ML16258A175
| ML16258A175 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/14/2016 |
| From: | Christopher Cahill Engineering Region 1 Branch 3 |
| To: | Heacock D Dominion Resources |
| References | |
| IR 2016007 | |
| Download: ML16258A175 (37) | |
See also: IR 05000336/2016007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD.
KING OF PRUSSIA, PA 19406-2713
September 14, 2016
Mr. David A. Heacock
President and Chief Nuclear Officer
Dominion Resources
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT: MILLSTONE POWER STATION - NRC TRIENNIAL FIRE PROTECTION
INSPECTION REPORT 05000336/2016007 AND 05000423/2016007
Dear Mr. Heacock:
On August 11, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial fire
protection inspection at Millstone Power Station, Units 2 and 3. The enclosed inspection report
documents the inspection results, which were discussed on August 11, 2016, with Mr. John
Daugherty, Site Vice President - Millstone Power Station, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commission's rules and regulations, and with the conditions of your
license. The inspectors reviewed selected procedures and records, observed activities, and
interviewed station personnel. The inspectors also reviewed mitigation strategies for addressing
large fires and explosions.
Based on the results of this inspection, one finding of very low safety significance (Green) was
identified. This finding was determined to be a violation of NRC requirements. However,
because of its very low safety significance, and because it was entered into your corrective
action program, the NRC is treating this finding as a non-cited violation (NCV) consistent with
Section 2.3.2 of the NRC Enforcement Policy. If you contest any NCV in this report, you should
provide a written response within 30 days of the date of this inspection report, with the basis for
your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk,
Washington D.C. 20555-0001; with copies to the Regional Administrator, Region I; the Director,
Office of Enforcement; and the NRC Resident Inspector at Millstone Power Stations.
D. Heacock 2
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's
"Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be
available electronically for public inspection in the NRC Public Document Room or from the
Publicly Available Records System (PARS) component of the NRC's document system,
Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible
from the NRC Web Site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic
Reading Room).
Sincerely,
/RA/
Christopher G. Cahill
Acting Branch Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-336, 50-423
Enclosure:
Inspection Report 05000336/2016007
and 05000423/2016007
w/Attachment: Supplemental Information
cc w/encl: Distribution via ListServ
Non-Sensitive Publicly Available
SUNSI Review
OFFICE RI/DRS RI/DRS RI/DRP RI/DRS
NAME JPatel WCook GDentel CCahill
DATE 09/09/16 09/09/16 09/09/16 09/14/16
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket Nos.: 50-336, 50-423
Report Nos.: 05000336/2016007 and 05000423/2016007
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
i Enclosure
SUMMARY OF FINDINGS
IR 05000336/2016007, 05000423/2016007; 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 Dominions 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)
ii
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
Dominions corrective action program (CAP). The violations and corrective action tracking
numbers are listed in Section 4OA7 of this report.
iii
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 Dominions 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 Report (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.
2
1. 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 licensees
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,
3
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 Dominions immediate and longer
term corrective actions appropriate.
Analysis: Dominions 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
4
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. Dominions 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 Dominions CAP (CR 1043458), this issue is being treated as an NCV
consistent with Section 2.3.2 of the Enforcement Policy. (NCV 05000336/2016007-01,
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
5
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 CO2 and
Halon suppression systems for the areas protection. The team walked down accessible
potions of the CO2 and Halon systems, including storage tanks and supply systems, to
6
independently assess the material condition, operational lineup, and availability of the
systems. The team also reviewed and walked down the associated firefighting
strategies and CO2 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 corrective 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 activities 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
7
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 components 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 performed 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;
8
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 licensees 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 teams 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
9
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
a. Inspection Scope
The team reviewed safe shutdown procedures, the safe shutdown analysis, and
associated documents to verify an adequate method of communications would be
available to plant operators following a fire. During this review the team considered the
effects of ambient noise levels, clarity of reception, reliability, and coverage patterns.
The team also inspected the designated emergency storage lockers to verify the
availability of portable radios for the fire brigade and for plant operators. The team also
verified that communications equipment such as repeaters and transmitters would not be
affected by a fire.
10
b. Findings
No findings were identified.
a. Inspection Scope
The team observed the placement and coverage area of eight-hour emergency lights
throughout the selected fire areas to evaluate their adequacy for illuminating access and
egress pathways and any equipment requiring local operation or instrumentation
monitoring for post-fire safe shutdown. The team also verified that the battery power
supplies were rated for at least an eight-hour capacity. Preventive maintenance
procedures, the vendor manual, completed surveillance tests, and battery replacement
practices were also reviewed to verify that the emergency lighting was being maintained
consistent with the manufacturers recommendations and in a manner that would ensure
reliable operation.
b. Findings
No findings were identified.
.09 Cold Shutdown Repairs
a. Inspection Scope
The team reviewed Dominion's dedicated repair procedures, for components which
might be damaged by fire and were required to achieve post-fire cold shutdown (CSD).
The team evaluated selected CSD repairs to determine whether they could be achieved
within the time frames assumed in the design and licensing bases. In addition, the team
verified whether the necessary repair equipment, tools, and materials (e.g., pre-cut
cables with prepared attachment lugs) were available and accessible on site.
b. Findings
No findings were identified.
.10 Compensatory Measures
a. Inspection Scope
The team verified compensatory measures were in place for out-of-service, degraded, or
inoperable fire protection and post-fire safe shutdown equipment, systems, or features
(e.g., detection and suppression systems and equipment, passive fire barriers, pumps,
valves, or electrical devices providing safe shutdown functions or capabilities). The
team evaluated whether the short term compensatory measures adequately
compensated for the degraded function or feature until appropriate corrective action
11
could be taken and that the licensee was effective in returning the equipment to service
in a reasonable period of time.
b. Findings
No findings were identified.
.11 Fire Protection Program Changes
a. Inspection Scope
The team reviewed recent changes to the approved fire protection program to verify that
the changes did not constitute an adverse effect on the ability to safely shutdown.
b. Findings
No findings were identified.
.12 Control of Transient Combustibles and Ignition Sources
a. Inspection Scope
The team reviewed the licensees procedures and programs for the control of ignition
sources and transient combustibles to assess their effectiveness in preventing fires and
in controlling combustible loading within limits established in the FHA. A sample of hot
work and transient combustible control permits were also reviewed. The team
performed plant walkdowns to verify that transient combustibles and ignition sources
were being implemented in accordance with the administrative controls.
b. Findings
No findings were identified.
.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.
12
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.
4. 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
13
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
manufacturers 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.
14
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 manufacturers 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.
15
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 Dominions corrective action program (CR530987), this violation is
16
being treated as a Green, licensee-identified NCV consistent with the NRCs
.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
Dominions corrective action program (CR541980), this violation is being treated as a
Green, licensee-identified NCV consistent with the NRCs 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
17
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 Dominions corrective action program
(CR541983), this violation is being treated as a Green, licensee-identified NCV
consistent with the NRCs Enforcement Policy.
ATTACHMENT: SUPPLEMENTAL INFORMATION
A-1
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
05000336/2016007-01 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
05000336/2013-003-00 LER Postulated DC Ammeter Circuit Hot Shorts (Unit 2),
(Section 4OA3.1)
05000336/2014-002-00 LER DC Circuit Hot Shorts (Unit 2), (Section 4OA3.2)
05000423/2014-002-00 LER DC Circuit Hot Shorts (Unit 3), (Section 4OA3.3)
Discussed
None
Attachment
A-2
LIST OF DOCUMENTS REVIEWED
Fire Protection Licensing Documents
25203-SP-M2-SU-1046, Unit 2 Appendix R Compliance Report, Revision 1
25212-BTP-9.5-1, Unit 3 Branch Technical Position 9.5-1 Compliance Report, Revision 4
25212-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
10 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
A-3
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
A-4
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
A-5
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
A-6
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 &
12/4/15
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 &
12/19/15
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
A-7
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
12/22/15
SP 3673.2, Unit 3 Fire Transfer Switch Panel Operational Testing for 3HVY*FN2A, Completed
12/18/12
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
A-8
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. 256 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, 1St Quarter 2016
ELU System Health Report, 4th Quarter 2015
Program/Comp Health Report FP- Fire Protection - Including Appendix R, 4th Quarter 2015
Program/Comp Health Report FP- Fire Protection - Including Appendix R, 1st Quarter 2016
System Health Report 2352, 3720B - Safe Shutdown Lighting, 1st Quarter 2016
System Health Report 2352, 3720B - Safe Shutdown Lighting, 4th Quarter 2015
U 2 Fire Protection & Deluge, CO2 Alterex, Halon Supression, 4th Quarter 2014
U 2 Fire Protection & Deluge, CO2 Alterex, Halon Supression, 4th Quarter 2015
Unit 2 AC and DC Systems, 4th qtr. 2015 and 1st Quarter 2016
Unit 3 AC and DC Systems, 4th qtr. 2015 and 1st Quarter 2016
A-9
Drawings and Wiring Diagrams
12179-30276, U3 Generator Seal Oil System Emergency Seal Oil pump 3GMO-P2 Control,
Revision 5
12179-FIG-77B, Fire Hazard Analysis Plan Elevation 24 Feet 6 inch, Revision 6
12179-FIG-77C, Fire Hazard Analysis Plant Elevation 38 Feet 6 inch, Revision 11
25203-24070, 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
25203-30001, Unit 2 Main Single Line Diagram, Revision 40
25203-30005, 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
21
25203-30023, U2 Single Line Diagram 125VDC System-Turbine Battery, Revision 9
25203-30024, U2 Single Line Diagram 125VDC Emergency & 120VAC Vital Systems, Revision
39
25203-30053, Sheet 1, U2 Schematic Diagram 125VDC Switchgear Bus D01, Revision 7
25203-30053, Sheet 3, U2 Schematic Diagram 125VDC Switchgear Bus D02, Revision 9
25203-30053, Sheet 5, U2 Switchgear Diagram 125VDC Switchgear Bus D03, Revision 10
25203-30102, 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
25203-32009, Sht. 37, Unit 2 Charging Line Distribution Solenoid Valve CH519, Revision 9
25203-32009, Sht. 41, Unit 2 Charging Pump Control MP18B, Revision 23
25203-32009, Sht. 42A, Unit 2 Charging Pump Control MP18B, Revision 3
25203-32009, 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
25203-39076, Sheet 9B, U2 Magnetic Starter Elementary Diagram, Revision 1
25203-39220, 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
A-10
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
25212-24036, Fire Stop & Seals Map Locations, Revision 0
25212-24037, Fire Stop & Seals Map Locations, Revision 0
25212-24273, 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
25212-30001, Unit 3 Main One Line Diagram, Revision 26
25212-30004, Unit 3 Main One Line Diagram 4160V Normal and Emergency Buses, Revision
20
25212-30010, Unit 3 6900V One Line Diagram Bus 35A and 35B, Revision 20
25212-30011, 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
25212-30343, 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
2
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
A-11
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
25203-26008, Sh. 2, Piping and Instrumentation Diagram Service Water, Revision 114
25203-26011, Fire Protection, Revision 57
25203-26014, 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
25212-25008, Yard Water & Fire Protection Piping, Revision 29
25212-25009, Yard Water & Fire Protection Piping, Revision 24
25212-26902, 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
25212-26904, Sht. 2, Unit 3 P&ID Chemical and Volume Control, Revision 17
25212-26905, Sht. 1, Unit 3 P&ID Charging Pump Seal and Lubrication, Revision 33
25212-26921, 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 386, Revision 0
MP2 Fire Fighting Strategies, Unit 2, Fire Area T-7, 69. And 4.16 KV Switchgear Room,
Revision 0
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
A-12
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 Transient 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
522722 522740 522848 522850
523785 527755 530987 541980
541983 553343 557088 576367
578178 578333 581890 582625
582652 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.
A-13
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
A-14
LIST OF ACRONYMS
ADAMS Agencywide Documents Access and Management System
ADV Atmospheric Dump Valve
AOP Abnormal Operating Procedure
BTP Branch Technical Position
CAP Corrective Action Program
CFR Code of Federal Regulations
CMEB Chemical Engineering Branch
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
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
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
UFSAR Updated Final Safety Analysis Report
V Volts
V dc Voltage Direct Current