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{{Adams | {{Adams | ||
| number = | | number = ML18256A251 | ||
| issue date = | | issue date = 09/11/2018 | ||
| title = | | title = NRC Triennial Fire Protection Inspection (Team) Report 05000348/2018011 and 05000364/2018011 | ||
| author name = Shaeffer S | | author name = Shaeffer S | ||
| author affiliation = NRC/ | | author affiliation = NRC/RGN-II/DRS/EB2 | ||
| addressee name = Madison D | | addressee name = Madison D | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = IR 2018011 | | document report number = IR 2018011 | ||
| document type = Inspection | | document type = Inspection Report, Letter | ||
| page count = | | page count = 15 | ||
}} | }} | ||
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=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 11, 2018 | ||
==SUBJECT:== | |||
JOSEPH M. FARLEY NUCLEAR PLANT - NRC TRIENNIAL FIRE PROTECTION INSPECTION (TEAM) REPORT NOS. 05000348/2018011 AND 05000364/2018011 | |||
SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT - | |||
==Dear Mr. Madison:== | ==Dear Mr. Madison:== | ||
On August 2, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Farley Nuclear Plant, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this NFPA 805 Triennial Fire Protection Inspection (TFPI) are documented in the enclosed report. | |||
NRC inspectors documented one finding of very low safety significance (Green) in this report. | |||
This finding involved a violation of NRC requirements. The NRC is treating the violation as a non-cited violation (NCV), consistent with Section 2.3.2.a of the NRCs Enforcement Policy. | |||
If you contest this violation or significance of this NCV, 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 II; the Director, Office of Enforcement; and the NRC Resident Inspector at the Farley Nuclear Plant. 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/ | |||
Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos.: 50-348, 50-364 License Nos.: NPF-2, NPF-8 | |||
===Enclosure:=== | |||
Inspection Report 05000348/2018011 and 05000364/2018011 | |||
==Inspection Report== | |||
Docket Number(s): 50-348, 50-364 License Number(s): NPF-2, NPF-8 Report Number(s): 05000348/2018011 and 05000364/2018011 Enterprise Identifier: I-2018-011-0022 Licensee: Southern Nuclear Operating Company, Inc. (SNC) | |||
Facility: Joseph M. Farley Nuclear Plant, Units 1 and 2 Location: Ashford, AL 36312 Inspection Dates: Week 1 of onsite inspection: July 16 - 20, 2018 Week 2 of onsite inspection: July 30 - August 2, 2018 Inspectors: J. Dymek, Reactor Inspector L. Jones, Senior Reactor Inspector W. Monk, Reactor Inspector (Team Leader) | |||
N. Staples, Senior Reactor Inspector Accompanying Personnel: T. Sippel, Fuel Facility Inspector (Training, Week 1 Only) | |||
Approved By: Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety (DRS) | |||
1 Enclosure | |||
=SUMMARY= | |||
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Southern Nuclear | |||
Companys performance by conducting an announced team TFPI at the Farley Nuclear Plant, | |||
Units 1 and 2, in accordance with the NRC Reactor Oversight Process. The Reactor Oversight Process (ROP) 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. NRC-identified findings and violations are summarized in the table below. | |||
List of Findings and Violations Failure to ensure fire barrier penetrations (including fire dampers) in fire zones protecting safety-related areas shall be functional in accordance with NFPA 805 Section 3.11.3, Fire Barrier Penetrations Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green H.8, Procedure 71111.05XT Systems NCV 05000348-364/2018011-01 Adherence - 02.02b Closed The NRC identified a Green finding and associated non-cited violation (NCV) of the Farleys Renewed Operating License Condition 2.C.(4) - Fire Protection for U1 and 2.C.(6) - Fire Protection for U2. This finding was identified for failure to maintain all provisions of the approved FPP, as described in NFPA 805, 2001 Edition to ensure that all fire barrier penetrations (including fire dampers) in fire zones protecting safety-related areas shall be functional. The functional failure of the two fire dampers in the A and B SWIS Battery Rooms was a performance deficiency and determined to be more-than-minor because it affected the Reactor Safety Mitigating Systems cornerstone attribute of protection against external factors, a fire, and it affected the fire protection Defense in Depth (DID) strategies involving the confinement of fires and to protect systems important to safety. Additionally, if left uncorrected, the issue could potentially lead to a more significant safety concern during fire events. | |||
=INSPECTION SCOPES= | |||
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) 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 team reviewed the selected procedures and records, observed activities, and interviewed plant personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and industry standards. | |||
==REACTOR SAFETY== | |||
===71111.05XT - NPFA 805 Fire Protection (Triennial) | |||
The team evaluated applicable fire protection licensing commitments from July 16, 2018 to August 2, 2018 by review of the following: | |||
Fire Protection Inspection Requirements === | |||
{{IP sample|IP=IP 71111.05|count=3}} | |||
The team evaluated fire protection program implementation in the following selected areas: | |||
1) FA 1-041, Train A SWGR and Load Center Rooms (Performance Based Area)2) FA 076, SWIS 5KV SWGR A and East Stairs (Performance Based Area)3) FA 1-018, Aux Building DC SWGR (Performance Based Area) | |||
===B.5.b Inspection Activities (1 Sample)=== | |||
The team evaluated the feasibility of the following B.5.b Mitigating Strategies: | |||
1) The team reviewed the strategy for manual operation of the Turbine Driven AFW (TDAFW) Pump strategy | |||
==OTHER ACTIVITIES - BASELINE== | |||
INSPECTION RESULTS Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green Finding H.8, Procedure 71111.05XT-Systems 50-348, 50-364/2018011-01 Adherence 02.02b Closed The NRC identified a Green finding and associated non-cited violation (NCV) of the licensees Fire Protection Program (FPP) and NPFA 805, Section 3.11.3, Fire Barrier Penetrations, for the licensees failure to ensure functional fire dampers, 1-188-332-01 and 1-188-332-02 in the A and B SWIS Battery Rooms. | |||
=====Description:===== | |||
Fire Dampers 1-188-332-01 and 1-188-332-02 in the A and B SWIS Battery Rooms were improperly installed per their design drawing U164049 and the B train Battery Room fire damper failed to shut when conducting a surveillance drop test on 7/20/2018. Specially, the angle clip bracket was not installed with the 90 degree leg pointed away from the damper skirt, which caused the damper skirt to not drop and seal off the barrier penetrations between the battery rooms (Deterministic fire areas) and SWIS Switchgear Rooms (Performance-Based fire areas). | |||
Additionally, according to drawing U164049, DAF-P-5990 Fire Damper with Optional SRD (Smoke Release Device), Note 1 states: Although construction is per these drawings, the damper will not be UL Label if equipped with the SRD. In the case of Fire Dampers 1-188-332-01 and 1-188-332-02, all four 1 1/2 hour rated curtain-type fire dampers were equipped with SRDs and fusible links, not electro-thermal links (ETLs). SRDs are not UL listed/labeled, but ETLs are UL listed/labeled. The referenced electrical elementary design drawings reflected use of ETLs, not SRDs. | |||
The improper fire damper installations and damper functional failure did not meet the licensees Fire Protection Program (FPP) nor NPFA 805 Section 3.11.3, Fire Barrier Penetrations, which states passive fire protection devices such as dampers shall conform with the following NFPA standard, NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating Systems. NFPA 90A, Code of Record 1973 states in section 905, Construction of Fire Dampers, Approved fire dampers shall have the following performance characteristics: | |||
a) They shall be arranged to close automatically in event of abnormal high temperature. | |||
b) They shall provide the maximum practical barrier to passage of air when in the closed position. | |||
Corrective Action(s): In response to the inspection discovery, the licensee promptly initiated condition reports to resolve the equipment deficiencies and conducted an extent of condition review throughout the plant. | |||
Corrective Action Reference(s): This issue is being tracked in the licensees corrective action program (CAP) by condition reports: | |||
* CR 10516723, NRC Inspector Identified Damper 1-188-332-02 Was Not Installed Correctly, 7/18/2018 | |||
* CR 10517136, Incorrect Fire Damper Installation - EOC, 7/19/2018 | |||
* CR 10517257, Damper Inspection Request for EOC, 7/20/2018 | |||
* CR 10517472, SWIS Battery Room B Fire Damper Failed Drop Test, 7/20/2018 | |||
* CR 10520516, 2018 NRC TFPI - Non-UL Listed Fire Damper, 7/30/2018 | |||
=====Performance Assessment:===== | |||
Performance Deficiency: The licensees failure to ensure the fire dampers were functional, as required by the approved Fire Protection Program and NPFA 805 was determined to be a performance deficiency (PD). | |||
Screening: This performance deficiency was determined to be more-than-minor because it affected the Reactor Safety Mitigating Systems cornerstone attribute of protection against external factors, a fire, and it affected the fire protection DID strategies involving the confinement of fires and to protect systems important to safety. Specifically, the failure to ensure functional fire dampers could affect the fire protection DID strategy involving the confinement of fires because it could allow smoke and heat to migrate beyond the room and affect adjacent fire areas (FAs). Additionally, if left uncorrected, the issue could potentially lead to a more significant fire propagation safety concern. | |||
Significance: The team assessed the finding using NRC Inspection Manual Chapter 0609, Significance Determination Process (SDP), Attachment 4, Initial Characterization of Findings, and determined the Mitigating Systems cornerstone was impacted and that a IMC 0609, Appendix F, Fire Protection SDP review was required as the finding involved the ability to confine a fire. The team further assessed the finding using NRC Inspection Manual Chapter 0609, Appendix F, Attachment 1, Fire Protection SDP Worksheet, and determined the finding to be of very low safety significance (Green) based upon Step 1.4.4, Question E, based upon if a fire were to spread from one fire area to another due to the degraded fire barriers, no additional targets would be damaged in the fire areas that could impact the credited safe shutdown strategy. | |||
Cross-Cutting Aspect: The team assessed the issue for cross-cutting aspects using IMC 0310, Aspects Within Cross Cutting Areas, and concluded this deficiency was indicative of current licensee performance because the fire dampers were last inspected in September 2017. Per IMC 0310, a cross cutting aspect of H.8, Procedure Adherence was assigned to this finding because individuals performing the fire damper surveillances did not fully follow the surveillances procedures and work instructions. Specially, the fire damper surveillance inspection procedure states under the Acceptance Criteria section, No damage or missing hardware exists on the damper as determined by a visual inspection and the wires and links are properly attached. | |||
=====Enforcement:===== | |||
NPFA 805 Section 3.11.3, Fire Barrier Penetrations, required passive fire protection devices such as dampers shall conform with the following NFPA standard, NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating Systems. NFPA 90A, Code of Record 1973, Section 905, Construction of Fire Dampers, required that approved fire dampers shall have the following performance characteristics: | |||
a) They shall be arranged to close automatically in event of abnormal high temperature. | |||
b) They shall provide the maximum practical barrier to passage of air when in the closed position. | |||
Contrary to the above, since the plants commercial operational date until July 2018, the licensee failed to ensure that fire dampers 1-188-332-01 and 1-888-332-02 were functional and that they met the requirements of NFPA 90A, to functionally shut during the conditions of a fire. | |||
Disposition: This violation is being treated as an NCV consistent with Section 2.3.2a of the NRC Enforcement Policy. | |||
==EXIT MEETINGS AND DEBRIEFS== | |||
The team verified no proprietary nor safeguards information was retained or documented in this report. Additionally, the team confirmed that proprietary and safeguards information was controlled to protect from public disclosure. On August 2, 2018, the lead inspector and team presented the NFPA 805 TFPI results to the Site Vice President, Mr. Dennis Madison, and other members of the Farley Nuclear Plant staff. | |||
THIRD PARTY REVIEWS The team did not perform any reviews of the Institute of Nuclear Power Operations (INPO)reports nor any other third party documents during the inspection period. | |||
KEY POINTS OF CONTACT Licensee Personnel Gene Surber, Licensing Supervisor Mandy Ludlam, Licensing Engineer Hilliard Cooper, Fire Protection Manager Meredith Smith, Fire Protection Program Engineer Kim Wilson, Fire Protection Engineer Robert Chandler, Site Fire Marshall NRC Personnel P. Niebaum, Senior Resident Inspector K. Miller, Resident Inspector S. Shaeffer, Chief, Engineering Branch 2, DRS, Region II LIST OF COMPONENTS REVIEWED Component ID Description Q1E21P0002B 1B Charging/HHSI Pump N1E21HIK122 Charging Flow Indication Q1B31V0053 U1 A/B PORV Q1E21LCV115B Excess Letdown Valve Q1N23HV3227B Train B MDAFW Pump Q1P17P001B Train B CCW Pump Q1N1PV3371B Main Steam Atmosphere Relief Valve Q1B31V0061 Pressurizer PORV Q2R16B0006 4.16KV Switchgear Bus 2D Q1E13PT0952 Unit 2 Containment Pressure Transmitter QSR42B0523B 125VDC SWIS Battery 2 N1B31LI0461 Pressurizer Level Channel 3 N1B31LI0459Z Pressurizer Level Indicator LI-459Z N1B21TI0410 RCS Cold Leg Temperature Indicator N1N11LI0477A Steam Generator 1A Wide Range Level Indicator LI-477A N1N11LI0497A Steam Generator 1C Wide Range Level Indicator LI-497A N1C55NI0031B Source Range Count Rate Indicator NI-31B | |||
=DOCUMENTS REVIEWED= | |||
Licensing Basis, Design Basis, & Regulatory | |||
DWG A-181805, NFPA 805 Fire Protection Program Design Basis Document, Rev. 1 | |||
Joseph M. Farley Nuclear Plant License Amendment Request to Adopt NFPA-805 Performance | |||
Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 | |||
Edition), 9/25/2012 | |||
Safety Evaluation Report, Joseph | |||
: [[contact::M. Farley Nuclear Plant]], Units 1 And 2 - Issuance Of | |||
Amendments Related To NFPA 805 Supplement (CAC Nos. MG0094, MG0095; EPID N | |||
: [[contact::O. | |||
L-2017-LLA-0261)]], 11/01/2017 | |||
Safety Evaluation Report, Joseph | |||
: [[contact::M. Farley Nuclear Plant]], Units 1 And 2 - Issuance Of | |||
Amendments Related To NFPA 805 Supplement (CAC Nos. MF7617 And MF7618), | |||
10/17/2016 | |||
Southern Nuclear Operating Company Alabama Power Company Docket No. 50-348 Joseph | |||
: [[contact::M. | |||
Farley Nuclear Plant]], Unit 1 Renewed Facility Operating License No. NPF-2 | |||
Southern Nuclear Operating Company Alabama Power Company Docket No. 50-364 Joseph | |||
: [[contact::M. | |||
Farley Nuclear Plant]], Unit 2 Renewed Facility Operating License No. NPF-8 | |||
Joseph M. Farley Nuclear Plant Response to Request for Additional Information Regarding | |||
License Amendment Request for Transition to 10 CFR 50.48(c) NFPA 805 Performance | |||
Based Standard for Fire Protection for Light Water Reactor Generating Plants, Attachment S - | |||
Modifications and Implementation Items | |||
Farley Nuclear Plant, UFSAR Chapter 9, Section 9.5.1, Fire Protection System, Rev. 26 | |||
Calculations | |||
ARC 4.3.1, Compliance Assessment by Scenario, 6/15/2018 | |||
F-RIE-FIREPRA-U00-017, NFPA 805 Transition Risk Results for Farley, 2/16/2018 | |||
NMP-ES-035-006-F06, NFPA 805 Change Evaluation - U1/U2 FLEX Communications & | |||
Gaitronics Upgrades, Version 2.0 | |||
Enclosure | |||
NMP-ES-035-006-F06, NFPA 805 Change Evaluation - Main Turbine (DEH) Controls Upgrade, | |||
Version 1.0 | |||
SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Rev. 2 | |||
SE-C051326701-008, Attachment - FRE for Unit 1 Fire Area 1-018, Auxiliary Building DC | |||
Switchgear Room, Rev. 0 | |||
SE-C051326701-010, Nuclear Safety Capability Assessment Fire Area Compliance | |||
Assessment, Rev. 4 | |||
SE-C051326701-011, Recovery Action Feasibility Evaluation, Rev. 0 | |||
SE-C051326701-012, NFPA 805 Defense in Depth (DID) Recovery Actions, Rev. 2 | |||
SM-C051326701-007, NFPA Code Conformance Review, Version 1.0 | |||
SM-C051326701-011, Fire Suppression Effects Analysis, Version 1.0 | |||
SM-1081426001-001, B.5.b Mitigation Strategy Flow Verification, Dated March 2012 | |||
TE-707175, Evaluation of Farley Triennial Fire Distribution System Flow Test, FNP-0-FSP-53, | |||
11/22/2013 | |||
Procedures | |||
FNP-0-AOP-29.0, Abnormal Operating Procedure - Plant Fire, Rev. 51.0 | |||
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 76-100, Version 1.0 | |||
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 51-75, Version 1.0 | |||
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 1-25, Version 1.0 | |||
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 26-50, Version 1.0 | |||
FNP-1-ECP-0.0, Emergency Contingency Procedure - Loss of All AC Power, Rev. 30 | |||
FNP-0-EIP-16.0, Emergency Equipment and Supplies, VERSION 72.0 | |||
FNP-0-EIP-16.0-F05, Checklist E Control Room Storage Locker, Version 1.0 | |||
FNP-0-EIP-16.0-F26, Fire Fighting Equipment (OPS) Checklist, Version 1.0 | |||
FNP-0-EIP-16.0-F40, Smoke Removal Equipment, Version 1.0 | |||
FNP-1-FPP-1.0, Unit 1 Auxiliary Building Pre-Fire Plan, Version 1.0 | |||
FNP-0-FPP-2.0, Protected Area Pre-Fire Plans, Version 1.0 | |||
FNP-0-FPP-3.0, Owner Controlled Area Pre-Fire Plan, Version 2.0 | |||
FNP-1-FPP-3.0, Unit 1 Containment Pre-Fire Plan, Version 1.0 | |||
FNP-0-FSP-201.1, No. 1 Diesel Driven Fire Pump Functionality Test, Version 21.0 | |||
FNP-0-FSP-201.3, Motor Driven Fire Pump Functionality Test, Version 12.0 | |||
FNP-0-FSP-203.2, #1 Diesel Driven Fire Pump Functional Test, Version 10.0 | |||
FNP-0-FSP-203.4, Motor Driven Fire Pump Functional Test (Pump Flow Test), Version 11.0 | |||
FNP-0-FSP-203.5, #1 Diesel Driven Fire Pump Functional Test (Pump Flow Test), | |||
Version 14.0 | |||
FNP-0-FSP-300.0, Fire Pump Diesel Starting Battery Monthly Inspection, Version 5.1 | |||
FNP-0-FSP-301, Fire Pump Diesel Starting Battery Quarterly Inspection, Version 8.0 | |||
FNP-0-SOP-0.4, Fire Protection Operability And LCO Requirements, Rev. 104 | |||
FNP-1-AOP-28.0, Control Room Inaccessibility, Version 18, Dated April 2018 | |||
NP-1-FSP-65.0A, Fire Dampers Functional Inspection Aux. Building - Diesel Building - Service | |||
Water Building Train A, Version 5.0 | |||
FNP-1-FSP-65.0B, Fire Dampers Functional Inspection Aux. Building - Diesel Building - | |||
Service Water Building Train B, Version 5.0 | |||
FNP-1-SOP-58.0, Auxiliary Building HVAC System, Version 80, Dated March 2018 | |||
FNP-1-SOP-62.0, Emergency Air System, Version 26, Dated April 2015 | |||
NMP-05-007-003, Standing Order - Fire Protection LCOs Peer Check Requirement, 7/11/2018 | |||
NMP-CH-002, Chemical Control Program, Version 12.2, 5/24/18 | |||
NMP-CH-002-003, Chemical Storage Areas, Version 9.0, 6/14/18 | |||
NMP-EP-402, Plant Farley Emergency Management Guideline (EMG), VERSION 14.1 | |||
NMP-EP-402, Manual Operation of TDAFW, Att. 7, Version 14.1 | |||
Enclosure | |||
NMP-EP-402, Temporary Instrumentation Installation, Att. 12, Version 14.1 | |||
NMP-EP-402, B.5.b Pump and Accessories, Att. 13, Version 14.1 | |||
NMP-ES-027-001, NFPA 805 Program, Version 9.0 | |||
NMP-ES-035-001, Fire Protection Program Implementation, Version 13.1 | |||
NMP-ES-035-003, Fleet Hot Work Instruction, Version 7.0 | |||
NMP-ES-035-007, Fleet Fire Watch Instruction, Version 4.1 | |||
NMP-ES-035-009, Quarterly Fire Safety Inspection, Version 4.0 | |||
NMP-ES-035-010, Fire Brigade, Version 5.0 | |||
NMP-ES-035-014, Fleet Transient Combustible Controls, Version 2.1 | |||
NMP-ES-035-GL01, Fire Protection Program Guideline, Version 3.0 | |||
NMP-OS-007-001, Conduct of Operations Standards and Expectations, Version 16.2 | |||
NMP-TR-425, Fire Drill Program, Version 8.0 | |||
NMP-TR-426, Fire Training Program, Version 5.1 | |||
Plant Modifications | |||
DCP SNC459687, NFPA 805: U1 Cable and Raceway Fire Protection, Version 8.0 | |||
DCP SNC834134, SWIS Security Enhancements Project - NFPA 805 Change Evaluation, | |||
Version 2.0 | |||
Miscellaneous Documents | |||
A-181017, J. M. Farley Nuclear Plant Unit 1 / 2 Functional System Description-Fire Protection | |||
System, Revision 43 | |||
American Warming and Ventilating, Inc., Mod. DAF-D-8403, U.L. Classified Type A Excel Fire | |||
Damper, Revision E | |||
Chemical Product Storage Permit, NMP-CH-002-03, Attachment 1, SWIS, 6/15/2015 | |||
Elsie Type A and Type B Fusible Link Vendor Data Sheet, 7/30/2018 | |||
EVAL-F-R45-03207, U1 R45-FO1 Emergency Lights, 4/8/2018 | |||
Farley Nuclear Plant Occurrence Report (OR) 1-98-017, Fire Damper Failed to Indicate Closed, | |||
1/22/1998 | |||
Information Notice No. 89-52: Potential Fire Damper Operational Problems, June 8, 1989 | |||
Information Notice No. 83-69: Improperly Installed Fire Dampers at Nuclear Power Plants, | |||
October 21, 1983 | |||
Maintenance Rule Expect Panel Meeting #18-06, 4/03/2018 | |||
Maintenance Rule Expect Panel Meeting #18-09, 6/22/2018 | |||
National Fire Protection Association (NFPA) 80, Fire Doors and Windows 1973 Code of Record | |||
NFPA 600, Standard for Industrial Fire Brigades, 2000 Edition | |||
NMP-ES-035-009-F01, Quarterly Fire Inspection Report Form, Q1 2018 | |||
NMP-ES-035-009-F01, Quarterly Fire Inspection Report Form, Q2 2018 | |||
RER SNC629964, RG 1.75 Marinite RER, Version 2.0 | |||
Request from Bechtel Eastern Power Company to American Warming and Ventilating Company | |||
Entitled Evaluation of Fire Damper Installation, (SS-1102-54), March 21, 1988 | |||
S-FP-PP-10100-07.1, Fire Training / Introduction to Fire Fighting, Rev. 7.1 | |||
TE 1009817, Take to the MREP: Tracking CR per NMP-GM-027-001, 4/17/2018 | |||
Work Orders | |||
WO SNC593970, FNP-1-FSP-307.0 - Zone 1A-32 - U1 A-Train Smoke Detector - Biennial | |||
Operability and Adjustment, 6/10/2016 | |||
WO SNC517737, FNP-1-FSP-65.0A - A-Train Rad Waste HVAC Fire Damper Inspection, | |||
8/5/2016 | |||
WO SNC578376, FNP-1-FSP-63.07 - Visual Inspection of Various AB Fire Barrier Penetrations, | |||
10/29/2016 | |||
Enclosure | |||
WO SNC719665, 1-2A Diesel Fire Roll-up Door, Rev. 1 | |||
WO SNC789081, FNP-0-FSP-201.3 - Motor Driven Fire Pump Operability Test, 11/19/2016 | |||
WO SNC806975, Addition of Fire Extinguishers for NFPA 10 Code Compliance, 3/22/2017 | |||
WO SNC822613, FNP-0-FSP-203.4 - Motor Driven Fire Pump Functional Test, 4/27/2017 | |||
WO SNC538103, Perform FNP-1-FSP-65.0A Data Sheet (A-Train) Visual Inspect, 9/22/2017 | |||
WO SNC958335, Incorrect Fire Damper Installation - EOC, 7/23/2018 | |||
Condition Reports Reviewed during inspection | |||
CR 10043210, Fire Watch Required, 3/19/2015 | |||
CR 10509998, Equipment Check Deficiency | |||
CR 10051606, Re-evaluate Postulated Hot Short Event, 4/07/2015 | |||
CR 10517355, Update for AOP FNP-0-EIP-16.0-F26 | |||
CR 10149000, Note Added to FNP-0-SOP-0.4, 11/19/2015 | |||
CR 10149001, 1-2A Diesel INOP MRULE MPFF, 11/19/2015 | |||
CR 10168712, NFPA 805 Potential License Condition Compliance Issue, 1/14/2016 | |||
CR 10170805, Impact Review for DCP SNC692210, 1/20/2016 | |||
CR 10172987, Risk Evaluation Needed for Three DCPs, 1/25/2016 | |||
CR 10207202, Combustibles Storage in a Level A Area Unapproved, 4/07/2016 | |||
CR 10281867, Fire PRA Qualifications NFPA 805 LAR Requirements, 10/04/2016 | |||
CR 10318639, NOS Fire Protection Identified Findings, 1/14/2017 | |||
CR 10356518, NFPA 805 Circuit Supervision Design for Dry Chemical Suppression (2A-120), | |||
4/20/2017 | |||
CR 10431122, Fire Extinguishers, 11/15/2017 | |||
CR 10442490, NFPA 805 Implementation, 12/24/2017 | |||
CR 10445795, AOP-29 Procedure Revision, 1/04/218 | |||
CR 10448087, Unanalyzed Condition Identified During NFPA 805 Transition, 1/09/2018 | |||
CR 10454233, MRule Unavailability Hours Exceeded for Sprinkler Systems, 1/25/2018 | |||
CR 10461010, Fire Extinguisher Hydro Date, 2/12/2018 | |||
CR 10464796, Fire Extinguishers, 2/22/2018 | |||
CR 10465621, Generate WOs for Fusible Link (ETL) Replacements, 2/23/2018 | |||
CR 10466131, HSS Fire Dampers Nonfunctional Due to Expired FSP, 2/26/2018 | |||
CR 10466136, LSS Fire Dampers Non Functional, 2/26/2018 | |||
CR 10470738, FPA Database Used to Track and Manage FP LCOs in Inadequate, 3/10/2018 | |||
CR 10483183, Tracking CR per NMP-GM-027-001, 4/17/2018 | |||
CR 10489319, Breaker in Cubicle N2R17BKRFC52R Oversized for the Application, 5/03/2018 | |||
CR 10494496, NFPA 805 S-3 Item 31, 5/17/2018 | |||
CR 10497446, WOs Needed to Perform Partial FNP-1-FSP-307.0 on Multiple FP Systems, | |||
5/25/2018 | |||
CAR 256103, Document Comp. Measures Taken, 4/23/2015 | |||
CAR 260875, Pre-Start Check on 1-2A Diesel Fire Roll-up Door, 12/11/2015 | |||
CAR 272312, 1-2A EDG Day Tank Room Fire Damper Closing Due to Failed Fusible Link, | |||
2/14/2017 | |||
Condition Reports Written Due to this Inspection | |||
CR 10516257, Dirt Dauber Nest in Vent Line of No. 2 Diesel Fire Pump Fuel Oil Tank, | |||
7/17/2018 | |||
CR 10516269, Conduit Labeling Error at SWIS, 7/17/2018 | |||
CR 10516551, NMP-ES-035-GL01 Contains Directions and Instructions Not IAW NMP-AP-001, | |||
7/18/2018 | |||
CR 10516553, Farley Fire Preplan Guidance, 7/18/2018 | |||
CR 10516573, Revise NMP-ES-035-001, Fire Protection Program Implementation, 7/18/2018 | |||
Enclosure | |||
CR 10516702, Typo in FRE Calculation SE-C051326701-008, 7/18/2018 | |||
CR 10516723, NRC Inspector Identified Damper 1-188-332-02 Was Not Installed Correctly, | |||
7/18/2018 | |||
CR 10516728, In-correct Version of Fire Pre-plans in Fire Brigade Ready Room, 7/18/2018 | |||
CR 10516948, EIP-16 Checklist C Found Expired Batteries, 7/19/2018 | |||
CR 10517133, FNP-0-SOP-0.4 Needs to be Clarified, 7/19/2018 | |||
CR 10517136, Incorrect Fire Damper Installation - EOC, 7/19/2018 | |||
CR 10517262, FNP-0-EIP-16 Checklist EOC Inspection, 7/20/2018 | |||
CR 10517257, Damper Inspection Request for EOC, 7/20/2018 | |||
CR 10517355, Procedure Revision Request for FNP-0-AOP-29, 7/20/2018 | |||
CR 10517472, SWIS Battery Room B Fire Damper Failed Drop Test, 7/20/2018 | |||
CR 10520516, 2018 NRC TFPI - Non-UL Listed Fire Damper, 7/30/2018 | |||
CR 10520806, Bolt Missing on Electrical Panel in MCR, 7/31/2018 | |||
CR 10520912, SSD Equipment Extension Cord Removed from Service, 7/31/2018 | |||
CR 10520916, NRC TFPI 2018 - Work Order Closed Inappropriately, 7/31/2018 | |||
CR 10521312, Issues Noted with Emergency Light PMs, 8/1/2018 | |||
CR 10521359, B.5.b Test Gauges Found Out of Calibration, 8/2/2018 | |||
CR 10521560, 2018 NRC TFPI CR - Fire Damper Technical Evaluation Needed, 8/2/2018 | |||
Drawings | |||
A-177539, Grounding - Details and Notes, Rev. 2 | |||
D-170331, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1 & 2]], Outdoor Concrete-Service Water Intake | |||
Structure, General Arrangement, Version 1.0 | |||
D-170343, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection Piping, Pump House & Tanks | |||
Plans & Details, Revision 10 | |||
D-177001, U1 Single Line Electrical Auxiliary System (Emergency 4160 & 600 V), Rev. 23 | |||
D-170366, Fire Protection P&ID - Yard Mains, Rev. 47 | |||
D-170366, Fire Protection P&ID - Pump House, Rev. 14 | |||
D-170366, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection, P & ID, Pump & Engine Details, | |||
Sheet 1, Version 1.0 | |||
D-170366, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection, P & ID, Pump House & Yard | |||
Mains, Version 1.0 | |||
D-170381, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection P&ID, High Pressure Carbon | |||
Dioxide, Sheet 1,Version 1.0, Revision 0 | |||
D-170381, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection P&ID, High Pressure Carbon | |||
Dioxide, Sheet 3,Version 1.0, Revision 0 | |||
D-170384, Fire Protection P&ID - Low Pressure Carbon Dioxide, Rev. 17 | |||
D-170385, Fire Protection P&ID - High Pressure Carbon Dioxide, Rev. 5 | |||
D-172099, D-170381, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Fire Protection, Thermostat | |||
Installation-600v Switchgear, Revision 0 | |||
D-175011, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], HVAC P&ID Radwaste Area System, Aux. Bldg. | |||
Plan at El. 121-0, Revision 0 | |||
D-175030, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], HVAC Process Flow Diagram, Non-Rad Area & | |||
Electrical Shop Rooms, Version 1.0 | |||
D-175115, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], HVAC System, Aux. Bldg. Plan at El. 121-0, | |||
Version 1.0 | |||
D-175048, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1 & 2]], Service Water Intake Structure, HVAC-P&ID, | |||
Revision 1 | |||
D-170332, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1 & 2]], Mechanical-Service Water Intake Structure, | |||
General Arrangement of Heat & Ventilation Systems- Floor Plan Section & Details, Rev. 22 | |||
D-205619, P&ID Chemical & Volume Control System, Rev. 4 | |||
Enclosure | |||
D-350857, | |||
: [[contact::J.M. Farley Nuclear Plant - Unit 1]], Aux. Bldg. Concrete-Penetration Seals @ El. | |||
21-0, Version 1.0 | |||
DAF-D-2217, Trap Door Fire Dampers, Rev. G | |||
DAF-D-2217, Type DAF-P-2217 Trap Door Fire Dampers, Rev. H | |||
DAF-D-8403, DAF P-5990 | |||
: [[contact::U.L. Classified Type A Excel Fire Damper]], Rev. 3 | |||
DAF-D-8406, UL Classified DAF-P-5990 Fire Damper with Factory Supplied Sleeves, Rev. D | |||
Enclosure | |||
}} | }} |
Latest revision as of 10:02, 2 November 2019
ML18256A251 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 09/11/2018 |
From: | Scott Shaeffer NRC/RGN-II/DRS/EB2 |
To: | Madison D Southern Nuclear Operating Co |
References | |
IR 2018011 | |
Download: ML18256A251 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 11, 2018
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NRC TRIENNIAL FIRE PROTECTION INSPECTION (TEAM) REPORT NOS. 05000348/2018011 AND 05000364/2018011
Dear Mr. Madison:
On August 2, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Farley Nuclear Plant, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this NFPA 805 Triennial Fire Protection Inspection (TFPI) are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
This finding involved a violation of NRC requirements. The NRC is treating the violation as a non-cited violation (NCV), consistent with Section 2.3.2.a of the NRCs Enforcement Policy.
If you contest this violation or significance of this NCV, 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 II; the Director, Office of Enforcement; and the NRC Resident Inspector at the Farley Nuclear Plant. 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/
Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos.: 50-348, 50-364 License Nos.: NPF-2, NPF-8
Enclosure:
Inspection Report 05000348/2018011 and 05000364/2018011
Inspection Report
Docket Number(s): 50-348, 50-364 License Number(s): NPF-2, NPF-8 Report Number(s): 05000348/2018011 and 05000364/2018011 Enterprise Identifier: I-2018-011-0022 Licensee: Southern Nuclear Operating Company, Inc. (SNC)
Facility: Joseph M. Farley Nuclear Plant, Units 1 and 2 Location: Ashford, AL 36312 Inspection Dates: Week 1 of onsite inspection: July 16 - 20, 2018 Week 2 of onsite inspection: July 30 - August 2, 2018 Inspectors: J. Dymek, Reactor Inspector L. Jones, Senior Reactor Inspector W. Monk, Reactor Inspector (Team Leader)
N. Staples, Senior Reactor Inspector Accompanying Personnel: T. Sippel, Fuel Facility Inspector (Training, Week 1 Only)
Approved By: Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety (DRS)
1 Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Southern Nuclear
Companys performance by conducting an announced team TFPI at the Farley Nuclear Plant,
Units 1 and 2, in accordance with the NRC Reactor Oversight Process. The Reactor Oversight Process (ROP) 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. NRC-identified findings and violations are summarized in the table below.
List of Findings and Violations Failure to ensure fire barrier penetrations (including fire dampers) in fire zones protecting safety-related areas shall be functional in accordance with NFPA 805 Section 3.11.3, Fire Barrier Penetrations Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green H.8, Procedure 71111.05XT Systems NCV 05000348-364/2018011-01 Adherence - 02.02b Closed The NRC identified a Green finding and associated non-cited violation (NCV) of the Farleys Renewed Operating License Condition 2.C.(4) - Fire Protection for U1 and 2.C.(6) - Fire Protection for U2. This finding was identified for failure to maintain all provisions of the approved FPP, as described in NFPA 805, 2001 Edition to ensure that all fire barrier penetrations (including fire dampers) in fire zones protecting safety-related areas shall be functional. The functional failure of the two fire dampers in the A and B SWIS Battery Rooms was a performance deficiency and determined to be more-than-minor because it affected the Reactor Safety Mitigating Systems cornerstone attribute of protection against external factors, a fire, and it affected the fire protection Defense in Depth (DID) strategies involving the confinement of fires and to protect systems important to safety. Additionally, if left uncorrected, the issue could potentially lead to a more significant safety concern during fire events.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) 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 team reviewed the selected procedures and records, observed activities, and interviewed plant personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and industry standards.
REACTOR SAFETY
===71111.05XT - NPFA 805 Fire Protection (Triennial)
The team evaluated applicable fire protection licensing commitments from July 16, 2018 to August 2, 2018 by review of the following:
Fire Protection Inspection Requirements ===
The team evaluated fire protection program implementation in the following selected areas:
1) FA 1-041, Train A SWGR and Load Center Rooms (Performance Based Area)2) FA 076, SWIS 5KV SWGR A and East Stairs (Performance Based Area)3) FA 1-018, Aux Building DC SWGR (Performance Based Area)
B.5.b Inspection Activities (1 Sample)
The team evaluated the feasibility of the following B.5.b Mitigating Strategies:
1) The team reviewed the strategy for manual operation of the Turbine Driven AFW (TDAFW) Pump strategy
OTHER ACTIVITIES - BASELINE
INSPECTION RESULTS Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green Finding H.8, Procedure 71111.05XT-Systems 50-348, 50-364/2018011-01 Adherence 02.02b Closed The NRC identified a Green finding and associated non-cited violation (NCV) of the licensees Fire Protection Program (FPP) and NPFA 805, Section 3.11.3, Fire Barrier Penetrations, for the licensees failure to ensure functional fire dampers, 1-188-332-01 and 1-188-332-02 in the A and B SWIS Battery Rooms.
Description:
Fire Dampers 1-188-332-01 and 1-188-332-02 in the A and B SWIS Battery Rooms were improperly installed per their design drawing U164049 and the B train Battery Room fire damper failed to shut when conducting a surveillance drop test on 7/20/2018. Specially, the angle clip bracket was not installed with the 90 degree leg pointed away from the damper skirt, which caused the damper skirt to not drop and seal off the barrier penetrations between the battery rooms (Deterministic fire areas) and SWIS Switchgear Rooms (Performance-Based fire areas).
Additionally, according to drawing U164049, DAF-P-5990 Fire Damper with Optional SRD (Smoke Release Device), Note 1 states: Although construction is per these drawings, the damper will not be UL Label if equipped with the SRD. In the case of Fire Dampers 1-188-332-01 and 1-188-332-02, all four 1 1/2 hour rated curtain-type fire dampers were equipped with SRDs and fusible links, not electro-thermal links (ETLs). SRDs are not UL listed/labeled, but ETLs are UL listed/labeled. The referenced electrical elementary design drawings reflected use of ETLs, not SRDs.
The improper fire damper installations and damper functional failure did not meet the licensees Fire Protection Program (FPP) nor NPFA 805 Section 3.11.3, Fire Barrier Penetrations, which states passive fire protection devices such as dampers shall conform with the following NFPA standard, NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating Systems. NFPA 90A, Code of Record 1973 states in section 905, Construction of Fire Dampers, Approved fire dampers shall have the following performance characteristics:
a) They shall be arranged to close automatically in event of abnormal high temperature.
b) They shall provide the maximum practical barrier to passage of air when in the closed position.
Corrective Action(s): In response to the inspection discovery, the licensee promptly initiated condition reports to resolve the equipment deficiencies and conducted an extent of condition review throughout the plant.
Corrective Action Reference(s): This issue is being tracked in the licensees corrective action program (CAP) by condition reports:
- CR 10516723, NRC Inspector Identified Damper 1-188-332-02 Was Not Installed Correctly, 7/18/2018
- CR 10520516, 2018 NRC TFPI - Non-UL Listed Fire Damper, 7/30/2018
Performance Assessment:
Performance Deficiency: The licensees failure to ensure the fire dampers were functional, as required by the approved Fire Protection Program and NPFA 805 was determined to be a performance deficiency (PD).
Screening: This performance deficiency was determined to be more-than-minor because it affected the Reactor Safety Mitigating Systems cornerstone attribute of protection against external factors, a fire, and it affected the fire protection DID strategies involving the confinement of fires and to protect systems important to safety. Specifically, the failure to ensure functional fire dampers could affect the fire protection DID strategy involving the confinement of fires because it could allow smoke and heat to migrate beyond the room and affect adjacent fire areas (FAs). Additionally, if left uncorrected, the issue could potentially lead to a more significant fire propagation safety concern.
Significance: The team assessed the finding using NRC Inspection Manual Chapter 0609, Significance Determination Process (SDP), Attachment 4, Initial Characterization of Findings, and determined the Mitigating Systems cornerstone was impacted and that a IMC 0609, Appendix F, Fire Protection SDP review was required as the finding involved the ability to confine a fire. The team further assessed the finding using NRC Inspection Manual Chapter 0609, Appendix F, Attachment 1, Fire Protection SDP Worksheet, and determined the finding to be of very low safety significance (Green) based upon Step 1.4.4, Question E, based upon if a fire were to spread from one fire area to another due to the degraded fire barriers, no additional targets would be damaged in the fire areas that could impact the credited safe shutdown strategy.
Cross-Cutting Aspect: The team assessed the issue for cross-cutting aspects using IMC 0310, Aspects Within Cross Cutting Areas, and concluded this deficiency was indicative of current licensee performance because the fire dampers were last inspected in September 2017. Per IMC 0310, a cross cutting aspect of H.8, Procedure Adherence was assigned to this finding because individuals performing the fire damper surveillances did not fully follow the surveillances procedures and work instructions. Specially, the fire damper surveillance inspection procedure states under the Acceptance Criteria section, No damage or missing hardware exists on the damper as determined by a visual inspection and the wires and links are properly attached.
Enforcement:
NPFA 805 Section 3.11.3, Fire Barrier Penetrations, required passive fire protection devices such as dampers shall conform with the following NFPA standard, NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating Systems. NFPA 90A, Code of Record 1973, Section 905, Construction of Fire Dampers, required that approved fire dampers shall have the following performance characteristics:
a) They shall be arranged to close automatically in event of abnormal high temperature.
b) They shall provide the maximum practical barrier to passage of air when in the closed position.
Contrary to the above, since the plants commercial operational date until July 2018, the licensee failed to ensure that fire dampers 1-188-332-01 and 1-888-332-02 were functional and that they met the requirements of NFPA 90A, to functionally shut during the conditions of a fire.
Disposition: This violation is being treated as an NCV consistent with Section 2.3.2a of the NRC Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The team verified no proprietary nor safeguards information was retained or documented in this report. Additionally, the team confirmed that proprietary and safeguards information was controlled to protect from public disclosure. On August 2, 2018, the lead inspector and team presented the NFPA 805 TFPI results to the Site Vice President, Mr. Dennis Madison, and other members of the Farley Nuclear Plant staff.
THIRD PARTY REVIEWS The team did not perform any reviews of the Institute of Nuclear Power Operations (INPO)reports nor any other third party documents during the inspection period.
KEY POINTS OF CONTACT Licensee Personnel Gene Surber, Licensing Supervisor Mandy Ludlam, Licensing Engineer Hilliard Cooper, Fire Protection Manager Meredith Smith, Fire Protection Program Engineer Kim Wilson, Fire Protection Engineer Robert Chandler, Site Fire Marshall NRC Personnel P. Niebaum, Senior Resident Inspector K. Miller, Resident Inspector S. Shaeffer, Chief, Engineering Branch 2, DRS, Region II LIST OF COMPONENTS REVIEWED Component ID Description Q1E21P0002B 1B Charging/HHSI Pump N1E21HIK122 Charging Flow Indication Q1B31V0053 U1 A/B PORV Q1E21LCV115B Excess Letdown Valve Q1N23HV3227B Train B MDAFW Pump Q1P17P001B Train B CCW Pump Q1N1PV3371B Main Steam Atmosphere Relief Valve Q1B31V0061 Pressurizer PORV Q2R16B0006 4.16KV Switchgear Bus 2D Q1E13PT0952 Unit 2 Containment Pressure Transmitter QSR42B0523B 125VDC SWIS Battery 2 N1B31LI0461 Pressurizer Level Channel 3 N1B31LI0459Z Pressurizer Level Indicator LI-459Z N1B21TI0410 RCS Cold Leg Temperature Indicator N1N11LI0477A Steam Generator 1A Wide Range Level Indicator LI-477A N1N11LI0497A Steam Generator 1C Wide Range Level Indicator LI-497A N1C55NI0031B Source Range Count Rate Indicator NI-31B
DOCUMENTS REVIEWED
Licensing Basis, Design Basis, & Regulatory
DWG A-181805, NFPA 805 Fire Protection Program Design Basis Document, Rev. 1
Joseph M. Farley Nuclear Plant License Amendment Request to Adopt NFPA-805 Performance
Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001
Edition), 9/25/2012
Safety Evaluation Report, Joseph
- M. Farley Nuclear Plant, Units 1 And 2 - Issuance Of
Amendments Related To NFPA 805 Supplement (CAC Nos. MG0094, MG0095; EPID N
- O.
L-2017-LLA-0261), 11/01/2017
Safety Evaluation Report, Joseph
- M. Farley Nuclear Plant, Units 1 And 2 - Issuance Of
Amendments Related To NFPA 805 Supplement (CAC Nos. MF7617 And MF7618),
10/17/2016
Southern Nuclear Operating Company Alabama Power Company Docket No. 50-348 Joseph
- M.
Farley Nuclear Plant, Unit 1 Renewed Facility Operating License No. NPF-2
Southern Nuclear Operating Company Alabama Power Company Docket No. 50-364 Joseph
- M.
Farley Nuclear Plant, Unit 2 Renewed Facility Operating License No. NPF-8
Joseph M. Farley Nuclear Plant Response to Request for Additional Information Regarding
License Amendment Request for Transition to 10 CFR 50.48(c) NFPA 805 Performance
Based Standard for Fire Protection for Light Water Reactor Generating Plants, Attachment S -
Modifications and Implementation Items
Farley Nuclear Plant, UFSAR Chapter 9, Section 9.5.1, Fire Protection System, Rev. 26
Calculations
ARC 4.3.1, Compliance Assessment by Scenario, 6/15/2018
F-RIE-FIREPRA-U00-017, NFPA 805 Transition Risk Results for Farley, 2/16/2018
NMP-ES-035-006-F06, NFPA 805 Change Evaluation - U1/U2 FLEX Communications &
Gaitronics Upgrades, Version 2.0
Enclosure
NMP-ES-035-006-F06, NFPA 805 Change Evaluation - Main Turbine (DEH) Controls Upgrade,
Version 1.0
SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Rev. 2
SE-C051326701-008, Attachment - FRE for Unit 1 Fire Area 1-018, Auxiliary Building DC
Switchgear Room, Rev. 0
SE-C051326701-010, Nuclear Safety Capability Assessment Fire Area Compliance
Assessment, Rev. 4
SE-C051326701-011, Recovery Action Feasibility Evaluation, Rev. 0
SE-C051326701-012, NFPA 805 Defense in Depth (DID) Recovery Actions, Rev. 2
SM-C051326701-007, NFPA Code Conformance Review, Version 1.0
SM-C051326701-011, Fire Suppression Effects Analysis, Version 1.0
SM-1081426001-001, B.5.b Mitigation Strategy Flow Verification, Dated March 2012
TE-707175, Evaluation of Farley Triennial Fire Distribution System Flow Test, FNP-0-FSP-53,
11/22/2013
Procedures
FNP-0-AOP-29.0, Abnormal Operating Procedure - Plant Fire, Rev. 51.0
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments76-100, Version 1.0
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 51-75, Version 1.0
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 1-25, Version 1.0
FNP-0-SOP-29.3, Reliable Equipment During a Plant Fire Attachments 26-50, Version 1.0
FNP-1-ECP-0.0, Emergency Contingency Procedure - Loss of All AC Power, Rev. 30
FNP-0-EIP-16.0, Emergency Equipment and Supplies, VERSION 72.0
FNP-0-EIP-16.0-F05, Checklist E Control Room Storage Locker, Version 1.0
FNP-0-EIP-16.0-F26, Fire Fighting Equipment (OPS) Checklist, Version 1.0
FNP-0-EIP-16.0-F40, Smoke Removal Equipment, Version 1.0
FNP-1-FPP-1.0, Unit 1 Auxiliary Building Pre-Fire Plan, Version 1.0
FNP-0-FPP-2.0, Protected Area Pre-Fire Plans, Version 1.0
FNP-0-FPP-3.0, Owner Controlled Area Pre-Fire Plan, Version 2.0
FNP-1-FPP-3.0, Unit 1 Containment Pre-Fire Plan, Version 1.0
FNP-0-FSP-201.1, No. 1 Diesel Driven Fire Pump Functionality Test, Version 21.0
FNP-0-FSP-201.3, Motor Driven Fire Pump Functionality Test, Version 12.0
FNP-0-FSP-203.2, #1 Diesel Driven Fire Pump Functional Test, Version 10.0
FNP-0-FSP-203.4, Motor Driven Fire Pump Functional Test (Pump Flow Test), Version 11.0
FNP-0-FSP-203.5, #1 Diesel Driven Fire Pump Functional Test (Pump Flow Test),
Version 14.0
FNP-0-FSP-300.0, Fire Pump Diesel Starting Battery Monthly Inspection, Version 5.1
FNP-0-FSP-301, Fire Pump Diesel Starting Battery Quarterly Inspection, Version 8.0
FNP-0-SOP-0.4, Fire Protection Operability And LCO Requirements, Rev. 104
FNP-1-AOP-28.0, Control Room Inaccessibility, Version 18, Dated April 2018
NP-1-FSP-65.0A, Fire Dampers Functional Inspection Aux. Building - Diesel Building - Service
Water Building Train A, Version 5.0
FNP-1-FSP-65.0B, Fire Dampers Functional Inspection Aux. Building - Diesel Building -
Service Water Building Train B, Version 5.0
FNP-1-SOP-58.0, Auxiliary Building HVAC System, Version 80, Dated March 2018
FNP-1-SOP-62.0, Emergency Air System, Version 26, Dated April 2015
NMP-05-007-003, Standing Order - Fire Protection LCOs Peer Check Requirement, 7/11/2018
NMP-CH-002, Chemical Control Program, Version 12.2, 5/24/18
NMP-CH-002-003, Chemical Storage Areas, Version 9.0, 6/14/18
NMP-EP-402, Plant Farley Emergency Management Guideline (EMG), VERSION 14.1
NMP-EP-402, Manual Operation of TDAFW, Att. 7, Version 14.1
Enclosure
NMP-EP-402, Temporary Instrumentation Installation, Att. 12, Version 14.1
NMP-EP-402, B.5.b Pump and Accessories, Att. 13, Version 14.1
NMP-ES-027-001, NFPA 805 Program, Version 9.0
NMP-ES-035-001, Fire Protection Program Implementation, Version 13.1
NMP-ES-035-003, Fleet Hot Work Instruction, Version 7.0
NMP-ES-035-007, Fleet Fire Watch Instruction, Version 4.1
NMP-ES-035-009, Quarterly Fire Safety Inspection, Version 4.0
NMP-ES-035-010, Fire Brigade, Version 5.0
NMP-ES-035-014, Fleet Transient Combustible Controls, Version 2.1
NMP-ES-035-GL01, Fire Protection Program Guideline, Version 3.0
NMP-OS-007-001, Conduct of Operations Standards and Expectations, Version 16.2
NMP-TR-425, Fire Drill Program, Version 8.0
NMP-TR-426, Fire Training Program, Version 5.1
Plant Modifications
DCP SNC459687, NFPA 805: U1 Cable and Raceway Fire Protection, Version 8.0
DCP SNC834134, SWIS Security Enhancements Project - NFPA 805 Change Evaluation,
Version 2.0
Miscellaneous Documents
A-181017, J. M. Farley Nuclear Plant Unit 1 / 2 Functional System Description-Fire Protection
System, Revision 43
American Warming and Ventilating, Inc., Mod. DAF-D-8403, U.L. Classified Type A Excel Fire
Damper, Revision E
Chemical Product Storage Permit, NMP-CH-002-03, Attachment 1, SWIS, 6/15/2015
Elsie Type A and Type B Fusible Link Vendor Data Sheet, 7/30/2018
EVAL-F-R45-03207, U1 R45-FO1 Emergency Lights, 4/8/2018
Farley Nuclear Plant Occurrence Report (OR) 1-98-017, Fire Damper Failed to Indicate Closed,
1/22/1998
Information Notice No. 89-52: Potential Fire Damper Operational Problems, June 8, 1989
Information Notice No. 83-69: Improperly Installed Fire Dampers at Nuclear Power Plants,
October 21, 1983
Maintenance Rule Expect Panel Meeting #18-06, 4/03/2018
Maintenance Rule Expect Panel Meeting #18-09, 6/22/2018
National Fire Protection Association (NFPA) 80, Fire Doors and Windows 1973 Code of Record
NFPA 600, Standard for Industrial Fire Brigades, 2000 Edition
NMP-ES-035-009-F01, Quarterly Fire Inspection Report Form, Q1 2018
NMP-ES-035-009-F01, Quarterly Fire Inspection Report Form, Q2 2018
RER SNC629964, RG 1.75 Marinite RER, Version 2.0
Request from Bechtel Eastern Power Company to American Warming and Ventilating Company
Entitled Evaluation of Fire Damper Installation, (SS-1102-54), March 21, 1988
S-FP-PP-10100-07.1, Fire Training / Introduction to Fire Fighting, Rev. 7.1
TE 1009817, Take to the MREP: Tracking CR per NMP-GM-027-001, 4/17/2018
Work Orders
WO SNC593970, FNP-1-FSP-307.0 - Zone 1A-32 - U1 A-Train Smoke Detector - Biennial
Operability and Adjustment, 6/10/2016
WO SNC517737, FNP-1-FSP-65.0A - A-Train Rad Waste HVAC Fire Damper Inspection,
8/5/2016
WO SNC578376, FNP-1-FSP-63.07 - Visual Inspection of Various AB Fire Barrier Penetrations,
10/29/2016
Enclosure
WO SNC719665, 1-2A Diesel Fire Roll-up Door, Rev. 1
WO SNC789081, FNP-0-FSP-201.3 - Motor Driven Fire Pump Operability Test, 11/19/2016
WO SNC806975, Addition of Fire Extinguishers for NFPA 10 Code Compliance, 3/22/2017
WO SNC822613, FNP-0-FSP-203.4 - Motor Driven Fire Pump Functional Test, 4/27/2017
WO SNC538103, Perform FNP-1-FSP-65.0A Data Sheet (A-Train) Visual Inspect, 9/22/2017
WO SNC958335, Incorrect Fire Damper Installation - EOC, 7/23/2018
Condition Reports Reviewed during inspection
CR 10043210, Fire Watch Required, 3/19/2015
CR 10509998, Equipment Check Deficiency
CR 10051606, Re-evaluate Postulated Hot Short Event, 4/07/2015
CR 10517355, Update for AOP FNP-0-EIP-16.0-F26
CR 10149000, Note Added to FNP-0-SOP-0.4, 11/19/2015
CR 10149001, 1-2A Diesel INOP MRULE MPFF, 11/19/2015
CR 10168712, NFPA 805 Potential License Condition Compliance Issue, 1/14/2016
CR 10170805, Impact Review for DCP SNC692210, 1/20/2016
CR 10172987, Risk Evaluation Needed for Three DCPs, 1/25/2016
CR 10207202, Combustibles Storage in a Level A Area Unapproved, 4/07/2016
CR 10281867, Fire PRA Qualifications NFPA 805 LAR Requirements, 10/04/2016
CR 10318639, NOS Fire Protection Identified Findings, 1/14/2017
CR 10356518, NFPA 805 Circuit Supervision Design for Dry Chemical Suppression (2A-120),
4/20/2017
CR 10431122, Fire Extinguishers, 11/15/2017
CR 10442490, NFPA 805 Implementation, 12/24/2017
CR 10445795, AOP-29 Procedure Revision, 1/04/218
CR 10448087, Unanalyzed Condition Identified During NFPA 805 Transition, 1/09/2018
CR 10454233, MRule Unavailability Hours Exceeded for Sprinkler Systems, 1/25/2018
CR 10461010, Fire Extinguisher Hydro Date, 2/12/2018
CR 10464796, Fire Extinguishers, 2/22/2018
CR 10465621, Generate WOs for Fusible Link (ETL) Replacements, 2/23/2018
CR 10466131, HSS Fire Dampers Nonfunctional Due to Expired FSP, 2/26/2018
CR 10466136, LSS Fire Dampers Non Functional, 2/26/2018
CR 10470738, FPA Database Used to Track and Manage FP LCOs in Inadequate, 3/10/2018
CR 10483183, Tracking CR per NMP-GM-027-001, 4/17/2018
CR 10489319, Breaker in Cubicle N2R17BKRFC52R Oversized for the Application, 5/03/2018
CR 10494496, NFPA 805 S-3 Item 31, 5/17/2018
CR 10497446, WOs Needed to Perform Partial FNP-1-FSP-307.0 on Multiple FP Systems,
5/25/2018
CAR 256103, Document Comp. Measures Taken, 4/23/2015
CAR 260875, Pre-Start Check on 1-2A Diesel Fire Roll-up Door, 12/11/2015
CAR 272312, 1-2A EDG Day Tank Room Fire Damper Closing Due to Failed Fusible Link,
2/14/2017
Condition Reports Written Due to this Inspection
CR 10516257, Dirt Dauber Nest in Vent Line of No. 2 Diesel Fire Pump Fuel Oil Tank,
7/17/2018
CR 10516269, Conduit Labeling Error at SWIS, 7/17/2018
CR 10516551, NMP-ES-035-GL01 Contains Directions and Instructions Not IAW NMP-AP-001,
7/18/2018
CR 10516553, Farley Fire Preplan Guidance, 7/18/2018
CR 10516573, Revise NMP-ES-035-001, Fire Protection Program Implementation, 7/18/2018
Enclosure
CR 10516702, Typo in FRE Calculation SE-C051326701-008, 7/18/2018
CR 10516723, NRC Inspector Identified Damper 1-188-332-02 Was Not Installed Correctly,
7/18/2018
CR 10516728, In-correct Version of Fire Pre-plans in Fire Brigade Ready Room, 7/18/2018
CR 10516948, EIP-16 Checklist C Found Expired Batteries, 7/19/2018
CR 10517133, FNP-0-SOP-0.4 Needs to be Clarified, 7/19/2018
CR 10517136, Incorrect Fire Damper Installation - EOC, 7/19/2018
CR 10517262, FNP-0-EIP-16 Checklist EOC Inspection, 7/20/2018
CR 10517257, Damper Inspection Request for EOC, 7/20/2018
CR 10517355, Procedure Revision Request for FNP-0-AOP-29, 7/20/2018
CR 10517472, SWIS Battery Room B Fire Damper Failed Drop Test, 7/20/2018
CR 10520516, 2018 NRC TFPI - Non-UL Listed Fire Damper, 7/30/2018
CR 10520806, Bolt Missing on Electrical Panel in MCR, 7/31/2018
CR 10520912, SSD Equipment Extension Cord Removed from Service, 7/31/2018
CR 10520916, NRC TFPI 2018 - Work Order Closed Inappropriately, 7/31/2018
CR 10521312, Issues Noted with Emergency Light PMs, 8/1/2018
CR 10521359, B.5.b Test Gauges Found Out of Calibration, 8/2/2018
CR 10521560, 2018 NRC TFPI CR - Fire Damper Technical Evaluation Needed, 8/2/2018
Drawings
A-177539, Grounding - Details and Notes, Rev. 2
D-170331,
- J.M. Farley Nuclear Plant - Unit 1 & 2, Outdoor Concrete-Service Water Intake
Structure, General Arrangement, Version 1.0
D-170343,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection Piping, Pump House & Tanks
Plans & Details, Revision 10
D-177001, U1 Single Line Electrical Auxiliary System (Emergency 4160 & 600 V), Rev. 23
D-170366, Fire Protection P&ID - Yard Mains, Rev. 47
D-170366, Fire Protection P&ID - Pump House, Rev. 14
D-170366,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection, P & ID, Pump & Engine Details,
Sheet 1, Version 1.0
D-170366,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection, P & ID, Pump House & Yard
Mains, Version 1.0
D-170381,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection P&ID, High Pressure Carbon
Dioxide, Sheet 1,Version 1.0, Revision 0
D-170381,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection P&ID, High Pressure Carbon
Dioxide, Sheet 3,Version 1.0, Revision 0
D-170384, Fire Protection P&ID - Low Pressure Carbon Dioxide, Rev. 17
D-170385, Fire Protection P&ID - High Pressure Carbon Dioxide, Rev. 5
D-172099, D-170381,
- J.M. Farley Nuclear Plant - Unit 1, Fire Protection, Thermostat
Installation-600v Switchgear, Revision 0
D-175011,
- J.M. Farley Nuclear Plant - Unit 1, HVAC P&ID Radwaste Area System, Aux. Bldg.
Plan at El. 121-0, Revision 0
D-175030,
- J.M. Farley Nuclear Plant - Unit 1, HVAC Process Flow Diagram, Non-Rad Area &
Electrical Shop Rooms, Version 1.0
D-175115,
- J.M. Farley Nuclear Plant - Unit 1, HVAC System, Aux. Bldg. Plan at El. 121-0,
Version 1.0
D-175048,
- J.M. Farley Nuclear Plant - Unit 1 & 2, Service Water Intake Structure, HVAC-P&ID,
Revision 1
D-170332,
- J.M. Farley Nuclear Plant - Unit 1 & 2, Mechanical-Service Water Intake Structure,
General Arrangement of Heat & Ventilation Systems- Floor Plan Section & Details, Rev. 22
D-205619, P&ID Chemical & Volume Control System, Rev. 4
Enclosure
D-350857,
- J.M. Farley Nuclear Plant - Unit 1, Aux. Bldg. Concrete-Penetration Seals @ El.
21-0, Version 1.0
DAF-D-2217, Trap Door Fire Dampers, Rev. G
DAF-D-2217, Type DAF-P-2217 Trap Door Fire Dampers, Rev. H
DAF-D-8403, DAF P-5990
DAF-D-8406, UL Classified DAF-P-5990 Fire Damper with Factory Supplied Sleeves, Rev. D
Enclosure