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=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 17, 2018
{{#Wiki_filter:October 17, 2018


==SUBJECT:==
==SUBJECT:==
Line 31: Line 31:


Sincerely,
Sincerely,
/RA/
/RA/  
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Docket Numbers: 50-220 and 50-410 License Numbers: DPR-63 and NPF-69
 
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety  
 
Docket Numbers: 50-220 and 50-410 License Numbers: DPR-63 and NPF-69  


===Enclosure:===
===Enclosure:===
Inspection Report 05000220/2018010 and 05000410/2018010
Inspection Report 05000220/2018010 and 05000410/2018010  


==Inspection Report==
==Inspection Report==
Docket Numbers: 05000220 and 05000410 License Numbers: DPR-63 and NPF-69 Report Numbers: 05000220/2018010 and 05000410/2018010 Enterprise Identifier: I-2018-010-0068 Licensee: Exelon Generation Company, LLC (Exelon)
Docket Numbers:
Facility: Nine Mile Point Nuclear Station, LLC (NMPNS)
05000220 and 05000410  
Units 1 and 2 Location: Oswego, New York Inspection Dates: September 10, 2018, to September 27, 2018 Inspectors: D. Kern, Senior Reactor Inspector (Team Lead)
 
L. Dumont, Reactor Inspector C. Hobbs, Reactor Inspector A. Patel, Senior Reactor Inspector J. Patel, Reactor Inspector J. Rady, Reactor Inspector D. Werkheiser, Senior Reactor Inspector Approved By: G. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
License Numbers:
DPR-63 and NPF-69  
 
Report Numbers:
05000220/2018010 and 05000410/2018010  
 
Enterprise Identifier: I-2018-010-0068  
 
Licensee:
Exelon Generation Company, LLC (Exelon)  
 
Facility:  
 
Nine Mile Point Nuclear Station, LLC (NMPNS)  
 
Units 1 and 2  
 
Location:
Oswego, New York  
 
Inspection Dates:
September 10, 2018, to September 27, 2018  
 
Inspectors:
D. Kern, Senior Reactor Inspector (Team Lead)
L. Dumont, Reactor Inspector
C. Hobbs, Reactor Inspector
A. Patel, Senior Reactor Inspector  
 
J. Patel, Reactor Inspector
J. Rady, Reactor Inspector
D. Werkheiser, Senior Reactor Inspector  
 
Approved By:
G. Dentel, Chief  
 
Engineering Branch 2  
 
Division of Reactor Safety  


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


NMPNS Units 1 and 2 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.
NMPNS Units 1 and 2 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.
Line 52: Line 93:
=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==
NMPNS Unit 1: 71111.05XT - Fire Protection - NFPA 805 (Triennial)
NMPNS Unit 1: 71111.05XT - Fire Protection - NFPA 805 (Triennial)
The inspectors evaluated the following from September 10 - 27, 2018:
The inspectors evaluated the following from September 10 - 27, 2018:  
Fire Protection Inspection Requirements (3 Samples)===
The inspectors evaluated fire protection program implementation in the following selected


===areas (FA) and/or fire zones (FZ):
===Fire Protection Inspection Requirements (3 Samples)===
The inspectors evaluated fire protection program implementation in the following selected areas (FA) and/or fire zones (FZ):
: (1) FA 2 / FZ R3B, Reactor Building West (elevation 281)
: (1) FA 2 / FZ R3B, Reactor Building West (elevation 281)
: (2) FA 5 / FZ T3B, Turbine Building West of Main Steam Isolation Valve Room (elevations 237, 261, 277)
: (2) FA 5 / FZ T3B, Turbine Building West of Main Steam Isolation Valve Room (elevations 237, 261, 277)
: (3) FA 11/ FZ C2, Auxiliary Control Room, Computer Room (elevation 261)
: (3) FA 11/ FZ C2, Auxiliary Control Room, Computer Room (elevation 261)  
 
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) PMP-80-23 (and associated power supply breaker), Containment Spray Pump 122
: (1) PMP-80-23 (and associated power supply breaker), Containment Spray Pump 122
Line 69: Line 110:
: (3) IV-39-05, Emergency Cooling Loop 11 Condensate Return Air Operated Isolation Valve
: (3) IV-39-05, Emergency Cooling Loop 11 Condensate Return Air Operated Isolation Valve
: (4) IV-39-10R, Motor Operated Loop 12 Steam Outlet Inside Isolation Valve 121
: (4) IV-39-10R, Motor Operated Loop 12 Steam Outlet Inside Isolation Valve 121
: (5) LI-60-22C, Emergency Condenser 111-112 Level Indicator Remote Shutdown B.5.b Inspection Activities (1 Samples)===
: (5) LI-60-22C, Emergency Condenser 111-112 Level Indicator Remote Shutdown  
 
===B.5.b Inspection Activities (1 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) N1-DRP-OPS-001 (section 6.6.1), Venting Primary Containment without AC power Method 1; Reverse Flow Using the Large De-inerting Lines NMPNS Unit 2: 71111.05T - Fire Protection (Triennial)


===(1) N1-DRP-OPS-001 (section 6.6.1), Venting Primary Containment without AC power Method 1; Reverse Flow Using the Large De-inerting Lines NMPNS Unit 2: 71111.05T - Fire Protection (Triennial)
The inspectors evaluated the following from September 10 - 27, 2018:  
The inspectors evaluated the following from September 10 - 27, 2018:
Fire Protection Inspection Requirements (4 Samples)===
The inspectors evaluated fire protection program implementation in the following selected


===areas and/or fire zones:
===Fire Protection Inspection Requirements (4 Samples)===
The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones:
: (1) FA 2 / FZ 204SW, Reactor Building, Reactor Core Isolation Cooling (RCIC) Pump Room (elevation 175)
: (1) FA 2 / FZ 204SW, Reactor Building, Reactor Core Isolation Cooling (RCIC) Pump Room (elevation 175)
: (2) FA 24/ FZ 356NZ/354SG, Control Building, Power Generation Control Complex Relay Room (elevation 288)
: (2) FA 24/ FZ 356NZ/354SG, Control Building, Power Generation Control Complex Relay Room (elevation 288)
: (3) FA 3 / FZ 208 SW, C Residual Heat Removal (RHR) Pump Room, South Auxiliary Bay (elevation 175)
: (3) FA 3 / FZ 208 SW, C Residual Heat Removal (RHR) Pump Room, South Auxiliary Bay (elevation 175)
: (4) FA 3 / FZ 239 SW, South Auxiliary Bay, Electrical Room (elevation 240)
: (4) FA 3 / FZ 239 SW, South Auxiliary Bay, Electrical Room (elevation 240)  
 
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) 2ICS*MOV120, RCIC Steam Supply Valve to Turbine
: (1) 2ICS*MOV120, RCIC Steam Supply Valve to Turbine
Line 88: Line 131:
: (4) 2RHS*MOV15B, B RHR Reactor Containment Spray
: (4) 2RHS*MOV15B, B RHR Reactor Containment Spray
: (5) 2EGS*EG3, 4160-V ACB-103-14 Division II Emergency Diesel Generator Output Breaker
: (5) 2EGS*EG3, 4160-V ACB-103-14 Division II Emergency Diesel Generator Output Breaker
: (6) 2CMS*TE54A, Suppression Pool Temperature Element B.5.b Inspection Activities (1 Samples)===
: (6) 2CMS*TE54A, Suppression Pool Temperature Element  
 
===B.5.b Inspection Activities (1 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) N2-DRP-OPS-001 (section 7.2.10), Injection of an Alternate Water Source into the Reactor Pressure Vessel via Residual Heat Removal Train A
: (1) N2-DRP-OPS-001 (section 7.2.10), Injection of an Alternate Water Source into the Reactor Pressure Vessel via Residual Heat Removal Train A
Line 142: Line 187:
ECP-12-000658, Portable Charger for Existing Battery Chargers, Revision 0
ECP-12-000658, Portable Charger for Existing Battery Chargers, Revision 0
ECP-13-000516 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for
ECP-13-000516 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for
Local Fire Control Panels Upgrade for 2FPM-PNL131, Revision 0
Local Fire Control Panels Upgrade for 2FPM-PNL131, Revision 0  
 
ECP-13-000517 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for
ECP-13-000517 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for
Local Fire Control Panels Upgrade for 2FPM-PNL128, Revision 0
Local Fire Control Panels Upgrade for 2FPM-PNL128, Revision 0
Line 195: Line 241:
Revision 27
Revision 27
B-40142-C Sht. 5, Fire Zones Reactor Bldg. F
B-40142-C Sht. 5, Fire Zones Reactor Bldg. F
: [[contact::L. EL.237 and 250]], Revision 2
: [[contact::L. EL.237 and 250]], Revision 2  
 
B-40143-C Sht. 5, Fire Zones Reactor Bldg. F
B-40143-C Sht. 5, Fire Zones Reactor Bldg. F
: [[contact::L. EL.261]], Revision 2
: [[contact::L. EL.261]], Revision 2
Line 242: Line 289:
EE-001CN, Nine Mile Point Unit 2 125V DC One Line Diagram, Emergency Switchgear
EE-001CN, Nine Mile Point Unit 2 125V DC One Line Diagram, Emergency Switchgear
2BYS*SWG002B, Revision 18
2BYS*SWG002B, Revision 18
EE-001D, Nine Mile Point Unit 2 Main One Line Diagram, Emergency 4.16KV & 600V System ,
EE-001D, Nine Mile Point Unit 2 Main One Line Diagram, Emergency 4.16KV & 600V System,
Revision 19
Revision 19
EE-001P, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG017 &
EE-001P, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG017 &
2NNS-SWG018, Revision 11
2NNS-SWG018, Revision 11  
 
EE-001R, Nine Mile Point Unit 2 4160V One Line Diagram, 2ENS*SWG103 Emergency Bus,
EE-001R, Nine Mile Point Unit 2 4160V One Line Diagram, 2ENS*SWG103 Emergency Bus,
Revision 16
Revision 16
Line 288: Line 336:
PID-82B-21, Nine Mile Point Unit 2 P&ID, Containment Atmosphere Monitoring System,
PID-82B-21, Nine Mile Point Unit 2 P&ID, Containment Atmosphere Monitoring System,
Revision 21
Revision 21
TL2CMS-065, Nine Mile Point Unit 2 Test Loop Diagram, Suppression Pool Water Temperature
TL2CMS-065, Nine Mile Point Unit 2 Test Loop Diagram, Suppression Pool Water Temperature  
      - 2CMS*TE54A, Sht.s 1-2, Revision 2
- 2CMS*TE54A, Sht.s 1-2, Revision 2
TL2ICS-018, Nine Mile Point Unit 2 Test Loop Diagram, 2ICS*P1 Discharge Flow 2ICS*FT101,
TL2ICS-018, Nine Mile Point Unit 2 Test Loop Diagram, 2ICS*P1 Discharge Flow 2ICS*FT101,
Sht.s 1-4, Revision 4
Sht.s 1-4, Revision 4
W-4162-S; Drawing EP-116C-20, Revision 20
W-4162-S; Drawing EP-116C-20, Revision 20
W-6746-C; Drawing 12177-EP-64X-18, Revision 18 and 12177-EP-64BB-4, Revision 4
W-6746-C; Drawing 12177-EP-64X-18, Revision 18 and 12177-EP-64BB-4, Revision 4  
 
Fire Brigade Drills and Critiques
Fire Brigade Drills and Critiques
Crew A Announced Drill Critique, dated 06/03/2018
Crew A Announced Drill Critique, dated 06/03/2018
Line 330: Line 379:
NMP Fire Brigade Training Lesson Plans, dated 08/22/2018
NMP Fire Brigade Training Lesson Plans, dated 08/22/2018
Issue Reports (* written as a result of the NRC inspection)
Issue Reports (* written as a result of the NRC inspection)
2386737                   02731612                04153695      04177242*
2386737
2451647                   03985725                 04165743       04177243*
2451647
2466129                    03987731                04168498*      04177301*
2466129
2512975                    04009918                04171603*      04177325*
2512975
2525704                    04056647                04172378*      04177360*
2525704
2539404                    04060022                04172682*      04177602*
2539404
2574976                    04134964                04172929*      04177679*
2574976
2594680                    04146572                04172933*      04177717*
2594680
2631360                    04147291                04173143*      04177730*
2631360
2641770                    04148844                04173174*      04177789*
2641770
2719945                    04148873                04173216*
2719945
2725444                    04153260                04177236*
2725444
2731612
03985725
03987731
04009918
04056647
04060022
04134964
04146572
04147291
04148844
04148873
04153260
04153695
04165743
04168498*
04171603*
04172378*
04172682*
04172929*
04172933*
04173143*
04173174*
04173216*
04177236*
04177242*
04177243*
04177301*
04177325*
04177360*
04177602*
04177679*
04177717*
04177730*
04177789*
 
Maintenance Orders/Work Orders
Maintenance Orders/Work Orders
C90944610                 C93592851               C93539647               C93624893
C90944610
C93455439                  C93188022              C93623262               C92787911
C93455439
C93455560                  C92073139              C91916097               C91987944
C93455560
C93469547                  C93633239              C93621049               N2060027
C93469547
C93469568                  C93298175              C93161344               N2072150
C93469568
C93470114                  C92807105              C93628910               N2089806
C93470114
C93470175                  C92073136              C93633631               N2101337
C93470175
C93470175                  C93552754              C93068249               N2104141
C93470175
C93502926                  C92938470              C92299697               N2111453
C93502926
C93586855                  C93167744              C93533770
C93586855
C99289531                  C92038944              C93155172
C99289531
C92902999                  C93176027              C93619558
C92902999
C93592851
C93188022
C92073139
C93633239
C93298175
C92807105
C92073136
C93552754
C92938470
C93167744
C92038944
C93176027
C93539647
C93623262
C91916097
C93621049
C93161344
C93628910
C93633631
C93068249
C92299697
C93533770
C93155172
C93619558
C93624893
C92787911
C91987944
N2060027
N2072150
N2089806
N2101337
N2104141
N2111453
Operating Experience
Operating Experience
NRC IN 2010-13, Failure to Ensure Post-Fire Shutdown Procedures Can be Performed
NRC IN 2010-13, Failure to Ensure Post-Fire Shutdown Procedures Can be Performed
Line 390: Line 507:
OP-AA-201-001, Fire Marshal Tours, Revision 6
OP-AA-201-001, Fire Marshal Tours, Revision 6
OP-AA-201-002, Fire Event reports, Revision 6
OP-AA-201-002, Fire Event reports, Revision 6
OP-AA-201-203, Fire Drill Performance, Revision 16
OP-AA-201-203, Fire Drill Performance, Revision 16  
 
OP-AA-201-004, Fire Prevention for Hot Work, Revision 15
OP-AA-201-004, Fire Prevention for Hot Work, Revision 15
OP-AA-201-005, Fire Brigade Qualification, Revision 9
OP-AA-201-005, Fire Brigade Qualification, Revision 9
Line 435: Line 553:
N2-PM-M007, Motor-Driven Fire Pump Operability Test, completed 07/27/2018
N2-PM-M007, Motor-Driven Fire Pump Operability Test, completed 07/27/2018
S-PM-004, Operation Equipment Inventories and Checklists, Completed on 6/14/18
S-PM-004, Operation Equipment Inventories and Checklists, Completed on 6/14/18
S-PM-004, Operation Equipment Inventories and Checklists, Completed on 8/24/18
S-PM-004, Operation Equipment Inventories and Checklists, Completed on 8/24/18  
 
Miscellaneous Documents
Miscellaneous Documents
List of Fire Brigade Members qualification Training, dated 9/13/18
List of Fire Brigade Members qualification Training, dated 9/13/18
MI-2AI-185, Foxboro 2AI-P2V Series Platinum Resistance to Voltage Converter Styles B and C,
MI-2AI-185, Foxboro 2AI-P2V Series Platinum Resistance to Voltage Converter Styles B and C,
issued August 1980
issued August 1980
Nine Mile Point Nuclear Station Unit 2, Individual Plant Examination for External Events
Nine Mile Point Nuclear Station Unit 2, Individual Plant Examination for External Events  
        (IPEEE), June 1995
(IPEEE), June 1995
NMP Operations Equipment Inventories and Checklists:
NMP Operations Equipment Inventories and Checklists:
Quarterly Inspection/Inventory of Fire Brigade Turnout Gear, 2018
Quarterly Inspection/Inventory of Fire Brigade Turnout Gear, 2018

Latest revision as of 11:25, 5 January 2025

Triennial Fire Protection Inspection Report 05000220/2018010 and 05000410/2018010
ML18290A670
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 10/17/2018
From: Glenn Dentel
NRC Region 1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2018010
Download: ML18290A670 (14)


Text

October 17, 2018

SUBJECT:

NINE MILE POINT NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000220/2018010 AND 05000410/2018010

Dear Mr. Hanson:

On September 27, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station (NMPNS), Units 1 and 2. On September 27, 2018, the NRC inspectors discussed the results of this inspection with Mr. Peter Orphanos, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any 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 Numbers: 50-220 and 50-410 License Numbers: DPR-63 and NPF-69

Enclosure:

Inspection Report 05000220/2018010 and 05000410/2018010

Inspection Report

Docket Numbers:

05000220 and 05000410

License Numbers:

DPR-63 and NPF-69

Report Numbers:

05000220/2018010 and 05000410/2018010

Enterprise Identifier: I-2018-010-0068

Licensee:

Exelon Generation Company, LLC (Exelon)

Facility:

Nine Mile Point Nuclear Station, LLC (NMPNS)

Units 1 and 2

Location:

Oswego, New York

Inspection Dates:

September 10, 2018, to September 27, 2018

Inspectors:

D. Kern, Senior Reactor Inspector (Team Lead)

L. Dumont, Reactor Inspector

C. Hobbs, Reactor Inspector

A. Patel, Senior Reactor Inspector

J. Patel, Reactor Inspector

J. Rady, Reactor Inspector

D. Werkheiser, Senior Reactor Inspector

Approved By:

G. Dentel, Chief

Engineering Branch 2

Division of Reactor Safety

SUMMARY

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

NMPNS Units 1 and 2 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

NMPNS Unit 1: 71111.05XT - Fire Protection - NFPA 805 (Triennial)

The inspectors evaluated the following from September 10 - 27, 2018:

Fire Protection Inspection Requirements (3 Samples)

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

(1) FA 2 / FZ R3B, Reactor Building West (elevation 281)
(2) FA 5 / FZ T3B, Turbine Building West of Main Steam Isolation Valve Room (elevations 237, 261, 277)
(3) FA 11/ FZ C2, Auxiliary Control Room, Computer Room (elevation 261)

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

(1) PMP-80-23 (and associated power supply breaker), Containment Spray Pump 122
(2) PMP-28-15, Control Rod Drive Pump 11 NC08A
(3) IV-39-05, Emergency Cooling Loop 11 Condensate Return Air Operated Isolation Valve
(4) IV-39-10R, Motor Operated Loop 12 Steam Outlet Inside Isolation Valve 121
(5) LI-60-22C, Emergency Condenser 111-112 Level Indicator Remote Shutdown

B.5.b Inspection Activities (1 Samples)

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

(1) N1-DRP-OPS-001 (section 6.6.1), Venting Primary Containment without AC power Method 1; Reverse Flow Using the Large De-inerting Lines NMPNS Unit 2: 71111.05T - Fire Protection (Triennial)

The inspectors evaluated the following from September 10 - 27, 2018:

Fire Protection Inspection Requirements (4 Samples)

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

(1) FA 2 / FZ 204SW, Reactor Building, Reactor Core Isolation Cooling (RCIC) Pump Room (elevation 175)
(2) FA 24/ FZ 356NZ/354SG, Control Building, Power Generation Control Complex Relay Room (elevation 288)
(3) FA 3 / FZ 208 SW, C Residual Heat Removal (RHR) Pump Room, South Auxiliary Bay (elevation 175)
(4) FA 3 / FZ 239 SW, South Auxiliary Bay, Electrical Room (elevation 240)

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

(1) 2ICS*MOV120, RCIC Steam Supply Valve to Turbine
(2) 2ICS*FE101, RCIC Flow Instrument
(3) 2RHS*P1B, B RHR Pump
(4) 2RHS*MOV15B, B RHR Reactor Containment Spray
(5) 2EGS*EG3, 4160-V ACB-103-14 Division II Emergency Diesel Generator Output Breaker
(6) 2CMS*TE54A, Suppression Pool Temperature Element

B.5.b Inspection Activities (1 Samples)

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

(1) N2-DRP-OPS-001 (section 7.2.10), Injection of an Alternate Water Source into the Reactor Pressure Vessel via Residual Heat Removal Train A

EXIT MEETINGS AND DEBRIEFS

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

  • On September 27, 2018, the inspectors presented the triennial fire protection team inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the Exelon staff.

DOCUMENTS REVIEWED

71111.05XT

Fire Protection Licensing and Design Basis Documents

DBD-Appendix R, Appendix R Safe Shutdown System, Revision 11

DCD-805, Nine Mile Point Unit 1 NFPA 805 Design Criteria, Revision 1

E208, Nine Mile Point 1 Nuclear Safety Capability Assessment, Revision 0

N1-FQ-F001, Fire PRA Notebook, Revision 5

N1-FRE-F001, Fire Risk Evaluation Report, Revision 3

Nine Mile Point Nuclear Station Unit 2, Renewed Facility Operating License NPF-69,

Amendment No. 144

Nine Mile Point Nuclear Station Unit 2, Updated Safety Analysis Report, Revision 22

NMP Unit 2 USAR - Chapter 9.5, Other Auxiliary Systems - Fire Protection System,

Revision 23

NMP Unit 2 USAR - Appendix 9A, Degree of Compliance with Branch Technical Position

CMED 9.5-1, Revision 2

NMP Unit 2 USAR - Appendix 9B, Appendix R Review Safe Shutdown Evaluation, Degree of

Compliance with Branch Technical Position CMED 9.5-1, Revision 22

NUREG-1047, Safety Evaluation Report (SER) related to the Operation of NMP Unit 2, dated

2/1985

NUREG-1047, SER Supplement 1 - NMP Unit 2, dated 07/1985

NUREG-1047, SER Supplement 2 - NMP Unit 2, dated 11/1985

NUREG-1047, SER Supplement 3 - NMP Unit 2, dated 07/1985

NUREG-1047, SER Supplement 4 - NMP Unit 2, dated 09/1986

NUREG-1047, SER Supplement 5 - NMP Unit 2, dated 10/1986

NUREG-1047, SER Supplement 6 - NMP Unit 2, dated 07/1987

Calculations, Analysis, and Engineering Evaluations

51-9156521-000, Recovery Action Review for Nine Mile Point Nuclear Power Station Unit 1

Transition to NFPA 805, Revision 0

130-5007D, Halon 1301 Evaluation - NMP2, Underfloor Area Zone #354SG, dated 04/08/1986

1NER-1E-035, Resolution of Issues Related to Fire-Induced Circuit Failures, Revision 2

1NER-1E-037, Nine Mile Point Unit 1 NFPA 805 - Cable Selection, Revision 1

1NER-1E-039, Nine Mile Point Unit 1 NFPA 805 Coordination Study, Revision 0

A10.1-N-401, Appendix R Service Water Flow Evaluation, Revision 0

E208, Nine Mile Point 1 Nuclear Safety Capability Assessment, Revision 0

EC-160, 125 VDC Breaker Coordination, Revision 0

EC-166, 4160 VAC Safety Related Breaker Coordination, Revision 0

EC-49, DC Short Circuit, Revision 7

ECP-12-000299, Multiple Spurious Operations (MSO) - 2RHS*MOV15A, 15B, 25A, and 25B,

Revision 0

ECP-12-000571, Unit 1 NFPA Transition Project - Modification for BV-37-01(02) Reactor Head

Vent Valves, Revision 0

ECP-12-000574, Reactor Water Cleanup System (RWCS), Revision 002

ECP-12-000576, Form 7 - Design Change Technical Evaluation, Revision 0

ECP-12-000658, Portable Charger for Existing Battery Chargers, Revision 0

ECP-13-000516 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for

Local Fire Control Panels Upgrade for 2FPM-PNL131, Revision 0

ECP-13-000517 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for

Local Fire Control Panels Upgrade for 2FPM-PNL128, Revision 0

ECP-13-000520 - NMP U2 Fire Protection Improvement Project - Fire Panel Replacement for

Local Fire Control Panels Upgrade for 2FPM-PNL129, Revision 3

ECP-13-000973, Fire Protection Review, dated 11/21/13

ECP-13-000973, Form 7 - Design Change Technical Evaluation, Revision 0

ECP-13-000972, Form 7 - Design Change Technical Evaluation, Revision 0

ECP-14-000514, Form 7 - Design Change Technical Evaluation, Revision 0

ECP-15-000297, Unit 2 Open Phase Detection Implementation (ABS and RTX Transformers),

Revision 1

ECP-18-000425, Temporary Modification for 2MTX-XM1A Low Conservator Oil Alarm,

Revision 0

FPEE1-12-001, Evaluation of NMP 1 Appendix R Exceptions for Transition to NFPA 805,

Revision 01

FPEE2-14-001, Fire Protection Engineering Evaluation - DC Hot Shorts on Non-safety Related

Ammeter Circuits, Revision 0

FPEE2-17-002, Use of Non IEEE-383 Rated Cabling in Power Generation Control Complex,

Revision 0

N1-HRA-F001, Fire PRA Notebook Human Reliability Analysis NMP1, Revision 4

NMP Unit 1 Fire PRA Notebook, Human Reliability Analysis, Revision 4

NMP Unit 1 PRA Success Criteria Notebook, Revision 0

S13.1100F002, Fire Protection Water Supply, dated 4/12/07

Drawings and Wiring Diagrams

0007.241-001-009, Nine Mile Point Unit 2 Elementary Diagram, Residual Heat Removal

System, Revision 3

0007.241-001-016, Nine Mile Point Unit 2 Elementary Diagram, Residual Heat Removal

System, Revision 4

0007.245-001-022, Nine Mile Point Unit 2 Elementary Diagram, Reactor Core Isolation Cooling

System, Revision 4

0007.511-980-574, Nine Mile Point Unit 2 Wiring Diagram, Remote Shutdown Panel 2CES*405,

Revision 3

01040209024, Nine Mile Point Unit 2, Control Schematic 2CES*IPNL406 (G) &

2CES*IPNL408 (Y), Revision 3

2177-EE-11HB-2, Nine Mile Point Unit 2 Wiring Diagram, Misc. Equipment, Revision 2

2177-EE-IJ-9, Nine Mile Point Unit 2 13.8KV One Line Diagram, Emergency Bus

2EPS*SWG001, 002, 003, 004, & Normal Bus 2NPS-SWG004, 005, Revision 9

2177-ESK-11RSS05, Nine Mile Point Unit 2 Wiring Diagram, D.C. Misc. Circuits - Suppression

Pool Temperature Selector, Revision 2

2177-ESK-5EGP03, Nine Mile Point Unit 2

D.C. Elementary Diagram, Standby Diesel

Generator 2EGS*EG3 ACB103-14, Sht.s 1-2, Revision 18

2177-ESK-5RHS05, Nine Mile Point Unit 2

D.C. Elementary Diagram, Residual Heat Removal

Pump 1B, Revision 6

2177-ESK-5SWP01, Sht. 1, Service Water Pump 1A Elementary Diagram, Revision 13

2177-ESK-5SWP01, Sht. 2, Service Water Pump 1A Elementary Diagram, Revision 13

2177-ESK-5SWP02, Sht. 1, Service Water Pump 1B Elementary Diagram, Revision 13

2177-ESK-5SWP03, Sht. 1, Service Water Pump 1C Elementary Diagram, Revision 15

2177-ESK-5SWP04, Sht. 1, Service Water Pump 1D Elementary Diagram, Revision 14

807E170TY, Nine Mile Point Unit 2 Elementary Diagram, Residual Heat Removal System,

Revision 27

B-40142-C Sht. 5, Fire Zones Reactor Bldg. F

L. EL.237 and 250, Revision 2

B-40143-C Sht. 5, Fire Zones Reactor Bldg. F

L. EL.261, Revision 2

B-40144-C, Fire Zones Reactor Building/Turbine Building el. 281/277, Revision 1

B-40144-C Sht. 5, Fire Zones Reactor Bldg. F

L. EL.277 and 281, Revision 2

C-18002-C, Sht. 1, Main Steam & High Pressure Turbine, Revision 49

C-18002-C, Sht. 2, Main Steam & High Pressure Turbine, Revision 36

C-18007-C, Sht. 1, Reactor Core Spray, Revision 62

C-18012-C, Sht. 1, Reactor Containment Spray Raw Water System, Revision 26

C-18015-C, Reactor Vessel Instrumentation P&ID Diagram, Revision 42

C-18017-C, Emergency Cooling System P&I Diagram, Revision 56

C-18030-C Sht. 2, Fire Protection Foam & Spray Water P&I Diagram, Revision 15

C-18030-C Sht. 3, Fire Protection Water System P&I Diagram, Revision 42

C-18030-C Sht. 4, Fire Protection Water System P&I Diagram, Revision 21

C-18030-C Sht. 5, Fire Protection Water System P&I Diagram, Revision 24

C-18030-C Sht. 6, Fire Protection Water System P&I Diagram, Revision 33

C-18030-C Sht. 7, Fire Protection Water System P&I Diagram, Revision 25

C-18030-C Sht. 8, Fire Protection Water System P&I Diagram, Revision 15

C-18039-C Sht. 2, Cardox Fire Extinguishing System, Revision 9

C-18039-C Sht. 3, Cardox Fire Extinguishing System, Revision 13

C-19409-C, Sht. 1B, Unit 1 AC Station Power Distribution One Line Diagram, Revision 18

C-19410-C, Sht. 6, Unit 1 4.16 kV Emergency Power Board & Diesel Generator, Revision 25

C-19436-C, Sht. 2, Unit 1 Elementary Wiring Diagram 600V Power Board #16, Revision 19

C-19437-C, Sht. 6, Unit 1 Elementary Wiring Diagram 600V Power Board 161B, Revision 26

C-19839-C, Sht. 19, Unit 1 One Line Diagram 125 VDC Control Bus, Revision 13

C-19839-C, Sht. 2, Unit 1 One Line Diagram 125 VDC Control Bus, Revision 23

C-19839-C, Sht. 3, Unit 1 One Line Diagram 125 VDC Control Bus, Revision 25

C-19839-C, Sht. 9, Unit 1 One Line Diagram 125 VDC Control Bus, Revision 4

C-19859-C, Sht. 8, Unit 1 Reactor Protection System, Revision 51

C-19859-C, Sht. 8A, Unit 1 Reactor Protection System, Revision 25

C-22014-C, Sht. 1, Unit 1 Wiring Diagram Emergency Cooling, Revision 18

C-23107-C, Sht. 2, Unit 1 Auxiliary Control Cabinet Emergency Cooling, Revision 29

C-34812-C, Sht. 1, Unit 1 Remote Reactor Shutdown System, Revision 7

C-34813-C, Sht. 1, Unit 1 Wiring Diagram Remote Reactor Shutdown System, Revision 13

EB-22A, Nine Mile Point Unit 2, Fire Protection Arrangement Unit 2 Station Buildings Plan

Elevation 175 & 198, Revision 15

EB-22C, Nine Mile Point Unit 2, Fire Protection Arrangement Unit 2 Station Buildings Plan

Elevation 237 & 240, Revision 19

EB-22D, Nine Mile Point Unit 2, Fire Protection Arrangement Unit 2 Station Buildings Plan

Elevation 250 & 274, Revision 22

EB-22E, Nine Mile Point Unit 2, Fire Protection Arrangement Unit 2 Station Buildings Plan

Elevation 277 & 288, Revision 20

EE-001C, Nine Mile Point Unit 2 Main One Line Diagram, 4.16KV Auxillary Transformer Normal

4.16KV & 600V System, Revision 13

EE-001CN, Nine Mile Point Unit 2 125V DC One Line Diagram, Emergency Switchgear

2BYS*SWG002B, Revision 18

EE-001D, Nine Mile Point Unit 2 Main One Line Diagram, Emergency 4.16KV & 600V System,

Revision 19

EE-001P, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG017 &

2NNS-SWG018, Revision 11

EE-001R, Nine Mile Point Unit 2 4160V One Line Diagram, 2ENS*SWG103 Emergency Bus,

Revision 16

EE-009NK, Nine Mile Point Unit 2 Wiring Diagram, 2EHS*MCC303 Bus D Control Room Bldg.

EL 261, Revision 6

EE-009SG, Nine Mile Point Unit 2 Wiring Diagram, 600V 2EHS*MCC303 Control Room Bldg.

EL 261, Revision 6

EE-011HA, Nine Mile Point Unit 2 Wiring Diagram, Misc. Equipment, Revision 6

EE-1AW, Nine Mile Point Unit 2 One Line Diagram, 600V 2EHS*MCC302 Reactor Building

Auxillary Bay South, Revision 14

EE-1CP, Nine Mile Point Unit 2 One Line Diagram, 125 VDC 2DMS*MCCA1 Auxillary Building,

Revision 15

EE-1K, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG011 &

2NNS-SWG012, Revision 13

EE-1L, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG013,

Revision 12

EE-1M, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG014,

Revision 11

EE-1N, Nine Mile Point Unit 2 4160V One Line Diagram, Normal Bus 2NNS-SWG015,

Revision 11

EE-1Q, Nine Mile Point Unit 2 4160V One Line Diagram, 2ENS*SWG101 Emergency Bus,

Revision 16

EE-3MG, Nine Mile Point Unit 2 Wiring Diagram, Remote Shutdown Panel - 2CES*PNL405,

Revision 4

EE-M01F, Nine Mile Point Unit 2 Plant Master One Line Diagram, Emergency & Normal 125V &

24/48 VDC, Revision 8

EE-MO001A, Nine Mile Point Unit 2 Plant Master One Line Diagram, Normal Power Distribution,

Revision 23

EE-MO001B, Nine Mile Point Unit 2 Plant Master One Line Diagram, Emergency Power

Distribution, Revision 9

ESK-06RHS008, Nine Mile Point Unit 2 Elementary Diagram, Residual Heat Removal 600V

MCC Circuit, Sht. 1, Revision 8

ESK-11ICS01, Nine Mile Point Unit 2 Elementary Diagram, Reactor Core Isolation Cooling

Steam Valve to Turbine 2ICS*MOV120, Revision 12

F-45094-C, Fire Protection Halon P&I Diagram, Revision 6

FSK-11RSS07, Nine Mile Point Unit 2 Elementary Diagram, 125 VDC Remote Shutdown

System, Revision 8

FSK-33-2C, Nine Mile Point Unit 2 Loop Diagram, Containment Atmosphere Monitoring -

2CMS*54, Revision 7

PID-31A, Nine Mile Point Unit 2 P&ID, Residual Heat Removal System, Revision 25

PID-31B, Nine Mile Point Unit 2 P&ID, Residual Heat Removal System, Revision 22

PID-82B-21, Nine Mile Point Unit 2 P&ID, Containment Atmosphere Monitoring System,

Revision 21

TL2CMS-065, Nine Mile Point Unit 2 Test Loop Diagram, Suppression Pool Water Temperature

- 2CMS*TE54A, Sht.s 1-2, Revision 2

TL2ICS-018, Nine Mile Point Unit 2 Test Loop Diagram, 2ICS*P1 Discharge Flow 2ICS*FT101,

Sht.s 1-4, Revision 4

W-4162-S; Drawing EP-116C-20, Revision 20

W-6746-C; Drawing 12177-EP-64X-18, Revision 18 and 12177-EP-64BB-4, Revision 4

Fire Brigade Drills and Critiques

Crew A Announced Drill Critique, dated 06/03/2018

Crew B Announced Drill Critique, dated 06/03/2018

Crew B Announced Drill Critique, dated 04/14/2018

Crew B UnSat Drill Critique, dated 04/04/2018

Crew B Unannounced Drill Critique, dated 03/28/2018

Crew C Announced Drill Critique, dated 06/02/2018

Crew D Announced Drill Critique, dated 06/09/2018

Crew D Unannounced Drill Critique, dated 11/29/2017 (NEIL Drill)

Crew E Announced Drill Critique, dated 06/09/2018

End of the Year Fire Drill Review, Completed on 12/28/16

End of the Year Fire Drill Review, Completed on 12/15/17

Fire Drill quarterly Review, Completed on 6/28/16

Fire Drill quarterly Review, Completed on 9/27/16

Fire Drill quarterly Review, Completed on 12/28/16

Fire Drill quarterly Review, Completed on 3/24/17

Fire Drill quarterly Review, Completed on 6/25/17

Fire Drill quarterly Review, Completed on 10/6/17

Fire Drill quarterly Review, Completed on 12/31/17

NMP Unsatisfactory Drill Summary, dated 08/22/2018

NMP Unannounced Drill Schedule 2016 - 2018, dated 08/22/2018

OP-AA-201-003, Announced Fire Drill Record, Completed on 7/13/16

OP-AA-201-003, Announced Fire Drill Record, Completed on9/7/16

OP-AA-201-003, Announced Fire Drill Record, Completed on 2/24/16

OP-AA-201-003, Announced Fire Drill Record, Completed on11/15/17

OP-AA-201-003, Announced Fire Drill Record, Completed on 2/25/17

OP-AA-201-003, Unannounced Fire Drill Record, Completed on 11/15/17

OP-AA-201-003, Unannounced Fire Drill Record, Completed on 11/29/17

OP-AA-201-003, Unannounced Fire Drill Record, Completed on 12/2/17

OP-AA-201-003, Unannounced Fire Drill Record, Completed on12/3/17

OP-AA-201-003, Unannounced Fire Drill Record, Completed on 12/10/17

Fire Fighting Strategies (i.e., Pre-Fire Plans)

N1-PFP-0101, Unit 1 Pre-Fire Plans, Revision 5

N2-FPI-PFP-0201, Nine Mile Point Unit 2 Pre-Fire Plans, Revision 5

NMP Fire Brigade Training Lesson Plans, dated 08/22/2018

Issue Reports (* written as a result of the NRC inspection)

2386737

2451647

2466129

2512975

2525704

2539404

2574976

2594680

2631360

2641770

2719945

2725444

2731612

03985725

03987731

04009918

04056647

04060022

04134964

04146572

04147291

04148844

04148873

04153260

04153695

04165743

04168498*

04171603*

04172378*

04172682*

04172929*

04172933*

04173143*

04173174*

04173216*

04177236*

04177242*

04177243*

04177301*

04177325*

04177360*

04177602*

04177679*

04177717*

04177730*

04177789*

Maintenance Orders/Work Orders

C90944610

C93455439

C93455560

C93469547

C93469568

C93470114

C93470175

C93470175

C93502926

C93586855

C99289531

C92902999

C93592851

C93188022

C92073139

C93633239

C93298175

C92807105

C92073136

C93552754

C92938470

C93167744

C92038944

C93176027

C93539647

C93623262

C91916097

C93621049

C93161344

C93628910

C93633631

C93068249

C92299697

C93533770

C93155172

C93619558

C93624893

C92787911

C91987944

N2060027

N2072150

N2089806

N2101337

N2104141

N2111453

Operating Experience

NRC IN 2010-13, Failure to Ensure Post-Fire Shutdown Procedures Can be Performed

NRC IN 2014-10, Potential Circuit Failure-Induced Secondary Fires or Equipment Damage

NRC IN 2015-02, Anti-Freeze Agents in Fire Water Sprinkler Systems

NRC LER 05000-263/2016-002-01, Inadequate Floor Fire Barrier for Control Room

Procedures

CC-AA-201, Plant Barrier Control Program, Revision 12

CC-AA-206, Fuse Control, Revision 11

CC-AA-209, Fire Protection Program Configuration Change Review, Revision 6

CC-AA-211, Fire Protection Program, Revision 8

CC-AA-211-1001, Fire Protection Engineering Evaluations, Revision 2

ER-AA-610-1003, NFA 805 Monitoring Program, Revision 0

N1-ARP-K1, Control Room Panel K1, Revision 7

N1-DRP-GEN-004, Emergency Damage Repair for Fire Zones C2 and C3, Revision 12

N1-EOP-2, RPV Control, Revision 16

N1-EOP-8, RPV Blowdown, Revision 12

N1-SOP-21.1, Nine Mile Point Unit 2 Special Operating Procedure, Revision 14

N1-SOP-21.2, Control Room Evacuation, Revision 16

N2-ARP-FPM, Fire Computer System Alarm Response Procedures, Revision 16

N2-DRP-OPS-001, Emergency Damage Repair, Revision 1

N2-EOP-6.11, Nine Mile Point Unit 2 Emergency Operating Procedure, Defeating WCS System

Isolation Interlocks, Revision 1

N2-EPM-GEN-555, GE 13.8 KV MAGNE-BLAST Breaker, Revision 4

N2-EPM-GEN-V582, Molded Case Circuit Breaker and Thermal Overload Relay Testing,

Revision 23

N2-OP-78, Remote Shutdown System, Revision 14

N2-OSP-FOF-M001, ENGINE DRIVEN FIRE PUMP OPERABILITY & STORAGE TANK LEVEL

TEST, Revision 3

N2-SOP-03, Loss of AC Power, Revision 18

N2-SOP-34, Stuck Open Safety Relief Valve, Revision 6

N2-SOP-78, Control Room Evacuation, Revision 9

N2-SOP-101C, Reactor Scram, Revision 13

N2-SOP-101D, Rapid Power Reduction, Revision 10

OP-AA-201-001, Fire Marshal Tours, Revision 6

OP-AA-201-002, Fire Event reports, Revision 6

OP-AA-201-203, Fire Drill Performance, Revision 16

OP-AA-201-004, Fire Prevention for Hot Work, Revision 15

OP-AA-201-005, Fire Brigade Qualification, Revision 9

OP-AA-201-006, Control of Temporary Heat Generating Equipment, Revision 8

OP-AA-201-007, Fire Protection System Impairment Control, Revision 0

OP-AA-201-008, Pre-Fire Plan Manual, Revision 4

OP-AA-201-009, Control of Transient Combustible Material, Revision 20

OP-AA-201-011-1001, Fire Marshal Certification Process, Revision 4

OP-NM-102-106, Operator Response Time Program at NMP, Revisions 9 and 10

OP-NM-201-007, FIRE PROTECTION SYSTEM IMPAIRMENT CONTROL, Revision 0

OP-NM-201-105, Commentary Measures for Inoperable Fire Protection Systems and

Components, Revision 4

S-EPM-GEN-551, 600 VAC, 480 VAC, and 125 VDC ITE Breaker and Breaker Load Test,

Revision 7

S-EPM-GEN-813, Annual Inspection of Emergency Battery Light Units, Revision 4

TQ-AA-173, Emergency Services Training Programs, Revision 3

Completed Tests and Surveillances

C93522067, Remote Shutdown Emergency Condenser Level Control Loop Calibration,

completed on 03/08/18

Halon 1301 Acceptance Test - NMP 2, dated 07/11/1986

N2-EPM-GEN-20Y712, Motor Control Center Bus Work, completed 04/05/14

N2-EPM-GEN-R@576, Remote Shutdown Panel 2CES*PNL405 Switch Checks for

SW16-2RSSN95, SW10-2RSSN89, completed 05/07/18

N2-EPM-GEN-R@576, Remote Shutdown Panel 2CES*PNL405 Switches 2, 3, 4, 5, 11, &14,

completed 05/14/18

N2-EPM-RSS-578, 2CES*PNL415 and 2CES*PNL416 Switch Checks, completed 05/03/18

N2-FSP-FPP-R001, Fire Rated Assemblies (Penetrations) Visual Inspection Test, completed

03/24/2014, 04/04/2016, 05/01/2018

N2-FSP-FPW-R001, Electric / Diesel Fire Pump Functional Test, completed 11/17/2017

N2-ISP-FPM-A104, Functional Test of the Fire Detection Zones for 2FPM-PNL104, completed

07/26/18

N2-MPM-FPW-A854, Diesel Fire Pump Engine Inspection 2FPW-ENG1 (5 Year and Annual),

completed 07/23/2013

N2-OSP-FOF-M001, Engine Driven Fire Pump Operability & Storage Tank Level, completed

8/17/2018

N2-OSP-RSS-R001, RCIC Remote Shutdown System Test, completed 05/12/18

N2-OSP-RSS-R002, RHS Shutdown and Suppression Pool Cooling Mode Remote Shutdown

System Test, completed 05/04/18

N2-OSP-RSS-R003, Service Water Remote Shutdown Operability Test, completed 09/18/17

N2-OSP-RSS-R005, RHS Shutdown Cooling Mode MOV Isolation Remote Shutdown System

Test, completed 05/06/18

N2-OSP-RSS-R006, Nitrogen Supply to ADS Remote Shutdown System Test, completed

05/03/18

N2-PM-M007, Motor-Driven Fire Pump Operability Test, completed 07/27/2018

S-PM-004, Operation Equipment Inventories and Checklists, Completed on 6/14/18

S-PM-004, Operation Equipment Inventories and Checklists, Completed on 8/24/18

Miscellaneous Documents

List of Fire Brigade Members qualification Training, dated 9/13/18

MI-2AI-185, Foxboro 2AI-P2V Series Platinum Resistance to Voltage Converter Styles B and C,

issued August 1980

Nine Mile Point Nuclear Station Unit 2, Individual Plant Examination for External Events

(IPEEE), June 1995

NMP Operations Equipment Inventories and Checklists:

Quarterly Inspection/Inventory of Fire Brigade Turnout Gear, 2018

Quarterly Inspection/Inventory of Fire Brigade Turnout Gear, 2017

Quarterly Inspection/Inventory of Fire Brigade Turnout Gear, 2016

Annual Inventory, Fire Cabinet: U2, 2017

NMP Unit 1 Fire Impairment Log, dated 08/22/2018

NMP Unit 1 Fire Protection Program Health Report, Period 2018

NMP Unit 1 and Unit 2 Fire Protection System Health Report, dated 06/27/2018

NMP Unit 2 Fire Protection Program Health Report, dated 2018P1

NMP Unit 2 South Auxiliary Bay, Electrical Room, Elevation 20 Halon System Piping and

Nozzle Pictures, dated 2017

NMP Transient Combustible Permit Log, dated 08/22/2018

NMP Transient Combustible Permits; Permit ID 469, 470, 472,473 and 475

NMP Unit 2 Training Lesson Plan 2100-PLTSOJ004, Perform RCIC Reactor Operator Actions,

Revision 0

NMP Unit 2 Training Lesson Plan 2100-PLTSOPJ003, Unit 2, Perform Lower Control Building

Actions, Revision 0

NMP Unit 2 Training Lesson Plan 2101-SOP78C01, N2-SOP-78, Unit 2, Control Room

Evacuation, Revision 0

NRC Information Notice 2014-10, Potential Circuit Failure Induced Secondary Fires or

Equipment Damage, issued 09/16/14

NRC Information Notice 2017-06, Battery and Battery Charger Short-Circuit Current

Contributions to a Fault on the Direct Current Distribution System, issued 09/26/17

PI-AA-126-1001, NMP-2018 Fire Protection Self-Assessment, completed 07/10/18

SAS-TR-95-001, NMP-2 IPEEE, dated 06/1995