibility

- Mobil DTE 372: Addition of New Generation Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008

EPRI Report 1019593, Radiation Stability of Modern Turbine Oils

- Group II Turbine Oils Exposed to Loss

-of-Coolant Accident Radiation, September 2009 GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation, November 1991 PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by Patel Engineers for use in Nuclear Power Plants, dated 5/5/86

PEP No. 42963, Project Engineer Program Test

- Dresser Relief Valve Actuator, dated 6/11/68

R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A, 581A, and 583A Differential Pressure Switches, dated 12/22/83

Report No. 45592

-3, Nuclear Environmental Qualification Test Program on Rosemount 1153 Series D Pressure Transmitters, dated 5/4/83

Report No. 46882

-0, Performance and Recertification Testing of Dresser Electromatic relief Valve (Type 1525VX

-3) for GPU Nuclear, Inc., dated 2/11/99

Report No. 58442

-1, Environmental Qualification Test Report of Raychem WCSF

-N Nuclear

In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80

Report No. 58722

-2, Environmental Qualification Test Report of Raychem WCSF

-N Nuclear

In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82

Work Orders

00028865 00028866 04348666 04357851 04584366 04682332 04688852 04700696 04712762 057890 510614 C0551610 C2013622 R2027147 R2060096 R2068283 R2094168 R2094317 R2119989 R2128488 R2132376 R2133635 R2134243 R2139132 R2145456 R2158529 R2173050 R2211760 R2215539 R2246426 Calculations

C-1302-411-5320-002, Oyster Creek EMRV Solenoid Heat Transfer Analysis, Revision 1

C-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy Calculation, Revision 0

C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study, Revision 3

C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0

GENE-0000-0027-3965, Similarity Analysis

- DD233A3620P001 vs. CR9503

-213CAT55 Solenoids, dated 3/26/04

Report No. 02

-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks, Revision 0

Drawings 102-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84 846D986, Sheet 1, Penetration Seal 'TH', Revision 5

GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35

GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout

- RB 51', Revision 0

GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2

GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4

Operating Experience

NRC Bulletin 90

-01, Supplement 1, Loss of Fill

-Oil in Transmitter Manufactured by Rosemount, dated 12/22/92

NRC Information Notice 89

-42, Failure of Rosemount Models 1153 and 1154 Transmitters, dated 4/21/89

Vendor Manuals

VM-OC-0002, 24" Main Steam Isolation Valve, Revision 10

VM-OC-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4

VM-OC-0039, PYCO Temperature Elements, Revision 2

VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11

VM-OC-0091, Raychem Product Selection and Installation Guides, Revision 6

VM-OC-0285, ITT Barton Model 580 A

-0 DPIS, Revision 5

VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with Model 224C DPU, Revision 5

VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical Connector, Revision 1

VM-OC-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3

VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2

VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH

-3160), Revision 8 VM-OC-6379, GEK-13903 Penetration Seals, Revision 0

Miscellaneous

21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1

21A5477, Relief Valve Specification, Revision 0

619.3.005, High

Flow in the Main Steam Line Test and Calibration, performed 10/2/17

DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor Evaluation, dated 12/4/98

ECR ECP 15

-00376, Core Spray Motor P

-20-1B As-Is Acceptance of Vibration

ECR IEC 10-00401, Canadian Core Spray Pump Motor

EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87, and 3/30/88 ES-027, Environmental Parameters

- Oyster Creek NGS, Revision 4

Five-Year Vibration Trend Plots

- NZ01B Core Spray Main Motor P

-20-1B LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical Equipment Important to Safety

- Oyster Creek Nuclear Generating Station, dated 5/28/85 OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray

Pump NZ01-B Maintenance Strategy

NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of Limited Life Items, dated May 1992

NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990

NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications

NRC Inspection Report 05000219/86

-08 (EQ Program Implementation), dated 8/8/86

OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain Installation, Revision 0

OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17

OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS

-RE0022A Maintenance Strategy, dated 6/7/17

OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A Maintenance Strategy, dated 6/7/17

Oyster Creek EQ Master List, dated 1/8/14

Pre-NRC EQ DBA Self

-Assessment, dated 11/13/17 (AR 03966720)

SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System, Revision 3

SE No. 000210

-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13 Level Transmitters Safety Evaluation, Revision 0

SE No. 315403

-019, Drywell Design Pressure Reduction

- Tech Spec Change, Revision 1

SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0

TDR 1003, Environmental Qualification 'Sound Reasons to the Contrary' Guidelines, Revision 0

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