IR 05000293/2018015

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

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

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

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.

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

3

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 III.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 R

oom, 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