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| issue date = 03/30/2017
| issue date = 03/30/2017
| title = Triennial Fire Protection Inspection Report 05000237/2017007; 05000249/2017007
| title = Triennial Fire Protection Inspection Report 05000237/2017007; 05000249/2017007
| author name = Daley R C
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS/EB3
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000237, 05000249, 07200037
| docket = 05000237, 05000249, 07200037
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:March 30, 2017
{{#Wiki_filter:UNITED STATES rch 30, 2017


==SUBJECT:==
==SUBJECT:==
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000237/2017007; 05000249/2017007
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000237/2017007; 05000249/2017007


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
On March 2, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a Triennial Fire Protection Inspection at your Dresden Nuclear Power Station, Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on March 2, 2017, with Mr. F. Gogliotti, and on February 17, 2017, with Mr. P. Karaba, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and tions and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The NRC inspectors documented two findings of very-low safety significance (Green) in this report. The findings were determined to involve a violations of NRC requirements. However, because of their very-low safety significance, and because the issues were entered into your Corrective Action Program, the NRC is treating the issues as Non-Cited Violation in accordance with Section 2.3.2 of the NRC Enforcement Policy. If you contest the violations or significance of these Non-Cited Violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC resident inspector at the Dresden Nuclear Power Station. 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 at the NRC Public Document Room in accordance with 10 CFR  
On March 2, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a Triennial Fire Protection Inspection at your Dresden Nuclear Power Station, Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on March 2, 2017, with Mr. F. Gogliotti, and on February 17, 2017, with Mr. P. Karaba, and other members of your staff.
 
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
 
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
 
The NRC inspectors documented two findings of very-low safety significance (Green) in this report. The findings were determined to involve a violations of NRC requirements. However, because of their very-low safety significance, and because the issues were entered into your Corrective Action Program, the NRC is treating the issues as Non-Cited Violation in accordance with Section 2.3.2 of the NRC Enforcement Policy.
 
If you contest the violations or significance of these Non-Cited Violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC resident inspector at the Dresden Nuclear Power Station. 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 at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely,
Sincerely,
/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50237, 50249; 72037 License Nos. DPR19; DPR25 Enclosure: IR 05000237/2017007; 05000249/2017007 cc: Distribution via LISTSERV
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-237, 50-249; 72-037 License Nos. DPR-19; DPR-25 Enclosure:
IR 05000237/2017007; 05000249/2017007 cc: Distribution via LISTSERV


=SUMMARY=
=SUMMARY=
Line 41: Line 51:
............................................................................ 4
............................................................................ 4


===.1 Protection of Safe Shutdown Capabilities ................................................ 5 .2 Passive Fire Protection ............................................................................ 5 .3 Active Fire Protection .............................................................................. 6 .4 Protection from Damage from Fire Suppression Activities ....................... 8 .5 Alternative Shutdown Capability .............................................................. 8 .6 Circuit Analyses ....................................................................................... 8 .7 Communications ...................................................................................... 9 .8 Emergency Lighting ................................................................................. 9 .9 Cold Shutdown Repairs ..........................................................................10 .10 Compensatory Measures .......................................................................12 .11 Review and Documentation of Fire Protection Program Changes ..........12 .12 Control of Transient Combustibles and Ignition Sources ........................13 .13 B.5.b Inspection Activities===
===.1 Protection of Safe Shutdown Capabilities ................................................ 5===
 
===.2 Passive Fire Protection............................................................................ 5===
 
===.3 Active Fire Protection .............................................................................. 6===
 
===.4 Protection from Damage from Fire Suppression Activities ....................... 8===
 
===.5 Alternative Shutdown Capability .............................................................. 8===
 
===.6 Circuit Analyses....................................................................................... 8===
 
===.7 Communications...................................................................................... 9===
 
===.8 Emergency Lighting ................................................................................. 9===
 
===.9 Cold Shutdown Repairs ..........................................................................10===
 
===.10 Compensatory Measures .......................................................................12===
 
===.11 Review and Documentation of Fire Protection Program Changes ..........12===
 
===.12 Control of Transient Combustibles and Ignition Sources ........................13===
 
===.13 B.5.b Inspection Activities===


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
Line 49: Line 83:
{{IP sample|IP=IP 71152}}
{{IP sample|IP=IP 71152}}
.........................................14
.........................................14
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Management Meetings ..................................................................................14 ==
==4OA6 Management Meetings ..................................................................................14==
.1 Exit Meeting Summary ...........................................................................14  
 
===.1 Exit Meeting Summary ...........................................................................14===


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
Licensee  
 
: [[contact::P. Karaba]], Site Vice President  
Licensee
: [[contact::J. Washko]], Station Plant Manager  
: [[contact::P. Karaba]], Site Vice President
: [[contact::M. Budelier]], Senior Engineering Manager  
: [[contact::J. Washko]], Station Plant Manager
: [[contact::T. Dean]], Training Director  
: [[contact::M. Budelier]], Senior Engineering Manager
: [[contact::H. Datil]], Engineer  
: [[contact::T. Dean]], Training Director
: [[contact::B. Franzen]], Regulatory Assurance Manager  
: [[contact::H. Datil]], Engineer
: [[contact::F. Gogliotti]], Engineering Director  
: [[contact::B. Franzen]], Regulatory Assurance Manager
: [[contact::P. Hansett]], Work Control Director  
: [[contact::F. Gogliotti]], Engineering Director
: [[contact::M. Kerchenfaut]], Fire Marshal  
: [[contact::P. Hansett]], Work Control Director
: [[contact::N. Kopczynski]], Engineer  
: [[contact::M. Kerchenfaut]], Fire Marshal
: [[contact::M. Martin]], Acting Maintenance Director  
: [[contact::N. Kopczynski]], Engineer
: [[contact::G. Morrow]], Operations Director
: [[contact::M. Martin]], Acting Maintenance Director
: [[contact::A. Rehn]], Regulatory Engineer  
: [[contact::G. Morrow]], Operations Director
: [[contact::B. Sampson]], Organizational Effectiveness Manager  
: [[contact::P. OBrien]], Senior Site Assessor
: [[contact::M. Taylor]], Senior Staff Engineer  
: [[contact::A. Rehn]], Regulatory Engineer
: [[contact::D. Walker]], Regulatory Assurance NRC Coordinator  
: [[contact::B. Sampson]], Organizational Effectiveness Manager
: [[contact::D. Wolverton]], Engineering Manager  
: [[contact::M. Taylor]], Senior Staff Engineer
: [[contact::U.S. Nuclear Regulatory Commission G. Roach]], Senior Resident Inspector  
: [[contact::D. Walker]], Regulatory Assurance - NRC Coordinator
: [[contact::R. Elliot]], Resident Inspector  
: [[contact::D. Wolverton]], Engineering Manager
U.S. Nuclear Regulatory Commission
: [[contact::G. Roach]], Senior Resident Inspector
: [[contact::R. Elliot]], Resident Inspector
 
==LIST OF ITEMS==
==LIST OF ITEMS==
OPENED, CLOSED AND DISCUSSED  
 
===OPENED, CLOSED AND DISCUSSED===
 
===Opened and Closed===
===Opened and Closed===
: 05000237/2017007-01;  
: 05000237/2017007-01;         NCV     Inadequate Pre-Fire Plans (Section 1R05.3.b)
: 05000249/2017007-01 NCV Inadequate Pre-Fire Plans (Section 1R05.3.b)  
: 05000249/2017007-01
: 05000237/2017007-02;
: 05000237/2017007-02;          NCV     Inadequate Procedure Steps to Ensure Proper Valve
: 05000249/2017007-02 NCV Inadequate Procedure Steps to Ensure Proper Valve Rotation for Cold Shutdown Repair (Section 1R05.9.b)  
: 05000249/2017007-02                  Rotation for Cold Shutdown Repair (Section 1R05.9.b)
 
===Discussed===
===Discussed===
None  
 
None


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
The following is a list of documents reviewed during the inspection.
 
: Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
: Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
: CALCULATIONS Number Description or Title Revision DR05 Unit 3 HPCI Pump Room Hydraulic Analysis 0 DR18 and DR19 Unit 2 Turbine Building Mezzanine Cable Concentration Hydraulic Analysis 0 DRE98-0030 Determination of Setpoint of CST Low-Low Level Switches to Prevent Potential Air Entrainment from Vortexing During HPCI Operation 0/0A
: EC 386234 Multiple Spurious Operation Scenario 2d Evaluation 0
: EC 406498 HPCI Pump Suction Temperature up to 165F 0
: CORRECTIVE ACTION PROGRAM DOCUMENTS ISSUED DURING INSPECTION Number Description or Title Date
: 03964026 Rope Passing Through Torus CW Hatch Fire Stop 01/18/2017
: 03964029 N2 Bottle Dolly not Secured 01/18/2017
: 03964552 Procedure Revision Needed 01/19/2017
: 03964952
: TSG-3 Walkdown Results 01/20/2017
: 03964955 B.5.b Observations 01/20/2017
: 03965024 Door in Unit 1 Crib House Difficult to Latch 01/20/2017
: 03968397 2/3 DFP Battery Space Heater 01/30/2017
: 03968698 Fire Protection Report is not Updated 01/31/2017
: 03969002 Evaluate 125Vdc Reactor Building Distribution Panel #3 Door 02/01/2017
: 03969091 Air Pack Storage 02/01/2017
: 03969228 Unit 2 HPCI Torus Suction MOV Light Covers Switched 02/01/2017
: 03969306 Errors Found in DSSP 0100-A1/B1 02/01/2017
: 03969535 Typo in DSSP 0200-T8 02/02/2017
: 03969715 Document Request 02/02/2017
: 03969727 Bus 40 Breaker C/S Labels do not Match Electrical Drawings 02/02/2017
: 03969967 DSSP Potential Enhancement 02/02/2017
: 03972679 Mislabeled Cold Safe Shutdown Equipment 02/10/2017
: 03972722 Clarification to
: OP-DR-102-106 02/10/2017
: 03973640 Current SCRAM Outlet Valve Position 02/13/2017
: 03974089 Combustible Material Near Tanks 02/14/2017
: 03974104 Breaker FME Issue 02/13/2017
: 03974158 Prefire Plan U3 H2 Area 02/14/2017
: 03974160 Unit 2 H2 Area Prefire Plan 02/14/2017
: 03974372 DSSP 0200-T8 Temporary Power Concerns 02/15/2017
: 03974470 Test Boiler
: PIT 02/14/2017
: 03974477 N2 Bottles in 2/3 EDG Room 02/15/2017
: 03974597 Evaluate Permanently Installing Gauge 02/15/2017
: 03975283 NRC Observation of DSSP 0100-B1 Action 02/17/2017
: 03975416 Communication During Post Fire Safe Shutdown 02/17/2017 
: CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title Date
: 02474202 U3 HPCI Pre-Action Valve Leaking After Actuation 03/25/2015
: 02478665 DSSP Action not Permissible for Appendix R 04/02/2015
: 02546029 Engineering Review Needed for Time Critical Action 4 08/25/2015
: 02547428 NOD ID A 1-Hour Fire Wrap Not Installed Correctly 08/27/2015
: 02587334 Fire Marshal Tour
: Extension Cord Routing Issues 11/14/2015
: 02648365 DSSP 0100-B1 Attachment C Revision 37 Correction 03/31/2016
: 02678245 Improving Margin in DSSP Response Times 06/06/2016
: 02730153 FP FASA: Elu 249-3 to be Redirected to For SSD
: 10/19/2016
: 02730409 Fire Door #73 Not Latching 10/20/2016
: 02732047 Contaminated Area Boundary Rope Routed thru 517 Fire Door 10/25/2016
: 03959918 DSSP 0100-1B Requires Revision 01/05/2017
: DRAWINGS Number Description or Title Revision 12E-2050 Cable Routing and Fire Stops Turbine and Reactor Building Ground Floor
: AS 12E-2351B Schematic Diagram
: Diesel Generator 2/3 Auxiliaries and Start Relays
: AT 12E-2420A Schematic Diagram Recirculation Pump 2A Motor Operated Valves
: AC 12E-2420B Schematic Diagram Recirculation Pump 2B Motor Operated Valves
: AA 12E-2441 Schematic Diagram LPCI/Containment Cooling System Motor Operated Valves
: 2-1501-21B,
: 2-1501-22B
: AI 12E-2508A Schematic Control Diagram Reactor Shut Down Cooling System Pumps Control Circuits N 12E-2517 Schematic Control Diagram Reactor Shut Down Cooling System Pumps Control Circuits M 12E-2594 Schematic Diagram Fire Protection Equipment Part 2 E 12E-2662D Schematic Diagram 480V Primary Containment Isolation System Motor Operated Valves 1001-1A & 1001-1B
: AG 12E-2676B Schematic Diagram
: 480V Turbine Building
: MCC 28-3
: AF 12E-2816B Wiring Diagram Reactor Low Penetration Power Penetration X-200B Z 12E-3507B Schematic Diagram
: Isolation Condenser Reactor Inlet valves R 12E-6802 Location Plan of Intra-Plant Radio System Antennas Flr. El. 517-06 Sheet 1 J 12E-6802M Block Diagram Intra-Plant Primary Radio System Arrangement H B-140 - V B-147 - AA B-149 Turbine Building Framing Plan El. 549-00 Control Room Area Unit 2 W B-574 Turbine --West Area DM B-575 - R B-578 - G M-26 Diagram of Nuclear Boiler & Reactor Recirculating Piping G M-35 Diagram of Demineralized Water System Piping EP
: PRE-FIRE PLANS Number Description or Title Revision 104 U2RB-4 Unit 2 HPCI Pump Room, Elevation 476
: 4 145 U2TB-48 Unit 2 Reactor Feedwater Pump Vent H2 Seal Area, Elevation 538 4 151 U2TB-53 Unit 2 Battery Room, Elevation 549 3 166 U3TB-77 Unit 3 Reactor Feedwater Pump Switchgear H2 Seal, Elevation 538 2 184 2/3 EDG Unit 2/3 Swing Diesel Generator Room 5
: PROCEDURES Number Description or Title Revision
: CC-AA-112 Temporary Configuration Changes 24
: DOS 0010-36 Operations Support Equipment Inspection 38
: OP-AA-201-006 Control of Temporary Heat Generating Equipment 8
: OP-AA-201-008 Pre-Fire Plan Manual 3
: OP-DR-106-101 Extensive Damage Mitigation (CM-1) 5
: TSG-3 Operational Contingency Action Guidelines 18 DSSP 0100-CR Hot Shutdown Procedure
: Control Room Evacuation 49 DSSP 0100-A Hot Shutdown Procedure
: Path A 28 DSSP 0100-D Hot Shutdown Procedure
: Path D 26
: DOP 1300-08 Filling Isolation Condenser Makeup Pump Oil Day Tanks with Diesel Fuel Oil Transfer System Unavailable 09
: DES 8300-13 Unit 1 And 2/3 Diesel Fire Pump & Security Diesel Starting Batteries Surveillance & Maintenance Procedure 19
: DOS 0010-14 Safe Shutdown Equipment Inspection 40 DSSP 0100-A Hot Shutdown Procedure-Part A 28 DSSP 0100-CR Hot Shutdown Procedure- Control Room Evacuation 49 DSSP 0200-T6 Temporary 4KV Feed Connections- SDC, LPCI, RBCCW, CCSW 08 DSSP 0200-T8 Temporary 480V Feed Connections- SDC & Recir. MOVs 10
: WORK ORDERS Number Description or Title Date
: 1666168 18 Month Fire Door / Oil Spill Barrier Surveillance 02/27/2016
: 1698050 D1 Annual Diesel Fire Pump Flow Capacity Test 09/10/2014
: 1901632 D1 Annual Diesel Fire Pump Flow Capacity Test 10/05/2016
==LIST OF ACRONYMS==
: [[USED]] [[]]
: [[AR]] [[Action Request]]
: [[CAP]] [[Corrective Action Program]]
: [[IMC]] [[Inspection Manual Chapter]]
: [[MCC]] [[Motor Control Center]]
: [[MOV]] [[Motor Operated Valves]]
: [[NCV]] [[Non-Cited Violation]]
: [[NRC]] [[]]
: [[U.S.]] [[Nuclear Regulatory Commission]]
: [[RECIRC]] [[Recirculation]]
: [[SDC]] [[Shutdown Cooling]]
: [[SSD]] [[Safe Shutdown]]
}}
}}

Latest revision as of 07:55, 3 November 2019

Triennial Fire Protection Inspection Report 05000237/2017007; 05000249/2017007
ML17089A309
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 03/30/2017
From: Robert Daley
Engineering Branch 3
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2017007
Download: ML17089A309 (23)
v • d • e


Text

UNITED STATES rch 30, 2017

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000237/2017007; 05000249/2017007

Dear Mr. Hanson:

On March 2, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a Triennial Fire Protection Inspection at your Dresden Nuclear Power Station, Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on March 2, 2017, with Mr. F. Gogliotti, and on February 17, 2017, with Mr. P. Karaba, and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

The NRC inspectors documented two findings of very-low safety significance (Green) in this report. The findings were determined to involve a violations of NRC requirements. However, because of their very-low safety significance, and because the issues were entered into your Corrective Action Program, the NRC is treating the issues as Non-Cited Violation in accordance with Section 2.3.2 of the NRC Enforcement Policy.

If you contest the violations or significance of these Non-Cited Violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC resident inspector at the Dresden Nuclear Power Station. 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 at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-237, 50-249;72-037 License Nos. DPR-19; DPR-25 Enclosure:

IR 05000237/2017007; 05000249/2017007 cc: Distribution via LISTSERV

SUMMARY

................................................................................................................................ 2

REPORT DETAILS

REACTOR SAFETY

.................................................................................................... 4

1R05 Fire Protection

Main article: IP 71111.05T

............................................................................ 4

.1 Protection of Safe Shutdown Capabilities ................................................ 5

.2 Passive Fire Protection............................................................................ 5

.3 Active Fire Protection .............................................................................. 6

.4 Protection from Damage from Fire Suppression Activities ....................... 8

.5 Alternative Shutdown Capability .............................................................. 8

.6 Circuit Analyses....................................................................................... 8

.7 Communications...................................................................................... 9

.8 Emergency Lighting ................................................................................. 9

.9 Cold Shutdown Repairs ..........................................................................10

.10 Compensatory Measures .......................................................................12

.11 Review and Documentation of Fire Protection Program Changes ..........12

.12 Control of Transient Combustibles and Ignition Sources ........................13

.13 B.5.b Inspection Activities

OTHER ACTIVITIES

..................................................................................................14

4OA2 Identification and Resolution of Problems

Main article: IP 71152

.........................................14

4OA6 Management Meetings ..................................................................................14

.1 Exit Meeting Summary ...........................................................................14

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

P. Karaba, Site Vice President
J. Washko, Station Plant Manager
M. Budelier, Senior Engineering Manager
T. Dean, Training Director
H. Datil, Engineer
B. Franzen, Regulatory Assurance Manager
F. Gogliotti, Engineering Director
P. Hansett, Work Control Director
M. Kerchenfaut, Fire Marshal
N. Kopczynski, Engineer
M. Martin, Acting Maintenance Director
G. Morrow, Operations Director
P. OBrien, Senior Site Assessor
A. Rehn, Regulatory Engineer
B. Sampson, Organizational Effectiveness Manager
M. Taylor, Senior Staff Engineer
D. Walker, Regulatory Assurance - NRC Coordinator
D. Wolverton, Engineering Manager

U.S. Nuclear Regulatory Commission

G. Roach, Senior Resident Inspector
R. Elliot, Resident Inspector

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened and Closed

05000237/2017007-01; NCV Inadequate Pre-Fire Plans (Section 1R05.3.b)
05000249/2017007-01
05000237/2017007-02; NCV Inadequate Procedure Steps to Ensure Proper Valve
05000249/2017007-02 Rotation for Cold Shutdown Repair (Section 1R05.9.b)

Discussed

None

LIST OF DOCUMENTS REVIEWED

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