Text

Triennial Fire Protection Inspection Report 05000237/2017007; 05000249/2017007
	ML17089A309
Person / Time
Site:	Dresden
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

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

IR 05000237/2017007