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Errata for Millstone Power Station - NRC Triennial Fire Protection Inspection Report 05000336/2016007 and 05000423/2016007 Amended to 05000336/2016008 and 05000423/2016008
	ML17004A249
Person / Time
Site:	Millstone
Issue date:	01/04/2017
From:	Dentel G T; Engineering Region 1 Branch 2
To:	Stoddard D G; Dominion Resources
	Dentel G T
References
	IR 2016008
	Download: ML17004A249 (36)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713 January 4, 2017

Mr. Daniel Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT: ERRATA FOR MILLSTONE POWER STATION - NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000336/2016007 AND 05000423/2016007 AMENDED TO 05000336/2016008 AND 05000423/2016008

Dear Mr. Stoddard:

The U.S. Nuclear Regulatory Commission (NRC) has identified an error in NRC Inspection Report 05000336/2016007 and 05000423/2016007, dated September 14, 2016 (ADAMS Accession No. ML16258A175). Specifically, the report incorrectly lists the report number as 2016007. The correct report number is 2016008. This error affects the first page of the cover letter, the distribution page, the report cover page, the summary of findings page, page 4 of the report, and the supplemental information page. As a result, the NRC has reissued the report in its entirety to correct this error.

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/ Glenn T. Dentel, Chief Engineering Branch 2

Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosure:

Inspection Report 05000336/2016008 and 05000423/2016008 w/Attachment:

Supplemental Information

cc w/encl: Distribution via ListServ

ML16258A175). Specifically, the report incorrectly lists the report number as 2016007. The correct report number is 2016008. This error affects the first page of the cover letter, the distribution page, the report cover page, the summary of findings page, page 4 of the report, and the supplemental information page. As a result, the NRC has reissued the report in its entirety to correct this error.

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/ Glenn T. Dentel, Chief Engineering Branch 2

Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosure:

Inspection Report 05000336/2016008 and 05000423/2016008 w/Attachment:

Supplemental Information

cc w/encl: Distribution via ListServ DISTRIBUTION: (via email)

DDorman, RA DLew, DRA MScott, DRP DPelton, DRP RLorson, DRS JYerokun, DRS EDiPaolo, DRP TSetzer, DRP JSchussler, DRP JAmbrosini, DRP, SRI LMcKown, DRP, RI CHighley, DRP, RI ARancourt, DRP, AA JBowen, RI OEDO RidsNrrPMMillstone Resource RidsNrrDorlLpl1-1 Resource ROPreports Resource DOCUMENT NAME: \\nrc.gov\nrc\R1\Office\DRS\Engineering Branch 3\Patel J\Millstone 2&3 FP 2016-008_ERRATA.docx ADAMS Accession No. ML17004A249 ADAMS Package: ML17004A230 SUNSI Review Complete By: JP ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive Keyword: OFFICE RI/DRS RI/DRS NAME JPatel GDentel DATE 1/4/17 1/4/17 i Enclosure U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Docket Nos.: 50-336, 50-423

License Nos.: DPR-65, NPF-49

Report Nos.: 05000336/2016008 and 05000423/2016008

Licensee: Dominion Nuclear Connecticut, Inc.

Facility: Millstone Power Station, Units 2 and 3

Location: P.O. Box 128 Waterford, CT 06385

Dates: July 25, 2016 through August 11, 2016

Inspectors: J. Patel, Reactor Inspector (Team Leader)

Division of Reactor Safety (DRS)

W. Cook, Senior Reactor Analyst, DRS E. DiPaolo, Senior Reactor Inspector, DRS D. Orr, Senior Reactor Inspector, DRS K. Young, Senior Reactor Inspector, DRS L. Dumont, Reactor Inspector, DRS S. Galbreath, Reactor Inspector, DRS J. Rady, Reactor Inspector, DRS Observers: S. Freeman, Senior Reactor Analyst, NRC, Region II, DRS

Approved by: Chris Cahill, Acting Branch Chief Engineering Branch 3 Division of Reactor Safety

ii

SUMMARY OF FINDINGS

IR 05000336/2016008, 05000423/2016008; 07/25/2016 - 08/11/2016; Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Units 2 and 3; Fire Protection (Triennial).

This report covered a two week on-site triennial fire protection team inspection by specialist inspectors. One finding of very low safety significance was identified. This finding was determined to be a non-cited violation. The significance of most findings is indicated by their color (Green, While, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process." The cross-cutting aspects associated with findings were determined using IMC 0310, "Components Within The Cross-Cutting Areas." Findings for which the significance determination process (SDP) does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6, dated July 2016.

Cornerstone: Mitigating Systems

Green.

The team identified a finding of very low safety significance (Green) involving a non-cited violation of Millstone Power Station, Unit 2, Renewed Facility Operating License Condition 2.C.(3) to implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report (FSAR). Specifically,

Dominion failed to maintain the #2 steam generator (SG) atmospheric dump valve (ADV)free from fire damage, which may have affected the availability to maintain hot shutdown conditions from the main control room for a fire in Fire Area R-14, Lower 4.16kV Switchgear Room and Cable Vault. Dominion promptly entered this safe shutdown issue into their corrective action program as condition report (CR) 1043458. Immediate corrective actions included implementing compensatory measures in the form of fire watches for fire area R-14 that are being tracked by Reasonable Assurance of Safety (RAS) determination 3037040.

Longer term corrective actions included submitting an exemption request to the NRC for use of a local operator manual action (OMA) to operate the #2 SG ADV in lieu of meeting fire protection requirements for fire area R-14. The team considered Dominion's immediate and longer term corrective actions appropriate.

The performance deficiency was more than minor because it affected the Mitigating Systems cornerstone objective to ensure the availability, reliability, and capability of systems that respond to an external event to prevent undesirable consequences in the event of a fire. Specifically, the use of an OMA during post-fire safe shutdown is not as reliable as normal systems operation which could be utilized had the requirements of 10 CFR Part 50,

Appendix R,Section III.G.2 been met and, therefore, prevented fire damage to credited components and/or cables, specifically the #2 SG ADV. The inspectors used IMC 0609, Appendix F, Fire Protection Significance Determination Process, Phase 1 and determined the reactor is able to reach and maintain a hot safe shutdown condition because the SG ADVs are used for transition to cold shutdown, therefore this finding was of very low safety significance (Green). This finding does not have a cross cutting aspect because the performance deficiency occurred greater than three years ago when the June 30, 2011 exemption request letter to the NRC was supplemented by letter on February 29, 2012, and is not indicative of current licensee performance. (Section 1R05.01)iii

Other Findings

Three violations of very low safety significance that were identified by Dominion were reviewed by the team. Corrective actions taken or planned by Dominion have been entered into Dominion's corrective action program (CAP). The violations and corrective action tracking numbers are listed in Section 4OA7 of this report.

REPORT DETAILS

Background

This report presents the results of a triennial fire protection inspection conducted in accordance

with the U.S. Nuclear Regulatory Commission (NRC) Inspection Procedure (IP) 71111.05T, "Fire Protection (Triennial)." The objective of the inspection was to assess whether Dominion Nuclear Connecticut, Inc. (Dominion) has implemented an adequate fire protection program (FPP) and that post-fire safe shutdown capabilities have been established and are being properly maintained at the Millstone Power Station Unit 2 and Unit 3 (Millstone). The following fire areas (FA) and/or fire zones (FZ) were selected for detailed review based on risk insights from the

Millstone Individual Plant Examination of External Events (IPEEE).

Unit 2 Fire Areas / Fire Zones R-7 / A-15, "A" Diesel Generator Room A R-1 / A-32, Main Ventilation Room (Air Handling Units) R-14 / T-7, 6.9 & 4.16 kV Switchgear Room R-14 / T-9, East Cable Vault Unit 3 Fire Areas AB-6, West MCC & Rod Control Area CB-11, Instrument Rack Room and Underfloor Area EG-3, North Emergency Generator Enclosure ESF-3, North Residual Heat Removal - Heat Exchanger Cubicle Inspection of these areas/zones fulfills the inspection procedure requirement to inspect a minimum of three samples.

The inspection team evaluated Dominion's FPP against applicable requirements which included Unit 2 Renewed Facility Operating License Condition 2.C.(3), Unit 3 Renewed Facility Operating License Conditions 2.H, NRC Safety Evaluation Reports (SERs), Title 10 of the Code of Federal Regulations (10 CFR) 50.48, 10 CFR Part 50, Appendix R and Branch Technical Position (BTP) Chemical Engineering Branch (CMEB) 9.5-1.

The team also reviewed related documents that included the Updated Final Safety Analysis Repor t (UFSAR), Fire Protection Program, Fire Hazards Analyses (FHA), and post-fire Safe Shutdown Analyses Reports.

The team also evaluated two Unit 2 and two Unit 3 licensee mitigating strategies for addressing large fires and explosions as required by Unit 2 Renewed Facility Operating License Condition 2.C.(13), Unit 3 Renewed Facility Operating License Condition 2.C.(10), and 10 CFR 50.54 (hh)(2). Inspection of these strategies fulfills the inspection procedure requirement to inspect a minimum of one sample.

Specific documents reviewed by the team are listed in the Attachment to this report.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R05 Fire Protection (IP 71111.05T)

.01 Protection of Safe Shutdown Capabilities

a. Inspection Scope

The team reviewed the FHA, safe shutdown analyses, and supporting drawings and documentation to verify that post-fire safe shutdown capabilities were properly protected. The team ensured that applicable separation requirements of Section III.G of 10 CFR Part 50, Appendix R for Unit 2 and BTP CMEB 9.5-1 for Unit 3 as well as the licensee's design and licensing bases were maintained for the credited safe shutdown equipment and their supporting power, control, and instrumentation cables. This review included an assessment of the adequacy of the selected systems for reactivity control, reactor coolant makeup, reactor heat removal, process monitoring, and associated support system functions.

b. Findings

Introduction:

The team identified a finding of very low safety significance (Green) involving a non-cited violation of Millstone Unit 2 Renewed Facility Operating License Condition 2.C.(3) to implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR. Specifically, Dominion failed to maintain the #2 SG ADV free from fire damage, which may have affected the availability to maintain hot shutdown conditions from the main control room for a fire in Fire Area R-14, Lower 4.16kV Switchgear Room and Cable Vault.

Description:

The inspectors reviewed the operator manual actions (OMAs) contained in operating procedure AOP 2579M, Fire Procedure for Hot Standby Appendix R Fire Area R-14, and compared them against the list of NRC approved OMAs in lieu of meeting III.G.2 fire protection requirements and determined that an unapproved OMA was being implemented in AOP 2579M. The OMAs in lieu of meeting III.G.2 fire protection requirements were approved in an NRC exemption dated December 18, 2012. The missing OMA was an action to locally operate air-operated valve, 2-MS-190B, #2 SG ADV. The OMA is necessary since a self-induced loss of offsite power (LOOP) will occur and station blackout (SBO) condition may occur from fire related cable damage. Either condition, LOOP or SBO, will cause a loss of instrument air in response to a significant fire in fire area R-14.

The LOOP will occur when AOP 2579M is implemented because step 3.4 requires the operators to trip the reactor (causing a loss of the normal station service transformer)and step 3.9 requires the operators to direct CONVEX (transmission operator) to de-energize the reserve station service transformer. A SBO may subsequently occur if the B emergency diesel generator (EDG) is running and its output breaker does not close, which could occur due to fire-related circuit damage. In either condition, LOOP or SBO, the 'F' instrument air compressor, will be de-energized and a loss of instrument air will occur. In 2011, Dominion submitted an exemption request to the NRC for several OMAs in lieu of meeting III.G.2 fire protection requirements in several fire areas and initially postulated a loss of instrument air for Fire Area R-14. Three OMAs were requested related to the loss of instrument air for Fire Area R-14 in a June 30, 2011 exemption request letter to the NRC. Subsequent to the June 30, 2011 exemption request letter, Dominion walked down several fire areas and from a mechanical perspective concluded that a loss of instrument air should no longer be postulated for several fire areas. R-14 was included as a fire area for which a loss of instrument air was no longer considered credible. In a request for additional information response letter dated February 29, 2012, Dominion stated that the loss of instrument air was no longer postulated in fire area R-14 and others, and requested the NRC delete the OMA for locally operating the #2 SG ADV. In a correction letter dated October 29, 2012, Dominion again reiterated that for Fire Area R-14, and others, a Loss of Instrument Air was not postulated, but Dominion clarified that some of the OMAs that were related to a loss of instrument air should be retained for postulated fire cable damage or loss of power. However, the OMA for locally operating the #2 SG ADV was not retained since it was not susceptible to cable damage or loss of power for a fire in area R-14.

Dominion stated in its June 30, 2011 exemption request letter to the NRC that after auxiliary feedwater (AFW) is established from the control room, operation of the ADV (2-MS-1 90B) is the required method of removing decay heat to maintain hot standby and transition to cold shutdown.

As described above, the inspectors determined that implementing AOP 2579M as written will cause a loss of instrument air and the OMA to locally operate the #2 SG ADV will be necessary after AFW is restored and decay heat removal is transitioned from the main steam safety valves to the #2 SG ADV for steam generator pressure control. The inspectors noted that Dominion is currently implementing an unapproved OMA in lieu of meeting III.G.2 fire protection requirements. Dominion promptly entered this safe shutdown issue into their corrective action program as CR 1043458. Immediate corrective actions included implementing compensatory measures in the form of fire watches for fire area R-14 that are being tracked by RAS determination 3037040.

Longer term corrective actions included submitting an exemption request to the NRC for use of a local OMA to operate the #2 SG ADV in lieu of meeting fire protection requirements for fire area R-14. The team considered Dominion's immediate and longer term corrective actions appropriate.

Analysis:

Dominion's failure to protect the #2 SG ADV, credited for post-fire safe shutdown from fire damage in Fire Area R-14 caused by single spurious actuation, is considered a performance deficiency. The performance deficiency was more than minor because it affected the Mitigating Systems cornerstone objective to ensure the availability, reliability, and capability of systems that respond to an external event to prevent undesirable consequences in the event of a fire. Specifically, the use of an OMA during post-fire safe shutdown may not be as reliable as normal systems operation which could be utilized had the requirements of 10 CFR Part 50, Appendix R, Section III.G.2 been met and, therefore, prevented fire damage to credited components and/or cables, specifically the #2 SG ADV.

The inspectors used IMC 0609, Appendix F, Fire Protection Significance Determination Process, Phase 1 and determined the reactor is able to reach and maintain a hot safe shutdown condition because the ADVs are used for transition to cold shutdown, therefore this finding was of very low safety significance (Green).

This finding does not have a cross cutting aspect because the performance deficiency occurred greater than three years ago when the June 30, 2011 exemption request letter to the NRC was supplemented by letter on February 29, 2012, and is not indicative of current licensee performance.

Enforcement:

Millstone Power Station, Unit 2, Renewed Facility Operating License Condition 2.C.(3) requires Dominion in part to implement and maintain in effect all provisions of the approved fire protection program as described in the FSAR. FSAR Section 9.10.6, Safety Shutdown Design Bases, states in part Paragraph 50.48(b) of 10 CFR 50, which became effective on February 17, 1981, that all nuclear plants licensed to operate prior to January 1, 1979, comply with specific portions of Section III of Appendix R to 10 CFR 50.Section III.G requires that fire protection features be provided for those systems, structures, and components important to safe shutdown. These features must be capable of limiting fire damage so that one train of systems necessary to achieve and maintain hot shutdown conditions from either the main control room or the emergency control stations is free of fire damage.

Contrary to the above, since February 17, 1981 (the effective date of Appendix R and revised 10 CFR 50.48), and ongoing as of the inspection exit date, Dominion failed to implement all provisions of the approved fire protection program. Specifically, the safe shutdown strategy in Fire Area R-14 for Millstone Unit 2 relied upon an unapproved OMA to mitigate post-fire safe shutdown equipment malfunctions caused by a single spurious actuation, in lieu of protecting the equipment in accordance with 10 CFR Part 50 Appendix R, Section III.G.2. The specific OMA associated with Fire Area R-14 includes local manual control of the #2 SG ADV. Dominion's immediate corrective actions included implementing compensatory measure in the form of fire watches for fire area R-14. Because this violation was of very low safety significance (Green), and was entered into Dominion's CAP (CR 1043458), this issue is being treated as an NCV consistent with Section 2.3.2 of the Enforcement Policy. (NCV 05000336/2016008-01, Unapproved OMA in Lieu of Meeting III.G.2 Fire Protection Requirements for Fire Area R-14, Lower 4kV Switchgear Room and Cable Vault)

.02 Passive Fire Protection

a. Inspection Scope

The team walked down accessible portions of the selected fire areas to evaluate whether the material conditions of the fire area boundaries were adequate for the fire hazards in the area. The team compared the fire area boundaries, including walls, ceilings, floors, fire doors, fire dampers, penetration seals, and redundant equipment fire barriers to design and licensing basis requirements, industry standards, and the Millstone Power Station Unit 2 and Unit 3 FPPs, as approved by the NRC, to identify any potential degradation or non-conformances.

The team reviewed selected engineering evaluations, installation and repair work orders, and qualification records for a sample of penetration seals to determine whether the fill material was properly installed and whether the as-left configuration satisfied design requirements for the intended fire rating.

The team also reviewed recent inspection and functional test records for fire dampers, and the inspection records for penetration seals and fire barriers, to verify whether the inspection and testing was adequately conducted, the acceptance criteria were met, and any potential performance degradation was identified.

b. Findings

No findings were identified.

.03 Active Fire Protection

a. Inspection Scope

The team evaluated manual and automatic fire suppression and detection systems in the selected fire areas to determine whether they were installed, tested, maintained, and operated in accordance with NRC requirements, National Fire Protection Association (NFPA) codes of record, and the Millstone FPPs, as approved by the NRC. The team also assessed whether the suppression systems capabilities were adequate to control and/or extinguish fires associated with the hazards in the selected areas.

The team reviewed the as-built capability of the fire water supply system to verify the design and licensing basis and NFPA code of record requirements were satisfied, and to assess whether those capabilities were adequate for the hazards involved. The team

reviewed the fire water system hydraulic analyses to assess the adequacy of a single fire water pump to supply the largest single hydraulic load on the fire water system plus concurrent fire hose usage. The team evaluated the fire pump performance tests to assess the adequacy of the test acceptance criteria for pump minimum discharge pressure at the required flow rate, to verify the criteria was adequate to ensure that the design basis and hydraulic analysis requirements were satisfied. The team also evaluated the underground fire loop flow tests to verify the tests adequately demonstrated that the flow distribution circuits were able to meet design basis requirements. In addition, the team reviewed recent pump and loop flow test results to verify the testing was adequately conducted, the acceptance criteria were met, and any potential performance degradation was identified.

The team reviewed initial discharge testing, design specifications, vendor requirements, modifications and engineering evaluations, and routine functional testing for the CO 2 and Halon suppression systems for the areas protection. The team walked down accessible potions of the CO 2 and Halon systems, including storage tanks and supply systems, to independently assess the material condition, operational lineup, and availability of the systems. The team also reviewed and walked down the associated firefighting strategies and CO 2 and Halon system operating procedures.

The team walked down accessible portions of the detection and water suppression systems in the selected areas and major portions of the fire water supply system, including motor and diesel driven fire pumps, interviewed system and program engineers, and reviewed selected correct ive action program documents (condition reports) to independently assess the material condition of the systems and components. In addition, the team reviewed recent test results for the fire detection and suppression systems for the selected fire areas to verify the testing was adequately conducted, the acceptance criteria were met, and any performance degradation was identified.

The team assessed the fire brigade capabilities by reviewing training, qualification, and drill critique records. The team also reviewed Millstone's firefighting strategies (i.e. pre-fire plans) and smoke removal plans for the selected fire areas to determine if appropriate information was provided to fire brigade members and plant operators to identify safe shutdown equipment and instrumentation, and to facilitate suppression of a fire that could impact post-fire safe shutdown capability. The team independently inspected the fire brigade equipment, including personnel protective gear (e.g. turnout gear) and smoke removal equipment, to determine operational readiness for firefighting.

In addition, the team reviewed Millstone's fire brigade equipment inventory and inspection procedure and recent inspection and inventory results to verify adequate equipment was available, and any potential material deficiencies were identified.

b. Findings

No findings were identified.

.04 Protection from Damage from Fire Suppression Activities

a. Inspection Scope

The team walked down the selected fire areas and adjacent areas, and reviewed selected documents to determine whether redundant safe shutdown trains could be potentially damaged from fire suppression activi ties or from the rupture or inadvertent operation of fire suppression systems. During the walkdowns, the team evaluated the adequacy and condition of floor drains, equipment elevations, and spray protection.

Specifically, to determine whether a potential existed to damage redundant safe shutdown trains, the team evaluated whether:

A fire in one of the selected fire areas would not release smoke, heat, or hot gases that could cause unintended activation of suppression systems in adjacent fire areas which could potentially damage all redundant safe shutdown trains; or A fire suppression system rupture, inadvertent actuation, or actuation due to a fire, in one of the selected fire areas, could not directly damage all redundant trains (e.g. sprinkler caused flooding of other than the locally affected train); and Adequate drainage was provided in areas protected by water suppression systems.

b. Findings

No findings were identified.

.05 Post-Fire Safe Shutdown Capability - Normal and Alternative

a. Inspection Scope

The team reviewed the safe shutdown analysis, thermal-hydraulic analysis, operating procedures, time critical operator action validation studies, piping and instrumentation drawings (P&lDs), electrical drawings, the UFSAR, and other supporting documents for the selected fire areas to verify whether Dominion had properly identified the systems and components necessary to achieve and maintain post-fire safe shutdown conditions.

The team evaluated selected systems and co mponents credited by the safe shutdown analysis for reactor pressure control, reactivity control, reactor coolant makeup, decay heat removal, process monitoring, and support system functions to assess the adequacy of Dominion's alternative shutdown methodology. The team also assessed whether alternative post-fire shutdown could be perfo rmed both with and without the availability of off-site power. The team walked down selected plant configurations to verify whether they were consistent with the assumptions and descriptions in the safe shutdown and fire hazards analyses. In addition, the team evaluated whether the systems and components credited for use during post-fire safe shutdown would remain free from fire damage.

The team reviewed the training program for licensed and non-licensed operators to verify whether it included alternative shutdown capability. The team also verified whether personnel required for post-fire safe shutdown, using either the normal or alternative shutdown methods, were trained and available on-site at all times, exclusive of those assigned as fire brigade members.

The team reviewed the adequacy of procedures utilized for post-fire shutdown and performed an independent walk through of procedure steps (i.e., a procedure tabletop) to assess the adequacy of implementation and human factors within the procedures. The team also evaluated the time required to perform specific actions to verify whether operators could reasonably be expected to perform those actions within sufficient time to maintain plant parameters within specified limits.

Specific procedures reviewed for normal and alternative post-fire shutdown included the following:

Unit 2 AOP 2559, Fire; AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1; AOP 2579AA, Fire Procedure for Cooldown and Cold Shutdown Appendix R Fire Area R-1; AOP 2579EE, Fire Procedure for Cooldown and Cold Shutdown Appendix R Fire Area R-7, R-9, R-14, and R-17; AOP 2579G, Fire Procedure for Hot Standby Appendix R Fire Area R-7; and, AOP 2579M, Fire Procedure for Hot Standby Appendix R Fire Area R-14.

Unit 3 EOP 3509, Fire Emergency; EOP 3509.1, Control Room, Cable Spreading Area or Instrument Rack Room Fire; EOP 3509.6, Auxiliary Building West MCC/Rod Control/ACU Area Fire; EOP 3509.15, North (A) EDG Enclosure or East (A) F.O. Vault Fire; and, EOP 3509.19, ESF Building North RHR Heat Exchanger Cubicle Fire.

The team reviewed selected operator manual actions to verify whether they had been properly reviewed and approved and whether the actions could be implemented in accordance with plant procedures in the time necessary to support the safe shutdown method for each fire area. The team also reviewed the periodic testing of the alternative shutdown transfer and isolation capability, and instrumentation and control functions, to evaluate whether the tests were adequate to ensure the functionality of the alternative shutdown capability.

b. Findings

No findings were identified.

.06 Circuit Analysis

a. Inspection Scope

The team verified that the licensee performed a post-fire safe shutdown analysis for the selected fire areas and the analysis appropriately identified the structures, systems, and components important to achieving and maintaining safe shutdown. Additionally, the team verified that the licensee's analysis ensured that necessary electrical circuits were properly protected and that circuits that could adversely impact safe shutdown due to hot shorts or shorts to ground were identified, evaluated, and dispositioned to ensure spurious actuations would not prevent safe shutdown.

The team's review considered fire and cable attributes, cable routing, potential undesirable consequences and common power supply/bus concerns. Specific items included the credibility of the fire threat, cable insulation attributes, cable failure modes, and actuations resulting in flow diversion or loss of coolant events.

The team also reviewed cable raceway drawings and/or cable routing databases for a sample of components required for post-fire safe shutdown to verify that cables were routed as described in the safe shutdown analysis. The team also reviewed equipment important to safe shutdown, but not part of the success path, to verify that the licensee had taken appropriate actions in accordance with the design and licensing basis and NRC Regulatory Guide 1.189, Revision 2.

Cable failure modes were reviewed for the following components:

Unit 2 P18B, Charging Pump 'B'; 2-CH-501, VCT Outlet Header to Charging Pumps Isolation Valve; 2-CH-519, Loop 1A Charging Isolation Valve; and, PI-1023B-1, SG #2 Pressure Indicator.

Unit 3 3RCS*LCV459, VCT Letdown Isolation Valve; 3RCS*SV8095A, Head Vent Isolation Valve; 3CHS*MV8438A, Charging Pump 'A' Header Isolation Valve; 3FWS*LI501A, SG #1 Level Indicator; and, 3RCS*PI405B, RCS Pressure Indicator.

The team reviewed a sample of circuit breaker coordination studies to ensure equipment needed to conduct post-fire safe shutdown activities would not be impacted due to a lack of coordination that could result in a common power supply or common bus concern.

The team verified that the transfer of control from the control room to the alternative shutdown location(s) would not be affected by fire-induced circuit faults (e.g. by the provision of separate fuses and power supplies for alternative shutdown control circuits).

b. Findings

No findings were identified.

.07 Communications

.13 Large Fires and Explosions Mitigation Strategies

a. Inspection Scope

The team conducted a review of selected mitigation strategies intended to maintain or restore core decay heat removal and spent fuel pool cooling capabilities under the circumstances associated with the loss of large areas of the plant due to explosions and/or fires. The team assessed whether Dominion continued to meet the requirements of the Millstone Power Station Units 2 and 3 Operating Licenses and 10 CFR

50.54(hh)(2).

The team reviewed the following mitigation strategies:

Unit 2 and 3 Manual Operation of Turbine-Driven AFW Pump; and, Unit 2 and 3 Manual Operation of SG ADVs.

The team's review included: a detailed assessment of the procedural guidance; a tabletop discussion with licensed operators; and a walk down of four mitigation strategies with operators to assess the feasibility of the strategies and operator familiarity; maintenance and surveillance testing of selected strategy equipment; and an inventory check of the B.5.b pump and equipment trailers to ensure the appropriateness of equipment storage and availability.

b. Findings

No findings were identified.

OTHER ACTIVITIES

[OA]

4OA2 Identification and Resolution of Problems (IP 71152)

.01 Corrective Actions for Fire Protection Deficiencies

a. Inspection Scope

The team reviewed a sample of condition reports associated with fire protection program and post-fire safe shutdown issues to determine whether Millstone was appropriately identifying, characterizing, and correcting problems in these areas, and to assess whether the planned or completed corrective actions were appropriate.

b. Findings

No findings were identified.

4OA3 Follow-up of Events and Notices of Enforcement Discretion (IP 71153)

.1 (Closed) Licensee Event Report (LER) 05000336/2013-003-00 (Unit 2):

Postulated DC Ammeter Circuit Hot Shorts On October 30, 2013, during a review of industry operating experience, Dominion identified a postulated fire induced circuit failure involving unfused direct current (DC)ammeter circuits for Millstone Power Station, Unit 2. The fire induced circuit failures could cause a secondary fire that could adversely affect safe shutdown equipment and cause a loss of alternate shutdown capability which is contrary to Unit 2 Renewed Facility Operating License Condition 2.C.(3) and Appendix R requirements. The license condition and regulation requires in part, post-fire safe shutdown cables remain free of the effects of fire-induced cable faults during postulated fires. Specifically, the licensee identified DC ammeter circuits for Unit 2, were not provided with overcurrent protection to limit fault current in the 125 volt (V) DC systems. Postulated fires that result in a short to ground concurrent with an opposite polarity short from the same battery could result in excessive current flow in the ammeter wiring. The excessive current could heat-up the conductor and could result in a secondary fire in another fire area. The secondary fire could adversely affect safe shutdown equipment and cause a loss of alternate shutdown capability. Dominion determined the cause of the condition was a latent design error that was made during plant construction involving the failure to include protective fuses in DC ammeter circuits.

The licensee submitted LER 05000336/2013-003-00 to report this event in accordance with 10 CFR 50.73(a)(2)(ii)(B) as an unanalyzed condition that significantly degraded plant safety. The licensee entered this issue into their corrective action program as condition report number CR530987 and implemented compensatory measures in the affected fire areas pending final resolution of the issue.

The licensee completed an engineering evaluation (RAS000244) of the issue and developed a design change (MP2-14-01007) to add fuses to the affected ammeter circuits. Dominion completed the necessary modifications for all affected ammeter circuits by May 7, 2014.

The significance and enforcement aspect of this issue are discussed in Section 4OA7.1 of this inspection report. LER 05000336/2013-003-00 is closed.

.2 (Closed) Licensee Event Report (LER) 05000336/2014-002-00 (Unit 2):

DC Circuit Hot Shorts On March 12, 2014, during a review of industry operating experience, Dominion identified postulated fire induced circuit failures involving unfused DC motor control circuits for Millstone Power Station Unit 2. The postulated fire induced circuit failures could cause a secondary fire that could adversely affect fire safe shutdown equipment contrary to Unit 2 Renewed Facility Operating License Condition 2.C.(3) and Appendix R requirements. The license condition and regulation requires in part, post-fire safe shutdown cables remain free of the effects of fire induced cable faults during postulated fires. Specifically, the licensee identified 125 V DC control and indication circuits for a non-safety related main turbine emergency lube oil pump that was not provided with overcurrent protection. Postulated fires in the turbine battery room, the cable vault, the plant equipment operator meeting area and the control room could cause failure of the unprotected 125 V DC circuits, which in turn could cause failure of the control circuits for safe shutdown equipment. Dominion determined the cause of the condition was a manufacturer's design error that involved the failure to include protective fuses in DC motor control circuits during plant construction.

The licensee submitted LER 05000336/2014-002-00 (Unit 2) to report this event in accordance with 10 CFR 50.73(a)(2)(ii)(B) as an unanalyzed condition that significantly degraded plant safety. The licensee entered this issue into their corrective action program as condition report number CR541980 and implemented compensatory measures in the affected fire areas pending final resolution of the issue.

The licensee completed an engineering evaluation (RAS000252) of the issue and developed a design change (MP2-14-01040) to add overcurrent protection (fuses) to the affected motor control circuit. Dominion completed the necessary modifications for the affected motor control circuit by May 5, 2014.

The significance and enforcement aspect of this issue are discussed in Section 4OA7.2 of this inspection report. LER 05000336/2014-002-00 (Unit 2) is closed.

.3 (Closed) Licensee Event Report (LER) 05000423/2014-002-00 (Unit 3):

DC Circuit Hot Shorts On March 12, 2014, during a review of industry operating experience, Dominion identified postulated fire induced circuit failures involving unfused DC motor control circuits for Millstone Power Station Unit 3. The postulated fire induced circuit failures could cause a secondary fire that could adversely affect fire safe shutdown equipment contrary to Unit 3 Renewed Facility Operating License Condition 2.H and the branch technical condition (BTP) 9.5-1 requirements. The license condition and the BTP requires in part, post-fire safe shutdown cables remain free of the effects of fire-induced cable faults during postulated fires. Specifically, the licensee identified 125 V DC control circuits for non-safety related main turbine emergency lube oil and a main generator emergency seal oil pumps that were not provided with overcurrent protection. Postulated fires in the turbine battery switchgear area, the cable spreading room, the instrument rack room, and the control room could cause failure of the unprotected 125 V DC control circuits, which in turn could cause failure of control circuits for safe shutdown equipment.

Dominion determined the cause of the condition was a manufacturer's design error that involved the failure to include protective fuses in DC motor control circuits during plant construction.

The licensee submitted LER 05000423/2014-002-00 (Unit 3) to report this event in accordance with 10 CFR 50.73(a)(2)(ii)(B) as an unanalyzed condition that significantly degraded plant safety. The licensee entered this issue into their corrective action program as condition report number CR541983 and implemented compensatory measures in the affected fire areas pending final resolution of the issue.

The licensee completed an engineering evaluation (RAS000253) of the issue and developed design change modifications (MP3-14-01071 and MP3-14-01092) to add overcurrent protection (fuses) to the affected motor control circuits. Dominion completed the necessary modifications for all affected motor control circuits by November 2, 2014.

The significance and enforcement aspect of this issue are discussed in Section 4OA7.3 of this inspection report. LER 05000289/2014-001-00 (Unit 3) is closed.

4OA6 Meetings, Including Exit

Exit Meeting Summary

The team presented the inspection results to Mr. John Daugherty, Site Vice President, Millstone Power Station, and other members of the site staff at an exit meeting on August 11, 2016. No proprietary information was included in this inspection report.

4OA7 Licensee-Identified Violations

The following violations of very low safety significance (Green) were identified by the

licensee and are violations of NRC requirements. These issues satisfy the criteria of the NRC Enforcement Policy of being dispositioned as Non-Cited Violations.

.1 LER 05000336/2013-003-00 (Unit 2) describes an unanalyzed condition in which Dominion identified their DC ammeter circuits were unfused.

Specifically, Dominion did not provide overcurrent protection for wiring associated with DC ammeter indication in the control room to prevent wires from overheating due to fire induced faults and excessive currents flowing through the cable. With enough current flowing through the cable, the potential existed that the overloaded ammeter wiring could damage system wiring or adjacent safety-related circuits in the cable raceways needed for post-fire safe shutdown. This condition could result in a loss of the associated safe shutdown components or a secondary fire in another fire area. The failure to protect safe shutdown cables from the effects of postulated fires was a performance deficiency.

This performance deficiency was a violation of Millstone Power Station, Unit 2, Renewed Facility Operating License Condition 2.C.(3), which requires in part, post-fire safe shutdown cables remain free of the effects of fire-induced cable faults during postulated fires. Contrary to the above, Dominion identified they failed to meet this requirement and the condition existed since initial construction of Unit 2. The issue was more than minor because it was associated with the protection against external events (fire) attribute of the mitigating systems cornerstone and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The team determined that the finding was of very low safety significance (Green), based IMC 0609, Appendix F, "Fire Protection Significance Determination Process (SDP)," Phase 2 screening criteria.

The finding screened to Green based upon, task number 2.3.5, because the affected cables were routed in alternate shutdown fire areas that are continually manned or protected by detection and automatic suppression systems. Remaining fire areas are protected by detection systems, automatic suppression systems or rely on manual fire-fighting activities. Additionally, the cable construction is Institute of Electrical and Electronics Engineers (IEEE) 383 (thermoset) which decreases the likelihood of inter-cable and intra-cable interactions. Based on a team walkdown, the team determined that the ammeter cable routing was not routed near a credible fire ignition source in the affected fire areas. Because this finding is of very low safety significance and had been entered into Dominion's corrective action program (CR530987), this violation is being treated as a Green, licensee-identified NCV consistent with the NRC's Enforcement Policy.

.2 LER 05000336/2014-002-00 (Unit 2) describes an unanalyzed condition in which Dominion identified DC motor control circuits were unfused.

Specifically, Dominion did not provide overcurrent protection for wiring associated with 125 V DC control circuits for a non-safety related main turbine emergency lube oil pump to prevent wires from overheating due to fire induced faults and excessive currents flowing through the cable. With enough current flowing through the cable, the potential existed that the overloaded motor control wiring could damage adjacent control circuit wiring for components which are needed to achieve and maintain post-fire safe shutdown for a fire in several fire areas (turbine battery room, cable vault, plant equipment operator meeting area, control room). This condition could result in a loss of the associated safe shutdown components or a secondary fire in another fire area. The failure to protect safe shutdown cables from the effect of postulated fires was a performance deficiency.

This performance deficiency was a violation of Millstone Power Station, Unit 2, Renewed Facility Operating License Condition 2.C.(3), which requires, in part, post-fire safe shutdown cables remain free of the effects of fire induced cable faults during postulated fires. Contrary to the above, Dominion identified they failed to meet this requirement and the condition existed since initial construction. The issue was more than minor because it was associated with the protection against external events (fire)attribute of the mitigating systems cornerstone and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The team determined that the finding was of very low safety significance (Green), based on IMC 0609, Appendix F, "Fire Protection Significance Determination Process," Phase 2 screening criteria.

The finding screened to Green based upon, task number 2.3.5, because the affected cables were routed in alternate shutdown fire areas that are continually manned or protected by detection and automatic suppression systems. Remaining fire areas are protected by detection systems, automatic suppression systems or rely on manual fire-fighting activities. Additionally, the cable construction is IEEE 383 (thermoset) which decreases the likelihood of inter-cable and intra-cable interactions. Based on a team walkdown, the team determined that the main turbine emergency lube oil pump cable routing was not routed near a credible fire ignition source in the affected fire areas.

Because this finding is of very low safety significance and had been entered into Dominion's corrective action program (CR541980), this violation is being treated as a

Green, licensee-identified NCV consistent with the NRC's Enforcement Policy.

.3 LER 05000423/2014-002-00 (Unit 3) describes an unanalyzed condition in which Dominion identified DC motor control circuits were unfused.

Specifically, Dominion did not provide overcurrent protection for wiring associated with 125 V DC control circuits for non-safety related main turbine emergency lube oil and main generator emergency seal oil pumps to prevent wires from overheating due to fire induced faults and excessive currents flowing through the cable. With enough current flowing through the cable, the potential existed that the overloaded motor control wiring could damage adjacent control circuit wiring for components which are needed to achieve and maintain post-fire safe shutdown for a fire in several fire areas (turbine battery switchgear area, cable spreading room, instrument rack room, control room). This condition could result in a loss of the associated safe shutdown components or a secondary fire in another fire area. The failure to protect safe shutdown cables from the effect of postulated fires was a performance deficiency.

This performance deficiency was a violation of Millstone Power Station, Unit 3, Renewed Facility Operating License Condition 2.H, which requires, in part, post-fire safe shutdown cables remain free of the effects of fire induced cable faults during postulated fires. Contrary to the above, Dominion identified they failed to meet this requirement and the condition existed since initial construction. The issue was more than minor because it was associated with the protection against external events (fire) attribute of the mitigating systems cornerstone and it adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The team determined that the finding was of very low safety significance (Green), based on IMC 0609, Appendix F, "Fire Protection Significance Determination Process," Phase 2 screening criteria.

The finding screened to Green based upon, task number 2.3.5, because the affected cables were routed in alternate shutdown fire areas that are continually manned or protected by detection and automatic suppression systems. Remaining fire areas are protected by detection systems, automatic suppression systems or rely on manual fire-fighting activities. Additionally, the cable construction is IEEE 383 (thermoset) which decreases the likelihood of inter-cable and intra-cable interactions. Based on a team walkdown, the team determined that the main turbine emergency lube oil and main generator emergency seal oil pump cable routing was not routed near a credible fire ignition source in the affected fire areas. Because this finding is of very low safety significance and had been entered into Dominion's corrective action program (CR541983), this violation is being treated as a Green, licensee-identified NCV consistent with the NRC's Enforcement Policy.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

J. Daugherty, Site Vice President

D. Blakeney, Assistant Plant Manager

P. Anastas, Safe Shutdown Engineer

J. Armstrong, Fire Protection Engineer

T. Bryant, Maintenance Supervisor

D. DelBiondo, Site Fire Marshal

J. Farley, Electrical System Engineer

B. Ferguson, Unit 2 Senior Reactor Operator

R. Garver, Engineering Director

L. Kelly, Engineering Lead

W. McCollum, Unit 2 Supervisor

D. Mello, Senior Fire Instructor

K. Perkins, Electrical Engineering Supervisor

P. Russell, Unit 3 Senior Reactor Operator

A. Vargas-Mendez, Licensing Engineer

NRC Personnel

C. Cahill, Acting Branch Chief, Engineering Brach 3, Division of Reactor Safety

C. Highley, Resident Inspector, Millstone Power Station

L. Mckown, Resident Inspector, Millstone Power Station

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

None

Opened and Closed

05000336/2016008-01 NCV Unapproved OMA in Lieu of Meeting III.G.2 Fire Protection Requirements for Fire Area R-14, Lower 4kV Switchgear Room and Cable Vault

Closed

05000336/LER-2013-003-00 LER Postulated DC Ammeter Circuit Hot Shorts (Unit 2), (Section 4OA3.1)

05000336/LER-2014-002-00 LER DC Circuit Hot Shorts (Unit 2), (Section 4OA3.2)

05000423/LER-2014-002-00 LER DC Circuit Hot Shorts (Unit 3), (Section 4OA3.3)

Discussed

None

LIST OF DOCUMENTS REVIEWED

Fire Protection Licensing Documents 25203-SP-M2-SU-1046, Unit 2 Appendix R Compliance Report, Revision 1

212-BTP-9.5-1, Unit 3 Branch Technical Position 9.5-1 Compliance Report, Revision 4

212-MP3-SFR, Millstone Power Station, Unit 3, Safety Function Requirement Manual, Revision 6 LBDCR 07-MP2-010, Millstone U2 Technical Requirements, dated 10/5/09 Letter from Dominion to NRC, Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 2 Response to Request for Additional Information Request for Exemption from

CFR 50, Appendix R, Section

III.G., Fire Protection of Safe Shutdown Capability, with Attachment, dated 2/29/12 Letter from Dominion to NRC, Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 2 Request for a Revision of an Exemption from 10

CFR 50, Appendix R, Section

III.G., Fire Protection of Safe Shutdown Capability, with Attachment, dated 10/29/12 Letter from Dominion to NRC, Dominion Nuclear Connecticut. Inc. Millstone Power Station Unit 2 Request for Exemption from 10

CFR 50. Appendix R. Section

III.G., Fire Protection of Safe Shutdown Capability, with Attachments, dated 6/30/11 Letter from NRC to Dominion, Millstone Power Station, Unit 2 -Correction to Previously Issued Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section III.G.2.

(TAC No. ME6693) with Enclosure, dated 12/18/12 Millstone Unit 2 Technical Requirement Manual, Section 3/4.7.9, Fire Protection System, 2/2/10 Millstone Unit 3 Fire Protection Evaluation Report, Revision 17.4

MP-SPEC-ENG-BTP-9.5-1, Millstone Unit 3 Branch Technical Position (BTP) 9.5-1 Compliance Report, Revision 4 U2-24-FPP-FHA, Unit 2 Fire Hazards Analysis, Revision 12

Updated Final Safety Analysis Report, Section 9.5.1, Fire Protection System, Revision 28.2

Design Basis Documents Fire Code Compliance Review of Safety Related Areas - Fire Protection Systems -Fire Alarm/Detection Systems and the plants Fire Pumps, dated 9/86

TR-151, Fire and Hose Stream Test of #TCO-003 High Density Silicone Elastomer used in Elec.

Opening, Revision 0

TR-189, Fire and Hose Stream Test of 6", 8", and 10" thick specimens of

TCO-050, Revision 1

Design Changes DCN

DM3-00-1286-97, Revision to the BTP 9.5-1 Compliance Report to Include RHS MOVs, dated 2/5/98 DCR M2-97034, Thermo-Lag Modifications for MP2, Revision 0 M2-98095, TDAFWP Redundant Power Supply, Revision 0

MP2-14-01007, DC Ammeter Hot Short Modification, Revision 1

MP2-14-01040, Appendix R Hot Short Circuit Modification for Emergency Bearing Oil Pump

P63, Revision 1

MP3-13-01183, RHR Cross-Train Suction Motor-Operated Valve Breaker Normal Alignment Change, dated 10/29/13

MP3-14-01071, Appendix R Hot Short Circuit Modification for Emergency Bearing Oil Pump

3TML-P1, Revision 0

MP3-14-01092, Appendix R Hot Short Circuit Modification for Emergency Seal Oil Pump 3GMO-

P2, Revision 0

MP3-14-01187, MP3 RPCCW Heat Exchanger 3CCP*E1B Replacement, dated 7/6/15

MPG-13-01131, MDM Flex Strategy Support Modification, dated 9/16/14

Calculations/Engineering Evaluation Reports 25203-ER-98-0151, Fire Test Performed for Florida Power & Light Company for Electrical Raceways Protected with Thermo-Lag Fire Barrier Systems, Revision, 0 25203-ER-99-0092, Millstone Unit 2 Appendix R Cooldown Analysis Assumptions and Results, Revision 3 97-ENG-01912E2, 4.16kV Switchgear Relay Settings, Revision 0

98-ENG-02411-C2, MP2 Evaluation Flooding Outside Containment, Revision 1 98-ENG-02621-M2, Determination of the Instrument Air Requirement for Certain Safety Related Valves, Revision 3 99-026, Calculation Change Notice No. 1, Millstone Site Fire Loop Flow Model Bench Markings, Revision 1 99-026, Calculation Change Notice No. 3, Millstone Site Fire Loop Flow Model Bench Markings, Revision 1 99-026, Calculation Change Notice No. 4, Millstone Site Fire Loop Flow Model Bench Markings, Revision 1 99-026, Millstone Site Fire Loop Flow Model Bench Markings, Revision 1

DNC 2512-ER-04-0030, Validation and Verification of

EOP 3509.1 Using Simulator, Field and Table Top Validation, dated 5/28/04

EMP-186, Millstone Nuclear Power Plant U2 Combustible Loading Re-Analysis Calculation, Revision 2

ER-97-0295, Sound Powered Phone and Trunked Radio Systems - Cable Selection, Routing and Figures, dated 1/16/98

ER-97-0302, MP3 BTP 9.5-1 Compliance Report Section 6.2 Revision - Communication Systems, dated 2/10/98 M2-EV-98-0113, Technical Evaluation for 120Vac Vital Bus Appendix R Coordination Study, Revision 1 M3-EV-98-0011, Technical Evaluation for The Use of an 800 MHz Carrier Frequency Trunked Radio System at Millstone Unit 3 for General Purposes and Appendix R Requirements, Revision 1

MP-CALC-ENG-S-0426535, MP3 BTP 9.5-1 RELAP5 Fire Shutdown Analysis 3650 and 3725 MWt, Revision 2 P1164-MP2-COORD, Unit 2 Breaker/Fuse Coordination for the Appendix R Circuits, Revision 0 RAS000244, Postulated DC Ammeter Circuit Hot Shorts, Revision 0

RAS000252, DC Circuit Hot Shorts, Revision 0 RAS000253, DC Circuit Hot Shorts, Revision 0 S-02824S2, Millstone Unit 2, R-2 Fire, Appendix R Analysis, Revision 2

SP-M3-EE-269, Unit 3 Electrical Design Criteria, Revision 3

W2-517-744-RE, MP2 Appendix R Cooldown, Revision 3

Procedures

3783EA, Component Cooling Pump Motor Replacement for Fire Protection, Revision 005-02 C

MP 790, Emergency Light Inspection and Testing, Revision 004-02

C

OP 200.18, Time Critical Action Validation and Verification, Revision 2

C

OP 200.18, Time Critical Action Validation and Verification, Revision 3

C

SP 600.24, Fire Brigade Equipment Inspection, Revision 000-04

C

SP 600.28, Fire Brigade vehicle Equipment Inspection Data Sheet (R3), Revision 000-05 C SP600.24, Unit 2 Fire Brigade Equipment Inspection, Revision 001-00

CM-AA-ETE-101, Engineering Technical Evaluation (ETE), Revision 6

CM-AA-FPA-10, Fire Protection/Appendix R (Fire Safe Shutdown) Program, Revision 2

CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe Shutdown) Program, Revision 11

CM-AA-FPA-101, Control of Combustible and Flammable Materials, Revision 8

CM-AA-FPA-102, Fire Protection and Fire Safe Shutdown review and preparation Process and Preparation Process and Design Change Process, Revision 6

COM-04-C, Plant Communication Systems, Revision 0

ER-AA-102, Preventive Maintenance Program, Revision 9

ER-AA-MRL-100, Implementing Maintenance Rule, Revision 10

FB-00012, Self-Contained Breathing Apparatus SCOTT 4.5, Revision 7

MP 2720U1, Cold Shutdown Fire Damage Repair Procedure for Fire Area R-1 (Appendix R), Revision 004-02

SA-AA-115, Conduct of Fire Drills, Revision 2

SFP 10, Fire Protection Inspections, Revision 005-03

SFP 21, Appendix R Fire Cage Inventory, Revision 002-06

SP 2402CR, Steam Generator Pressure Rack Instrument Calibration, Revision 0

SP 2601P, CVCS Valve Operability Tests From C-10 and C-02, Revision 0

SP 2610B, Turbine Driven Auxiliary Feed Pump Operational Tests from C-10, Revision 1

SP 2610E, Atmospheric Dump Valve Testing from C-10, C-70A and C-70B, Revision 1

SP 2610M, Power Operated Relief Valve Hot Functional Test, Revision 0

SP 3442J01, RCS Wide Range Pressure Rack Calibration, Revision 7

SP 3444A02, Steam Generator Water Level Wide Range Calibration, Revision 7

SP 3641D.3, Fire Detection and Control System Operability Check, Revision 015

SP 3641D.5, Fire Damper Operability Verification, Revision 012

SP 3641F.1, Functional Check of the East and West Switchgear Breathing Air Systems, Revision 2

SP 3673.2, Fire Transfer Switch Panel Operational Testing, Revision 002-06

SP 3673.4, Auxiliary Shutdown Panel Operability Test, Revision 010

TR-MP-TPG-2300, Fire Protection Programs Training Program Guide (TPG), Revision 2

WC5, Fuse Control, Revision 2

Operations Procedures

AOP 2559, Millstone Unit 2 Fire, Revision 10

AOP 2559, Procedure Basis Document, Fire, Revision 009-00

AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1, Revision 011-00

AOP 2579A, Procedure Basis Document, Fire Procedure for Hot Standby Appendix R Fire Area R-1, Revision 011-00

AOP 2579A, Unit 2 Fire Procedure for Hot Standby Appendix R Fire Area R-1, Revision 11

AOP 2579AA, Fire Procedure for Cooldown and Cold Shutdown, Appendix R Fire Area R-1, Revision 004-08

AOP 2579EE, Fire Procedure for Cooldown and Cold Shutdown, Appendix R Fire Area R-7, R-9, R-14, and R-17, Revision 005-09

AOP 2579G, Fire Procedure for Hot Standby Appendix R Fire Area R-7, Revision 006-10

AOP 2579M, Fire Procedure for Hot Standby Appendix R Fire Area R-14, Revision 006-06

AOP 3577, Loss of Normal and Offsite Power to a 4.16 kV Emergency Bus, Revision 003

AOP 3577, Procedure Basis Document, Loss of Normal and Offsite Power to a 4.16 kV Emergency Bus, Revision 002-00

AOP 3581, Immediate Operator Actions, Revision 003

COP 200.2AIR, "Airborne Threat," Revision 002-03

EDMG 2.01, MP2 B.5.b Event Control Room Response, Revision 004

EDMG 2.02, MP2 B.5.b Event TSC Response, Revision 010

EOP 2540, Functional Recovery, Revision 025-00

EOP 2540D, Functional Recovery of Heat Removal, Revision 022-00

EOP 2541, Appendix 36, ADV Local Operation, Revision 000-02

EOP 2541, Appendix 7, TDAFW Pump Abnormal Startup, Revision 000-01

EOP 2541, Standard Appendices, Revision 006

EOP 35

GA-31, Locally Restoring AFW Flow, Revision 004

EOP 3509, Fire Emergency, Revision 027-00

EOP 3509, Procedure Basis Document, Fire Emergency, Revision 026-00

EOP 3509.1, Control Room, Cable Spreading Area or Instrument Rack Room Fire, Revision 019-00

EOP 3509.1, Procedure Basis Document, Control Room, Cable Spreading Area or Instrument Rack Room Fire, Revision 019-00

EOP 3509.15, North (A) EDG Enclosure or East (A) F.O. Vault Fire, Revision 001

EOP 3509.15, Procedure Basis Document, North (A) EDG Enclosure or East (A) F.O. Vault Fire, Revision 001

EOP 3509.19, ESF Building North RHR Heat Exchanger Cubicle Fire, Revision 000-01

EOP 3509.19, Procedure Basis Document, ESF Building North RHR Heat Exchanger Cubicle Fire, Revision 000-01

EOP 3509.6, Auxiliary Building West MCC/Rod Control/ACU Area Fire, Revision 002-01

EOP 3509.6, Procedure Basis Document, Auxiliary Building West MCC/Rod Control/ACU Area Fire, Revision 002-01

MP-PROC-OPS-OP-2322, Auxiliary Feedwater System, Revision 029

OP 2343, 4160 Volt Electrical System, Revision 022

OP 3341B, Fire Protection Halon System, Revision 005-06

OP 3353.MB4A, Main Board 4A Annunciator Response, Revision 003

OP 3353.MB4B, Main Board 4B Annunciator Response, Revision 005

OP-3322, Auxiliary Feedwater System, Revision 025

SACRG-3, Severe Accident CR Guideline for MP3 B.5.b Initial Event Response, Revision 004

SAG-1, Injection into the Steam Generators, Revision 011

SAG-2, Depressurize the RCS, Revision 003

SAG-9, MP3 B.5.b Event TSC Response (EDMG), Revision 016

SP 2669A, Unit 2 Auxiliary Building Rounds, Revision 063

Completed Tests/Surveillances

722481, B.5.b pump annual preventive maintenance, Completed 7/26/16 C

OP 200.18, Time Critical Action Validation and Verification, Completed 8/4/16

C

SP 600.13, P-82 Electric Fire Pump Annual Operability Demonstration, Completed 5/19/16 &

9/17/16 C

SP 600.14, P-82 Electric Fire Pump Annual Operability Demonstration, Completed 12/4/14 &

2/4/15 C

SP 600.16 Fire Protection System Underground Main Flush & Flow Test, Completed 10/13/10

& 10/9/13 C

SP 600.18, Unit 2 Fire Hose Station Inspection, Completed 6/22/16

C

SP 600.22, Unit 2 Fire Hose Station Flow Test, Completed 2/13/15

C

SP 600.24, Unit 2 Fire Brigade Equipment Inspection, Completed 4/24/16 C

SP 600.24, Unit 2 Fire Brigade Equipment Inspection, Completed 5/25/16 C

SP 600.25, Unit 2 Fire Door Inspection, Completed 6/20/16

C

SP 600.25, Unit 3 Fire Door Inspection, Completed 9/3/15

C

SP 600.28, Fire Brigade Vehicle Equipment Inspection Data Sheet (R1), Completed 5/21/16

C

SP 600.6, Electric Fire Pump M7-8 Monthly Operability Demonstration, Completed 5/10/16 &

6/3/16 C

SP 600.7, Electric Fire Pump M7-8 Annual Operability Demonstration, Completed 12/22/14 &

2/19/15 C

SP 600.8, Diesel Fire Pump M7-7 Monthly Operability Demonstration, Completed 5/13/16 &

6/8/16 C

SP 600.9, Diesel Fire Pump M7-7 Annual Operability Demonstration, Completed 8/6/15 &

6/8/16 C

SP 788A, Fire Pump Diesel Engine Battery Quarterly Surveillance, Completed 6/16/16

C

SP 788B, Fire Pump Diesel Engine Battery 18-Month Surveillance, Completed 6/10/16

C

SP 788C, Fire Pump Diesel Engine Battery Weekly Surveillance, Completed 6/16/16

CSP 600.24, Fire Brigade Equipment Inspection, Completed 6/3/16

SFP 17, Unit 3 Fire Penetration Seal and Barrier Inspection- Group 1, Completed 2/10/06

SFP 17, Unit 3 Fire Penetration Seal and Barrier Inspection- Group 4, Completed 2/9/11

SFP 17, Unit 3 Fire Penetration Seal and Barrier Inspection- Group 4, Completed 10/9/14

SFP 17, Unit 3 Fire Penetration Seal and Barrier Inspection- Group 9, Completed 12/27/13

SFP 21, Unit 2 Appendix R Fire Cage Inventory, Completed 11/25/15

SFP 9, Unit 3 - Fire Extinguisher Inspection Data Sheet - Train B, Completed 6/29/16 SFP 9, Unit 3 - Fire Extinguisher Inspection Data Sheet - Train A, Completed 7/11/16 SFP Procedure 21, Unit 3 Safe Shutdown Fire Cage Inventory, Completed on 11/26/2015

SP 2402CR, Steam Generator Pressure Rack Instrument Calibration, Revision 0, Completed 8/12/14 and 3/16/16

SP 2601P, Unit 2 CVCS Valve Operability Tests from C-10 and C-02, Revision 0, Completed

10/30/15

SP 2610B, Turbine Driven Auxiliary Feed Pump Operational Tests from C-10, Completed 3/2/16

SP 2610E, Atmospheric Dump Valve Testing From C-10, C-70A and C-70B, Completed

10/21/15

SP 2610M, Power Operated Relief Valve Hot Functional Test, Completed 11/1/15

SP 2657, EOP Equipment Inventory, Completed 9/7/15

SP 3442J01, RCS Wide Range Pressure Rack Calibration, Completed 9/16/14 and 2/11/16

SP 3444A02, Steam Generator Water Level Wide Range Calibration, Completed 7/10/13 and 3/11/15

SP 3451Q01, Unit 3 Instrument Rack Room and Fire Pump House - Halon Fire System Test, Completed 2/26/16

SP 3641B.2, IRR Halon System Flow Test, Completed 5/17/15

SP 3641B.2, IRR Halon System Flow Test, Completed 5/8/14

SP 3641D.3, Fire Protection Zone Panel 3B Detector Operability Checks, Completed 1/8/15

SP 3641D.3, Fire Protection Zone Panel 3B Detector Operability Checks, Completed 1/19/13

SP 3641D.3, Fire Protection Zone Panel 3B Detector Operability Checks, Completed 12/21/14

SP 3641D.3, Fire Protection Zone Panel 5C EDG A Area Detector Operability Checks, Completed 2/25/16

SP 3641D.5, Fire Damper Operability Verification, Completed 1/25/06

SP 3641D.5, Fire Damper Operability Verification, Completed 5/8/11

SP 3641D.5, Fire Damper Operability Verification, Completed 9/5/99

SP 3641D.6, Fire Rated Assemblies Inspection, Completed 8/2/15

SP 3641F.1, Functional Check of the East and West Switchgear Breathing Air System, Completed 6/21/15

SP 3672.2-10, Fire Transfer Switch Panel Operational Testing-3RCS*PCV455A, Completed 11/9/14

SP 3672.2-2, Fire Transfer Switch Panel Operational Testing-3HVP*FN1A and FN1C, Completed 3/20/12

SP 3672.2-7, Fire Transfer Switch Panel Operational Testing-3SWP*MOV54A and MOV54C, Completed 8/1/13

SP 3672.2-8, Fire Transfer Switch Panel Operational Testing-3SWP*MOV71A Completed 11/23/15

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVP*FN1A and 3HVP*FN1C, Completed 3/20/12

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVR*FN14A, Completed

10/25/14

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVR*MOD50A, Completed 12/20/12

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVR*ACU1A, Completed

2/22/15

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVY*FN2A, Completed

2/18/12

SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3SWP*MOV71A, Completed 11/23/15

SP 3673.4, Auxiliary Shutdown Panel Operability Test for Charging Injection Path, Completed

5/1/16

SP 3673.4, Auxiliary Shutdown Panel Operability Test for Charging Isolation Path, Completed

5/1/16

SP 3673.4, Auxiliary Shutdown Panel Operability Test for Train A CVCS Components, Completed 1/14/15

SP 3673.4-001, Auxiliary Shutdown Panel Operability Test, Completed 5/8/16

SP 3673.4-004, Auxiliary Shutdown Panel Operability Test Train A Auxiliary Feedwater Components, Completed 2/8/15

SP 3673.4-007, Auxiliary Shutdown Panel Operability Test Train B Auxiliary Feedwater Components, Completed 2/1/15

SP 3673.4-009, Auxiliary Shutdown Panel Operability Test Train B CVCS Components, Completed 5/22/16

SP 3673.4-011, Auxiliary Shutdown Panel Operability Test Train A PORV and Block Valves, Completed 1/9/14

SP 3673.4-014, Auxiliary Shutdown Panel Operability Test Non-Train Related Components, Completed 5/1/16 SP2618C, Smoke and Heat Detector Testing, Auxiliary Building, Completed 3/24/16

SP2618C, Smoke Detector Testing, Switchgear Detector Testing, Facility 1, Completed 5/30/16

SP2618C, Smoke Detector Testing, Turbine Building, Completed 1/19/16

SP2618C, Turbine Bldg. 25'6 Cable Vault and Vertical Shaft Smoke Detector Test, Completed

3/4/16 SP2618D, "A" DG Deluge Systems Design Function Test, Completed 1/12/16

SP2618D, Fire Protection System sprinkler and Deluge Design Function test, Completed

5/20/15 SP2618H, Fire Protection System Deluge Nozzle Flow Test, Completed 7/16/14 SP2618L, Fire Protection Coating Inspection, Completed 8/4/15

SP2618L, TSI Fire Wrap Inspection, Completed 8/7/15

SP2657, Inventory Remote Shutdown Station Storage, Completed 5/13/16

Operating Experience

Evaluations Information Notice 2014-10, Potential Circuit Failure-Induced Secondary Fires or Equipment Damage, dated 9/16/14

Quality Assurance Audits and Self Assessments Audit 15-04, Fire Protection Program, dated 7/15/15

System Health Reports 3341 A, B, C, F - Fire Protections Water, Halon, CO2, Emerg. Breathing Air, dated

10/1/14- 12/31/14 3341 A, B, C, F - Fire Protections Water, Halon, CO2, Emerg. Breathing Air, dated

10/1/15- 12/31/15 3341D - Fire Detection, dated 10/1/14- 12/31/14

3341D - Fire Detection, dated 10/1/15- 12/31/15

ELU System Health Report, 1

St Quarter 2016

ELU System Health Report, 4

th Quarter 2015 Program/Comp Health Report FP- Fire Protection - Including Appendix R, 4

th Quarter 2015 Program/Comp Health Report FP- Fire Protection - Including Appendix R, 1

st Quarter 2016 System Health Report 2352, 3720B - Safe Shutdown Lighting, 1

st Quarter 2016 System Health Report 2352, 3720B - Safe Shutdown Lighting, 4

th Quarter 2015 U 2 Fire Protection & Deluge, CO2 Alterex, Halon Supression, 4

th Quarter 2014 U 2 Fire Protection & Deluge, CO2 Alterex, Halon Supression, 4

th Quarter 2015 Unit 2 AC and DC Systems, 4

th qtr. 2015 and 1

st Quarter 2016 Unit 3 AC and DC Systems, 4

th qtr. 2015 and 1

st Quarter 2016

Drawings

and Wiring Diagrams

2179-30276, U3 Generator Seal Oil System Em ergency Seal Oil pump 3GMO-P2 Control, Revision 5 12179-FIG-77B, Fire Hazard Analysis Plan Elevation 24 Feet 6 inch, Revision 6

2179-FIG-77C, Fire Hazard Analysis Plant Elevation 38 Feet 6 inch, Revision 11

203-24070, Sheet 10, RCP Oil Collection System Details for RCP Motor in Cubicle "A", Revision 2 25203-24070, Sheet 11, RCP Oil Collection System Details for RCP Motor in Cubicle "A", dated 5/16/95 25203-24070, Sheet 12, RCP Oil Collection System Details for RCP Motor in Cubicle "A", dated 4/19/95 25203-24070, Sheet 13, RCP Oil Collection System Details for RCP Motor in Cubicle "A", dated 4/20/95 25203-28500, Sht.356, Unit 2

PT-1023B Steam Generator Pressure Loop Diagram, Revision 10

203-30001, Unit 2 Main Single Line Diagram, Revision 40

203-30005, Unit 2 Single Line Meter and Relay Diagram 4.16kV Emergency Buses 24C and

24D, Revision 21 25203-30009, Unit 2 Single Line Meter and Relay Diagram 4.16kV Emergency Buses 25E and 24G, Revision 13 25203-30022, Sht. 3, Unit 2 DV20 125Vdc and 120Vac Distribution Panel Schedule, Revision

25203-30023, U2 Single Line Diagram 125VDC System-Turbine Battery, Revision 9

203-30024, U2 Single Line Diagram 125VDC Emergency & 120VAC Vital Systems, Revision

25203-30053, Sheet 1, U2 Schematic Diagram 125VDC Switchgear Bus D01, Revision 7

203-30053, Sheet 3, U2 Schematic Diagram 125VDC Switchgear Bus D02, Revision 9

203-30053, Sheet 5, U2 Switchgear Diagram 125VDC Switchgear Bus D03, Revision 10

203-30102, Unit 2 Instrument Rack Loading Diagram Fire Shutdown Panel C09, Revision 3 25203-32002, Sh. 16, 4.16kV Switchgear Kirk Key Interlocks, Revision 5 25203-32006, Sheet 13, U2 Magnetic Starter Elementary Diagram, Revision 8

203-32009, Sht. 37, Unit 2 Charging Line Distribution Solenoid Valve CH519, Revision 9

203-32009, Sht. 41, Unit 2 Charging Pump Control MP18B, Revision 23

203-32009, Sht. 42A, Unit 2 Charging Pump Control MP18B, Revision 3

203-32009, Sht. 6, Unit 2 Volume Control Tank Discharge MOV CH501, Revision 13 25203-34051, Unit 2 Auxiliary Building Miscellaneous Plan Section and Details, Revision 40 25203-39076, Sheet 9A, U2 Magnetic Starter Elementary Diagram, Revision 1

203-39076, Sheet 9B, U2 Magnetic Starter Elementary Diagram, Revision 1

203-39220, Sht. 1B, Unit 2 Instrument Rack Loading Diagram Spec 200 Cabinet RC30B, Revision 19 25203-39352, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP1 & Static Sw. VS1, Revision 5 25203-39353, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP2 & Static Sw. VS2, Revision 5 25203-39354, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP3 & Static Sw. VS3, Revision 5 25203-39355, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP4 & Static Sw. VS4, Revision 3 25203-39356, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP5, Revision 5

25203-39357, Sheet 1, U2 One Line Diagram, 15KVA Inverter VIP6, Revision 6 25203-39367, Sheet 6, U2 Schematic Totalizing Box Turbine Battery Charger 201D/DC4, Revision 2 25205-25003, Station Fire Loop Operating & Hydraulic Analysis Schematic, Revision 14

212-24036, Fire Stop & Seals Map Locations, Revision 0

212-24037, Fire Stop & Seals Map Locations, Revision 0

212-24273, Wall Pene. Map Aux. BLDG. EL. 45'-6", Revision 2 25212-29367

SH 20, Fire Protection & Detection Systems, dated 6/2/75 25212-29680

SH.0010,

TCO-003 High Density Silicone Elastomer Fire, Air, and/or Radiation Seal for Electrical Blockout Openings, dated 8/20/84 25212-29680

SH.0023,

TCO-050 Silicone Foam Fire or Air Seals for Sleeve, Conduit, Cast or Core Bored Openings up to 5" Dial, dated 1/26/85

212-30001, Unit 3 Main One Line Diagram, Revision 26 25212-30004, Unit 3 Main One Line Diagram 4160V Normal and Emergency Buses, Revision

25212-30010, Unit 3 6900V One Line Diagram Bus 35A and 35B, Revision 20

212-30011, Unit 3 6900V One Line Diagram Bus 35C and 35D, Revision 21 25212-30027, Sht. 3, Unit 3 480V Motor Control Center One Line Diagram Auxiliary Building, Revision 44 25212-30272, Sht. 29A, Unit 3 Feedwater System Steam Generator 3RCS*SG1A Wide Range Level Indication, Revision 8 25212-30272, Sht. 30, Feedwater System Steam Generator 3RCS*SG1A, Revision 5

212-30343, Sht. 10A, Unit 3 Reactor Coolant System Channel 1 Wide Range Pressure Loop Diagram, Revision 6 25212-30343, Sht. 10B, Unit 3 Reactor Coolant System Channel 1 Wide Range Pressure Loop Diagram, Revision 5 25212-30343, Sht. 10C, Unit 3 Reactor Coolant System Channel 1 Wide Range Pressure Loop Diagram, Revision 5 25212-30343, Sht. 11, Unit 3 Reactor Coolant System Channel 1 Wide Range Pressure Loop Diagram, Revision 5 25212-30379, Sheet 8, U3 Turbine Generator Lube Oil System Emergency Bearing Oil Pump Control, Revision 3 25212-3200, Sht. 7, Elementary Diagram Reactor Head Vent Isolation Valves 3RCS*SV8095A(B), Revision 6 25212-32001, Elementary Diagram 480V MCC Charging Header Isolation Valve 2CHS*MV8438A, Revision 15 25212-32001, Sheet 6CI, U3 Elementary Diagram 125VDC Emergency Bearing Oil Pump [3TML-P1], Revision 10 25212-32001, Sheet 6CS, U3 Elementary Diagram 125VDC Generator Emergency Seal Oil Pump [3GMO-P2], Revision 14 25212-32001, Sht. 7DX, Elementary Diagram Letdown Line Isolation Valves 3RCS*LCV459 and 3RCS*LCV460, Revision 9 25212-32068, U3 Elementary Diagram Diesel Driven Fire Pump M7-7 Control Circuit, Revision

25212-39002, Sheet 1020, U3 DC Starter Emergency Seal Oil Elementary, Revision D 25212-39002, Sheet 1021, U3 DC Starter Emergency Seal Oil Schematic, Revision C 25212-39002, Sheet 1062, U3 Emergency Bearing Oil Pump Starter-Outline Schematic & Conn.

Diagram, Revision E

SKE-3.1-ELEC DIST, Emergency System One Line Diagram for Appendix R, Revision 2

Piping and Instrumentation Diagrams 25203-26005, Sht. 2, Unit 2 P&ID Feed System, Revision 73

203-26008, Sh. 2, Piping and Instrumentation Diagram Service Water, Revision 114

203-26011, Fire Protection, Revision 57

203-26014, Sht. 1, Unit 2 P&ID Reactor Coolant System, Revision 41 25203-26014, Sht. 2, Unit 2 P&ID Reactor Coolant System, Revision 46 25203-26017, Sht. 1, Unit 2 P&ID Charging System, Revision 63

212-25008, Yard Water & Fire Protection Piping, Revision 29

212-25009, Yard Water & Fire Protection Piping, Revision 24

212-26902, Sht. 1, Unit 3 P&ID Reactor Coolant System, Revision 33 25212-26902, Sht. 3, Unit 3 P&ID Reactor Coolant System, Revision 25 25212-26904, Sht. 1, Unit 3 P&ID Chemical and Volume Control, Revision 54

212-26904, Sht. 2, Unit 3 P&ID Chemical and Volume Control, Revision 17

212-26905, Sht. 1, Unit 3 P&ID Charging Pump Seal and Lubrication, Revision 33

212-26921, Sht. 1, Unit 3 P&ID Component Cooling Water, Revision 33 25212-26970, Fire Protection System, Revision 12

Pre-Fire Plans Fire Area

AB-6, Auxiliary Building West MCC and Rod Control Area, Revision 0

Fire Area

CB-11, Control Building Instrument Rack Room Underfloor Area, Revision 0

Fire Area

EG-3, Emergency Generator North Emergency generator Enclosure, Revision 0 Fire Area

ESF-3, Engineered Safety Features Building North Residual Heat Removal Heat Exchanger Cubicle, Revision 0 MP2 Fire Fighting Strategies, Unit 2, Fire Area A-15, Diesel Generator A Cubicle, Revision 0

MP2 Fire Fighting Strategies, Unit 2, Fire Area A-32, Air Handling Units 38'6, Revision 0

MP2 Fire Fighting Strategies, Unit 2, Fire Area T-7, 69. And 4.16 KV Switchgear Room, Revision

MP2 Fire Fighting Strategies, Unit 2, Fire Area T-9, East 45' Cable Vault (Z1 train), Revision 0

Fire Drills and Critiques Fire in Building 454, Completed 6/7/16

Fire in U1 Maintenance Shop, Completed 12/14/15 Fire in U2 H2 Seal Oil Skid Pass, Completed 6/18/15 Fire in U2 Intake, Completed 12/4/15

Fire in U2 Lube Oil Room, Completed 6/9/15

Fire in U2 Upper 4160 Switch Gear, Completed 4/28/15

Fire in U3 Maintenance Shop, Completed 12/12/15

Fire Brigade Training B5b Familiarization PowerPoint Presentation

B5b Hands-On Training attendance records, dated 5/12/15 and 11/17/15

Beyond Design Basis, Non-Licensed Operator Training Presentation

Operator Safe Shutdown Training 15605L,

EOP 3509.1 Self-Guided in Plant Walkdown, Revision 0

AOP 2559 - Fire

AOP 2579A/AA - Appendix R Fire in R-1, Aux Bldg including Control Room/Computer Rooms/25' Cable Vault, Millstone Unit 2 Licensed Operator Training Program Slides ASP115C, Auxiliary Shutdown Equipment/Auxiliary Shutdown Panel Lesson Plan, Revision 3 C15506N, MP3*NLCT*EOP 3509.1, Revision 0 Common Operating Procedure 200.18 Time Critical Action Validation and Verification Slides, dated 7/12/16 JPM P003, Isolate Emergency Bus 34C in Accordance with

EOP 3509.1, Revision 7

JPM P011 (MC-00094), Primary Side Plant Equipment Operator (PEO) Actions on a Control Room Evacuation (Parts 1 and 2), Revision 9/0 JPM P012, Secondary Side PEO Actions on a Control Room Evacuation, Revision 6 JPM P015, Secondary Side PEO Actions on a Control Room Evacuation due to Fire, Revision 8

JPM P173, Aligning the Fire Transfer Switch Panel and Auxiliary Shutdown Panel in Response to a Fire, Revision 2 JPM P188, Installation of 3CHS-PI102T, Revision 0 JPM P209, Cross-Connect Service Water to East Switchgear Ventilation, Revision 1 SEG S13406L, Respond to a Control Room, Cable Spreading Area or Instrument Rack Room Fire, Revision 0 SEG S15304L, Fire in Instrument Rack Room, Revision 0

Unit 2 Licensed Operator Requalification Program Attendance Sheet for Cycle 16-3, 5/10 - 6/17

Hot Work and Ignition Source Permits, and Tr ansient Combustible Permits and Evaluations

29633-12-FP 30391-13-IS 31960-15-IS 41224-12-FP

41316-12-FP 41399-12-IS 43879-15-FP 43965-15-IS

44356-16-FP 44385-16-IS 44389-16-IS 44390-16-IS 44499-16-FP

Corrective Action Program Documents (Condition Reports)

463259

515160

520964

522469

2722

522740

522848

522850

523785

527755

530987

541980

541983

553343

557088

576367

578178

578333

581890

582625

2652

582665

1004974

1009069

1037462

1041883

1042283*

1043063*

1043417*

1043422*

1043425*

1043455*

1043458*

1043959*

1044278*

1044301*

1044326*

1044332*

1044334*

1044348*

1044422*

1044536*

1044760*

NRC identified during this inspection.

Work Orders

53M20807693 53012768647 53102490410 53102502011

53102582983 53102605405 53102649190 53102656386

53102659739 53102669361 53102693811 53102695870

53102698825 53102698915 53102698922 53102698928

53102698931 53102716240 53102716256 53102732991 53102735138 53102759052 53102760642 53102764120 53102786767 53102814722 53102846681 53102853315

53102854686 53102861679 53102871440 53102873143

53102887195 53102892290 53102900241 53102905692

53102914238 53102952946 53102958935

Vendor Manuals 25212-902-001, Vendor Technical Manual for Emergency Lighting from Exide, Holophane, Dualite, Birns, Revision 6 TI 2AI-130, Spec 200 Current-To-Voltage Converters, dated 10/77

Industry Standards NFPA 10-1968, Installation for Portable Fire Extinguishers

NFPA 13-1971, Installation of Sprinkler Systems

NFPA 14-1978, Installation of Standpipe and Hose Systems

NFPA 15-1985, Water Spray for Fixed Systems for Fire Protection NFPA 27-1975, Private Fire Brigade NFPA 72D-1986, Maintenance and Use of Proprietary protective Signaling Systems

NFPA 72E-1984, Automatic Fire Detectors

Miscellaneous Documents

Aid Agreement letter Between Millstone and the Waterford Fire Service, dated 8/6/15 Electrical Cable and Conduit Routing Information - SAFE

Fire and Hose-Stream tests for Penetration Seal Systems, dated 4/82

Fire Qualification Test on Floor Penetration Seals, dated 11/30/79

Hazard Evaluation Sheet Building - CB, dated 12/11/85

Millstone Site Fire Protection Active Impairment List, dated 7/11/16 Millstone Site Fire Protection Active Impairment List, dated 7/26/16 Millstone Site Fire Protection Active Impairment List, dated 7/27/16

Waterford Ambulance Service

Memorandum of Understanding (MOU), dated 8/5/15

Waterford Fire Service MOU, dated 8/6/15

Waterford Police Department MOU, dated 9/14/15

LIST OF ACRONYMS

ADAMS Agencywide Documents Access and Management System

ADV Atmospheric Dump Valve

AFW Auxiliary Feedwater

AOP Abnormal Operating Procedure

BTP Branch Technical Position

CAP Corrective Action Program

CFR Code of Federal Regulations

CMEB Chemical Engineering Branch

CO 2 Carbon Dioxide

CONVEX Connecticut Valley Electric Exchange

CR Condition Report

CSD Cold Shutdown

DC Direct Current

Dominion Dominion Nuclear Connecticut, Inc.

DRS Division of Reactor Safety

EDG Emergency Diesel Generator

EOP Emergency Operating Procedure

FA Fire Area

FHA Fire Hazards Analysis

FPP Fire Protection Program

FSAR Final Safety Analysis Report

FZ Fire Zone

IEEE Institute of Electrical and Electronics Engineering

IMC Inspection Manual Chapter

IP Inspection Procedure

IPEEE Individual Plant Examination of External Events

IR Inspection Report

LER Licensee Event Report

LOOP Loss of Offsite Power

Millstone Millstone Power Station Unit 2 and Unit 3

NCV Non-Cited Violation

NFPA National Fire Protection Association

NRC Nuclear Regulatory Commission

OMA Operator Manual Action

P&ID Piping and Instrumentation Drawing

PARS Publicly Available Records System

RAS Reasonable Assurance of Safety

SBO Station Blackout

SDP Significance Determination Process

SER Safety Evaluation Report

SFP Site Fire Protection

SG Steam Generator

UFSAR Updated Final Safety Analysis Report V Volts V dc Voltage Direct Current

@@ Line 18: / Line 18: @@
 =Text=
-{{#Wiki_filter:
+{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713 January 4, 2017
-[[Issue date::January 4, 2017]]
 Mr. Daniel Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
 Glen Allen, VA 23060-6711
 SUBJECT: ERRATA FOR MILLSTONE POWER STATION - NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000336/2016007 AND 05000423/2016007 AMENDED TO 05000336/2016008 AND 05000423/2016008

IR 05000336/2016007: Difference between revisions

Revision as of 08:16, 17 May 2019

Text

Dear Mr. Stoddard:

REGION I

SUMMARY OF FINDINGS

Cornerstone: Mitigating Systems

Other Findings

REPORT DETAILS

REACTOR SAFETY

1R05 Fire Protection (IP 71111.05T)

.01 Protection of Safe Shutdown Capabilities

a. Inspection Scope

b. Findings

Introduction:

Description:

Analysis:

Enforcement:

.02 Passive Fire Protection

a. Inspection Scope

b. Findings

.03 Active Fire Protection

a. Inspection Scope

b. Findings

.04 Protection from Damage from Fire Suppression Activities

a. Inspection Scope

b. Findings

.05 Post-Fire Safe Shutdown Capability - Normal and Alternative

a. Inspection Scope

b. Findings

.06 Circuit Analysis

a. Inspection Scope

b. Findings

.07 Communications

a. Inspection Scope

b. Findings

.08 Emergency Lighting

a. Inspection Scope

b. Findings

.09 Cold Shutdown Repairs

a. Inspection Scope

b. Findings

.10 Compensatory Measures

a. Inspection Scope

b. Findings

.11 Fire Protection Program Changes

a. Inspection Scope

b. Findings

.12 Control of Transient Combustibles and Ignition Sources

a. Inspection Scope

b. Findings

.13 Large Fires and Explosions Mitigation Strategies

a. Inspection Scope

b. Findings

OTHER ACTIVITIES

4OA2 Identification and Resolution of Problems (IP 71152)

.01 Corrective Actions for Fire Protection Deficiencies

a. Inspection Scope

b. Findings

4OA3 Follow-up of Events and Notices of Enforcement Discretion (IP 71153)

.1 (Closed) Licensee Event Report (LER) 05000336/2013-003-00 (Unit 2):

.2 (Closed) Licensee Event Report (LER) 05000336/2014-002-00 (Unit 2):

.3 (Closed) Licensee Event Report (LER) 05000423/2014-002-00 (Unit 3):

4OA6 Meetings, Including Exit

Exit Meeting Summary

4OA7 Licensee-Identified Violations

.1 LER 05000336/2013-003-00 (Unit 2) describes an unanalyzed condition in which Dominion identified their DC ammeter circuits were unfused.

.2 LER 05000336/2014-002-00 (Unit 2) describes an unanalyzed condition in which Dominion identified DC motor control circuits were unfused.

.3 LER 05000423/2014-002-00 (Unit 3) describes an unanalyzed condition in which Dominion identified DC motor control circuits were unfused.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

NRC Personnel

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

Opened and Closed

Closed

Discussed

LIST OF DOCUMENTS REVIEWED

Procedures