IR 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
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