IR 05000293/2018015: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:November 21, 2018
{{#Wiki_filter:UNITED STATES November 21, 2018


==SUBJECT:==
==SUBJECT:==
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==Dear Mr. Sullivan:==
==Dear Mr. Sullivan:==
On November 1, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an  
On November 1, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Pilgrim Nuclear Power Station and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
 
inspection at Pilgrim Nuclear Power Station and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.


The NRC inspectors did not identify any finding or violation of more than minor significance.
The NRC inspectors did not identify any finding or violation of more than minor significance.


This letter, its enclosure, and your response (if any) will be made available for public inspection  
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 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.
 
and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC 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  
/RA/
 
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Docket Number: 50-293 License Number: DPR-35
Division of Reactor Safety Docket Number: 50-293 License Number: DPR-35  


===Enclosure:===
===Enclosure:===
Inspection Report 05000293/2018015  
Inspection Report 05000293/2018015


==Inspection Report==
==Inspection Report==
 
Docket Number: 50-293 License Number: DPR-35 Report Number: 05000293/2018015 Enterprise Identifier: I-2018-015-0000 Licensee: Entergy Nuclear Operations, Inc. (Entergy)
Docket Number: 50-293  
Facility: Pilgrim Nuclear Power Station Location: Plymouth, Massachusetts Inspection Dates: October 15, 2018, to November 1, 2018 Inspectors: A. Patel, Senior Reactor Inspector (Team Lead)
 
J. Mateychick, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector D. Werkheiser, Senior Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
License Number: DPR-35  
 
Report Number: 05000293/2018015  
 
Enterprise Identifier: I-2018-015-0000  
 
Licensee: Entergy Nuclear Operations, Inc. (Entergy)  
 
Facility: Pilgrim Nuclear Power Station  
 
Location: Plymouth, Massachusetts  
 
Inspection Dates: October 15, 2018, to November 1, 2018  
 
Inspectors: A. Patel, Senior Reactor Inspector (Team Lead)
J. Mateychick, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector D. Werkheiser, Senior Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety  
 
2


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Entergy's performance at Pilgrim by conducting the triennial fire protection team inspection 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.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Entergys performance at Pilgrim by conducting the triennial fire protection team inspection 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.
3


=INSPECTION SCOPES=
=INSPECTION SCOPES=


===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."
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==
==REACTOR SAFETY==
Line 82: Line 57:
Fire Protection Inspection Requirements ===
Fire Protection Inspection Requirements ===
{{IP sample|IP=IP 71111.05|count=5}}
{{IP sample|IP=IP 71111.05|count=5}}
The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones:
The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones:
: (1) Fire Area 3.1: Main Control Room (Fire Zone 3.1)
: (1) Fire Area 3.1: Main Control Room (Fire Zone 3.1)
: (2) Fire Area 2.2: 'A' Switchgear Room (Fire Zone 2.2)/'A' Battery Room (Fire Zone 2.3)
: (2) Fire Area 2.2: A Switchgear Room (Fire Zone 2.2)/A Battery Room (Fire Zone 2.3)
: (3) Fire Area 4.1: 'B' Emergency Diesel Generator Room (Fire Zone 4.1)
: (3) Fire Area 4.1: B Emergency Diesel Generator Room (Fire Zone 4.1)
: (4) Fire Area 1.10: Reactor Core Isolation Cooling Pump Quadrant (Fire Zone 1.5)
: (4) Fire Area 1.10: Reactor Core Isolation Cooling Pump Quadrant (Fire Zone 1.5)
: (5) Fire Area 1.9: Spent Fuel Pool Pump Area (Fire Zone 1.13)
: (5) Fire Area 1.9: Spent Fuel Pool Pump Area (Fire Zone 1.13)
 
In performing this review, the inspectors performed an analysis of the following electrical circuits:
In performing this review, the inspectors performed an analysis of the following electrical circuits:
: (1) X107B, 'B' Emergency Diesel Generator Governor Circuit
: (1) X107B, B Emergency Diesel Generator Governor Circuit
: (2) MO-1001-7B, 'B' Residual Heat Removal Loop Suction Valve
: (2) MO-1001-7B, B Residual Heat Removal Loop Suction Valve
: (3) MO-1301-22, Reactor Core Isolation Cooling Condensate Storage Tanks Suction Valve
: (3) MO-1301-22, Reactor Core Isolation Cooling Condensate Storage Tanks Suction Valve
: (4) MO-1400-3B, 'B' Core Spray Loop Pump Suction Valve
: (4) MO-1400-3B, B Core Spray Loop Pump Suction Valve
: (5) MO-2301-5, High Pressure Coolant Injection Outboard Steam Isolation Valve
: (5) MO-2301-5, High Pressure Coolant Injection Outboard Steam Isolation Valve
: (6) P215B, 'B' Core Spray Pump
: (6) P215B, B Core Spray Pump
: (7) TI-9019, 'B' Channel Drywell Air Temperature Monitoring  
: (7) TI-9019, B Channel Drywell Air Temperature Monitoring
 
B.5.b Inspection Activities (2 Samples)===


===B.5.b Inspection Activities (2 Samples)===
The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:
The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:
: (1) 5.3.36 (Attachment 5), Reactor Pressure Vessel Depressurization using Direct Current Power Supplies
: (1) 5.3.36 (Attachment 5), Reactor Pressure Vessel Depressurization using Direct Current Power Supplies
: (2) 5.3.36 (Attachment 8), Makeup to the Condensate Storage Tank  
: (2) 5.3.36 (Attachment 8), Makeup to the Condensate Storage Tank


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
Line 113: Line 85:


71111.05T
71111.05T
Calculations 89XM-1-ER-Q-17, Updated Fire Hazards Analysis, Revision 17 APR 86-006, Appendix R Emergency Lighting, dated 12/15/86
Calculations
89XM-1-ER-Q-17, Updated Fire Hazards Analysis, Revision 17
APR 86-006, Appendix R Emergency Lighting, dated 12/15/86
CR-PNP-2015-09136 CA-01, Safe Shutdown Evaluation, dated 11/20/15
CR-PNP-2015-09136 CA-01, Safe Shutdown Evaluation, dated 11/20/15
EC 61965, Engineering Evaluation Tables, dated 5/12/17 FP-1, Back-up Voice Communication System, dated 7/11/1979 FP53, Determine Adequacy of B.5.b Mitigation Strategies, Revision 1
EC 61965, Engineering Evaluation Tables, dated 5/12/17
FP-1, Back-up Voice Communication System, dated 7/11/1979
FP53, Determine Adequacy of B.5.b Mitigation Strategies, Revision 1
M1380, PNPS FLEX Strategy Thermal-Hydraulic Analysis, Revision 1
M1380, PNPS FLEX Strategy Thermal-Hydraulic Analysis, Revision 1
M1413, PNPS Fire Event Safe Shutdown Path & Alternate Shutdown Cooling Evaluation,
M1413, PNPS Fire Event Safe Shutdown Path & Alternate Shutdown Cooling Evaluation,
Revision 0 PDC 86-45, Emergency Lighting, Revision A PS32, Appendix R Safe Shutdown Analysis, Revision 7
Revision 0
PDC 86-45, Emergency Lighting, Revision A
PS32, Appendix R Safe Shutdown Analysis, Revision 7
SUDDSRF 86-123, Pilgrim Nuclear Power Station Emergency Light Illumination and Visibility
SUDDSRF 86-123, Pilgrim Nuclear Power Station Emergency Light Illumination and Visibility
Test Results, Revision 1C15.0.2805, Qualification of Doors #145/159, #147 and #150 for
Test Results, Revision 1C15.0.2805, Qualification of Doors #145/159, #147 and #150 for
Design Loads, Revision 2
Design Loads, Revision 2
Completed Tests and Surveillances 2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, dated 10/2/2018
Completed Tests and Surveillances
2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, dated 10/2/2018
3.M.3-49 Attachment 1, Emergency Lighting Battery Maintenance/Preventive Maintenance and
3.M.3-49 Attachment 1, Emergency Lighting Battery Maintenance/Preventive Maintenance and
Battery Replacement Procedure, completed 4/14/18
Battery Replacement Procedure, completed 4/14/18
3.M.3-49 Attachment 3, Emergency Lighting Battery Maintenance/Preventive Maintenance and Battery Replacement Procedure, completed 7/27/18 8.5.2.6, RHR Motor-Operated Valve Operability from Alternate Shutdown Panels, completed 5/1/17, 8/19/17, and 10/8/17
3.M.3-49 Attachment 3, Emergency Lighting Battery Maintenance/Preventive Maintenance and
8.5.3.9, Salt Service Water (SSW) Pump Alternate Shutdown Panel Test, completed 5/29/18 and 7/9/18 8.5.4.6, HPCI Pump and Valve Operability from Alternate Shutdown Panel, completed 8/15/14 and 11/8/16
Battery Replacement Procedure, completed 7/27/18
8.5.2.6, RHR Motor-Operated Valve Operability from Alternate Shutdown Panels, completed
5/1/17, 8/19/17, and 10/8/17
8.5.3.9, Salt Service Water (SSW) Pump Alternate Shutdown Panel Test, completed 5/29/18
and     7/9/18
8.5.4.6, HPCI Pump and Valve Operability from Alternate Shutdown Panel, completed 8/15/14
and 11/8/16
8.5.5.6, RCIC Pump and Valve Operability from Alternate Shutdown Panel, completed 6/28/17
8.5.5.6, RCIC Pump and Valve Operability from Alternate Shutdown Panel, completed 6/28/17
8.5.6.4, ADS Operability from Alternate Shutdown Panel, completed 5/8/17
8.5.6.4, ADS Operability from Alternate Shutdown Panel, completed 5/8/17
8.9.13, Diesel Generator Alternate Shutdown Panel Test, completed 4/23/17 and 5/10/17 8.B.3.1 Attachment 1, Interior Fire Hose Stations and Cabinets Inspection - FSAR Related, completed 5/9/18 8.B.3.1 Attachment 2, Fire Hose Station Equipment Inspection - FSAR Related, completed 6/9/18
8.9.13, Diesel Generator Alternate Shutdown Panel Test, completed 4/23/17 and 5/10/17
8.B.3.1 Attachment 1, Interior Fire Hose Stations and Cabinets Inspection - FSAR Related,
completed 5/9/18
8.B.3.1 Attachment 2, Fire Hose Station Equipment Inspection - FSAR Related, completed
6/9/18
8.B.13.1 Attachment 1, Interior Fire Hose Station Annual Hose Hydrostatic Test Checklist -
8.B.13.1 Attachment 1, Interior Fire Hose Station Annual Hose Hydrostatic Test Checklist -
FSAR Related, completed 5/26/18 8.B.13.1 Attachment 2, Interior Hose Station and Coupling Gasket Surveillance, completed 1/3/18
FSAR Related, completed 5/26/18
8.B.13.1 Attachment 2, Interior Hose Station and Coupling Gasket Surveillance, completed
1/3/18
8.B.20 Attachment 1, Fire Hazard(s) Inspection, completed 8/21/18 and 9/18/18
8.B.20 Attachment 1, Fire Hazard(s) Inspection, completed 8/21/18 and 9/18/18
8.B.21 Attachment 1, Emergency Lighting Units, completed 7/21/18
8.B.21 Attachment 1, Emergency Lighting Units, completed 7/21/18
8.B.21 Attachment 2, Emergency Lighting Units, completed 7/22/18
8.B.21 Attachment 2, Emergency Lighting Units, completed 7/22/18
8.B.21 Attachment 3, Emergency Lighting Units, completed 7/24/18 8.B.21 Attachment 4A, Emergency Lighting Units, completed 5/21/18 8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, completed May 2017,
8.B.21 Attachment 3, Emergency Lighting Units, completed 7/24/18
June 2017, May 2018, June 2018  
8.B.21 Attachment 4A, Emergency Lighting Units, completed 5/21/18
 
8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, completed May 2017,
8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, completed February 2017, December 2017
June 2017, May 2018, June 2018
8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, completed November 2017, January 2018 8.B.6.2, EDG "B" Pre-Action Sprinkler System Functional Test, completed March 2016,
8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, completed
February 2017, December 2017
8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, completed November 2017,
January 2018
8.B.6.2, EDG B Pre-Action Sprinkler System Functional Test, completed March 2016,
November 2017
November 2017
8.B.12, Fire Protection system Flow Tests, completed November 2016 & completed
8.B.12, Fire Protection system Flow Tests, completed November 2016 & completed
December 2017
December 2017
8.B.17.1, Inspection of Fire Door Assemblies, Attachment 2 completed September 2016, April 2018 8.B.17.2, Inspection of Fire Damper Assemblies, Attachment 1, completed September 2011,
8.B.17.1, Inspection of Fire Door Assemblies, Attachment 2 completed September 2016,
April 2018
8.B.17.2, Inspection of Fire Damper Assemblies, Attachment 1, completed September 2011,
completed November 2011, Attachment 4 completed March 2015, &
completed November 2011, Attachment 4 completed March 2015, &
10 completed May 2015
10 completed May 2015
8.B.20, Fire Hazard(s) Inspection, completed August 2018 and September 2018 8.B.29, Inspection of Fire Barriers, completed April 2009, September 2010, October 2010, May 2011, April 2012, May 2012, June 2012, December 2012, January 2013, March 2013
8.B.20, Fire Hazard(s) Inspection, completed August 2018 and September 2018
8.B.29, Inspection of Fire Barriers, completed April 2009, September 2010, October 2010,
May 2011, April 2012, May 2012, June 2012, December 2012, January 2013, March 2013
September 2013, December 2014, November 2015, December 2017
September 2013, December 2014, November 2015, December 2017
Radio Maintenance Record (Alternate Shutdown Communication System), dated 12/12/2017
Radio Maintenance Record (Alternate Shutdown Communication System), dated 12/12/2017
Condition Reports (*initiated in response to inspection). 2018-08176* 2018-08177* 2018-08180* 2018-08206*   2018-08208* 2018-08221* 2018-08225* 2018-08239*
Condition Reports (*initiated in response to inspection).
2018-08254* 2018-08269* 2018-08270* 2018-08271*
2018-08176*           2018-08177*           2018-08180*         2018-08206*
2018-08271* 2018-08273* 2018-08274* 2018-08275*
2018-08208*           2018-08221*           2018-08225*         2018-08239*
2018-08282* 2018-08283* 2018-08295* 2018-08304*   2018-08321* 2018-08542* 2018-08571* 2018-08574*   2018-08575* 2018-08581* 2018-08582* 2018-08585*
2018-08254*           2018-08269*           2018-08270*         2018-08271*
2018-08588* 2018-08589* 2018-08590* 2018-08591*
2018-08271*           2018-08273*           2018-08274*         2018-08275*
2018-08626* 2018-08628* 2018-08642* 2018-08644*
2018-08282*           2018-08283*           2018-08295*         2018-08304*
2018-08645* 2018-08646* 2018-08647* 2018-08474   2018-08402 2018-08228 2018-08186 2018-08120   2018-08081 2018-08017 2018-08005 2018-08001
2018-08321*           2018-08542*           2018-08571*         2018-08574*
2018-07815 2018-06878 2016-00791 2016-00111
2018-08575*           2018-08581*           2018-08582*         2018-08585*
2015-09136 2015-09134 2012-04158 2009-04204  
2018-08588*           2018-08589*           2018-08590*         2018-08591*
 
2018-08626*           2018-08628*           2018-08642*         2018-08644*
Design Change EC-25867, Establish Equipment IDs for B.5.b Battery Carts and As Required, Revision 0
2018-08645*           2018-08646*           2018-08647*         2018-08474
2018-08402             2018-08228             2018-08186         2018-08120
2018-08081             2018-08017             2018-08005         2018-08001
2018-07815             2018-06878             2016-00791         2016-00111
2015-09136             2015-09134             2012-04158         2009-04204
Design Change
EC-25867, Establish Equipment IDs for B.5.b Battery Carts and As Required, Revision 0
EC 40493, Remove Pilotex System and Install Sprinkler Heads, Revision 1
EC 40493, Remove Pilotex System and Install Sprinkler Heads, Revision 1
EC-50538, Evaluate the Processes used to Design and Procure B.5.b Equipment, Revision 0
EC-50538, Evaluate the Processes used to Design and Procure B.5.b Equipment, Revision 0
EC 61965, PNPS 10 CFR Part 50 Appendix R Fire Event Safe Shutdown Path Design Criteria for Fire-Induced Multiple Spurious Operations Establish MOVs to be Modified for NRC Information Notice 92-18, Revision 0 EC 62352, ECN to EC 40493 - Install Pipe Plugs in Pilotex Lines as Alternative to Installing
EC 61965, PNPS 10 CFR Part 50 Appendix R Fire Event Safe Shutdown Path Design Criteria
for Fire-Induced Multiple Spurious Operations Establish MOVs to be Modified for NRC
Information Notice 92-18, Revision 0
EC 62352, ECN to EC 40493 - Install Pipe Plugs in Pilotex Lines as Alternative to Installing
Sprinkler Heads, Revision 0
Sprinkler Heads, Revision 0
EC 76462, Demolition and Permanent Removal of Startup Transformer (SUT) Deluge System,
EC 76462, Demolition and Permanent Removal of Startup Transformer (SUT) Deluge System,
Revision 0
Revision 0
Drawings E5-157-7, Schematic Dia - ECCS Pump Feeder 4160V Bus A6, Sh. 21, Revision 6 E13, Single Line Relay & Meter Dia 125V 250V DC Systems, Revision 86
Drawings
E5-157-7, Schematic Dia - ECCS Pump Feeder 4160V Bus A6, Sh. 21, Revision 6
E13, Single Line Relay & Meter Dia 125V 250V DC Systems, Revision 86
E27, Wiring Block Dia - Diesel Generator 2 X107B, Sh. 2, Revision 24
E27, Wiring Block Dia - Diesel Generator 2 X107B, Sh. 2, Revision 24
E27, Wiring Block Dia - Diesel Generator A & B, Sh. 3, Revision 27 E83, Wiring Block Dia - Core Spray System, Sh. 1, Revision 11
E27, Wiring Block Dia - Diesel Generator A & B, Sh. 3, Revision 27
E84, Wiring Block Dia - Core Spray System, Sh. 2, Revision 9 E126, Wiring Block DIa - Residual Heat Removal System, Sh. 2, Revision 10 E418, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature
E83, Wiring Block Dia - Core Spray System, Sh. 1, Revision 11
Instrumentation, Sh.1, Revision 15 E419, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature
E84, Wiring Block Dia - Core Spray System, Sh. 2, Revision 9
Instrumentation, Sh.2, Revision 14 E532 S
E126, Wiring Block DIa - Residual Heat Removal System, Sh. 2, Revision 10
E418, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature
Instrumentation, Sh.1, Revision 15
E419, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature
Instrumentation, Sh.2, Revision 14
E532 S
: [[contact::H. 15]], Connection Diagram Alternate Shutdown Panel C157, Revision E3
: [[contact::H. 15]], Connection Diagram Alternate Shutdown Panel C157, Revision E3
E539, Radiax Antenna Cable Riser Dia, Revision E2 E550, Schematic Dia - Instrument Loop: Drywell Atmosphere Temperature, Sh.34, Revision 3
E539, Radiax Antenna Cable Riser Dia, Revision E2
E550, Schematic Dia - Instrument Loop: Drywell Atmosphere Temperature, Sh.34, Revision 3
E906, Plant Radio System (security, fire brigade, operations), Revision 0
E906, Plant Radio System (security, fire brigade, operations), Revision 0
M1G15-9, ELemetnary Dia RCIC System, Sh. 5, Revision E17
M1G15-9, ELemetnary Dia RCIC System, Sh. 5, Revision E17
M1H1-7BC, Functional Control Dia - Residual Heat Removal System, Sh. 2, Revision E1 M1H3-6, Functional Control Dia - Residual Heat Removal System, Revision 11 M1H5-1-15, Elementary Dia - Residual Heat Removal System, Sh. 1, Revision 20
M1H1-7BC, Functional Control Dia - Residual Heat Removal System, Sh. 2, Revision E1
M1H3-6, Functional Control Dia - Residual Heat Removal System, Revision 11
M1H5-1-15, Elementary Dia - Residual Heat Removal System, Sh. 1, Revision 20
M1H11-8, Elementary Dia - Residual Heat Removal System, Sh. 7, Revision E12
M1H11-8, Elementary Dia - Residual Heat Removal System, Sh. 7, Revision E12
M1H40, Elementary Dia - Residual Heat Removal System, Sh. 18, Revision 18
M1H40, Elementary Dia - Residual Heat Removal System, Sh. 18, Revision 18
M1J14-14, HPCI System DC MOV & Control Center, Sh. 2, Revision 6 M1J19-9, Elementary Dia, HPCI, Sh. 9, Revision E16 M1K1-8, Functional Control Dia - Core Spray System, Revision 28
M1J14-14, HPCI System DC MOV & Control Center, Sh. 2, Revision 6
M1J19-9, Elementary Dia, HPCI, Sh. 9, Revision E16
M1K1-8, Functional Control Dia - Core Spray System, Revision 28
M1K3-15, Elementary Dia - Core Spray System, Revision E15
M1K3-15, Elementary Dia - Core Spray System, Revision E15
M1K4-11, Elementary Dia - Core Spray System, Revision 17
M1K4-11, Elementary Dia - Core Spray System, Revision 17
M1K5-11, Elementary Dia - Core Spray System, Revision 15
M1K5-11, Elementary Dia - Core Spray System, Revision 15
M1K7-7, Elementary Dia - Core Spray System, Revision 12 M218, Sht.1, P&ID Fire Protection System, Revision 60 M6-20-9, Schematic Dia - Diesel Generator "B" X107B Auxiliary Control Equipment, Sh. 2,
M1K7-7, Elementary Dia - Core Spray System, Revision 12
Revision 15 M6-22-14, Schematic Dia - Diesel Generator "B" X107B Engine Control, Sh. 2, Revision 37
M218, Sht.1, P&ID Fire Protection System, Revision 60
M6-20-9, Schematic Dia - Diesel Generator B X107B Auxiliary Control Equipment, Sh. 2,
Revision 15
M6-22-14, Schematic Dia - Diesel Generator B X107B Engine Control, Sh. 2, Revision 37
M6-46-6, Schematic & Interconnection Dia - Static Exciter & Voltage Regulator Diesel
M6-46-6, Schematic & Interconnection Dia - Static Exciter & Voltage Regulator Diesel
Generator "B" - C102, Sh. 2, Revision 8 MMOV1, Motor Operated Valves Information Table, Revision 62
Generator B - C102, Sh. 2, Revision 8
MMOV2, Motor Operated Valves Information Table, Revision 39  
MMOV1, Motor Operated Valves Information Table, Revision 62
 
MMOV2, Motor Operated Valves Information Table, Revision 39
Fire Protection Licensing Documents 2.77.23, Fire Protection System Evaluation with respect to BTP APCSB 9.5-1, dated 3/1/1977 2.78.116, PNPS Fire Protection Information and Commitments to NRC, dated 7/10/1978 89XM-1-ER-Q, Updated Fire Hazards Analysis, Revision 17
Fire Protection Licensing Documents
2.77.23, Fire Protection System Evaluation with respect to BTP APCSB 9.5-1, dated 3/1/1977
2.78.116, PNPS Fire Protection Information and Commitments to NRC, dated 7/10/1978
89XM-1-ER-Q, Updated Fire Hazards Analysis, Revision 17
ELNRC1.2.83.130, Appendix R Exemption Requests, dated 5/17/83
ELNRC1.2.83.130, Appendix R Exemption Requests, dated 5/17/83
NRCLE1.1.83.267, Safety Evaluation for Appendix R to 10 CFR Part 50 Items III.G.3 and III.L,
NRCLE1.1.83.267, Safety Evaluation for Appendix R to 10 CFR Part 50 Items III.G.3 and III.L,
dated 11/2/83 NRCLE1.1.84.379, Exemptions to Section II
dated 11/2/83
: [[contact::I.G of Appendix R]], dated 12/18/84 NRCLE1.1.88.120, Exemption for Certain Requirements of 10CFR50, Appendix R, Section
NRCLE1.1.84.379, Exemptions to Section II
: [[contact::I.G of Appendix R]], dated 12/18/84
NRCLE1.1.88.120, Exemption for Certain Requirements of 10CFR50, Appendix R, Section
III.G.1 (TAC #66369), dated 4/14/88
III.G.1 (TAC #66369), dated 4/14/88
NRCLE1.1.88.254, Exemption for Certain Requirements of 10CFR50, Appendix R, Section III.G
NRCLE1.1.88.254, Exemption for Certain Requirements of 10CFR50, Appendix R, Section II
in Certain Areas of the Plant PNPS (TAC No. 523416), dated 7/14/88
: [[contact::I.G
in Certain Areas of the Plant PNPS (TAC No. 523416)]], dated 7/14/88
TDBD105, Design Basis Document for Fire Protection/Appendix R Program, Revision 2
TDBD105, Design Basis Document for Fire Protection/Appendix R Program, Revision 2
Miscellaneous Documents
Miscellaneous Documents
341309-0, Laboratory Report Compressed Air/Gas Quality Testing, dated 8/24/18 Alternate Shutdown Communication Radio System Simplified Arrangement, 10/18/18
341309-0, Laboratory Report Compressed Air/Gas Quality Testing, dated 8/24/18
Boston Edison Company Letter 77-23, Fire Protection Program, 3/09/77 Boston Edison Company Letter 87-116, Pilgrim Nuclear Power Station Fire Protection
Alternate Shutdown Communication Radio System Simplified Arrangement, 10/18/18
Information, 7/10/78 Boston Edison Company Letter 81-59, Status of Boston Edison Effort in Meeting the Scheduler Requirement of Appendix R to 10 CFR Part 50, 3/18/81
Boston Edison Company Letter 77-23, Fire Protection Program, 3/09/77
Boston Edison Company Letter 87-116, Pilgrim Nuclear Power Station Fire Protection
Information, 7/10/78
Boston Edison Company Letter 81-59, Status of Boston Edison Effort in Meeting the
Scheduler Requirement of Appendix R to 10 CFR Part 50, 3/18/81
Cylinder Retest Data Sheet Hydrostatic Volumetric Test Method Report, dated 6/12/15 - 9/12/17
Cylinder Retest Data Sheet Hydrostatic Volumetric Test Method Report, dated 6/12/15 - 9/12/17
EN-OP-123 Attachment 3 Scenario #1, SRV Isolation at ASPs TCA Validation, completed
EN-OP-123 Attachment 3 Scenario #1, SRV Isolation at ASPs TCA Validation, completed
8/30/18
8/30/18
EN-OP-123 Attachment 3 Scenario #2, 4KV Bkr, EDG-B, and CS B Local Op TCA Validation, completed 8/30/18 EN-RP-502, Inspection and Maintenance of Respiratory Equipment, dated 9/19/18 - 10/12/18
EN-OP-123 Attachment 3 Scenario #2, 4KV Bkr, EDG-B, and CS B Local Op TCA Validation,
completed 8/30/18
EN-RP-502, Inspection and Maintenance of Respiratory Equipment, dated 9/19/18 - 10/12/18
Fire Impairments Report, dated 9/28/18
Fire Impairments Report, dated 9/28/18
FPEE 43, Recessed Panel in Diesel Generator Building Wall No. 198.501
FPEE 43, Recessed Panel in Diesel Generator Building Wall No. 198.501
FSAR Section 10.8, Fire Protection System, Revision 31 Operations Night Order, SCBA Respirator Mask Staging in the Control Room, dated 10/17/18 LO-PNPLO-2018-004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment, 03/28/2018PDC/FRN No. 02-43-2, Fire Wrap conduit 2620, September 2004
FSAR Section 10.8, Fire Protection System, Revision 31
Operations Night Order, SCBA Respirator Mask Staging in the Control Room, dated 10/17/18
LO-PNPLO-2018-004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment,
03/28/2018PDC/FRN No. 02-43-2, Fire Wrap conduit 2620, September 2004
Program Section No. SEP-FPP-PNP-001, Fire Protection Plan, Revision 34
Program Section No. SEP-FPP-PNP-001, Fire Protection Plan, Revision 34
NRC Letter Denton to Morisi, Pilgrim I - Fire Protection Exemption Request, 11/10/81 QA-9-2016-PNP-1, Quality Assurance Audit Report - Fire Protection, 01/11/66-02/16/16
NRC Letter Denton to Morisi, Pilgrim I - Fire Protection Exemption Request, 11/10/81
Operator Safe Shutdown Training JPM-200-39, Establish Reactor Pressure and Water Level Control from Outside the Control
QA-9-2016-PNP-1, Quality Assurance Audit Report - Fire Protection, 01/11/66-02/16/16
Operator Safe Shutdown Training
JPM-200-39, Establish Reactor Pressure and Water Level Control from Outside the Control
Room (at ASPS) Job Performance Measure, Revision 4
Room (at ASPS) Job Performance Measure, Revision 4
JPM-217-06, RCIC Start from the Alternate Shutdown Panels Job Performance Measure, Revision 13 JPM-264-04, Emergency Diesel Generator Operation Outside the Control Room Job
JPM-217-06, RCIC Start from the Alternate Shutdown Panels Job Performance Measure,
Revision 13
JPM-264-04, Emergency Diesel Generator Operation Outside the Control Room Job
Performance Measure, Revision 7
Performance Measure, Revision 7
O-NL-03-07-08, General and Special Fire Procedures, Revision 2
O-NL-03-07-08, General and Special Fire Procedures, Revision 2
O-NL-03-07-07, Fire Hazard Inspection, Revision 6 O-RQ-04-01-257, 2016-2018 LOR HIT PSU, Revision 1 O-RQ-04-01-289, 2016-2018 Cycle 10 PSU, Revision 0
O-NL-03-07-07, Fire Hazard Inspection, Revision 6
O-RQ-06-02-180, Fire in the Main Control R
O-RQ-04-01-257, 2016-2018 LOR HIT PSU, Revision 1
oom, Shutdown from Outside the Control Room, Revision 0  
O-RQ-04-01-289, 2016-2018 Cycle 10 PSU, Revision 0
 
O-RQ-06-02-180, Fire in the Main Control Room, Shutdown from Outside the Control Room,
Procedures  1.3.34, Operations Administrative Policies and Processes, Revision 164
Revision 0
Procedures
1.3.34, Operations Administrative Policies and Processes, Revision 164
2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 52
2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 52
2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 53
2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 53
2.2.22, Reactor Core Isolation Cooling System (RCIC), Revision 82
2.2.22, Reactor Core Isolation Cooling System (RCIC), Revision 82
2.4.143.1, Shutdown With a fire in Reactor Building East (Fire area 1.9) and affected "ADivision Fire Areas 1.21, 2.2, 2.16, 3.3, 4.3), Revision 27 2.4.143.2, Shutdown With a fire in Reactor Building West (Fire area 1.10) and affected "B"
2.4.143.1, Shutdown With a fire in Reactor Building East (Fire area 1.9) and affected A
Division Fire Areas 1.21, 2.2, 2.16, 3.3, 4.3), Revision 27
2.4.143.2, Shutdown With a fire in Reactor Building West (Fire area 1.10) and affected B
Division Fire Areas 1.22, 1.23, 1.28, 2.1, 2.10, 3.5, 4.1, 5.3), Revision 30
Division Fire Areas 1.22, 1.23, 1.28, 2.1, 2.10, 3.5, 4.1, 5.3), Revision 30
3.M.1-18, Core Drilling and/or Breach of a Fire Seal/Vital area/Secondary
3.M.1-18, Core Drilling and/or Breach of a Fire Seal/Vital area/Secondary
Containment/CRHEAFS Barrier, Revision 22
Containment/CRHEAFS Barrier, Revision 22
3.M.3-49, Emergency Lighting Battery Maintenance/Preventive Maintenance and Battery Replacement Procedure, Revision 31 5.5.1, General Fire Procedure, Revision 27
3.M.3-49, Emergency Lighting Battery Maintenance/Preventive Maintenance and Battery
5.5.2, Special Fire Procedure, Revision 59  
Replacement Procedure, Revision 31
 
5.5.1, General Fire Procedure, Revision 27
5.5.2, Special Fire Procedure, Revision 59
5.3.36, Extensive Damage Mitigation Guidelines (EDMG) Support Procedures and Strategies,
5.3.36, Extensive Damage Mitigation Guidelines (EDMG) Support Procedures and Strategies,
Revision 13 6.7.1-202, PNPS Emergency Use Respiratory Protection Equipment Inspection, Revision 1 8.A.13, Plant Emergency Alarms and Radio Test, Revision 23 8.B.1, Fire Pump Test, Revision 100
Revision 13
6.7.1-202, PNPS Emergency Use Respiratory Protection Equipment Inspection, Revision 1
8.A.13, Plant Emergency Alarms and Radio Test, Revision 23
8.B.1, Fire Pump Test, Revision 100
8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, Revision 10
8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, Revision 10
8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, Revision 12
8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, Revision 12
8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, Revision 12
8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, Revision 12
8.B.6.2, EDG "B" Pre-Action Sprinkler System Functional Test, Revision 14 8.B.9.2, Wet and Dry Pipe Sprinklers Alarm Test - FSAR Related, Revision 10 8.B.12, Fire Protection system Flow Tests, Revision 44
8.B.6.2, EDG B Pre-Action Sprinkler System Functional Test, Revision 14
8.B.9.2, Wet and Dry Pipe Sprinklers Alarm Test - FSAR Related, Revision 10
8.B.12, Fire Protection system Flow Tests, Revision 44
8.B.14, Fire Protection Technical Requirements, Revision 58
8.B.14, Fire Protection Technical Requirements, Revision 58
8.B.15, Functional Tests of Fire Pumps - P-135, P140, and P-181, Revision 57
8.B.15, Functional Tests of Fire Pumps - P-135, P140, and P-181, Revision 57
8.B.17.1, Inspection of Fire Door Assemblies, Revision 26 8.B.17.2, Inspection of Fire Damper Assemblies, Revision 17 8.B.19, Fire Brigade Equipment Inspection, Revision 29
8.B.17.1, Inspection of Fire Door Assemblies, Revision 26
8.B.17.2, Inspection of Fire Damper Assemblies, Revision 17
8.B.19, Fire Brigade Equipment Inspection, Revision 29
8.B.20, Fire Hazard(s) Inspection, Revision 18
8.B.20, Fire Hazard(s) Inspection, Revision 18
8.B.21, Emergency Lighting Units, Revision 46
8.B.21, Emergency Lighting Units, Revision 46
8.B.27, Radiax Backup Voice Communication System for Fire Fighting, Revision 13 8.B.29, Inspection of Fire Barriers, Revision 13 A316, Sht. 1, Reactor & Turbine Building Floor Plan El. (-) 17'-6" & 6'-0" Fire Barrier System,   Revision 7
8.B.27, Radiax Backup Voice Communication System for Fire Fighting, Revision 13
A317, Sht. 1, Reactor & Turbine Building Floor Plan at El. 23'-0" Fire Barrier System,
8.B.29, Inspection of Fire Barriers, Revision 13
A316, Sht. 1, Reactor & Turbine Building Floor Plan El. (-) 17-6 & 6-0 Fire Barrier System,
Revision 7
A317, Sht. 1, Reactor & Turbine Building Floor Plan at El. 23-0 Fire Barrier System,
Revision 10
Revision 10
A318, Sht. 1, Reactor & Turbine Building Floor Plan at El. 37'-0" Fire Barrier System, Revision 7 A320, Sht. 1, Reactor & Turbine Building Floor Plans - El. 117'-0", 101'-0", 91'-3", 74'-3" 7
A318, Sht. 1, Reactor & Turbine Building Floor Plan at El. 37-0 Fire Barrier System,
Intake Building Plan - Fire Barrier System & 6'-0" Fire Barrier System, Revision E4 A321, Reactor & Turbine Building Section A-A Fire Barrier System, Revision 3
Revision 7
ARP-C7R, Alarm Response Procedure, Revision 23 EN-LI-102, Corrective Action Program, Revision 35 EN-LI-121, Trending and Performance Review Process, Revision 25
A320, Sht. 1, Reactor & Turbine Building Floor Plans - El. 117-0, 101-0, 91-3, 74-3 7
Intake Building Plan - Fire Barrier System & 6-0 Fire Barrier System, Revision E4
A321, Reactor & Turbine Building Section A-A Fire Barrier System, Revision 3
ARP-C7R, Alarm Response Procedure, Revision 23
EN-LI-102, Corrective Action Program, Revision 35
EN-LI-121, Trending and Performance Review Process, Revision 25
EN-NS-112, Medical Program, Revision 19
EN-NS-112, Medical Program, Revision 19
EN-OP-115-03, Shift Turnover and Relief Procedure, Revision 2
EN-OP-115-03, Shift Turnover and Relief Procedure, Revision 2
EN-OP-123, Time Critical Action/Time Sensitive Action Program Standard, Revision 0
EN-OP-123, Time Critical Action/Time Sensitive Action Program Standard, Revision 0
EN-PL-147, Personnel Expectations Relative to Emergency Response at Entergy Nuclear Sites, Revision 3 EN-RP-501, Respiratory Protection Program, Revision 5
EN-PL-147, Personnel Expectations Relative to Emergency Response at Entergy Nuclear Sites,
Revision 3
EN-RP-501, Respiratory Protection Program, Revision 5
EN-RP-502, Inspection and Maintenance of Respiratory Equipment, Revision 10
EN-RP-502, Inspection and Maintenance of Respiratory Equipment, Revision 10
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7
EN-RP-505, PortaCount Respirator Fit Testing, Revision 7 EP-AD-425, BDBEE Communications Equipment Functionality and Inventory, Revision 2
EN-RP-505, PortaCount Respirator Fit Testing, Revision 7
Quality Assurance Audits and Self Assessments CR-PNP-2016-2061, Initial Screening of Existing Self-Assessments - Fire Protection Program, dated 7/21/16
EP-AD-425, BDBEE Communications Equipment Functionality and Inventory, Revision 2
LO-PNPLO-2018-0004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment, dated 3/28/18 QA-9-2016-PNP-1, Fire Protection Quality Assurance Audit Report, dated 2/16/16
Quality Assurance Audits and Self Assessments
 
CR-PNP-2016-2061, Initial Screening of Existing Self-Assessments - Fire Protection Program,
dated 7/21/16
LO-PNPLO-2018-0004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment, dated
3/28/18
QA-9-2016-PNP-1, Fire Protection Quality Assurance Audit Report, dated 2/16/16
Work Order
Work Order
2645165 52654363 52684842 52699713 52788716 52699712
2645165   52654363 52684842 52699713 52788716 52699712
2771221 52761762 52664402 52788716 52725473
2771221   52761762 52664402 52788716 52725473
}}
}}

Latest revision as of 07:32, 2 November 2019

Triennial Fire Protection Inspection Report 05000293/2018015
ML18330A084
Person / Time
Site: Pilgrim
Issue date: 11/21/2018
From: Glenn Dentel
Engineering Region 1 Branch 2
To: Brian Sullivan
Entergy Nuclear Operations
Dentel G
References
IR 2018015
Download: ML18330A084 (12)


Text

UNITED STATES November 21, 2018

SUBJECT:

PILGRIM NUCLEAR POWER STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000293/2018015

Dear Mr. Sullivan:

On November 1, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Pilgrim Nuclear Power Station and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation 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 NRC 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 Safety Docket Number: 50-293 License Number: DPR-35

Enclosure:

Inspection Report 05000293/2018015

Inspection Report

Docket Number: 50-293 License Number: DPR-35 Report Number: 05000293/2018015 Enterprise Identifier: I-2018-015-0000 Licensee: Entergy Nuclear Operations, Inc. (Entergy)

Facility: Pilgrim Nuclear Power Station Location: Plymouth, Massachusetts Inspection Dates: October 15, 2018, to November 1, 2018 Inspectors: A. Patel, Senior Reactor Inspector (Team Lead)

J. Mateychick, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector D. Werkheiser, Senior Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Entergys performance at Pilgrim by conducting the triennial fire protection team inspection 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 SCOPES

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

===71111.05T - Fire Protection (Triennial)

The inspectors evaluated the following from October 15, 2018 to November 1, 2018:

Fire Protection Inspection Requirements ===

The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones:

(1) Fire Area 3.1: Main Control Room (Fire Zone 3.1)
(2) Fire Area 2.2: A Switchgear Room (Fire Zone 2.2)/A Battery Room (Fire Zone 2.3)
(3) Fire Area 4.1: B Emergency Diesel Generator Room (Fire Zone 4.1)
(4) Fire Area 1.10: Reactor Core Isolation Cooling Pump Quadrant (Fire Zone 1.5)
(5) Fire Area 1.9: Spent Fuel Pool Pump Area (Fire Zone 1.13)

In performing this review, the inspectors performed an analysis of the following electrical circuits:

(1) X107B, B Emergency Diesel Generator Governor Circuit
(2) MO-1001-7B, B Residual Heat Removal Loop Suction Valve
(3) MO-1301-22, Reactor Core Isolation Cooling Condensate Storage Tanks Suction Valve
(4) MO-1400-3B, B Core Spray Loop Pump Suction Valve
(5) MO-2301-5, High Pressure Coolant Injection Outboard Steam Isolation Valve
(6) P215B, B Core Spray Pump
(7) TI-9019, B Channel Drywell Air Temperature Monitoring

B.5.b Inspection Activities (2 Samples)

The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:

(1) 5.3.36 (Attachment 5), Reactor Pressure Vessel Depressurization using Direct Current Power Supplies
(2) 5.3.36 (Attachment 8), Makeup to the Condensate Storage Tank

EXIT MEETINGS AND DEBRIEFS

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

On November 1, 2018, the inspectors presented the triennial fire protection team inspection results to Mr. Brian Sullivan, Site Vice President, and other members of the Entergy staff.

DOCUMENTS REVIEWED

71111.05T

Calculations

89XM-1-ER-Q-17, Updated Fire Hazards Analysis, Revision 17

APR 86-006, Appendix R Emergency Lighting, dated 12/15/86

CR-PNP-2015-09136 CA-01, Safe Shutdown Evaluation, dated 11/20/15

EC 61965, Engineering Evaluation Tables, dated 5/12/17

FP-1, Back-up Voice Communication System, dated 7/11/1979

FP53, Determine Adequacy of B.5.b Mitigation Strategies, Revision 1

M1380, PNPS FLEX Strategy Thermal-Hydraulic Analysis, Revision 1

M1413, PNPS Fire Event Safe Shutdown Path & Alternate Shutdown Cooling Evaluation,

Revision 0

PDC 86-45, Emergency Lighting, Revision A

PS32, Appendix R Safe Shutdown Analysis, Revision 7

SUDDSRF 86-123, Pilgrim Nuclear Power Station Emergency Light Illumination and Visibility

Test Results, Revision 1C15.0.2805, Qualification of Doors #145/159, #147 and #150 for

Design Loads, Revision 2

Completed Tests and Surveillances

2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, dated 10/2/2018

3.M.3-49 Attachment 1, Emergency Lighting Battery Maintenance/Preventive Maintenance and

Battery Replacement Procedure, completed 4/14/18

3.M.3-49 Attachment 3, Emergency Lighting Battery Maintenance/Preventive Maintenance and

Battery Replacement Procedure, completed 7/27/18

8.5.2.6, RHR Motor-Operated Valve Operability from Alternate Shutdown Panels, completed

5/1/17, 8/19/17, and 10/8/17

8.5.3.9, Salt Service Water (SSW) Pump Alternate Shutdown Panel Test, completed 5/29/18

and 7/9/18

8.5.4.6, HPCI Pump and Valve Operability from Alternate Shutdown Panel, completed 8/15/14

and 11/8/16

8.5.5.6, RCIC Pump and Valve Operability from Alternate Shutdown Panel, completed 6/28/17

8.5.6.4, ADS Operability from Alternate Shutdown Panel, completed 5/8/17

8.9.13, Diesel Generator Alternate Shutdown Panel Test, completed 4/23/17 and 5/10/17

8.B.3.1 Attachment 1, Interior Fire Hose Stations and Cabinets Inspection - FSAR Related,

completed 5/9/18

8.B.3.1 Attachment 2, Fire Hose Station Equipment Inspection - FSAR Related, completed

6/9/18

8.B.13.1 Attachment 1, Interior Fire Hose Station Annual Hose Hydrostatic Test Checklist -

FSAR Related, completed 5/26/18

8.B.13.1 Attachment 2, Interior Hose Station and Coupling Gasket Surveillance, completed

1/3/18

8.B.20 Attachment 1, Fire Hazard(s) Inspection, completed 8/21/18 and 9/18/18

8.B.21 Attachment 1, Emergency Lighting Units, completed 7/21/18

8.B.21 Attachment 2, Emergency Lighting Units, completed 7/22/18

8.B.21 Attachment 3, Emergency Lighting Units, completed 7/24/18

8.B.21 Attachment 4A, Emergency Lighting Units, completed 5/21/18

8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, completed May 2017,

June 2017, May 2018, June 2018

8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, completed

February 2017, December 2017

8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, completed November 2017,

January 2018

8.B.6.2, EDG B Pre-Action Sprinkler System Functional Test, completed March 2016,

November 2017

8.B.12, Fire Protection system Flow Tests, completed November 2016 & completed

December 2017

8.B.17.1, Inspection of Fire Door Assemblies, Attachment 2 completed September 2016,

April 2018

8.B.17.2, Inspection of Fire Damper Assemblies, Attachment 1, completed September 2011,

completed November 2011, Attachment 4 completed March 2015, &

10 completed May 2015

8.B.20, Fire Hazard(s) Inspection, completed August 2018 and September 2018

8.B.29, Inspection of Fire Barriers, completed April 2009, September 2010, October 2010,

May 2011, April 2012, May 2012, June 2012, December 2012, January 2013, March 2013

September 2013, December 2014, November 2015, December 2017

Radio Maintenance Record (Alternate Shutdown Communication System), dated 12/12/2017

Condition Reports (*initiated in response to inspection).

2018-08176* 2018-08177* 2018-08180* 2018-08206*

2018-08208* 2018-08221* 2018-08225* 2018-08239*

2018-08254* 2018-08269* 2018-08270* 2018-08271*

2018-08271* 2018-08273* 2018-08274* 2018-08275*

2018-08282* 2018-08283* 2018-08295* 2018-08304*

2018-08321* 2018-08542* 2018-08571* 2018-08574*

2018-08575* 2018-08581* 2018-08582* 2018-08585*

2018-08588* 2018-08589* 2018-08590* 2018-08591*

2018-08626* 2018-08628* 2018-08642* 2018-08644*

2018-08645* 2018-08646* 2018-08647* 2018-08474

2018-08402 2018-08228 2018-08186 2018-08120

2018-08081 2018-08017 2018-08005 2018-08001

2018-07815 2018-06878 2016-00791 2016-00111

2015-09136 2015-09134 2012-04158 2009-04204

Design Change

EC-25867, Establish Equipment IDs for B.5.b Battery Carts and As Required, Revision 0

EC 40493, Remove Pilotex System and Install Sprinkler Heads, Revision 1

EC-50538, Evaluate the Processes used to Design and Procure B.5.b Equipment, Revision 0

EC 61965, PNPS 10 CFR Part 50 Appendix R Fire Event Safe Shutdown Path Design Criteria

for Fire-Induced Multiple Spurious Operations Establish MOVs to be Modified for NRC

Information Notice 92-18, Revision 0

EC 62352, ECN to EC 40493 - Install Pipe Plugs in Pilotex Lines as Alternative to Installing

Sprinkler Heads, Revision 0

EC 76462, Demolition and Permanent Removal of Startup Transformer (SUT) Deluge System,

Revision 0

Drawings

E5-157-7, Schematic Dia - ECCS Pump Feeder 4160V Bus A6, Sh. 21, Revision 6

E13, Single Line Relay & Meter Dia 125V 250V DC Systems, Revision 86

E27, Wiring Block Dia - Diesel Generator 2 X107B, Sh. 2, Revision 24

E27, Wiring Block Dia - Diesel Generator A & B, Sh. 3, Revision 27

E83, Wiring Block Dia - Core Spray System, Sh. 1, Revision 11

E84, Wiring Block Dia - Core Spray System, Sh. 2, Revision 9

E126, Wiring Block DIa - Residual Heat Removal System, Sh. 2, Revision 10

E418, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature

Instrumentation, Sh.1, Revision 15

E419, Schematic Dia - Drywell Pressure & Temperature and Torus Temperature

Instrumentation, Sh.2, Revision 14

E532 S

H. 15, Connection Diagram Alternate Shutdown Panel C157, Revision E3

E539, Radiax Antenna Cable Riser Dia, Revision E2

E550, Schematic Dia - Instrument Loop: Drywell Atmosphere Temperature, Sh.34, Revision 3

E906, Plant Radio System (security, fire brigade, operations), Revision 0

M1G15-9, ELemetnary Dia RCIC System, Sh. 5, Revision E17

M1H1-7BC, Functional Control Dia - Residual Heat Removal System, Sh. 2, Revision E1

M1H3-6, Functional Control Dia - Residual Heat Removal System, Revision 11

M1H5-1-15, Elementary Dia - Residual Heat Removal System, Sh. 1, Revision 20

M1H11-8, Elementary Dia - Residual Heat Removal System, Sh. 7, Revision E12

M1H40, Elementary Dia - Residual Heat Removal System, Sh. 18, Revision 18

M1J14-14, HPCI System DC MOV & Control Center, Sh. 2, Revision 6

M1J19-9, Elementary Dia, HPCI, Sh. 9, Revision E16

M1K1-8, Functional Control Dia - Core Spray System, Revision 28

M1K3-15, Elementary Dia - Core Spray System, Revision E15

M1K4-11, Elementary Dia - Core Spray System, Revision 17

M1K5-11, Elementary Dia - Core Spray System, Revision 15

M1K7-7, Elementary Dia - Core Spray System, Revision 12

M218, Sht.1, P&ID Fire Protection System, Revision 60

M6-20-9, Schematic Dia - Diesel Generator B X107B Auxiliary Control Equipment, Sh. 2,

Revision 15

M6-22-14, Schematic Dia - Diesel Generator B X107B Engine Control, Sh. 2, Revision 37

M6-46-6, Schematic & Interconnection Dia - Static Exciter & Voltage Regulator Diesel

Generator B - C102, Sh. 2, Revision 8

MMOV1, Motor Operated Valves Information Table, Revision 62

MMOV2, Motor Operated Valves Information Table, Revision 39

Fire Protection Licensing Documents

2.77.23, Fire Protection System Evaluation with respect to BTP APCSB 9.5-1, dated 3/1/1977

2.78.116, PNPS Fire Protection Information and Commitments to NRC, dated 7/10/1978

89XM-1-ER-Q, Updated Fire Hazards Analysis, Revision 17

ELNRC1.2.83.130, Appendix R Exemption Requests, dated 5/17/83

NRCLE1.1.83.267, Safety Evaluation for Appendix R to 10 CFR Part 50 Items III.G.3 and III.L,

dated 11/2/83

NRCLE1.1.84.379, Exemptions to Section II

I.G of Appendix R, dated 12/18/84

NRCLE1.1.88.120, Exemption for Certain Requirements of 10CFR50, Appendix R, Section

III.G.1 (TAC #66369), dated 4/14/88

NRCLE1.1.88.254, Exemption for Certain Requirements of 10CFR50, Appendix R, Section II

I.G

in Certain Areas of the Plant PNPS (TAC No. 523416), dated 7/14/88

TDBD105, Design Basis Document for Fire Protection/Appendix R Program, Revision 2

Miscellaneous Documents

341309-0, Laboratory Report Compressed Air/Gas Quality Testing, dated 8/24/18

Alternate Shutdown Communication Radio System Simplified Arrangement, 10/18/18

Boston Edison Company Letter 77-23, Fire Protection Program, 3/09/77

Boston Edison Company Letter 87-116, Pilgrim Nuclear Power Station Fire Protection

Information, 7/10/78

Boston Edison Company Letter 81-59, Status of Boston Edison Effort in Meeting the

Scheduler Requirement of Appendix R to 10 CFR Part 50, 3/18/81

Cylinder Retest Data Sheet Hydrostatic Volumetric Test Method Report, dated 6/12/15 - 9/12/17

EN-OP-123 Attachment 3 Scenario #1, SRV Isolation at ASPs TCA Validation, completed

8/30/18

EN-OP-123 Attachment 3 Scenario #2, 4KV Bkr, EDG-B, and CS B Local Op TCA Validation,

completed 8/30/18

EN-RP-502, Inspection and Maintenance of Respiratory Equipment, dated 9/19/18 - 10/12/18

Fire Impairments Report, dated 9/28/18

FPEE 43, Recessed Panel in Diesel Generator Building Wall No. 198.501

FSAR Section 10.8, Fire Protection System, Revision 31

Operations Night Order, SCBA Respirator Mask Staging in the Control Room, dated 10/17/18

LO-PNPLO-2018-004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment,

03/28/2018PDC/FRN No. 02-43-2, Fire Wrap conduit 2620, September 2004

Program Section No. SEP-FPP-PNP-001, Fire Protection Plan, Revision 34

NRC Letter Denton to Morisi, Pilgrim I - Fire Protection Exemption Request, 11/10/81

QA-9-2016-PNP-1, Quality Assurance Audit Report - Fire Protection, 01/11/66-02/16/16

Operator Safe Shutdown Training

JPM-200-39, Establish Reactor Pressure and Water Level Control from Outside the Control

Room (at ASPS) Job Performance Measure, Revision 4

JPM-217-06, RCIC Start from the Alternate Shutdown Panels Job Performance Measure,

Revision 13

JPM-264-04, Emergency Diesel Generator Operation Outside the Control Room Job

Performance Measure, Revision 7

O-NL-03-07-08, General and Special Fire Procedures, Revision 2

O-NL-03-07-07, Fire Hazard Inspection, Revision 6

O-RQ-04-01-257, 2016-2018 LOR HIT PSU, Revision 1

O-RQ-04-01-289, 2016-2018 Cycle 10 PSU, Revision 0

O-RQ-06-02-180, Fire in the Main Control Room, Shutdown from Outside the Control Room,

Revision 0

Procedures

1.3.34, Operations Administrative Policies and Processes, Revision 164

2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 52

2.1.26, Inventory of Alternate Shutdown and EOP Support Tools and Materials, Revision 53

2.2.22, Reactor Core Isolation Cooling System (RCIC), Revision 82

2.4.143.1, Shutdown With a fire in Reactor Building East (Fire area 1.9) and affected A

Division Fire Areas 1.21, 2.2, 2.16, 3.3, 4.3), Revision 27

2.4.143.2, Shutdown With a fire in Reactor Building West (Fire area 1.10) and affected B

Division Fire Areas 1.22, 1.23, 1.28, 2.1, 2.10, 3.5, 4.1, 5.3), Revision 30

3.M.1-18, Core Drilling and/or Breach of a Fire Seal/Vital area/Secondary

Containment/CRHEAFS Barrier, Revision 22

3.M.3-49, Emergency Lighting Battery Maintenance/Preventive Maintenance and Battery

Replacement Procedure, Revision 31

5.5.1, General Fire Procedure, Revision 27

5.5.2, Special Fire Procedure, Revision 59

5.3.36, Extensive Damage Mitigation Guidelines (EDMG) Support Procedures and Strategies,

Revision 13

6.7.1-202, PNPS Emergency Use Respiratory Protection Equipment Inspection, Revision 1

8.A.13, Plant Emergency Alarms and Radio Test, Revision 23

8.B.1, Fire Pump Test, Revision 100

8.B.4.9, Fire Panel C223, Water Treatment Area, Functional Test, Revision 10

8.B.4.12, Fire Panel C93, Emergency Diesel Generator Building, Functional Test, Revision 12

8.B.4.13, Fire Panel C94, Turbine Building, Functional Test, Revision 12

8.B.6.2, EDG B Pre-Action Sprinkler System Functional Test, Revision 14

8.B.9.2, Wet and Dry Pipe Sprinklers Alarm Test - FSAR Related, Revision 10

8.B.12, Fire Protection system Flow Tests, Revision 44

8.B.14, Fire Protection Technical Requirements, Revision 58

8.B.15, Functional Tests of Fire Pumps - P-135, P140, and P-181, Revision 57

8.B.17.1, Inspection of Fire Door Assemblies, Revision 26

8.B.17.2, Inspection of Fire Damper Assemblies, Revision 17

8.B.19, Fire Brigade Equipment Inspection, Revision 29

8.B.20, Fire Hazard(s) Inspection, Revision 18

8.B.21, Emergency Lighting Units, Revision 46

8.B.27, Radiax Backup Voice Communication System for Fire Fighting, Revision 13

8.B.29, Inspection of Fire Barriers, Revision 13

A316, Sht. 1, Reactor & Turbine Building Floor Plan El. (-) 17-6 & 6-0 Fire Barrier System,

Revision 7

A317, Sht. 1, Reactor & Turbine Building Floor Plan at El. 23-0 Fire Barrier System,

Revision 10

A318, Sht. 1, Reactor & Turbine Building Floor Plan at El. 37-0 Fire Barrier System,

Revision 7

A320, Sht. 1, Reactor & Turbine Building Floor Plans - El. 117-0, 101-0, 91-3, 74-3 7

Intake Building Plan - Fire Barrier System & 6-0 Fire Barrier System, Revision E4

A321, Reactor & Turbine Building Section A-A Fire Barrier System, Revision 3

ARP-C7R, Alarm Response Procedure, Revision 23

EN-LI-102, Corrective Action Program, Revision 35

EN-LI-121, Trending and Performance Review Process, Revision 25

EN-NS-112, Medical Program, Revision 19

EN-OP-115-03, Shift Turnover and Relief Procedure, Revision 2

EN-OP-123, Time Critical Action/Time Sensitive Action Program Standard, Revision 0

EN-PL-147, Personnel Expectations Relative to Emergency Response at Entergy Nuclear Sites,

Revision 3

EN-RP-501, Respiratory Protection Program, Revision 5

EN-RP-502, Inspection and Maintenance of Respiratory Equipment, Revision 10

EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7

EN-RP-505, PortaCount Respirator Fit Testing, Revision 7

EP-AD-425, BDBEE Communications Equipment Functionality and Inventory, Revision 2

Quality Assurance Audits and Self Assessments

CR-PNP-2016-2061, Initial Screening of Existing Self-Assessments - Fire Protection Program,

dated 7/21/16

LO-PNPLO-2018-0004, Pre-Triennial NRC Fire Protection Inspection-Self Assessment, dated

3/28/18

QA-9-2016-PNP-1, Fire Protection Quality Assurance Audit Report, dated 2/16/16

Work Order 2645165 52654363 52684842 52699713 52788716 52699712

2771221 52761762 52664402 52788716 52725473