IR 05000219/2018010: Difference between revisions

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| issue date = 02/28/2018
| issue date = 02/28/2018
| title = Design Bases Assurance Inspection (Programs) Report 05000219/2018010
| title = Design Bases Assurance Inspection (Programs) Report 05000219/2018010
| author name = Dentel G T
| author name = Dentel G
| author affiliation = NRC/RGN-I
| author affiliation = NRC/RGN-I
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000219
| docket = 05000219
| license number = DPR-016
| license number = DPR-016
| contact person = Dentel G T
| contact person = Dentel G
| document report number = IR 2018010
| document report number = IR 2018010
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:Addressee (First Init UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406
{{#Wiki_filter:February 28, 2018
-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
==SUBJECT:==
: 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
OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)  
-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."
REPORT 05000219/2018010
 
==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 Station. The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
 
The NRC inspectors did not identify any findings or violations of more-than-minor significance.
 
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 NRCs 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,
Sincerely,
/RA/ Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects Docket Number:
/RA/  
50-219 License Number:
 
DPR-16 Enclosure:
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Projects  
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:
Docket Number: 50-219 License Number: DPR-16
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
===Enclosure:===
Inspection Report 05000219/2018010


==Inspection Report==
==Inspection Report==
Docket Number: 50-219 License Number: DPR-16 Report Number: 05000 219/20 18010 Enterprise Identifier:
Docket Number:
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:
50-219  
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
License Number:
DPR-16  
 
Report Number:
05000219/2018010
 
Enterprise Identifier: I-2018-010-0055  
 
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  


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at


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.
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 NRCs 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.
No findings or more-than-minor violations were identified.
Line 55: Line 89:
=INSPECTION SCOPE=
=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
This inspection was 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.
-rm/doc-collections/insp
 
-manual/inspection
==REACTOR SAFETY==
-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
===71111.21N - Design Bases Assurance Inspection (Programs) Programs (Environmental Qualification)===
-Water Reactor Inspection Program - Operations Phase."
{{IP sample|IP=IP 71111.21|count=7}}
 
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:


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.
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-1-007 [solenoid valve coil and elastomers]
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
3) Core spray pump NZ01-B [motor and motor lubrication]  
]  2) Main steam isolation valve V 007 [solenoid valve coil and elastomers
 
]  3) Core spray pump NZ01
4) Narrow range drywell pressure instrument PT-642-9A [pressure transmitter, operational amplifier, and O-ring]  
-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
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 1A [thermocouple, head gasket and silicone sealant
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-56-1A [thermocouple, head gasket and silicone sealant]


==EXIT MEETING S AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
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.
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=
=DOCUMENTS REVIEWED=


71111.21 N  Procedures
71111.21N
2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation, Revision 25
Procedures
610.4.012, Core Spray System 1 Pump Comprehensive/Preservice In
2400-SME-3918.03, EMRV Solenoid Operator Removal, Refurbishment, and Installation,
-Service Test, Revision 72
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
665.3.021, Containment Electrical Penetration Nitrogen Blanket Surveillance, Revision 15
EMG-3200.01A-FC, RPV Control  
EMG-3200.01A-FC, RPV Control - No ATWS EOP Flowchart, Revision 10
- No ATWS EOP Flowchart, Revision 10
MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5
MA-AA-716-230-1002, Vibration Analysis/Acceptance Guideline, Revision 5
PES-S-002, Shelf Life, Revision 8
PES-S-002, Shelf Life, Revision 8
SM-AA-102, Warehouse Operations, Revision 24
SM-AA-102, Warehouse Operations, Revision 24
Issue Reports (*initiated in response to inspection)
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
280415
354622
354637
554544
756924
844027
847413
2399
875631
880917
893317
911682
983859
1008809
1147890
26157
1518358
1568796
1680592
2394239
2397876
24903
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-301, Dresser Electromatic Actuator, Model 1525VX, Revision 8
OC-302, Dresser Controllers, Model 1539VX, Revision 6
OC-302, Dresser Controllers, Model 1539VX, Revision 6
OC-303, General Electric Electrical Penetrations, Model F01, Revision 5
OC-303, General Electric Electrical Penetrations, Model F01, Revision 5
OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5
OC-305, ITE/Gould Motor Control Center, Model 5600, Revision 5
OC-306, General Electric Motor Control Center (MCC), Model IC
OC-306, General Electric Motor Control Center (MCC), Model IC-7700, Revision 5
-7700, Revision 5
OC-307, General Electric Pump Motor, Revision 9
OC-307, General Electric Pump Motor, Revision 9
OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6
OC-320, ITT Barton, Models 580A & 581A, Differential Pressure Indicating Switches, Revision 6
Line 108: Line 187:
OC-396, Raychem Cable Splice, Revision 7
OC-396, Raychem Cable Splice, Revision 7
Test Reports
Test Reports
EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical Connectors Model 841203
EGS-TR-23050-0074-02, Test Report for Nuclear Environmental Qualification of EGS Electrical
-7-12, dated 9/15/00
Connectors Model 841203-7-12, dated 9/15/00
EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06
EGS-TR-23050-0264-03, Final Report for Barksdale Pressure Switches, dated 5/19/06  


EPRI Report 1016272, Turbine Oil Compatibility  
EPRI Report 1016272, Turbine Oil Compatibility - Mobil DTE 372: Addition of New Generation
- Mobil DTE 372: Addition of New Generation Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008
Oil to Traditional DTE 797 and Teresstic GT 32 Oil, Technical Update, March 2008
EPRI Report 1019593, Radiation Stability of Modern Turbine Oils  
EPRI Report 1019593, Radiation Stability of Modern Turbine Oils - Group II Turbine Oils
- Group II Turbine Oils Exposed to Loss
Exposed to Loss-of-Coolant Accident Radiation, September 2009
-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
GENE-189-22-0591, 500HP Core Spray Pump Motor for GPU Nuclear Corporation,
PEP No. 42963, Project Engineer Program Test  
November 1991
- Dresser Relief Valve Actuator, dated 6/11/68
PEI-TR-841203-05, Final Test Report on Patel Electrical Connectors Manufactured by
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
Patel Engineers for use in Nuclear Power Plants, dated 5/5/86
Report No. 45592
PEP No. 42963, Project Engineer Program Test - Dresser Relief Valve Actuator, dated 6/11/68
-3, Nuclear Environmental Qualification Test Program on Rosemount 1153 Series D Pressure Transmitters, dated 5/4/83
R3-580A-9, Class 1E Qualification Test Program and Results for ITT Barton Models 580A,
Report No. 46882
581A, and 583A Differential Pressure Switches, dated 12/22/83
-0, Performance and Recertification Testing of Dresser Electromatic relief Valve (Type 1525VX
Report No. 45592-3, Nuclear Environmental Qualification Test Program on Rosemount 1153
-3) for GPU Nuclear, Inc., dated 2/11/99
Series D Pressure Transmitters, dated 5/4/83
Report No. 58442
Report No. 46882-0, Performance and Recertification Testing of Dresser Electromatic relief
-1, Environmental Qualification Test Report of Raychem WCSF
Valve (Type 1525VX-3) for GPU Nuclear, Inc., dated 2/11/99
-N Nuclear
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
In-Line Cable Splice Assemblies for Raychem Corporation, dated 5/15/80
Report No. 58722
Report No. 58722-2, Environmental Qualification Test Report of Raychem WCSF-N Nuclear
-2, Environmental Qualification Test Report of Raychem WCSF
-N Nuclear
In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82
In-Line Bolted Splice Assemblies for Raychem Corporation, dated 11/18/82
Work Orders
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
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-1302-411-5320-002, 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-1302-642-5350-004, Oyster Creek Containment Spray Mod Drywell Pressure Accuracy
C-1302-731-E510-015, OC Degraded Grid Undervoltage Relay Setpoint Evaluation Study, Revision 3
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
C-1302-822-E610-076, Flooding due to HELBs Outside of Containment, Revision 0
GENE-0000-0027-3965, Similarity Analysis  
GENE-0000-0027-3965, Similarity Analysis - DD233A3620P001 vs. CR9503-213CAT55
- DD233A3620P001 vs. CR9503
Solenoids, dated 3/26/04
-213CAT55 Solenoids, dated 3/26/04
Report No. 02-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks,
Report No. 02
Revision 0
-0370-1336, Evaluation of Environment Conditions from High Energy Line Breaks, Revision 0
Drawings
Drawings 102-0270, Sheet 1, Thermocouple Assembly, dated 4/5/84 846D986, Sheet 1, Penetration Seal 'TH', Revision 5
2-0270, 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
GE 729E182, Auto Depressurization SYS Electrical Elementary Diagram, Revision 35
GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout  
GU 3D-622-14-001, Reactor Plant Instrumentation Conduit Layout - RB 51, Revision 0
- RB 51', Revision 0
GU 3D-642-15-001, Elec. Conn. and Splice Details Automatic Depressurization SYS, Revision 2
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
GU 3D-642-18-001, Interconnection Diagram Automatic Depressurization SYS, Revision 4
Operating Experience
Operating Experience
NRC Bulletin 90
NRC Bulletin 90-01, Supplement 1, Loss of Fill-Oil in Transmitter Manufactured by Rosemount,
-01, Supplement 1, Loss of Fill
dated 12/22/92
-Oil in Transmitter Manufactured by Rosemount, dated 12/22/92
NRC Information Notice 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters,
NRC Information Notice 89
dated 4/21/89
-42, Failure of Rosemount Models 1153 and 1154 Transmitters, dated 4/21/89
 
Vendor Manuals
Vendor Manuals
VM-OC-0002, 24" Main Steam Isolation Valve, Revision 10
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-0030, Installation and Maintenance Manual for Electromatic Relief Valves, Revision 4
VM-OC-0039, PYCO Temperature Elements, Revision 2
VM-OC-0039, PYCO Temperature Elements, Revision 2
VM-OC-0083, ASCO Solenoid Valve Installation and Maintenance Manual, Revision 11
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-0091, Raychem Product Selection and Installation Guides, Revision 6
VM-OC-0285, ITT Barton Model 580 A
VM-OC-0285, ITT Barton Model 580 A-0 DPIS, Revision 5
-0 DPIS, Revision 5
VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with
VM-OC-0347, Barton Model 227A DPIs and Model 224 DPUs, and Cameron Model 227C with Model 224C DPU, Revision 5
Model 224C DPU, Revision 5
VM-OC-2253, Installation & Assembly Procedure for Patel Quick Disconnect Electrical Connector, Revision 1
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-2317, Model 1154 Rosemount Pressure Transmitters, Revision 3
VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2
VM-OC-2369, 500HP Core Spray Pump Motor EN 139149, Revision 2
VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH
VM-OC-5016, GE Industrial Motors Including Custom 8000 Horizontal Motor (GEH-3160),
-3160), Revision 8 VM-OC-6379, GEK-13903 Penetration Seals, Revision 0
Revision 8
VM-OC-6379, GEK-13903 Penetration Seals, Revision 0
Miscellaneous
Miscellaneous
21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1
21067, EPRI Plant Support Engineering: Nuclear Power Plant Equipment Qualification
Reference Manual, Revision 1
21A5477, Relief Valve Specification, Revision 0
21A5477, Relief Valve Specification, Revision 0
619.3.005, High
619.3.005, High Flow in the Main Steam Line Test and Calibration, performed 10/2/17
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
DRF A61-00049 Tab 15, Oyster Creek Nuclear Generating Station Core Spray Pump Motor Evaluation, dated 12/4/98
Evaluation, dated 12/4/98
ECR ECP 15
ECR ECP 15-00376, Core Spray Motor P-20-1B As-Is Acceptance of Vibration
-00376, Core Spray Motor P
-20-1B As-Is Acceptance of Vibration
ECR IEC 10-00401, Canadian Core Spray Pump Motor
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  
EQ-301-12, Replacement/Upgrade of Components Qualified to DOR Guidelines, dated 7/7/87,
- Oyster Creek NGS, Revision 4
and 3/30/88
Five-Year Vibration Trend Plots  
ES-027, Environmental Parameters - Oyster Creek NGS, Revision 4
- NZ01B Core Spray Main Motor P
Five-Year Vibration Trend Plots - NZ01B Core Spray Main Motor P-20-1B
-20-1B LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical Equipment Important to Safety  
LS05-85-031, Safety Evaluation for Final Resolution of Environmental Qualification of Electrical
- Oyster Creek Nuclear Generating Station, dated 5/28/85 OYS-01-212-E-ET-MTR-P-20-1B, Motor for Core Spray
Equipment Important to Safety - Oyster Creek Nuclear Generating Station, dated
Pump NZ01-B Maintenance Strategy
5/28/85
NP-6408, Guideline for Establishing, Maintaining and Extending the Shelf Life Capability of Limited Life Items, dated May 1992
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
NP-6731, Guide to Optimized Replacement of Equipment Seals, dated March 1990
NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications
NQA-1-2015, Quality Assurance Requirements for Nuclear Facility Applications
NRC Inspection Report 05000219/86
NRC Inspection Report 05000219/86-08 (EQ Program Implementation), dated 8/8/86
-08 (EQ Program Implementation), dated 8/8/86
OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain
OCIS-402742-004, Installation Specification for Motor Control Center Shower Curtain Installation, Revision 0
Installation, Revision 0
OYS-01-212-E-ET-S-NR108A, EMRV NR108A Maintenance Strategy, dated 6/7/17
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
OYS-01-411-I-ET-SW-DPIS-RE0022A, Main Steam Flow Sensor DPIS-RE0022A Maintenance
-RE0022A Maintenance Strategy, dated 6/7/17
Strategy, dated 6/7/17
OYS-01-642-I-ET-T-PT-642-9A, PT-642-9A 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
Oyster Creek EQ Master List, dated 1/8/14
Pre-NRC EQ DBA Self
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,
SDBD-OC-212-A, System Design Basis Document for Low Pressure Core Spray System, Revision 3
Revision 3
SE No. 000210
SE No. 000210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13
-001, Evaluation of EQ Master List Inclusion of IA83 Pressure switches and ID13 Level Transmitters Safety Evaluation, Revision 0
Level Transmitters Safety Evaluation, Revision 0
SE No. 315403
SE No. 315403-019, Drywell Design Pressure Reduction - Tech Spec Change, Revision 1
-019, Drywell Design Pressure Reduction  
- Tech Spec Change, Revision 1
SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0
SP 1302-12-245, Refurbishment of Electromatic Relief Valves, Revision 0
TDR 1003, Environmental Qualification 'Sound Reasons to the Contrary' Guidelines, Revision 0
TDR 1003, Environmental Qualification Sound Reasons to the Contrary Guidelines, Revision 0
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Latest revision as of 07:53, 6 January 2025

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


Text

February 28, 2018

SUBJECT:

OYSTER CREEK - DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)

REPORT 05000219/2018010

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 Station. The NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any findings or violations of more-than-minor significance.

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 NRCs 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

Inspection Report

Docket Number:

50-219

License Number:

DPR-16

Report Number:

05000219/2018010

Enterprise Identifier: I-2018-010-0055

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

SUMMARY

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

71111.21N - Design Bases Assurance Inspection (Programs) Programs (Environmental Qualification)

Main article: IP 71111.21

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]

2) Main steam isolation valve V-1-007 [solenoid valve coil and elastomers]

3) Core spray pump NZ01-B [motor and motor lubrication]

4) Narrow range drywell pressure instrument PT-642-9A [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-56-1A [thermocouple, head gasket and silicone sealant]

EXIT MEETINGS 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

71111.21N

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

2399

875631

880917

893317

911682

983859

1008809

1147890

26157

1518358

1568796

1680592

2394239

2397876

24903

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

2-0270, 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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