IR 05000336/2018001: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:D. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSLYVANIA 19406-2713
{{#Wiki_filter:D.


May 3, 2018 Mr. Daniel Senior Vice President and Chief Nuclear Officer
UNITED STATES NUCLEAR REGULATORY COMMISSION May 3, 2018


Dominion Energy, Inc. Innsbrook Technical Center 5000 Dominion Blvd.
==SUBJECT:==
 
MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT 05000336/2018001 AND 05000423/2018001
Glen Allen, VA 23060-6711
 
SUBJECT: MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT 05000336/2018001 AND 05000423/2018001


==Dear Mr. Stoddard:==
==Dear Mr. Stoddard:==
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No NRC-identified or self-revealing findings were identified during this inspection.
No NRC-identified or self-revealing findings were identified during this inspection.


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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely,
Sincerely,
/RA/ Daniel L. Schroeder, Chief  
/RA/
 
Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49
Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49


===Enclosure:===
===Enclosure:===
Inspection Report 05000336/2018001 and 05000423/2018001  
Inspection Report 05000336/2018001 and 05000423/2018001


==Inspection Report==
==Inspection Report==
 
Docket Numbers: 50-336 and 50-423 License Numbers: DPR-65 and NPF-49 Report Numbers: 05000336/2018001 and 05000423/2018001 Enterprise Identifier: I-2018-001-0082 Licensee: Dominion Energy Nuclear Connecticut, Inc. (Dominion)
Docket Numbers: 50-336 and 50-423  
Facility: Millstone Power Station, Units 2 and 3 Location: P.O. Box 128 Waterford, CT 06385 Inspection Dates: January 1 to March 31, 2018 Inspectors: J. Fuller, Senior Resident Inspector L. McKown, Resident Inspector C. Highley, Resident Inspector H. Anagnostopoulos, Senior Health Physicist J. Brand, Reactor Inspector Approved By: Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure
 
License Numbers: DPR-65 and NPF-49  
 
Report Numbers: 05000336/2018001 and 05000423/2018001  
 
Enterprise Identifier: I-2018-001-0082  
 
Licensee: Dominion Energy Nuclear Connecticut, Inc. (Dominion)  
 
Facility: Millstone Power Station, Units 2 and 3  
 
Location: P.O. Box 128 Waterford, CT 06385  
 
Inspection Dates: January 1 to March 31, 2018 Inspectors: J. Fuller, Senior Resident Inspector L. McKown, Resident Inspector C. Highley, Resident Inspector H. Anagnostopoulos, Senior Health Physicist J. Brand, Reactor Inspector
 
Approved By: Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects  
 
2


=SUMMARY=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominion's performance at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified non-cited violations are documented in report section 71153.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominions performance at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified non-cited violations are documented in report section 71153.


No findings or more-than-minor violations were identified.
No findings or more-than-minor violations were identified.


Additional Tracking Items Type Issue number Title Report Section Status LER 05000336/2016-001-00 Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open 71153 Closed 3
Additional Tracking Items Type     Issue number             Title                         Report           Status Section LER       05000336/2016-001-00     Turbine Driven Auxiliary       71153            Closed Feedwater Pump Room HELB Door Left Open


=PLANT STATUS=
=PLANT STATUS=
Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.


=====INSPECTION SCOPES==
===Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light-Water Reactor Inspection Program - Operations Phase."


The inspectors performed plant status activities described in IMC 2515, Appendix D, "Plant Status," and conducted routine reviews using IP 71152, "Problem Identification and Resolution.The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Dominion Energy's performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
==INSPECTION SCOPES==
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Dominion Energys performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.


==REACTOR SAFETY==
==REACTOR SAFETY==
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The inspectors evaluated system configurations during partial walkdowns of the following systems/trains at Unit 3:
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains at Unit 3:
: (1) 'B' emergency diesel generator (EDG) air start system on January 22, 2018
: (1) B emergency diesel generator (EDG) air start system on January 22, 2018
: (2) Charging system with both 'A' and  
: (2) Charging system with both 'A' and 'B' pumps in service on January 31, 2018
'B' pumps in service on January 31, 2018
: (3) Control building chiller service water booster pump trains on February 6, 2018
: (3) Control building chiller service water booster pump trains on February 6, 2018
: (4) Auxiliary feedwater injection lines on February 12, 2018
: (4) Auxiliary feedwater injection lines on February 12, 2018
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{{IP sample|IP=IP 71111.05A/Q|count=7}}
{{IP sample|IP=IP 71111.05A/Q|count=7}}


The inspectors evaluated fire protection program implementation in the following selected  
The inspectors evaluated fire protection program implementation in the following selected areas:
 
areas:  
 
Unit 2
Unit 2
: (1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven auxiliary feedwater pump room) on January 24, 2018
: (1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven auxiliary feedwater pump room) on January 24, 2018
: (2) Fire area A-21, west direct current switchgear room on January 26, 2018
: (2) Fire area A-21, west direct current switchgear room on January 26, 2018
: (3) Fire area A-15 and A-16, 'A' and 'B' EDG rooms on February 2, 2018
: (3) Fire area A-15 and A-16, A and B EDG rooms on February 2, 2018
: (4) Fire area T-10, upper vital switchgear room on February 8, 2018 Unit 3
: (4) Fire area T-10, upper vital switchgear room on February 8, 2018 Unit 3
: (5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [21'6"] on January 10, 2018
: (5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [216] on January 10, 2018
: (6) Fire area CB-8, cable spreading area on January 23, 2018
: (6) Fire area CB-8, cable spreading area on January 23, 2018
: (7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29, 2018
: (7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29, 2018
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{{IP sample|IP=IP 71111.11|count=2}}
{{IP sample|IP=IP 71111.11|count=2}}


The inspectors observed and evaluated Unit 2 operator requalification training on reactor coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586), rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-2525), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips, heater drain pump trips, and feed water heater tube leak on February 6, 2018.
The inspectors observed and evaluated Unit 2 operator requalification training on reactor coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586),
rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-2525), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips, heater drain pump trips, and feed water heater tube leak on February 6, 2018.


The inspectors observed and evaluated Unit 3 control room simulator licensed operator requalification training including a small break loss of coolant accident, rapid downpower, and nuclear instrument failure, and verified completion of risk significant operator actions, including the use of alarm response, abnormal, and emergency operating procedures on  
The inspectors observed and evaluated Unit 3 control room simulator licensed operator requalification training including a small break loss of coolant accident, rapid downpower, and nuclear instrument failure, and verified completion of risk significant operator actions, including the use of alarm response, abnormal, and emergency operating procedures on February 13, 2018 Operator Performance (2 Samples)===
The inspectors observed Unit 2 operator performance on plant downpower, turbine valve


February 13, 2018 Operator Performance (2 Samples)===
===testing, annunciator response procedure usage for various turbine control alarms, and control room rounds on January 19, 2018.
The inspectors observed Unit 2 operator performance on plant downpower, turbine valve testing, annunciator response procedure usage for various turbine control alarms, and control room rounds on January 19, 2018.


===The inspectors observed Unit 3 operator performance during 'B' EDG endurance surveillance testing, emergency generator logic sequencer auto test failure and manual re-test, failure and restoration of power range channel 41, and a medical emergency on February 20, 2018.
The inspectors observed Unit 3 operator performance during 'B' EDG endurance surveillance testing, emergency generator logic sequencer auto test failure and manual re-test, failure and restoration of power range channel 41, and a medical emergency on February 20, 2018.


==71111.12 - Maintenance Effectiveness==
==71111.12 - Maintenance Effectiveness==
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The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
Unit 2
Unit 2
: (1) 'B' direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018
: (1) B direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018
: (2) Radiation monitor failures on February 1, 2018 Unit 3
: (2) Radiation monitor failures on February 1, 2018 Unit 3
: (3) 'B' EDG air start system on January 22, 2018
: (3) 'B' EDG air start system on January 22, 2018
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The inspectors evaluated the risk assessments for the following planned and emergent work activities:
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
Unit 2
Unit 2
: (1) 'B' EDG inoperable due to low oil temperature increased risk associated with other scheduled work on January 12, 2018
: (1) B EDG inoperable due to low oil temperature increased risk associated with other scheduled work on January 12, 2018
: (2) Elevated risk due to charging and letdown outage required to perform replacement and calibration of M2LY-110Q, I to P converter, on January 18, 2018
: (2) Elevated risk due to charging and letdown outage required to perform replacement and calibration of M2LY-110Q, I to P converter, on January 18, 2018
: (3) Functional testing of the steam generator level and auto auxiliary feedwater initiation logic potential Yellow risk window on February 12, 2018
: (3) Functional testing of the steam generator level and auto auxiliary feedwater initiation logic potential Yellow risk window on February 12, 2018
Line 179: Line 153:
Unit 2
Unit 2
: (1) CR1078830 - through wall leakage in emergency core cooling system recirculation piping to refueling water storage tank on January 12, 2018
: (1) CR1078830 - through wall leakage in emergency core cooling system recirculation piping to refueling water storage tank on January 12, 2018
: (2) 'B' EDG keep warm pump relay failure for oil temperatures on January 16, 2018
: (2) B EDG keep warm pump relay failure for oil temperatures on January 16, 2018
: (3) Channel 'C' reactor protection system pre-trip light on January 24, 2018
: (3) Channel C reactor protection system pre-trip light on January 24, 2018
: (4) Indication of possible over power condition due to leading edge flow meter and total venturi flow mismatch on January 30, 2018 Unit 3
: (4) Indication of possible over power condition due to leading edge flow meter and total venturi flow mismatch on January 30, 2018 Unit 3
: (5) Reactor plant chilled water system containment isolation valves possible inadequate closing force operability determination and six month periodic review on January 11, 2018
: (5) Reactor plant chilled water system containment isolation valves possible inadequate closing force operability determination and six month periodic review on January 11, 2018
: (6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11, 2018
: (6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11, 2018
: (7) CR1088497 - 'B' EDG air start system on January 22, 2018
: (7) CR1088497 - 'B' EDG air start system on January 22, 2018
: (8) CR1090807 - additional purging performed during monthly 'A' EDG fuel oil storage tank dewatering on February 27, 2018
: (8) CR1090807 - additional purging performed during monthly A EDG fuel oil storage tank dewatering on February 27, 2018


==71111.18 - Plant Modifications==
==71111.18 - Plant Modifications==
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{{IP sample|IP=IP 71111.19|count=11}}
{{IP sample|IP=IP 71111.19|count=11}}


The inspectors evaluated post maintenance testing for the following maintenance/repair  
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
 
activities:
Unit 2
Unit 2
: (1) Shim switch failure on January 11, 2018
: (1) Shim switch failure on January 11, 2018
: (2) 'B' EDG keep warm pump relay failure on January 16, 2018
: (2) B EDG keep warm pump relay failure on January 16, 2018
: (3) M2LY-110Q, I to P converter associated with chemical and volume control system, on January 18, 2018
: (3) M2LY-110Q, I to P converter associated with chemical and volume control system, on January 18, 2018
: (4) 'B' train control room air conditioning unit 2A instrumentation calibration (removal and installation) and compressor inspection on January 22, 2018
: (4) B train control room air conditioning unit 2A instrumentation calibration (removal and installation) and compressor inspection on January 22, 2018
: (5) 'B' direct current switchgear room chiller (Vital chiller) after failure to start on January 24, 2018
: (5) B direct current switchgear room chiller (Vital chiller) after failure to start on January 24, 2018
: (6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on February 12, 2018 Unit 3
: (6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on February 12, 2018 Unit 3
: (7) Normal station service transformer to bus 34B seismic door replacement on January 23, 2018
: (7) Normal station service transformer to bus 34B seismic door replacement on January 23, 2018
: (8) 'B' EDG air compressors following troubleshooting and maintenance associated with inability to restore starting air flasks to normal standby pressure on January 23, 2018
: (8) B' EDG air compressors following troubleshooting and maintenance associated with inability to restore starting air flasks to normal standby pressure on January 23, 2018
: (9) 'D' steam generator level instrument bistable card on February 9, 2018
: (9) 'D' steam generator level instrument bistable card on February 9, 2018
: (10) Power range nuclear instrument channel 41 power supply failure and restoration on February 20, 2018
: (10) Power range nuclear instrument channel 41 power supply failure and restoration on February 20, 2018
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==71111.22 - Surveillance Testing==
==71111.22 - Surveillance Testing==


The inspectors evaluated the following surveillance tests:  
The inspectors evaluated the following surveillance tests:
 
Routine===
Routine===
{{IP sample|IP=IP 71111.13|count=8}}
{{IP sample|IP=IP 71111.13|count=8}}
: (1) Unit 2 'A' EDG monthly surveillances with a slow start on January 3, 2018
: (1) Unit 2 A EDG monthly surveillances with a slow start on January 3, 2018
: (2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability test on January 19, 2018
: (2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability test on January 19, 2018
: (3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on February 12, 2018
: (3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on February 12, 2018
: (4) Unit 2 auxiliary feedwater valve testing on February 13, 2018
: (4) Unit 2 auxiliary feedwater valve testing on February 13, 2018
: (5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10, 2018
: (5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10, 2018
: (6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet on January 31, 2018
: (6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet on January 31, 2018
: (7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart, Revision 002, performed February 20-21, 2018
: (7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart, Revision 002, performed February 20-21, 2018
: (8) Unit 3 'C' SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28, 2018 Inservice (2 Samples)===
: (8) Unit 3 C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28, 2018 Inservice (2 Samples)===
: (1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201, V202, and V464 valve stroke and timing tests on January 24, 2018
: (1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201,
: (2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A


===group B test on February 7, 2018
===V202, and V464 valve stroke and timing tests on January 24, 2018
: (2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A group B test on February 7, 2018


==71114.06 - Drill Evaluation==
==71114.06 - Drill Evaluation==
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Drill/Training Evolution (1 Sample)===
Drill/Training Evolution (1 Sample)===
The inspectors evaluated licensed operator requalification training, including a drill and exercise performance classification opportunity, at Unit 3 on January 9, 2018.
The inspectors evaluated licensed operator requalification training, including a drill and
 
===exercise performance classification opportunity, at Unit 3 on January 9, 2018.


=====RADIATION SAFETY==
==RADIATION SAFETY==


==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls==
==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls==
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: (4) ALARA Plan AP-3-17-03
: (4) ALARA Plan AP-3-17-03
: (5) ALARA Plan AP-3-17-11
: (5) ALARA Plan AP-3-17-11
: (6) ALARA Plan AP-3-18-01  
: (6) ALARA Plan AP-3-18-01 Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
 
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities.
The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities.


The inspectors evaluated the adjustment of exposure estimates or replanning of work. The  
The inspectors evaluated the adjustment of exposure estimates or replanning of work. The inspectors reviewed post-job ALARA evaluations.
 
inspectors reviewed post-job ALARA evaluations.


==OTHER ACTIVITIES - BASELINE==
==OTHER ACTIVITIES - BASELINE==
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{{IP sample|IP=IP 71152|count=1}}
{{IP sample|IP=IP 71152|count=1}}


The inspectors reviewed the licensee's implementation of its corrective action program related to the following issue:
The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:
: (1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the 'A' chiller and three failures of the 'B' chiller) since implementation of corrective actions for multiple failures of the Unit 3 'A' chiller in 2014.
: (1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the A chiller and three failures of the B chiller) since implementation of corrective actions for multiple failures of the Unit 3 A chiller in 2014.
 
===71153 - Follow-up of Events and Notices of Enforcement Discretion


Licensee Event Reports ===
===71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports ===
{{IP sample|IP=IP 71153|count=1}}
{{IP sample|IP=IP 71153|count=1}}
 
The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx
:
: (1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.
: (1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Observations Annual Follow-up of Selected Issues 71152 The inspectors assessed Dominion's problem identification threshold, assessment and operability determinations for each of the identified issues, maintenance rule applicability, extent of condition reviews, and the prioritization and timeliness of corrective actions to determine whether Dominion staff was appropriately identifying, characterizing, and correcting problems associated with the chillers and whether the corrective actions were appropriate.
Observations                                             71152 Annual Follow-up of Selected Issues The inspectors assessed Dominions problem identification threshold, assessment and operability determinations for each of the identified issues, maintenance rule applicability, extent of condition reviews, and the prioritization and timeliness of corrective actions to determine whether Dominion staff was appropriately identifying, characterizing, and correcting problems associated with the chillers and whether the corrective actions were appropriate.


The prior failures in 2014 involved a failed card, several loose and/or broken connections and an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes on the bearing temperature module. The inspectors determined these conditions have not recurred; and the subsequent failures have been properly evaluated and adequate corrective actions have been completed and/or planned. Specifically, for each of the chiller failures since 2014, Dominion conducted the appropriate level of cause evaluation and properly identified and implemented appropriate applicable corrective actions. Included in these corrective actions were developing modifications for both chillers to prevent spurious electrical signal spike trips and for replacing the existing electromechanical timers with solid state timers. Dominion also reviewed preventive maintenance activities and adjusted specific activity frequencies to enhance the service life of the components.
The prior failures in 2014 involved a failed card, several loose and/or broken connections and an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes on the bearing temperature module. The inspectors determined these conditions have not recurred; and the subsequent failures have been properly evaluated and adequate corrective actions have been completed and/or planned. Specifically, for each of the chiller failures since 2014, Dominion conducted the appropriate level of cause evaluation and properly identified and implemented appropriate applicable corrective actions. Included in these corrective actions were developing modifications for both chillers to prevent spurious electrical signal spike trips and for replacing the existing electromechanical timers with solid state timers. Dominion also reviewed preventive maintenance activities and adjusted specific activity frequencies to enhance the service life of the components.


Licensee Event Report (Closed)  
Licensee Event         Turbine Driven Auxiliary Feedwater Pump Room HELB              71153 Report (Closed)       [High Energy Line Break] Door Left Open on April 27, 2016 LER 2016-001-00


Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016  
=====Description:=====
On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100%
power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp room open. This condition existed for less than one hour. The door is a high energy line break (HELB) barrier. With the door open there was no HELB protection for the motor driven auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater inoperable. The licensee determined that the cause was human performance error. The door is conspicuously labeled on each side that it is a HELB boundary door and must be closed except for entry and exit from the room. Corrective actions were taken in accordance with the station's corrective action program, and condition report 1035792 was initiated to address this issue.


LER 2016-001-00 71153
Closure Basis: The inspectors determined that Dominion's immediate actions to close the HELB door and subsequent corrective actions that created a computer based training, assigned to current and future contractor personnel, to reinforce the requirements associated with HELB doors were adequate. The inspectors determined that the failure to close and latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50, Appendix B, Criterion V. This Green licensee identified violation is documented under Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues during the review of the LER. This LER is closed.


=====Description:=====
Licensee Identified Non-Cited Violation                          71153 This violation of very low safety significant was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100% power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp room open. This condition existed for less than one hour. The door is a high energy line break (HELB) barrier. With the door open there was no HELB protection for the motor driven auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater inoperable. The licensee determined that the cause was human performance error. The door is conspicuously labeled on each side that it is a HELB boundary door and must be closed except for entry and exit from the room. Corrective actions were taken in accordance with the station's corrective action program, and condition report 1035792 was initiated to address this issue.


Closure Basis: The inspectors determined that Dominion's immediate actions to close the HELB door and subsequent corrective actions that created a computer based training, assigned to current and future contractor personnel, to reinforce the requirements associated with HELB doors were adequate. The inspectors determined that the failure to close and latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50, Appendix B, Criterion V. This Green licensee identified violation is documented under Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues during the review of the LER. This LER is closed.
Violation: 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.


Licensee Identified Non-Cited Violation 71153 This violation of very low safety significant was identified by the licensee and has been entered into the licensee's corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy. Violation: 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," requires that "activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Section 4.4 of Operating Procedure 2356, Doors, Revision 004, states in part, site personnel are responsible for ensuring doors [high energy line break boundary doors] are closed and latched after passage.
 
Section 4.4 of Operating Procedure 2356, "Doors," Revision 004, states in part, "site personnel are responsible for ensuring doors [high energy line break boundary doors] are closed and latched after passage."


Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2 in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier door between the steam driven and motor driven auxiliary feedwater pumps, which rendered both trains of auxiliary feedwater inoperable for approximately 57 minutes.
Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2 in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier door between the steam driven and motor driven auxiliary feedwater pumps, which rendered both trains of auxiliary feedwater inoperable for approximately 57 minutes.


Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, "Initial Characterization of Findings," and IMC 0609, Appendix A, Exhibit 2, "Mitigating Systems Screening Questions.The inspectors determined that the finding was of very low safety significance (Green).
Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, Initial Characterization of Findings, and IMC 0609, Appendix A, Exhibit 2, Mitigating Systems Screening Questions. The inspectors determined that the finding was of very low safety significance (Green).


Corrective Action Reference: CR 1035792  
Corrective Action Reference: CR 1035792


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
Line 324: Line 288:


71111.01 - Adverse Weather Protection
71111.01 - Adverse Weather Protection
Miscellaneous Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in
Miscellaneous
Condenser, dated March 6, 2018 Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in
Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in
Condenser, dated March 6, 2018
Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in
Condenser), dated March 6, 2018
Condenser), dated March 6, 2018
71111.04 - Equipment Alignment
71111.04 - Equipment Alignment
Procedures OP 3304A, Charging and Letdown SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
Procedures
01, performed January 31, 2018 SP 3604A.1, Charging Pump 'A' Leaktightness Verification Check, Revision 005-04, performed
OP 3304A, Charging and Letdown
January 31, 2018 SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
01, performed January 31, 2018
SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed
January 31, 2018
SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Test, Revision 012-01
Test, Revision 012-01
Condition Reports CA3100943 CA3114923 1068440 1087819
Condition Reports
1088497 1088897 1090041 1090044
CA3100943             CA3114923               1068440               1087819
1088497               1088897                 1090041               1090044
1090717
1090717
Maintenance Orders/Work Orders 53103053362 53103079863 53103084426 53103104435
Maintenance Orders/Work Orders
53103108717 53203153366
53103053362           53103079863             53103084426           53103104435
Miscellaneous 25212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20
53103108717           53203153366
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
Miscellaneous
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54 25212-26933, Sheet 2, PID Service Water System, Revision 90 25212-26933, Sheet 4, PID Service Water System, Revision 54
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
212-26930, Sheet 2, PID 'B' Auxiliary Feedwater System, Revision 49
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
212-26930, Sheet 3, PID Feed Water System, Revision 30  
Leakage
 
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49
212-26930, Sheet 3, PID Feed Water System, Revision 30
71111.05 - Fire Protection
71111.05 - Fire Protection
Procedures MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0
Procedures
MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0
Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14
Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14
Miscellaneous U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0 Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3  
Miscellaneous
 
U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0
Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3
71111.06 - Flood Protection Measures
71111.06 - Flood Protection Measures
Condition Reports CA277474 1087853
Condition Reports
Miscellaneous ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0
CA277474             1087853
Miscellaneous
ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0
71111.11 - Licensed Operator Requalification Program
71111.11 - Licensed Operator Requalification Program
Procedures SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
Procedures
SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651N, Main Control Valve Operability Test, Revision 007
SP 2651N, Main Control Valve Operability Test, Revision 007
OP 2204, Load Changes, Revision 038 SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
OP 2204, Load Changes, Revision 038
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 2651N-001, Main Control Operability Test, Revision 003-01
SP 2651N-001, Main Control Operability Test, Revision 003-01
AOP 2585, Immediate Operator Actions, Revision 003-00 AOP 2568, Reactor Coolant System Leak, Revision 016 AOP 2575, Rapid Down Power, Revision 010-00
AOP 2585, Immediate Operator Actions, Revision 003-00
AOP 2568, Reactor Coolant System Leak, Revision 016
AOP 2575, Rapid Down Power, Revision 010-00
EOP 2526, Reactor Trip Recovery, Revision 019-00
EOP 2526, Reactor Trip Recovery, Revision 019-00
EOP 2525, Standard Post Trip Action, Revision 028-00
EOP 2525, Standard Post Trip Action, Revision 028-00
AOP 2586, RCP Malfunctions, Revision 004
AOP 2586, RCP Malfunctions, Revision 004
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01 SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
Work Orders 53102961788 53103112699 53203157223
SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
Condition Reports 1088243 1088260 1088261 1090369 1090404 1090469  
Work Orders
 
53102961788           53103112699         53203157223
Miscellaneous ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018 LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions course # 70260 LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160
Condition Reports
1088243               1088260             1088261               1090369
1090404               1090469
Miscellaneous
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions
course # 70260
LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160
71111.12 - Maintenance Effectiveness
71111.12 - Maintenance Effectiveness
Procedures SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Procedures
Test, Revision 012-01 SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017
SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Work Orders 53102987484 53103053362 53103079863 53103084426 53103104183 53103104435 53103108717 53203153366  
Test, Revision 012-01
 
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
Condition Reports CA3064516 CA3040023 CA3114923 CA3100943 1068440 1087819 1088497 1088897 1090041 1090044 1090717
Work Orders
Miscellaneous Failure report number 361 for 'B' DC SWGR room chiller, dated March 21, 2002
53102987484           53103053362         53103079863           53103084426
53103104183           53103104435         53103108717           53203153366
Condition Reports
CA3064516             CA3040023             CA3114923           CA3100943
1068440               1087819               1088497             1088897
1090041               1090044               1090717
Miscellaneous
Failure report number 361 for 'B DC SWGR room chiller, dated March 21, 2002
Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016
Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016
212-26933, Sheet 2, PID Service Water System, Revision 90 25212-26933, Sheet 4, PID Service Water System, Revision 54 3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
212-26933, Sheet 2, PID Service Water System, Revision 90
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20 25212-26930, Sheet 2, PID 'B' Auxiliary Feedwater System, Revision 49
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
Leakage
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49
71111.13 - Maintenance Risk Assessments and Emergent Work Control
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Procedures IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03
Procedures
IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03
C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013
C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013
SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating, Revision 001 SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001
SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating,
SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001 SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic, Revision 011 SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001
Revision 001
SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001
SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001
SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic,
Revision 011
SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
Condition Reports 1086031 1090369 1090404 1090469
Condition Reports
Work Orders 53102961788 53103112699 53203149868 53203157223
1086031               1090369               1090404             1090469
Miscellaneous Medium Risk Plan for CR1086138 dated January 17, 2018 Operator risk report unit 2 dated February 13, 2018
Work Orders
53102961788           53103112699           53203149868         53203157223
Miscellaneous
Medium Risk Plan for CR1086138 dated January 17, 2018
Operator risk report unit 2 dated February 13, 2018
Operator risk report unit 2 dated February 12, 2018
Operator risk report unit 2 dated February 12, 2018
WO# TMC80101 EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018 EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018
WO# TMC80101
EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018
EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018
High Risk Plan, Eversource TOA 18-00852 and 18-00768
High Risk Plan, Eversource TOA 18-00852 and 18-00768
EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018
EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018
EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018  
EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018
 
71111.15 - Operability Determinations and Functionality Assessments
71111.15 - Operability Determinations and Functionality Assessments
Procedures
Procedures
Line 401: Line 414:
C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed
C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed
February 28, 2018
February 28, 2018
Condition Reports CA3061625 CA3114923 CA3100943 1078830
Condition Reports
1087718 1087785 1087819   1088497 1088558 1088839 1089030 1090041 1090044 1090807  
CA3061625             CA3114923             CA3100943           1078830
 
1087718               1087785               1087819             1088497
Maintenance Orders/Work Orders 53203152143  53203153366
1088558               1088839               1089030             1090041
Miscellaneous Periodic review of OD CR1073242/CA3061625 dated January 11, 2018
1090044               1090807
Maintenance Orders/Work Orders
203152143          53203153366
Miscellaneous
Periodic review of OD CR1073242/CA3061625 dated January 11, 2018
Prompt operability determination documentation for CR1073242 dated July 14, 2017
Prompt operability determination documentation for CR1073242 dated July 14, 2017
P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated December 1, 2004 Unit 2 Control room narrative logs, dated January 25, 2018 Unit 2 Control room narrative logs, dated March 2, 2018
P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated
December 1, 2004
Unit 2 Control room narrative logs, dated January 25, 2018
Unit 2 Control room narrative logs, dated March 2, 2018
Unit 2 Control room narrative logs, dated February 5-8, 2018
Unit 2 Control room narrative logs, dated February 5-8, 2018
Unit 2 Control room narrative logs, dated January 30, 2018
Unit 2 Control room narrative logs, dated January 30, 2018
212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20 ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6"-HCD-3, Return to RWST, Revision 0 25203-26015, PID  
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6-HCD-3,
Return to RWST, Revision 0
203-26015, PID  
: [[contact::L.P. Safety Injection System]], Revision 50
: [[contact::L.P. Safety Injection System]], Revision 50
71111.18 - Plant Modifications
71111.18 - Plant Modifications
Procedures SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
Procedures
01, performed January 31, 2018 SP 3604A.1, Charging Pump 'A' Leaktightness Verification Check, Revision 005-04, performed
SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
01, performed January 31, 2018
SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed
January 31, 2018
January 31, 2018
Condition Reports 1088897 1090717  
Condition Reports
 
1088897               1090717
Miscellaneous 3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
Miscellaneous
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54  
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
 
Leakage
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
71111.19 - Post-Maintenance Testing
71111.19 - Post-Maintenance Testing
Procedures SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A, Revision 000, performed February 12, 2018 SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004  
Procedures
 
SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A,
Condition Reports CA3114923 565360 1087675 1087718 1088410 1088418 1088497 1089726 1089754 1089767 1090369 1090404  
Revision 000, performed February 12, 2018
 
SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004
Maintenance Orders/Work Orders 53102748541 53102756227 53102916491 53102987484 53103104183 53103123688 53203149868 53203152142 53203152143  53203153366 53203156607   53203156690
Condition Reports
203156704 53203157223  
CA3114923             565360                 1087675               1087718
 
1088410               1088418               1088497               1089726
Miscellaneous Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated
1089754               1089767               1090369               1090404
January 11, 2018 Failure report number 361 for 'B' DC SWGR room chiller, dated March 21, 2002
Maintenance Orders/Work Orders
P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1, Revision 17 25212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20
53102748541           53102756227           53102916491           53102987484
53103104183           53103123688           53203149868           53203152142
203152143          53203153366           53203156607           53203156690
203156704           53203157223
Miscellaneous
Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated
January 11, 2018
Failure report number 361 for B DC SWGR room chiller, dated March 21, 2002
P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1,
Revision 17
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
71111.22 - Surveillance Testing
71111.22 - Surveillance Testing
Procedures SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision
Procedures
2 SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-Service Inspection Testing (IST), Revision 002 SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service Inspection Testing (IST), Revision 002 SP 2651M, Combined Intermediate Valves Operability Test, Revision 005 SP 2651L, Main Stop Valve Operability Test, Revision 004-01 SP 2651N, Main Control Valve Operability Test, Revision 007
SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision
2
SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-
Service Inspection Testing (IST), Revision 002
SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service
Inspection Testing (IST), Revision 002
SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651N, Main Control Valve Operability Test, Revision 007
OP 2204, Load Changes, Revision 038
OP 2204, Load Changes, Revision 038
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002 SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002 SP 2651N-001, Main Control Operability Test, Revision 003-01
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List, Revision 7 SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST Group B Pump Tests, dated January 10, 2018 SP 2619G, AC Electrical Sources Inoperability, Revision 005
SP 2651N-001, Main Control Operability Test, Revision 003-01
CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List,
Revision 7
SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027
SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST
Group B Pump Tests, dated January 10, 2018
SP 2619G, AC Electrical Sources Inoperability, Revision 005
SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007
SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007
SP 2670, Saltwater Cooled HX D/P Determination, Revision 016
SP 2670, Saltwater Cooled HX D/P Determination, Revision 016
OP 2346A, 'A' Emergency Diesel Generator, Revision 034 OP 2346A-002, 'A' DG Pre-start Checklist, Revision 021
OP 2346A, A Emergency Diesel Generator, Revision 034
OP 2346A-004, 'A' DG Data Sheet, Revision 024-03 SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005 SP 2670-004, Diesel Generator 'A' HX D/P Determination, Revision 001-05
OP 2346A-002, A DG Pre-start Checklist, Revision 021
OP 2346A-009, 'A' DG Air Roll, Revision 000-04
OP 2346A-004, A DG Data Sheet, Revision 024-03
SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005
SP 2670-004, Diesel Generator A HX D/P Determination, Revision 001-05
OP 2346A-009, A DG Air Roll, Revision 000-04
SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01
SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01
SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests, Operating, Revision 001 SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001 SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001
SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests,
SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic, Revision 011 SP 3646A.2, Emergency Diesel Generator 'B' Operability Test, Revision 025 SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017
Operating, Revision 001
Work Orders 53102961788 53103053362 53103079863 53103084426
SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001
53103096824 53103104435 53103104903 53103104933 53103104942 53103108717 53103112699 53203157223
SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001
Condition Reports 1068440 1088243 1088260 1088261
SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic,
1088557 1088897 1090369 1090404
Revision 011
1090469 1090717 1090807
SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
Miscellaneous ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
Work Orders
53102961788           53103053362           53103079863           53103084426
53103096824           53103104435           53103104903           53103104933
53103104942           53103108717           53103112699           53203157223
Condition Reports
1068440               1088243               1088260               1088261
1088557               1088897               1090369               1090404
1090469               1090717               1090807
Miscellaneous
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26933, Sheet 4, PID Service Water System, Revision 54
71114.06 - Drill Evaluation
71114.06 - Drill Evaluation
Miscellaneous EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018
Miscellaneous
SERO Log Sheet, dated February 28, 2018 Drill Incident Response Forms EOF Protective Action Recommendations for Drill dated February 28, 2018
EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018
SERO Log Sheet, dated February 28, 2018
Drill Incident Response Forms
EOF Protective Action Recommendations for Drill dated February 28, 2018
Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018
Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018
71151 - Performance Indicator Verification
71151 - Performance Indicator Verification
Procedures SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00
Procedures
SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00
SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8
SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8
SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds
SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds
SP 2602A, Reactor Coolant Leakage, Revision 10 C OP 200.15, RCS Leakage Trending and Investigation, Revision 3
SP 2602A, Reactor Coolant Leakage, Revision 10
SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56  
C OP 200.15, RCS Leakage Trending and Investigation, Revision 3
 
SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56
Surveillance Test Reports SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017 SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017 SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017
Surveillance Test Reports
Miscellaneous 2017 Monthly Leakage Spreadsheet for Units 2 and 3
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017
2017 RCS Activity Spreadsheet for Units 2 and 3  
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017
 
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017
Miscellaneous
2017 Monthly Leakage Spreadsheet for Units 2 and 3
2017 RCS Activity Spreadsheet for Units 2 and 3
71152 - Problem Identification and Resolution
71152 - Problem Identification and Resolution
Condition Reports 570737 571897 578532 1001480 1005259 1044700 1054758 1057865 1057896 1073086 1076228 1083510
Condition Reports
Miscellaneous ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -
570737                 571897               578532             1001480
December 13, 2014, Revision 0 CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 'A' Control Building Chiller Trips, dated September 11, 2015 ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System Selection, Revision 0
1005259                 1044700             1054758           1057865
Modification MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13, 2016
1057896                 1073086             1076228           1083510
Work Orders 53102695494 53102906138
Miscellaneous
ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -
December 13, 2014, Revision 0
CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 A Control
Building Chiller Trips, dated September 11, 2015
ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System
Selection, Revision 0
Modification
MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13,
2016
Work Orders
53102695494             53102906138
71153 - Follow-up of Events and Notices of Enforcement Discretion
71153 - Follow-up of Events and Notices of Enforcement Discretion
Procedures
Procedures
OP 2356, Doors, Revision 004
OP 2356, Doors, Revision 004
Condition Reports
Condition Reports
CR1035792 Apparent Cause Evaluation #3030473 (2016)
CR1035792
Apparent Cause Evaluation #019415 (2013)  
Apparent Cause Evaluation #3030473 (2016)
: [[contact::D. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD]], SUITE 100 KING OF PRUSSIA, PENNSLYVANIA 19406-2713
Apparent Cause Evaluation #019415 (2013)
D.
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PENNSLYVANIA 19406-2713
May 3, 2018
May 3, 2018
Mr. Daniel G. Stoddard
Mr. Daniel G. Stoddard
Senior Vice President and Chief Nuclear Officer
Senior Vice President and Chief Nuclear Officer
Dominion Energy, Inc. Innsbrook Technical Center 5000 Dominion Blvd.
Dominion Energy, Inc.
Glen Allen, VA 23060-6711  
Innsbrook Technical Center
 
5000 Dominion Blvd.
SUBJECT: MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT
Glen Allen, VA 23060-6711
SUBJECT:         MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT
05000336/2018001 AND 05000423/2018001
05000336/2018001 AND 05000423/2018001
Dear Mr. Stoddard:  
Dear Mr. Stoddard:
 
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Millstone Power Station (Millstone), Units 2 and 3. On April 4, 2018, the NRC inspectors discussed the results of this inspection with Mr. John Daugherty, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.  
at Millstone Power Station (Millstone), Units 2 and 3. On April 4, 2018, the NRC inspectors
 
discussed the results of this inspection with Mr. John Daugherty, Site Vice President, and other
members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
No NRC-identified or self-revealing findings were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at
and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room
http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public
Sincerely,  
Inspections, Exemptions, Requests for Withholding.
          /RA/ Daniel  
Sincerely,
                                                  /RA/
Daniel  
: [[contact::L. Schroeder]], Chief
: [[contact::L. Schroeder]], Chief
Reactor Projects Branch
Reactor Projects Branch 2
Division of Reactor Projects
Division of Reactor Projects
Docket Nos. 50-336 and 50-423
Docket Nos. 50-336 and 50-423
License Nos. DPR-65 and NPF-49
License Nos. DPR-65 and NPF-49
 
Enclosure:
Enclosure: Inspection Report 05000336/2018001     and 05000423/2018001  
Inspection Report 05000336/2018001
 
and 05000423/2018001
cc w/encl: Distribution via ListServ
cc w/encl: Distribution via ListServ
ML18124A023
ML18124A023
Non-Sensitive                            Publicly Available
SUNSI Review
SUNSI Review
Non-Sensitive Sensitive
Sensitive                                 Non-Publicly Available
Publicly Available  Non-Publicly Available
OFFICE         RI/DRP                 RI/DRP                 RI/DRP
OFFICE RI/DRP RI/DRP RI/DRP   NAME JFuller via telecom TSetzer/DSchroeder for DSchroeder   DATE 5/3/18 5/3/18 5/3/18
NAME           JFuller via telecom   TSetzer/DSchroeder for DSchroeder
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
DATE           5/3/18                 5/3/18                 5/3/18
 
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Inspection Report
 
Docket Numbers:       50-336 and 50-423
Docket Numbers: 50-336 and 50-423
License Numbers:       DPR-65 and NPF-49
License Numbers: DPR-65 and NPF-49  
Report Numbers:       05000336/2018001 and 05000423/2018001
 
Enterprise Identifier: I-2018-001-0082
Report Numbers: 05000336/2018001 and 05000423/2018001  
Licensee:             Dominion Energy Nuclear Connecticut, Inc. (Dominion)
 
Facility:             Millstone Power Station, Units 2 and 3
Enterprise Identifier: I-2018-001-0082  
Location:             P.O. Box 128
 
Waterford, CT 06385
Licensee: Dominion Energy Nuclear Connecticut, Inc. (Dominion)  
Inspection Dates:     January 1 to March 31, 2018
 
Inspectors:          
Facility: Millstone Power Station, Units 2 and 3  
: [[contact::J. Fuller]], Senior Resident Inspector
 
: [[contact::L. McKown]], Resident Inspector
Location:
: [[contact::C. Highley]], Resident Inspector
: [[contact::P.O. Box 128   Waterford]], CT 06385  
: [[contact::H. Anagnostopoulos]], Senior Health Physicist
 
Inspection Dates: January 1
to March 31, 2018
Inspectors:  
: [[contact::J. Fuller]], Senior Resident Inspector  
: [[contact::L. McKown]], Resident Inspector  
: [[contact::C. Highley]], Resident Inspector  
: [[contact::H. Anagnostopoulos]], Senior Health Physicist  
: [[contact::J. Brand]], Reactor Inspector
: [[contact::J. Brand]], Reactor Inspector
 
Approved By:           Daniel  
Approved By: Daniel  
: [[contact::L. Schroeder]], Chief
: [[contact::L. Schroeder]], Chief
Reactor Projects Branch 2   Division of Reactor Projects  
Reactor Projects Branch 2
Division of Reactor Projects


SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominion's
SUMMARY
performance at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominions performance
at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in
accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs
program for overseeing the safe operation of commercial nuclear power reactors. Refer to
program for overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified non-cited violations are documented in report section 71153.
https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified
non-cited violations are documented in report section 71153.
No findings or more-than-minor violations were identified.
No findings or more-than-minor violations were identified.
Additional Tracking Items
Additional Tracking Items
Type Issue number Title Report
Type     Issue number             Title                         Report           Status
Section Status LER 05000336/2016-001-00 Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open
Section
71153 Closed
LER       05000336/2016-001-00     Turbine Driven Auxiliary       71153            Closed
PLANT STATUS Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.
Feedwater Pump Room
HELB Door Left Open
PLANT STATUS
Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.
INSPECTION SCOPES
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light-Water Reactor Inspection Program - Operations Phase."
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
The inspectors performed plant status activities described in IMC 2515, Appendix D, "Plant Status," and conducted routine reviews using IP 71152, "Problem
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
Identification and Resolution.The inspectors reviewed selected procedures and records,
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
observed activities, and interviewed personnel to assess Dominion Energy's performance and compliance with Commission rules and regulations, license conditions, site procedures, and
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed plant status activities described in
IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem
Identification and Resolution. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess Dominion Energys performance and
compliance with Commission rules and regulations, license conditions, site procedures, and
standards.
standards.
REACTOR SAFETY
REACTOR SAFETY
71111.01 - Adverse Weather Protection
71111.01 - Adverse Weather Protection
Impending Severe Weather (2 Samples)
Impending Severe Weather (2 Samples)
The inspectors evaluated readiness for impending adverse weather conditions for the onset of a severe storm with heavy snow and high winds on January 3, 2018.  
The inspectors evaluated readiness for impending adverse weather conditions for the onset
 
of a severe storm with heavy snow and high winds on January 3, 2018.
The inspectors evaluated readiness for impending adverse weather conditions for a winter
The inspectors evaluated readiness for impending adverse weather conditions for a winter
storm watch on March 6, 2018.
storm watch on March 6, 2018.
71111.04 - Equipment Alignment
71111.04 - Equipment Alignment
Partial Walkdown (5 Samples)
Partial Walkdown (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains at Unit 3:  
The inspectors evaluated system configurations during partial walkdowns of the following
(1) 'B' emergency diesel generator (EDG) air start system on January 22, 2018 (2) Charging system with both 'A' and  
systems/trains at Unit 3:
'B' pumps in service on January 31, 2018 (3) Control building chiller service water booster pump trains on February 6, 2018 (4) Auxiliary feedwater injection lines on February 12, 2018  
    (1) B emergency diesel generator (EDG) air start system on January 22, 2018
(5) 'A' steam generator feedwater regulating bypass valve operator and control circuit on
    (2) Charging system with both 'A' and 'B' pumps in service on January 31, 2018
March 27, 2018  
    (3) Control building chiller service water booster pump trains on February 6, 2018
 
    (4) Auxiliary feedwater injection lines on February 12, 2018
    (5) 'A' steam generator feedwater regulating bypass valve operator and control circuit on
March 27, 2018
71111.05A/Q - Fire Protection Annual/Quarterly
71111.05A/Q - Fire Protection Annual/Quarterly
Quarterly Inspection (7 Samples)
Quarterly Inspection (7 Samples)
The inspectors evaluated fire protection program implementation in the following selected
The inspectors evaluated fire protection program implementation in the following selected
areas:
areas:
Unit 2 (1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven
Unit 2
auxiliary feedwater pump room) on January 24, 2018 (2) Fire area A-21, west direct current switchgear room on January 26, 2018  
  (1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven
(3) Fire area A-15 and A-16, 'A' and 'B' EDG rooms on February 2, 2018  
auxiliary feedwater pump room) on January 24, 2018
(4) Fire area T-10, upper vital switchgear room on February 8, 2018
  (2) Fire area A-21, west direct current switchgear room on January 26, 2018
Unit 3 (5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [21'6"] on January 10, 2018  
  (3) Fire area A-15 and A-16, A and B EDG rooms on February 2, 2018
(6) Fire area CB-8, cable spreading area on January 23, 2018 (7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29, 2018
  (4) Fire area T-10, upper vital switchgear room on February 8, 2018
Unit 3
  (5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [216] on January 10, 2018
  (6) Fire area CB-8, cable spreading area on January 23, 2018
  (7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29,
2018
71111.06 - Flood Protection Measures
71111.06 - Flood Protection Measures
Cables (1 Sample)
Cables (1 Sample)
The inspectors evaluated cable submergence protection in:  
The inspectors evaluated cable submergence protection in:
(1) Unit 3 north and south cable tunnels on January 23, 2018
    (1) Unit 3 north and south cable tunnels on January 23, 2018
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (2 Samples)
Operator Requalification (2 Samples)
The inspectors observed and evaluated Unit 2 operator requalification training on reactor
The inspectors observed and evaluated Unit 2 operator requalification training on reactor
coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586), rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-2525), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips,
coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586),
heater drain pump trips, and feed water heater tube leak on February 6, 2018.  
rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-
 
25), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips,
The inspectors observed and evaluated Unit 3 control room simulator licensed operator requalification training including a small break loss of coolant accident, rapid downpower, and nuclear instrument failure, and verified completion of risk significant operator actions,
heater drain pump trips, and feed water heater tube leak on February 6, 2018.
The inspectors observed and evaluated Unit 3 control room simulator licensed operator
requalification training including a small break loss of coolant accident, rapid downpower,
and nuclear instrument failure, and verified completion of risk significant operator actions,
including the use of alarm response, abnormal, and emergency operating procedures on
including the use of alarm response, abnormal, and emergency operating procedures on
February 13, 2018  
February 13, 2018
 
Operator Performance (2 Samples)
Operator Performance (2 Samples)
The inspectors observed Unit 2 operator performance on plant downpower, turbine valve testing, annunciator response procedure usage for various turbine control alarms, and control room rounds on January 19, 2018.  
The inspectors observed Unit 2 operator performance on plant downpower, turbine valve
 
testing, annunciator response procedure usage for various turbine control alarms, and control
room rounds on January 19, 2018.
The inspectors observed Unit 3 operator performance during 'B' EDG endurance
The inspectors observed Unit 3 operator performance during 'B' EDG endurance
surveillance testing, emergency generator logic sequencer auto test failure and manual re-
surveillance testing, emergency generator logic sequencer auto test failure and manual re-
Line 611: Line 718:
February 20, 2018.
February 20, 2018.
71111.12 - Maintenance Effectiveness
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness  
Routine Maintenance Effectiveness (6 Samples)
(6 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
with the following equipment and/or safety significant functions:
Unit 2
Unit 2
(1) 'B' direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018  
  (1) B direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018
(2) Radiation monitor failures on February 1, 2018
  (2) Radiation monitor failures on February 1, 2018
Unit 3 (3) 'B' EDG air start system on January 22, 2018  
Unit 3
(4) Charging pump seal leakage on January 31, 2018 (5) Control building chiller service water booster pump trains on February 6, 2018 (6) Auxiliary feed water injection lines on February 12, 2018
  (3) 'B' EDG air start system on January 22, 2018
  (4) Charging pump seal leakage on January 31, 2018
  (5) Control building chiller service water booster pump trains on February 6, 2018
  (6) Auxiliary feed water injection lines on February 12, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (8 Samples)
71111.13 - Maintenance Risk Assessments and Emergent Work Control (8 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
work activities:
Unit 2 (1) 'B' EDG inoperable due to low oil temperature increased risk associated with other scheduled work on January 12, 2018 (2) Elevated risk due to charging and letdown outage required to perform replacement and calibration of M2LY-110Q, I to P converter, on January 18, 2018 (3) Functional testing of the steam generator level and auto auxiliary feedwater initiation logic potential Yellow risk window on February 12, 2018 (4) Auxiliary feedwater testing with potential for causing a Yellow risk window on
Unit 2
February 13, 2018  
  (1) B EDG inoperable due to low oil temperature increased risk associated with other
 
scheduled work on January 12, 2018
Unit 3 (5) 'A' turbine driven feed pump overspeed trip push button restoration on January 31, 2018 (6) Offsite line 310 outage concurrent with deep downpower first contingency to support offsite grid maintenance on February 9, 2018 (7) Procedurally controlled high risk plan for the manual performance of 'B' train emergency generator logic sequencer testing on February 20, 2018 (8) Line 348 outage and single output breaker operation on March 29, 2018
  (2) Elevated risk due to charging and letdown outage required to perform replacement and
calibration of M2LY-110Q, I to P converter, on January 18, 2018
  (3) Functional testing of the steam generator level and auto auxiliary feedwater initiation
logic potential Yellow risk window on February 12, 2018
  (4) Auxiliary feedwater testing with potential for causing a Yellow risk window on
February 13, 2018
Unit 3
  (5) 'A' turbine driven feed pump overspeed trip push button restoration on January 31, 2018
  (6) Offsite line 310 outage concurrent with deep downpower first contingency to support
offsite grid maintenance on February 9, 2018
  (7) Procedurally controlled high risk plan for the manual performance of 'B' train emergency
generator logic sequencer testing on February 20, 2018
  (8) Line 348 outage and single output breaker operation on March 29, 2018
71111.15 - Operability Determinations and Functionality Assessments (8 Samples)
71111.15 - Operability Determinations and Functionality Assessments (8 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
The inspectors evaluated the following operability determinations and functionality
Unit 2 (1) CR1078830 - through wall leakage in emergency core cooling system recirculation piping to refueling water storage tank on January 12, 2018 (2) 'B' EDG keep warm pump relay failure for oil temperatures on January 16, 2018 (3) Channel 'C' reactor protection system pre-trip light on January 24, 2018 (4) Indication of possible over power condition due to leading edge flow meter and total
assessments:
Unit 2
  (1) CR1078830 - through wall leakage in emergency core cooling system recirculation
piping to refueling water storage tank on January 12, 2018
  (2) B EDG keep warm pump relay failure for oil temperatures on January 16, 2018
  (3) Channel C reactor protection system pre-trip light on January 24, 2018
  (4) Indication of possible over power condition due to leading edge flow meter and total
venturi flow mismatch on January 30, 2018
venturi flow mismatch on January 30, 2018
Unit 3 (5) Reactor plant chilled water system containment isolation valves possible inadequate closing force operability determination and six month periodic review on January 11,
Unit 3
2018 (6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11, 2018 (7) CR1088497 - 'B' EDG air start system on January 22, 2018 (8) CR1090807 - additional purging performed during monthly 'A' EDG fuel oil storage tank
  (5) Reactor plant chilled water system containment isolation valves possible inadequate
closing force operability determination and six month periodic review on January 11,
2018
  (6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11,
2018
  (7) CR1088497 - 'B' EDG air start system on January 22, 2018
  (8) CR1090807 - additional purging performed during monthly A EDG fuel oil storage tank
dewatering on February 27, 2018
dewatering on February 27, 2018
71111.18 - Plant Modifications (1 Sample)
71111.18 - Plant Modifications (1 Sample)
The inspectors evaluated the following temporary modification:  
The inspectors evaluated the following temporary modification:
(1) Unit 3 alternate plant configuration (temporary modification) of charging 'A' and 'C' pumps to support 'A' seal troubleshooting on February 26, 2018
  (1) Unit 3 alternate plant configuration (temporary modification) of charging 'A' and 'C'
pumps to support 'A' seal troubleshooting on February 26, 2018
71111.19 - Post Maintenance Testing (11 Samples)
71111.19 - Post Maintenance Testing (11 Samples)
The inspectors evaluated post maintenance testing for the following maintenance/repair
The inspectors evaluated post maintenance testing for the following maintenance/repair
activities:
activities:
Unit 2 (1) Shim switch failure on January 11, 2018 (2) 'B' EDG keep warm pump relay failure on January 16, 2018
Unit 2
(3) M2LY-110Q, I to P converter associated with chemical and volume control system, on
  (1) Shim switch failure on January 11, 2018
January 18, 2018 (4) 'B' train control room air conditioning unit 2A instrumentation calibration (removal and installation) and compressor inspection on January 22, 2018 (5) 'B' direct current switchgear room chiller (Vital chiller) after failure to start on January 24, 2018 (6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on
  (2) B EDG keep warm pump relay failure on January 16, 2018
  (3) M2LY-110Q, I to P converter associated with chemical and volume control system, on
January 18, 2018
  (4) B train control room air conditioning unit 2A instrumentation calibration (removal and
installation) and compressor inspection on January 22, 2018
  (5) B direct current switchgear room chiller (Vital chiller) after failure to start on January 24,
2018
  (6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on
February 12, 2018
February 12, 2018
Unit 3 (7) Normal station service transformer to bus 34B seismic door replacement on January 23, 2018 (8) 'B' EDG air compressors following troubleshooting and maintenance associated with inability to restore starting air flasks to normal standby pressure on January 23, 2018 (9) 'D' steam generator level instrument bistable card on February 9, 2018 (10) Power range nuclear instrument channel 41 power supply failure and restoration on
Unit 3
February 20, 2018 (11) 'A' wide range containment sump level indication troubleshooting and calibration on
  (7) Normal station service transformer to bus 34B seismic door replacement on January 23,
2018
  (8) B' EDG air compressors following troubleshooting and maintenance associated with
inability to restore starting air flasks to normal standby pressure on January 23, 2018
  (9) 'D' steam generator level instrument bistable card on February 9, 2018
  (10) Power range nuclear instrument channel 41 power supply failure and restoration on
February 20, 2018
  (11) 'A' wide range containment sump level indication troubleshooting and calibration on
February 21, 2018
February 21, 2018
71111.22 - Surveillance Testing
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
The inspectors evaluated the following surveillance tests:
Routine (8 Samples)
Routine (8 Samples)
  (1) Unit 2 'A' EDG monthly surveillances with a slow start on January 3, 2018  
  (1) Unit 2 A EDG monthly surveillances with a slow start on January 3, 2018
(2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability test on January 19, 2018 (3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on
  (2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability
February 12, 2018 (4) Unit 2 auxiliary feedwater valve testing on February 13, 2018  
test on January 19, 2018
(5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10, 2018 (6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet
  (3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on
on January 31, 2018 (7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart, Revision 002, performed February 20-21, 2018 (8) Unit 3 'C' SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28, 2018 Inservice (2 Samples)  
February 12, 2018
(1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201, V202, and V464 valve stroke and timing tests on January 24, 2018 (2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A
  (4) Unit 2 auxiliary feedwater valve testing on February 13, 2018
group B test on February 7, 2018  
  (5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10,
 
2018
  (6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet
on January 31, 2018
  (7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart,
Revision 002, performed February 20-21, 2018
  (8) Unit 3 C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28,
2018
Inservice (2 Samples)
  (1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201,
V202, and V464 valve stroke and timing tests on January 24, 2018
  (2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A
group B test on February 7, 2018
71114.06 - Drill Evaluation
71114.06 - Drill Evaluation
Emergency Planning Drill
Emergency Planning Drill (1 Sample)
(1 Sample)
The inspectors evaluated the conduct of a routine Unit 3 emergency planning drill on
The inspectors evaluated the conduct of a routine Unit 3 emergency planning drill on February 28, 2018.
February 28, 2018.
Drill/Training Evolution
Drill/Training Evolution (1 Sample)
(1 Sample)
The inspectors evaluated licensed operator requalification training, including a drill and
The inspectors evaluated licensed operator requalification training, including a drill and exercise performance classification opportunity, at Unit 3 on January 9, 2018.
exercise performance classification opportunity, at Unit 3 on January 9, 2018.
RADIATION SAFETY
RADIATION SAFETY
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
Radiological Work Planning (1 Sample)
Radiological Work Planning (1 Sample)
The inspectors evaluated Dominions radiological work planning by reviewing the following
The inspectors evaluated Dominions radiological work planning by reviewing the following
activities:  
activities:
(1) ALARA Plan AP-2-17-01  
  (1) ALARA Plan AP-2-17-01
(2) ALARA Plan AP-2-17-02  
  (2) ALARA Plan AP-2-17-02
(3) ALARA Plan AP-2-17-13 (4) ALARA Plan AP-3-17-03 (5) ALARA Plan AP-3-17-11  
  (3) ALARA Plan AP-2-17-13
(6) ALARA Plan AP-3-18-01  
  (4) ALARA Plan AP-3-17-03
 
  (5) ALARA Plan AP-3-17-11
  (6) ALARA Plan AP-3-18-01
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities.
The inspectors reviewed the current annual collective dose estimate; basis methodology;
and measures to track, trend, and reduce occupational doses for ongoing work activities.
The inspectors evaluated the adjustment of exposure estimates or replanning of work. The
The inspectors evaluated the adjustment of exposure estimates or replanning of work. The
inspectors reviewed post-job ALARA evaluations.
inspectors reviewed post-job ALARA evaluations.
Line 681: Line 843:
71151 - Performance Indicator Verification
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below for the
The inspectors verified licensee performance indicators submittals listed below for the
period from January 2017
period from January 2017 through December 2017. (4 Samples)
through December 2017. (4 Samples)
Unit 2
Unit 2 (1) RCS specific activity  
  (1) RCS specific activity
(2) RCS identified leak rate  
  (2) RCS identified leak rate
 
Unit 3
Unit 3 (3) RCS specific activity (4) RCS identified leak rate
    (3) RCS specific activity
    (4) RCS identified leak rate
71152 - Problem Identification and Resolution
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issue (1 Sample)
Annual Follow-up of Selected Issue (1 Sample)
The inspectors reviewed the licensee's implementation of its corrective action program related to the following issue:  
The inspectors reviewed the licensees implementation of its corrective action program
 
related to the following issue:
(1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the 'A' chiller and three failures of the 'B' chiller) since implementation of corrective actions for multiple failures of the Unit 3 'A' chiller in 2014.
    (1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the A
chiller and three failures of the B chiller) since implementation of corrective actions for
multiple failures of the Unit 3 A chiller in 2014.
71153 - Follow-up of Events and Notices of Enforcement Discretion
71153 - Follow-up of Events and Notices of Enforcement Discretion
Licensee Event Reports (1 Sample)
Licensee Event Reports (1 Sample)
The inspectors evaluated the following licensee event reports which can be accessed at
The inspectors evaluated the following licensee event reports which can be accessed at
https://lersearch.inl.gov/LERSearchCriteria.aspx
https://lersearch.inl.gov/LERSearchCriteria.aspx:
(1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.
        (1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater
Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.
INSPECTION RESULTS
INSPECTION RESULTS
Observations Annual Follow-up of Selected Issues
Observations                                             71152
71152 The inspectors assessed Dominion's problem identification threshold, assessment and operability determinations for each of the identified issues, maintenance rule applicability,
Annual Follow-up of Selected Issues
extent of condition reviews, and the prioritization and timeliness of corrective actions to determine whether Dominion staff was appropriately identifying, characterizing, and correcting problems associated with the chillers and whether the corrective actions were appropriate.
The inspectors assessed Dominions problem identification threshold, assessment and
operability determinations for each of the identified issues, maintenance rule applicability,
extent of condition reviews, and the prioritization and timeliness of corrective actions to
determine whether Dominion staff was appropriately identifying, characterizing, and correcting
problems associated with the chillers and whether the corrective actions were appropriate.
The prior failures in 2014 involved a failed card, several loose and/or broken connections and
The prior failures in 2014 involved a failed card, several loose and/or broken connections and
an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes on the bearing temperature module. The inspectors determined these conditions have not recurred; and the subsequent failures have been properly evaluated and adequate corrective
an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes
on the bearing temperature module. The inspectors determined these conditions have not
recurred; and the subsequent failures have been properly evaluated and adequate corrective
actions have been completed and/or planned. Specifically, for each of the chiller failures
actions have been completed and/or planned. Specifically, for each of the chiller failures
since 2014, Dominion conducted the appropriate level of cause evaluation and properly
since 2014, Dominion conducted the appropriate level of cause evaluation and properly
identified and implemented appropriate applicable corrective actions. Included in these
identified and implemented appropriate applicable corrective actions. Included in these
corrective actions were developing modifications for both chillers to prevent spurious electrical signal spike trips and for replacing the existing electromechanical timers with solid state timers. Dominion also reviewed preventive maintenance activities and adjusted specific activity frequencies to enhance the service life of the components.  
corrective actions were developing modifications for both chillers to prevent spurious electrical
 
signal spike trips and for replacing the existing electromechanical timers with solid state
Licensee Event
timers. Dominion also reviewed preventive maintenance activities and adjusted specific
Report (Closed)
activity frequencies to enhance the service life of the components.
Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016
Licensee Event         Turbine Driven Auxiliary Feedwater Pump Room HELB               71153
Report (Closed)        [High Energy Line Break] Door Left Open on April 27, 2016
LER 2016-001-00
LER 2016-001-00
71153 Description: On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100% power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp room open. This condition existed for less than one hour. The door is a high energy line
Description: On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100%
break (HELB) barrier. With the door open there was no HELB protection for the motor driven auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater inoperable. The licensee determined that the cause was human performance error. The door
power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp
room open. This condition existed for less than one hour. The door is a high energy line
break (HELB) barrier. With the door open there was no HELB protection for the motor driven
auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater
inoperable. The licensee determined that the cause was human performance error. The door
is conspicuously labeled on each side that it is a HELB boundary door and must be closed
is conspicuously labeled on each side that it is a HELB boundary door and must be closed
except for entry and exit from the room. Corrective actions were taken in accordance with the station's corrective action program, and condition report 1035792 was initiated to address this
except for entry and exit from the room. Corrective actions were taken in accordance with the
station's corrective action program, and condition report 1035792 was initiated to address this
issue.
issue.
Closure Basis: The inspectors determined that Dominion's immediate actions to close the HELB door and subsequent corrective actions that created a computer based training,
Closure Basis: The inspectors determined that Dominion's immediate actions to close the
HELB door and subsequent corrective actions that created a computer based training,
assigned to current and future contractor personnel, to reinforce the requirements associated
assigned to current and future contractor personnel, to reinforce the requirements associated
with HELB doors were adequate. The inspectors determined that the failure to close and latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50, Appendix B, Criterion V. This Green licensee identified violation is documented under
with HELB doors were adequate. The inspectors determined that the failure to close and
latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50,
Appendix B, Criterion V. This Green licensee identified violation is documented under
Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues
Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues
during the review of the LER. This LER is closed.
during the review of the LER. This LER is closed.
Licensee Identified Non-Cited Violation
Licensee Identified Non-Cited Violation                         71153
71153 This violation of very low safety significant was identified by the licensee and has been entered into the licensee's corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy. Violation: 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," requires that "activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
This violation of very low safety significant was identified by the licensee and has been
Section 4.4 of Operating Procedure 2356, "Doors," Revision 004, states in part, "site personnel are responsible for ensuring doors [high energy line break boundary doors] are closed and latched after passage."
entered into the licensees corrective action program and is being treated as a non-cited
Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2 in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier
violation, consistent with Section 2.3.2 of the Enforcement Policy.
door between the steam driven and motor driven
Violation: 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings,
auxiliary feedwater pumps, which rendered both trains of auxiliary feedwater inoperable for approximately 57 minutes.
requires that activities affecting quality shall be prescribed by documented instructions,
Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, "Initial Characterization of Findings," and IMC 0609, Appendix A, Exhibit 2, "Mitigating Systems
procedures, or drawings, of a type appropriate to the circumstances and shall be
Screening Questions.The inspectors determined that the finding was of very low safety
accomplished in accordance with these instructions, procedures, or drawings.
Section 4.4 of Operating Procedure 2356, Doors, Revision 004, states in part, site
personnel are responsible for ensuring doors [high energy line break boundary doors] are
closed and latched after passage.
Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2
in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier
door between the steam driven and motor driven auxiliary feedwater pumps, which rendered
both trains of auxiliary feedwater inoperable for approximately 57 minutes.
Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, Initial
Characterization of Findings, and IMC 0609, Appendix A, Exhibit 2, Mitigating Systems
Screening Questions. The inspectors determined that the finding was of very low safety
significance (Green).
significance (Green).
Corrective Action Reference: CR 1035792  
Corrective Action Reference: CR 1035792
 
EXIT MEETINGS AND DEBRIEFS
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
The inspectors verified no proprietary information was retained or documented in this report.
On April 4, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. John Daugherty, Site Vice President, and other members of the Millstone staff.  
On April 4, 2018, the inspectors presented the quarterly resident inspector inspection results
 
to Mr. John Daugherty, Site Vice President, and other members of the Millstone staff.
DOCUMENTS REVIEWED
DOCUMENTS REVIEWED
71111.01 - Adverse Weather Protection
71111.01 - Adverse Weather Protection
Miscellaneous Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in
Miscellaneous
Condenser, dated March 6, 2018 Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in
Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in
Condenser, dated March 6, 2018
Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in
Condenser), dated March 6, 2018
Condenser), dated March 6, 2018
71111.04 - Equipment Alignment
71111.04 - Equipment Alignment
Procedures OP 3304A, Charging and Letdown SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
Procedures
01, performed January 31, 2018 SP 3604A.1, Charging Pump 'A' Leaktightness Verification Check, Revision 005-04, performed
OP 3304A, Charging and Letdown
January 31, 2018 SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
01, performed January 31, 2018
SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed
January 31, 2018
SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Test, Revision 012-01
Test, Revision 012-01
Condition Reports CA3100943 CA3114923 1068440 1087819
Condition Reports
1088497 1088897 1090041 1090044
CA3100943             CA3114923               1068440               1087819
1088497               1088897                 1090041               1090044
1090717
1090717
Maintenance Orders/Work Orders 53103053362 53103079863 53103084426 53103104435
Maintenance Orders/Work Orders
53103108717 53203153366
53103053362           53103079863             53103084426           53103104435
Miscellaneous 25212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20
53103108717           53203153366
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
Miscellaneous
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54 25212-26933, Sheet 2, PID Service Water System, Revision 90 25212-26933, Sheet 4, PID Service Water System, Revision 54
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
212-26930, Sheet 2, PID 'B' Auxiliary Feedwater System, Revision 49
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
212-26930, Sheet 3, PID Feed Water System, Revision 30  
Leakage
 
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49
212-26930, Sheet 3, PID Feed Water System, Revision 30
71111.05 - Fire Protection
71111.05 - Fire Protection
Procedures MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0
Procedures
MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0
Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14
Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14
Miscellaneous U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0 Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3  
Miscellaneous
 
U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0
Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3
71111.06 - Flood Protection Measures
71111.06 - Flood Protection Measures
Condition Reports CA277474 1087853
Condition Reports
Miscellaneous ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0
CA277474             1087853
Miscellaneous
ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0
71111.11 - Licensed Operator Requalification Program
71111.11 - Licensed Operator Requalification Program
Procedures SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
Procedures
SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651N, Main Control Valve Operability Test, Revision 007
SP 2651N, Main Control Valve Operability Test, Revision 007
OP 2204, Load Changes, Revision 038 SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
OP 2204, Load Changes, Revision 038
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 2651N-001, Main Control Operability Test, Revision 003-01
SP 2651N-001, Main Control Operability Test, Revision 003-01
AOP 2585, Immediate Operator Actions, Revision 003-00 AOP 2568, Reactor Coolant System Leak, Revision 016 AOP 2575, Rapid Down Power, Revision 010-00
AOP 2585, Immediate Operator Actions, Revision 003-00
AOP 2568, Reactor Coolant System Leak, Revision 016
AOP 2575, Rapid Down Power, Revision 010-00
EOP 2526, Reactor Trip Recovery, Revision 019-00
EOP 2526, Reactor Trip Recovery, Revision 019-00
EOP 2525, Standard Post Trip Action, Revision 028-00
EOP 2525, Standard Post Trip Action, Revision 028-00
AOP 2586, RCP Malfunctions, Revision 004
AOP 2586, RCP Malfunctions, Revision 004
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01 SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
Work Orders 53102961788 53103112699 53203157223
SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
Condition Reports 1088243 1088260 1088261 1090369 1090404 1090469  
Work Orders
 
53102961788           53103112699         53203157223
Miscellaneous ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018 LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions course # 70260 LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160
Condition Reports
1088243               1088260             1088261               1090369
1090404               1090469
Miscellaneous
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions
course # 70260
LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160
71111.12 - Maintenance Effectiveness
71111.12 - Maintenance Effectiveness
Procedures SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Procedures
Test, Revision 012-01 SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017
SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B
Work Orders 53102987484 53103053362 53103079863 53103084426 53103104183 53103104435 53103108717 53203153366  
Test, Revision 012-01
 
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
Condition Reports CA3064516 CA3040023 CA3114923 CA3100943 1068440 1087819 1088497 1088897 1090041 1090044 1090717
Work Orders
Miscellaneous Failure report number 361 for 'B' DC SWGR room chiller, dated March 21, 2002
53102987484           53103053362         53103079863           53103084426
53103104183           53103104435         53103108717           53203153366
Condition Reports
CA3064516             CA3040023             CA3114923           CA3100943
1068440               1087819               1088497             1088897
1090041               1090044               1090717
Miscellaneous
Failure report number 361 for 'B DC SWGR room chiller, dated March 21, 2002
Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016
Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016
212-26933, Sheet 2, PID Service Water System, Revision 90 25212-26933, Sheet 4, PID Service Water System, Revision 54 3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
212-26933, Sheet 2, PID Service Water System, Revision 90
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20 25212-26930, Sheet 2, PID 'B' Auxiliary Feedwater System, Revision 49
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
Leakage
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49
71111.13 - Maintenance Risk Assessments and Emergent Work Control
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Procedures IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03
Procedures
IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03
C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013
C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013
SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating, Revision 001 SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001
SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating,
SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001 SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic, Revision 011 SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001
Revision 001
SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001
SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001
SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic,
Revision 011
SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01
Condition Reports 1086031 1090369 1090404 1090469
Condition Reports
Work Orders 53102961788 53103112699 53203149868 53203157223
1086031               1090369               1090404             1090469
Miscellaneous Medium Risk Plan for CR1086138 dated January 17, 2018 Operator risk report unit 2 dated February 13, 2018
Work Orders
53102961788           53103112699           53203149868         53203157223
Miscellaneous
Medium Risk Plan for CR1086138 dated January 17, 2018
Operator risk report unit 2 dated February 13, 2018
Operator risk report unit 2 dated February 12, 2018
Operator risk report unit 2 dated February 12, 2018
WO# TMC80101 EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018 EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018
WO# TMC80101
EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018
EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018
High Risk Plan, Eversource TOA 18-00852 and 18-00768
High Risk Plan, Eversource TOA 18-00852 and 18-00768
EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018
EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018
EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018  
EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018
 
71111.15 - Operability Determinations and Functionality Assessments
71111.15 - Operability Determinations and Functionality Assessments
Procedures
Procedures
Line 816: Line 1,055:
C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed
C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed
February 28, 2018
February 28, 2018
Condition Reports CA3061625 CA3114923 CA3100943 1078830
Condition Reports
1087718 1087785 1087819   1088497 1088558 1088839 1089030 1090041 1090044 1090807  
CA3061625             CA3114923             CA3100943           1078830
 
1087718               1087785               1087819             1088497
Maintenance Orders/Work Orders 53203152143  53203153366
1088558               1088839               1089030             1090041
Miscellaneous Periodic review of OD CR1073242/CA3061625 dated January 11, 2018
1090044               1090807
Maintenance Orders/Work Orders
203152143          53203153366
Miscellaneous
Periodic review of OD CR1073242/CA3061625 dated January 11, 2018
Prompt operability determination documentation for CR1073242 dated July 14, 2017
Prompt operability determination documentation for CR1073242 dated July 14, 2017
P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated December 1, 2004 Unit 2 Control room narrative logs, dated January 25, 2018 Unit 2 Control room narrative logs, dated March 2, 2018
P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated
December 1, 2004
Unit 2 Control room narrative logs, dated January 25, 2018
Unit 2 Control room narrative logs, dated March 2, 2018
Unit 2 Control room narrative logs, dated February 5-8, 2018
Unit 2 Control room narrative logs, dated February 5-8, 2018
Unit 2 Control room narrative logs, dated January 30, 2018
Unit 2 Control room narrative logs, dated January 30, 2018
212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20 ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6"-HCD-3, Return to RWST, Revision 0 25203-26015, PID  
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6-HCD-3,
Return to RWST, Revision 0
203-26015, PID  
: [[contact::L.P. Safety Injection System]], Revision 50
: [[contact::L.P. Safety Injection System]], Revision 50
71111.18 - Plant Modifications
71111.18 - Plant Modifications
Procedures SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
Procedures
01, performed January 31, 2018 SP 3604A.1, Charging Pump 'A' Leaktightness Verification Check, Revision 005-04, performed
SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-
01, performed January 31, 2018
SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed
January 31, 2018
January 31, 2018
Condition Reports 1088897 1090717  
Condition Reports
 
1088897               1090717
Miscellaneous 3C19-CHS01-0002, Alternate Plant Configuration for Isolation of 'A' Charging Pump due to Seal
Miscellaneous
Leakage 25212-26904, Sheet 1, PID Charging and Letdown System, Revision 54  
3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal
 
Leakage
212-26904, Sheet 1, PID Charging and Letdown System, Revision 54
71111.19 - Post-Maintenance Testing
71111.19 - Post-Maintenance Testing
Procedures SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A, Revision 000, performed February 12, 2018 SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004  
Procedures
 
SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A,
Condition Reports CA3114923 565360 1087675 1087718 1088410 1088418 1088497 1089726 1089754 1089767 1090369 1090404  
Revision 000, performed February 12, 2018
 
SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004
Maintenance Orders/Work Orders 53102748541 53102756227 53102916491 53102987484 53103104183 53103123688 53203149868 53203152142 53203152143  53203153366 53203156607   53203156690
Condition Reports
203156704 53203157223  
CA3114923             565360                 1087675               1087718
 
1088410               1088418               1088497               1089726
Miscellaneous Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated
1089754               1089767               1090369               1090404
January 11, 2018 Failure report number 361 for 'B' DC SWGR room chiller, dated March 21, 2002
Maintenance Orders/Work Orders
P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1, Revision 17 25212-26916, Sheet 4, PID 'B' Emergency Diesel Generator Air Start System, Revision 20
53102748541           53102756227           53102916491           53102987484
53103104183           53103123688           53203149868           53203152142
203152143          53203153366           53203156607           53203156690
203156704           53203157223
Miscellaneous
Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated
January 11, 2018
Failure report number 361 for B DC SWGR room chiller, dated March 21, 2002
P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1,
Revision 17
212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20
71111.22 - Surveillance Testing
71111.22 - Surveillance Testing
Procedures SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision
Procedures
2 SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-Service Inspection Testing (IST), Revision 002 SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service Inspection Testing (IST), Revision 002 SP 2651M, Combined Intermediate Valves Operability Test, Revision 005 SP 2651L, Main Stop Valve Operability Test, Revision 004-01 SP 2651N, Main Control Valve Operability Test, Revision 007
SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision
2
SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-
Service Inspection Testing (IST), Revision 002
SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service
Inspection Testing (IST), Revision 002
SP 2651M, Combined Intermediate Valves Operability Test, Revision 005
SP 2651L, Main Stop Valve Operability Test, Revision 004-01
SP 2651N, Main Control Valve Operability Test, Revision 007
OP 2204, Load Changes, Revision 038
OP 2204, Load Changes, Revision 038
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002 SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002 SP 2651N-001, Main Control Operability Test, Revision 003-01
SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002
CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List, Revision 7 SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027
SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002
SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST Group B Pump Tests, dated January 10, 2018 SP 2619G, AC Electrical Sources Inoperability, Revision 005
SP 2651N-001, Main Control Operability Test, Revision 003-01
CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List,
Revision 7
SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027
SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST
Group B Pump Tests, dated January 10, 2018
SP 2619G, AC Electrical Sources Inoperability, Revision 005
SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007
SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007
SP 2670, Saltwater Cooled HX D/P Determination, Revision 016
SP 2670, Saltwater Cooled HX D/P Determination, Revision 016
OP 2346A, 'A' Emergency Diesel Generator, Revision 034 OP 2346A-002, 'A' DG Pre-start Checklist, Revision 021
OP 2346A, A Emergency Diesel Generator, Revision 034
OP 2346A-004, 'A' DG Data Sheet, Revision 024-03 SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005 SP 2670-004, Diesel Generator 'A' HX D/P Determination, Revision 001-05
OP 2346A-002, A DG Pre-start Checklist, Revision 021
OP 2346A-009, 'A' DG Air Roll, Revision 000-04
OP 2346A-004, A DG Data Sheet, Revision 024-03
SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005
SP 2670-004, Diesel Generator A HX D/P Determination, Revision 001-05
OP 2346A-009, A DG Air Roll, Revision 000-04
SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01
SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01
SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests, Operating, Revision 001 SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001 SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001
SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests,
SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic, Revision 011 SP 3646A.2, Emergency Diesel Generator 'B' Operability Test, Revision 025 SP 3604A.1, Charging Pump 'A' Operational Readiness Test, Revision 017
Operating, Revision 001
Work Orders 53102961788 53103053362 53103079863 53103084426
SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001
53103096824 53103104435 53103104903 53103104933 53103104942 53103108717 53103112699 53203157223
SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001
Condition Reports 1068440 1088243 1088260 1088261
SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic,
1088557 1088897 1090369 1090404
Revision 011
1090469 1090717 1090807
SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025
Miscellaneous ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017
Work Orders
53102961788           53103053362           53103079863           53103084426
53103096824           53103104435           53103104903           53103104933
53103104942           53103108717           53103112699           53203157223
Condition Reports
1068440               1088243               1088260               1088261
1088557               1088897               1090369               1090404
1090469               1090717               1090807
Miscellaneous
ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 2, PID Service Water System, Revision 90
212-26933, Sheet 4, PID Service Water System, Revision 54
212-26933, Sheet 4, PID Service Water System, Revision 54
71114.06 - Drill Evaluation
71114.06 - Drill Evaluation
Miscellaneous EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018
Miscellaneous
SERO Log Sheet, dated February 28, 2018 Drill Incident Response Forms EOF Protective Action Recommendations for Drill dated February 28, 2018
EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018
SERO Log Sheet, dated February 28, 2018
Drill Incident Response Forms
EOF Protective Action Recommendations for Drill dated February 28, 2018
Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018
Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018
71151 - Performance Indicator Verification
71151 - Performance Indicator Verification
Procedures SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00
Procedures
SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00
SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8
SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8
SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds
SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds
SP 2602A, Reactor Coolant Leakage, Revision 10 C OP 200.15, RCS Leakage Trending and Investigation, Revision 3
SP 2602A, Reactor Coolant Leakage, Revision 10
SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56  
C OP 200.15, RCS Leakage Trending and Investigation, Revision 3
 
SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56
Surveillance Test Reports SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017 SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017 SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017
Surveillance Test Reports
Miscellaneous 2017 Monthly Leakage Spreadsheet for Units 2 and 3
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017
2017 RCS Activity Spreadsheet for Units 2 and 3  
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017
 
SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017
Miscellaneous
2017 Monthly Leakage Spreadsheet for Units 2 and 3
2017 RCS Activity Spreadsheet for Units 2 and 3
71152 - Problem Identification and Resolution
71152 - Problem Identification and Resolution
Condition Reports 570737 571897 578532 1001480 1005259 1044700 1054758 1057865 1057896 1073086 1076228 1083510
Condition Reports
Miscellaneous ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -
570737                 571897               578532             1001480
December 13, 2014, Revision 0 CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 'A' Control Building Chiller Trips, dated September 11, 2015 ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System Selection, Revision 0
1005259                 1044700             1054758           1057865
Modification MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13, 2016
1057896                 1073086             1076228           1083510
Work Orders 53102695494 53102906138
Miscellaneous
ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -
December 13, 2014, Revision 0
CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 A Control
Building Chiller Trips, dated September 11, 2015
ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System
Selection, Revision 0
Modification
MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13,
2016
Work Orders
53102695494             53102906138
71153 - Follow-up of Events and Notices of Enforcement Discretion
71153 - Follow-up of Events and Notices of Enforcement Discretion
Procedures
Procedures
OP 2356, Doors, Revision 004
OP 2356, Doors, Revision 004
Condition Reports
Condition Reports
CR1035792 Apparent Cause Evaluation #3030473 (2016)
CR1035792
Apparent Cause Evaluation #3030473 (2016)
Apparent Cause Evaluation #019415 (2013)
Apparent Cause Evaluation #019415 (2013)
}}
}}

Revision as of 06:48, 21 October 2019

Integrated Inspection Report 05000336/2018001 and 05000423/2018001
ML18124A023
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 05/03/2018
From: Daniel Schroeder
Reactor Projects Branch 2
To: Stoddard D
Dominion Energy Nuclear Connecticut, Dominion Energy
Schroeder D
References
IR 2018001
Download: ML18124A023 (20)


Text

D.

UNITED STATES NUCLEAR REGULATORY COMMISSION May 3, 2018

SUBJECT:

MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT 05000336/2018001 AND 05000423/2018001

Dear Mr. Stoddard:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Millstone Power Station (Millstone), Units 2 and 3. On April 4, 2018, the NRC inspectors discussed the results of this inspection with Mr. John Daugherty, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection.

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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosure:

Inspection Report 05000336/2018001 and 05000423/2018001

Inspection Report

Docket Numbers: 50-336 and 50-423 License Numbers: DPR-65 and NPF-49 Report Numbers: 05000336/2018001 and 05000423/2018001 Enterprise Identifier: I-2018-001-0082 Licensee: Dominion Energy Nuclear Connecticut, Inc. (Dominion)

Facility: Millstone Power Station, Units 2 and 3 Location: P.O. Box 128 Waterford, CT 06385 Inspection Dates: January 1 to March 31, 2018 Inspectors: J. Fuller, Senior Resident Inspector L. McKown, Resident Inspector C. Highley, Resident Inspector H. Anagnostopoulos, Senior Health Physicist J. Brand, Reactor Inspector Approved By: Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominions performance at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified non-cited violations are documented in report section 71153.

No findings or more-than-minor violations were identified.

Additional Tracking Items Type Issue number Title Report Status Section LER 05000336/2016-001-00 Turbine Driven Auxiliary 71153 Closed Feedwater Pump Room HELB Door Left Open

PLANT STATUS

===Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Dominion Energys performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather

The inspectors evaluated readiness for impending adverse weather conditions for the onset of a severe storm with heavy snow and high winds on January 3, 2018.

The inspectors evaluated readiness for impending adverse weather conditions for a winter storm watch on March 6, 2018.

71111.04 - Equipment Alignment

Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains at Unit 3:

(1) B emergency diesel generator (EDG) air start system on January 22, 2018
(2) Charging system with both 'A' and 'B' pumps in service on January 31, 2018
(3) Control building chiller service water booster pump trains on February 6, 2018
(4) Auxiliary feedwater injection lines on February 12, 2018
(5) 'A' steam generator feedwater regulating bypass valve operator and control circuit on March 27, 2018

71111.05A/Q - Fire Protection Annual/Quarterly

Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

Unit 2

(1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven auxiliary feedwater pump room) on January 24, 2018
(2) Fire area A-21, west direct current switchgear room on January 26, 2018
(3) Fire area A-15 and A-16, A and B EDG rooms on February 2, 2018
(4) Fire area T-10, upper vital switchgear room on February 8, 2018 Unit 3
(5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [216] on January 10, 2018
(6) Fire area CB-8, cable spreading area on January 23, 2018
(7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29, 2018

71111.06 - Flood Protection Measures

Cables

The inspectors evaluated cable submergence protection in:

(1) Unit 3 north and south cable tunnels on January 23, 2018

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification

The inspectors observed and evaluated Unit 2 operator requalification training on reactor coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586),

rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-2525), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips, heater drain pump trips, and feed water heater tube leak on February 6, 2018.

The inspectors observed and evaluated Unit 3 control room simulator licensed operator requalification training including a small break loss of coolant accident, rapid downpower, and nuclear instrument failure, and verified completion of risk significant operator actions, including the use of alarm response, abnormal, and emergency operating procedures on February 13, 2018 Operator Performance (2 Samples)===

The inspectors observed Unit 2 operator performance on plant downpower, turbine valve

===testing, annunciator response procedure usage for various turbine control alarms, and control room rounds on January 19, 2018.

The inspectors observed Unit 3 operator performance during 'B' EDG endurance surveillance testing, emergency generator logic sequencer auto test failure and manual re-test, failure and restoration of power range channel 41, and a medical emergency on February 20, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

Unit 2

(1) B direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018
(2) Radiation monitor failures on February 1, 2018 Unit 3
(3) 'B' EDG air start system on January 22, 2018
(4) Charging pump seal leakage on January 31, 2018
(5) Control building chiller service water booster pump trains on February 6, 2018
(6) Auxiliary feed water injection lines on February 12, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control

===

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

Unit 2

(1) B EDG inoperable due to low oil temperature increased risk associated with other scheduled work on January 12, 2018
(2) Elevated risk due to charging and letdown outage required to perform replacement and calibration of M2LY-110Q, I to P converter, on January 18, 2018
(3) Functional testing of the steam generator level and auto auxiliary feedwater initiation logic potential Yellow risk window on February 12, 2018
(4) Auxiliary feedwater testing with potential for causing a Yellow risk window on February 13, 2018 Unit 3
(5) 'A' turbine driven feed pump overspeed trip push button restoration on January 31, 2018
(6) Offsite line 310 outage concurrent with deep downpower first contingency to support offsite grid maintenance on February 9, 2018
(7) Procedurally controlled high risk plan for the manual performance of 'B' train emergency generator logic sequencer testing on February 20, 2018
(8) Line 348 outage and single output breaker operation on March 29, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

Unit 2

(1) CR1078830 - through wall leakage in emergency core cooling system recirculation piping to refueling water storage tank on January 12, 2018
(2) B EDG keep warm pump relay failure for oil temperatures on January 16, 2018
(3) Channel C reactor protection system pre-trip light on January 24, 2018
(4) Indication of possible over power condition due to leading edge flow meter and total venturi flow mismatch on January 30, 2018 Unit 3
(5) Reactor plant chilled water system containment isolation valves possible inadequate closing force operability determination and six month periodic review on January 11, 2018
(6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11, 2018
(7) CR1088497 - 'B' EDG air start system on January 22, 2018
(8) CR1090807 - additional purging performed during monthly A EDG fuel oil storage tank dewatering on February 27, 2018

71111.18 - Plant Modifications

The inspectors evaluated the following temporary modification:

(1) Unit 3 alternate plant configuration (temporary modification) of charging 'A' and 'C' pumps to support 'A' seal troubleshooting on February 26, 2018

71111.19 - Post Maintenance Testing

The inspectors evaluated post maintenance testing for the following maintenance/repair activities:

Unit 2

(1) Shim switch failure on January 11, 2018
(2) B EDG keep warm pump relay failure on January 16, 2018
(3) M2LY-110Q, I to P converter associated with chemical and volume control system, on January 18, 2018
(4) B train control room air conditioning unit 2A instrumentation calibration (removal and installation) and compressor inspection on January 22, 2018
(5) B direct current switchgear room chiller (Vital chiller) after failure to start on January 24, 2018
(6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on February 12, 2018 Unit 3
(7) Normal station service transformer to bus 34B seismic door replacement on January 23, 2018
(8) B' EDG air compressors following troubleshooting and maintenance associated with inability to restore starting air flasks to normal standby pressure on January 23, 2018
(9) 'D' steam generator level instrument bistable card on February 9, 2018
(10) Power range nuclear instrument channel 41 power supply failure and restoration on February 20, 2018
(11) 'A' wide range containment sump level indication troubleshooting and calibration on February 21, 2018

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine===

(1) Unit 2 A EDG monthly surveillances with a slow start on January 3, 2018
(2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability test on January 19, 2018
(3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on February 12, 2018
(4) Unit 2 auxiliary feedwater valve testing on February 13, 2018
(5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10, 2018
(6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet on January 31, 2018
(7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart, Revision 002, performed February 20-21, 2018
(8) Unit 3 C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28, 2018 Inservice (2 Samples)===
(1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201,

===V202, and V464 valve stroke and timing tests on January 24, 2018

(2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A group B test on February 7, 2018

71114.06 - Drill Evaluation

Emergency Planning Drill

The inspectors evaluated the conduct of a routine Unit 3 emergency planning drill on February 28, 2018.

Drill/Training Evolution (1 Sample)===

The inspectors evaluated licensed operator requalification training, including a drill and

===exercise performance classification opportunity, at Unit 3 on January 9, 2018.

RADIATION SAFETY

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls

Radiological Work Planning

The inspectors evaluated Dominions radiological work planning by reviewing the following activities:

(1) ALARA Plan AP-2-17-01
(2) ALARA Plan AP-2-17-02
(3) ALARA Plan AP-2-17-13
(4) ALARA Plan AP-3-17-03
(5) ALARA Plan AP-3-17-11
(6) ALARA Plan AP-3-18-01 Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===

The inspectors reviewed the current annual collective dose estimate; basis methodology; and measures to track, trend, and reduce occupational doses for ongoing work activities.

The inspectors evaluated the adjustment of exposure estimates or replanning of work. The inspectors reviewed post-job ALARA evaluations.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below for the period from January 2017 through December 2017.

Unit 2

(1) RCS specific activity
(2) RCS identified leak rate Unit 3
(3) RCS specific activity
(4) RCS identified leak rate

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issue

The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:

(1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the A chiller and three failures of the B chiller) since implementation of corrective actions for multiple failures of the Unit 3 A chiller in 2014.

71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports

The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.

INSPECTION RESULTS

Observations 71152 Annual Follow-up of Selected Issues The inspectors assessed Dominions problem identification threshold, assessment and operability determinations for each of the identified issues, maintenance rule applicability, extent of condition reviews, and the prioritization and timeliness of corrective actions to determine whether Dominion staff was appropriately identifying, characterizing, and correcting problems associated with the chillers and whether the corrective actions were appropriate.

The prior failures in 2014 involved a failed card, several loose and/or broken connections and an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes on the bearing temperature module. The inspectors determined these conditions have not recurred; and the subsequent failures have been properly evaluated and adequate corrective actions have been completed and/or planned. Specifically, for each of the chiller failures since 2014, Dominion conducted the appropriate level of cause evaluation and properly identified and implemented appropriate applicable corrective actions. Included in these corrective actions were developing modifications for both chillers to prevent spurious electrical signal spike trips and for replacing the existing electromechanical timers with solid state timers. Dominion also reviewed preventive maintenance activities and adjusted specific activity frequencies to enhance the service life of the components.

Licensee Event Turbine Driven Auxiliary Feedwater Pump Room HELB 71153 Report (Closed) [High Energy Line Break] Door Left Open on April 27, 2016 LER 2016-001-00

Description:

On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100%

power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp room open. This condition existed for less than one hour. The door is a high energy line break (HELB) barrier. With the door open there was no HELB protection for the motor driven auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater inoperable. The licensee determined that the cause was human performance error. The door is conspicuously labeled on each side that it is a HELB boundary door and must be closed except for entry and exit from the room. Corrective actions were taken in accordance with the station's corrective action program, and condition report 1035792 was initiated to address this issue.

Closure Basis: The inspectors determined that Dominion's immediate actions to close the HELB door and subsequent corrective actions that created a computer based training, assigned to current and future contractor personnel, to reinforce the requirements associated with HELB doors were adequate. The inspectors determined that the failure to close and latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50, Appendix B, Criterion V. This Green licensee identified violation is documented under Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues during the review of the LER. This LER is closed.

Licensee Identified Non-Cited Violation 71153 This violation of very low safety significant was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Section 4.4 of Operating Procedure 2356, Doors, Revision 004, states in part, site personnel are responsible for ensuring doors [high energy line break boundary doors] are closed and latched after passage.

Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2 in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier door between the steam driven and motor driven auxiliary feedwater pumps, which rendered both trains of auxiliary feedwater inoperable for approximately 57 minutes.

Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, Initial Characterization of Findings, and IMC 0609, Appendix A, Exhibit 2, Mitigating Systems Screening Questions. The inspectors determined that the finding was of very low safety significance (Green).

Corrective Action Reference: CR 1035792

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On April 4, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. John Daugherty, Site Vice President, and other members of the Millstone staff.

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

Miscellaneous

Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in

Condenser, dated March 6, 2018

Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in

Condenser), dated March 6, 2018

71111.04 - Equipment Alignment

Procedures

OP 3304A, Charging and Letdown

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-

01, performed January 31, 2018

SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed

January 31, 2018

SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B

Test, Revision 012-01

Condition Reports

CA3100943 CA3114923 1068440 1087819

1088497 1088897 1090041 1090044

1090717

Maintenance Orders/Work Orders

53103053362 53103079863 53103084426 53103104435

53103108717 53203153366

Miscellaneous

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49

212-26930, Sheet 3, PID Feed Water System, Revision 30

71111.05 - Fire Protection

Procedures

MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0

Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14

Miscellaneous

U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0

Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3

71111.06 - Flood Protection Measures

Condition Reports

CA277474 1087853

Miscellaneous

ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0

71111.11 - Licensed Operator Requalification Program

Procedures

SP 2651M, Combined Intermediate Valves Operability Test, Revision 005

SP 2651L, Main Stop Valve Operability Test, Revision 004-01

SP 2651N, Main Control Valve Operability Test, Revision 007

OP 2204, Load Changes, Revision 038

SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002

SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002

SP 2651N-001, Main Control Operability Test, Revision 003-01

AOP 2585, Immediate Operator Actions, Revision 003-00

AOP 2568, Reactor Coolant System Leak, Revision 016

AOP 2575, Rapid Down Power, Revision 010-00

EOP 2526, Reactor Trip Recovery, Revision 019-00

EOP 2525, Standard Post Trip Action, Revision 028-00

AOP 2586, RCP Malfunctions, Revision 004

SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01

SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025

Work Orders

53102961788 53103112699 53203157223

Condition Reports

1088243 1088260 1088261 1090369

1090404 1090469

Miscellaneous

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions

course # 70260

LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160

71111.12 - Maintenance Effectiveness

Procedures

SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B

Test, Revision 012-01

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

Work Orders

53102987484 53103053362 53103079863 53103084426

53103104183 53103104435 53103108717 53203153366

Condition Reports

CA3064516 CA3040023 CA3114923 CA3100943

1068440 1087819 1088497 1088897

1090041 1090044 1090717

Miscellaneous

Failure report number 361 for 'B DC SWGR room chiller, dated March 21, 2002

Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Procedures

IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03

C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013

SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating,

Revision 001

SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001

SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001

SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic,

Revision 011

SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001

SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01

Condition Reports

1086031 1090369 1090404 1090469

Work Orders

53102961788 53103112699 53203149868 53203157223

Miscellaneous

Medium Risk Plan for CR1086138 dated January 17, 2018

Operator risk report unit 2 dated February 13, 2018

Operator risk report unit 2 dated February 12, 2018

WO# TMC80101

EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018

EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018

High Risk Plan, Eversource TOA 18-00852 and 18-00768

EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018

EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018

71111.15 - Operability Determinations and Functionality Assessments

Procedures

ER-M2-THM-201 attachment 1, Feed flow correction factor determination, Revision 0

ER-M2-THM-201, Determining feed flow correction factors for MP Unit 2, Revision 0

EN 21002, Core Heat Balance, Revision 017

SP 2601D-001, Power range channel and delta T power channel calibration, Revision 016-01

C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed

February 28, 2018

Condition Reports

CA3061625 CA3114923 CA3100943 1078830

1087718 1087785 1087819 1088497

1088558 1088839 1089030 1090041

1090044 1090807

Maintenance Orders/Work Orders

203152143 53203153366

Miscellaneous

Periodic review of OD CR1073242/CA3061625 dated January 11, 2018

Prompt operability determination documentation for CR1073242 dated July 14, 2017

P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated

December 1, 2004

Unit 2 Control room narrative logs, dated January 25, 2018

Unit 2 Control room narrative logs, dated March 2, 2018

Unit 2 Control room narrative logs, dated February 5-8, 2018

Unit 2 Control room narrative logs, dated January 30, 2018

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6-HCD-3,

Return to RWST, Revision 0

203-26015, PID

L.P. Safety Injection System, Revision 50

71111.18 - Plant Modifications

Procedures

SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-

01, performed January 31, 2018

SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed

January 31, 2018

Condition Reports

1088897 1090717

Miscellaneous

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

71111.19 - Post-Maintenance Testing

Procedures

SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A,

Revision 000, performed February 12, 2018

SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004

Condition Reports

CA3114923 565360 1087675 1087718

1088410 1088418 1088497 1089726

1089754 1089767 1090369 1090404

Maintenance Orders/Work Orders

53102748541 53102756227 53102916491 53102987484

53103104183 53103123688 53203149868 53203152142

203152143 53203153366 53203156607 53203156690

203156704 53203157223

Miscellaneous

Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated

January 11, 2018

Failure report number 361 for B DC SWGR room chiller, dated March 21, 2002

P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1,

Revision 17

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

71111.22 - Surveillance Testing

Procedures

SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision

2

SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-

Service Inspection Testing (IST), Revision 002

SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service

Inspection Testing (IST), Revision 002

SP 2651M, Combined Intermediate Valves Operability Test, Revision 005

SP 2651L, Main Stop Valve Operability Test, Revision 004-01

SP 2651N, Main Control Valve Operability Test, Revision 007

OP 2204, Load Changes, Revision 038

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002

SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002

SP 2651N-001, Main Control Operability Test, Revision 003-01

CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List,

Revision 7

SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027

SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST

Group B Pump Tests, dated January 10, 2018

SP 2619G, AC Electrical Sources Inoperability, Revision 005

SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007

SP 2670, Saltwater Cooled HX D/P Determination, Revision 016

OP 2346A, A Emergency Diesel Generator, Revision 034

OP 2346A-002, A DG Pre-start Checklist, Revision 021

OP 2346A-004, A DG Data Sheet, Revision 024-03

SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005

SP 2670-004, Diesel Generator A HX D/P Determination, Revision 001-05

OP 2346A-009, A DG Air Roll, Revision 000-04

SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01

SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests,

Operating, Revision 001

SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001

SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001

SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic,

Revision 011

SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

Work Orders

53102961788 53103053362 53103079863 53103084426

53103096824 53103104435 53103104903 53103104933

53103104942 53103108717 53103112699 53203157223

Condition Reports

1068440 1088243 1088260 1088261

1088557 1088897 1090369 1090404

1090469 1090717 1090807

Miscellaneous

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

71114.06 - Drill Evaluation

Miscellaneous

EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018

SERO Log Sheet, dated February 28, 2018

Drill Incident Response Forms

EOF Protective Action Recommendations for Drill dated February 28, 2018

Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018

71151 - Performance Indicator Verification

Procedures

SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00

SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8

SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds

SP 2602A, Reactor Coolant Leakage, Revision 10

C OP 200.15, RCS Leakage Trending and Investigation, Revision 3

SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56

Surveillance Test Reports

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017

Miscellaneous

2017 Monthly Leakage Spreadsheet for Units 2 and 3

2017 RCS Activity Spreadsheet for Units 2 and 3

71152 - Problem Identification and Resolution

Condition Reports

570737 571897 578532 1001480

1005259 1044700 1054758 1057865

1057896 1073086 1076228 1083510

Miscellaneous

ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -

December 13, 2014, Revision 0

CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 A Control

Building Chiller Trips, dated September 11, 2015

ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System

Selection, Revision 0

Modification

MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13,

2016

Work Orders

53102695494 53102906138

71153 - Follow-up of Events and Notices of Enforcement Discretion

Procedures

OP 2356, Doors, Revision 004

Condition Reports

CR1035792

Apparent Cause Evaluation #3030473 (2016)

Apparent Cause Evaluation #019415 (2013)

D.

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BOULEVARD, SUITE 100

KING OF PRUSSIA, PENNSLYVANIA 19406-2713

May 3, 2018

Mr. Daniel G. Stoddard

Senior Vice President and Chief Nuclear Officer

Dominion Energy, Inc.

Innsbrook Technical Center

5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT: MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT

05000336/2018001 AND 05000423/2018001

Dear Mr. Stoddard:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at Millstone Power Station (Millstone), Units 2 and 3. On April 4, 2018, the NRC inspectors

discussed the results of this inspection with Mr. John Daugherty, Site Vice President, and other

members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection.

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 the NRC Public Document Room

in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public

Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Daniel

L. Schroeder, Chief

Reactor Projects Branch 2

Division of Reactor Projects

Docket Nos. 50-336 and 50-423

License Nos. DPR-65 and NPF-49

Enclosure:

Inspection Report 05000336/2018001

and 05000423/2018001

cc w/encl: Distribution via ListServ

ML18124A023

Non-Sensitive Publicly Available

SUNSI Review

Sensitive Non-Publicly Available

OFFICE RI/DRP RI/DRP RI/DRP

NAME JFuller via telecom TSetzer/DSchroeder for DSchroeder

DATE 5/3/18 5/3/18 5/3/18

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers: 50-336 and 50-423

License Numbers: DPR-65 and NPF-49

Report Numbers: 05000336/2018001 and 05000423/2018001

Enterprise Identifier: I-2018-001-0082

Licensee: Dominion Energy Nuclear Connecticut, Inc. (Dominion)

Facility: Millstone Power Station, Units 2 and 3

Location: P.O. Box 128

Waterford, CT 06385

Inspection Dates: January 1 to March 31, 2018

Inspectors:

J. Fuller, Senior Resident Inspector
L. McKown, Resident Inspector
C. Highley, Resident Inspector
H. Anagnostopoulos, Senior Health Physicist
J. Brand, Reactor Inspector

Approved By: Daniel

L. Schroeder, Chief

Reactor Projects Branch 2

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Dominions performance

at Millstone Units 2 and 3 by conducting the baseline inspections described in this report in

accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs

program for overseeing the safe operation of commercial nuclear power reactors. Refer to

https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified

non-cited violations are documented in report section 71153.

No findings or more-than-minor violations were identified.

Additional Tracking Items

Type Issue number Title Report Status

Section

LER 05000336/2016-001-00 Turbine Driven Auxiliary 71153 Closed

Feedwater Pump Room

HELB Door Left Open

PLANT STATUS

Unit 2 and 3 operated at or near rated thermal power for the entire inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in

effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with

their attached revision histories are located on the public website at http://www.nrc.gov/reading-

rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared

complete when the IP requirements most appropriate to the inspection activity were met

consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection

Program - Operations Phase. The inspectors performed plant status activities described in

IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem

Identification and Resolution. The inspectors reviewed selected procedures and records,

observed activities, and interviewed personnel to assess Dominion Energys performance and

compliance with Commission rules and regulations, license conditions, site procedures, and

standards.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather (2 Samples)

The inspectors evaluated readiness for impending adverse weather conditions for the onset

of a severe storm with heavy snow and high winds on January 3, 2018.

The inspectors evaluated readiness for impending adverse weather conditions for a winter

storm watch on March 6, 2018.

71111.04 - Equipment Alignment

Partial Walkdown (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains at Unit 3:

(1) B emergency diesel generator (EDG) air start system on January 22, 2018

(2) Charging system with both 'A' and 'B' pumps in service on January 31, 2018

(3) Control building chiller service water booster pump trains on February 6, 2018

(4) Auxiliary feedwater injection lines on February 12, 2018

(5) 'A' steam generator feedwater regulating bypass valve operator and control circuit on

March 27, 2018

71111.05A/Q - Fire Protection Annual/Quarterly

Quarterly Inspection (7 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

Unit 2

(1) Fire areas T-3 (motor driven auxiliary feedwater pump room) and T-4 (steam driven

auxiliary feedwater pump room) on January 24, 2018

(2) Fire area A-21, west direct current switchgear room on January 26, 2018

(3) Fire area A-15 and A-16, A and B EDG rooms on February 2, 2018

(4) Fire area T-10, upper vital switchgear room on February 8, 2018

Unit 3

(5) Fire area ESF-5, SE floor area auxiliary feed pump cubicle [216] on January 10, 2018

(6) Fire area CB-8, cable spreading area on January 23, 2018

(7) Fire area FB-1, fuel building elevation 11' pipe chase / pipe tunnel pit on January 29,

2018

71111.06 - Flood Protection Measures

Cables (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Unit 3 north and south cable tunnels on January 23, 2018

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (2 Samples)

The inspectors observed and evaluated Unit 2 operator requalification training on reactor

coolant system (RCS) leak (AOP-2568), reactor coolant pump malfunctions (AOP-2586),

rapid downpower (AOP-2575), immediate operator actions (AOP-2585), reactor trip (EOP-

25), reactor trip recovery (EOP-2526), RCS leak rate calculation, condensate pump trips,

heater drain pump trips, and feed water heater tube leak on February 6, 2018.

The inspectors observed and evaluated Unit 3 control room simulator licensed operator

requalification training including a small break loss of coolant accident, rapid downpower,

and nuclear instrument failure, and verified completion of risk significant operator actions,

including the use of alarm response, abnormal, and emergency operating procedures on

February 13, 2018

Operator Performance (2 Samples)

The inspectors observed Unit 2 operator performance on plant downpower, turbine valve

testing, annunciator response procedure usage for various turbine control alarms, and control

room rounds on January 19, 2018.

The inspectors observed Unit 3 operator performance during 'B' EDG endurance

surveillance testing, emergency generator logic sequencer auto test failure and manual re-

test, failure and restoration of power range channel 41, and a medical emergency on

February 20, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (6 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

Unit 2

(1) B direct current switchgear room chiller (Vital Chiller) maintenance on January 23, 2018

(2) Radiation monitor failures on February 1, 2018

Unit 3

(3) 'B' EDG air start system on January 22, 2018

(4) Charging pump seal leakage on January 31, 2018

(5) Control building chiller service water booster pump trains on February 6, 2018

(6) Auxiliary feed water injection lines on February 12, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control (8 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent

work activities:

Unit 2

(1) B EDG inoperable due to low oil temperature increased risk associated with other

scheduled work on January 12, 2018

(2) Elevated risk due to charging and letdown outage required to perform replacement and

calibration of M2LY-110Q, I to P converter, on January 18, 2018

(3) Functional testing of the steam generator level and auto auxiliary feedwater initiation

logic potential Yellow risk window on February 12, 2018

(4) Auxiliary feedwater testing with potential for causing a Yellow risk window on

February 13, 2018

Unit 3

(5) 'A' turbine driven feed pump overspeed trip push button restoration on January 31, 2018

(6) Offsite line 310 outage concurrent with deep downpower first contingency to support

offsite grid maintenance on February 9, 2018

(7) Procedurally controlled high risk plan for the manual performance of 'B' train emergency

generator logic sequencer testing on February 20, 2018

(8) Line 348 outage and single output breaker operation on March 29, 2018

71111.15 - Operability Determinations and Functionality Assessments (8 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

Unit 2

(1) CR1078830 - through wall leakage in emergency core cooling system recirculation

piping to refueling water storage tank on January 12, 2018

(2) B EDG keep warm pump relay failure for oil temperatures on January 16, 2018

(3) Channel C reactor protection system pre-trip light on January 24, 2018

(4) Indication of possible over power condition due to leading edge flow meter and total

venturi flow mismatch on January 30, 2018

Unit 3

(5) Reactor plant chilled water system containment isolation valves possible inadequate

closing force operability determination and six month periodic review on January 11,

2018

(6) CR1087819 - steam generator back leakage into auxiliary feedwater on January 11,

2018

(7) CR1088497 - 'B' EDG air start system on January 22, 2018

(8) CR1090807 - additional purging performed during monthly A EDG fuel oil storage tank

dewatering on February 27, 2018

71111.18 - Plant Modifications (1 Sample)

The inspectors evaluated the following temporary modification:

(1) Unit 3 alternate plant configuration (temporary modification) of charging 'A' and 'C'

pumps to support 'A' seal troubleshooting on February 26, 2018

71111.19 - Post Maintenance Testing (11 Samples)

The inspectors evaluated post maintenance testing for the following maintenance/repair

activities:

Unit 2

(1) Shim switch failure on January 11, 2018

(2) B EDG keep warm pump relay failure on January 16, 2018

(3) M2LY-110Q, I to P converter associated with chemical and volume control system, on

January 18, 2018

(4) B train control room air conditioning unit 2A instrumentation calibration (removal and

installation) and compressor inspection on January 22, 2018

(5) B direct current switchgear room chiller (Vital chiller) after failure to start on January 24,

2018

(6) Replacement of SI-647 relay (high pressure safety injection isolation valve) on

February 12, 2018

Unit 3

(7) Normal station service transformer to bus 34B seismic door replacement on January 23,

2018

(8) B' EDG air compressors following troubleshooting and maintenance associated with

inability to restore starting air flasks to normal standby pressure on January 23, 2018

(9) 'D' steam generator level instrument bistable card on February 9, 2018

(10) Power range nuclear instrument channel 41 power supply failure and restoration on

February 20, 2018

(11) 'A' wide range containment sump level indication troubleshooting and calibration on

February 21, 2018

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (8 Samples)

(1) Unit 2 A EDG monthly surveillances with a slow start on January 3, 2018

(2) Unit 2 main control valve, main stop valve, and combined intermediate valve operability

test on January 19, 2018

(3) Unit 2 functional test of S/G level and auto auxiliary feedwater initiation logic on

February 12, 2018

(4) Unit 2 auxiliary feedwater valve testing on February 13, 2018

(5) Unit 3 auxiliary feedwater pump 3FWA*P2 operational readiness test on January 10,

2018

(6) Unit 3 SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet

on January 31, 2018

(7) Unit 3 SP 3646A.2-006, Emergency Diesel Generator B 24 Hour Run and Restart,

Revision 002, performed February 20-21, 2018

(8) Unit 3 C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results on February 28,

2018

Inservice (2 Samples)

(1) Unit 2 turbine driven auxiliary feedwater pump quarterly operational testing, MS-V201,

V202, and V464 valve stroke and timing tests on January 24, 2018

(2) Unit 3 SP 3626.10-001, motor control center and rod control booster pump 3SWP*P3A

group B test on February 7, 2018

71114.06 - Drill Evaluation

Emergency Planning Drill (1 Sample)

The inspectors evaluated the conduct of a routine Unit 3 emergency planning drill on

February 28, 2018.

Drill/Training Evolution (1 Sample)

The inspectors evaluated licensed operator requalification training, including a drill and

exercise performance classification opportunity, at Unit 3 on January 9, 2018.

RADIATION SAFETY

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls

Radiological Work Planning (1 Sample)

The inspectors evaluated Dominions radiological work planning by reviewing the following

activities:

(1) ALARA Plan AP-2-17-01

(2) ALARA Plan AP-2-17-02

(3) ALARA Plan AP-2-17-13

(4) ALARA Plan AP-3-17-03

(5) ALARA Plan AP-3-17-11

(6) ALARA Plan AP-3-18-01

Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)

The inspectors reviewed the current annual collective dose estimate; basis methodology;

and measures to track, trend, and reduce occupational doses for ongoing work activities.

The inspectors evaluated the adjustment of exposure estimates or replanning of work. The

inspectors reviewed post-job ALARA evaluations.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below for the

period from January 2017 through December 2017. (4 Samples)

Unit 2

(1) RCS specific activity

(2) RCS identified leak rate

Unit 3

(3) RCS specific activity

(4) RCS identified leak rate

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issue (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issue:

(1) Continued failures (trips) of the Unit 3 control building chillers (nine failures of the A

chiller and three failures of the B chiller) since implementation of corrective actions for

multiple failures of the Unit 3 A chiller in 2014.

71153 - Follow-up of Events and Notices of Enforcement Discretion

Licensee Event Reports (1 Sample)

The inspectors evaluated the following licensee event reports which can be accessed at

https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) Licensee Event Report (LER) 2016-001-00, Turbine Driven Auxiliary Feedwater

Pump Room HELB [High Energy Line Break] Door Left Open on April 27, 2016.

INSPECTION RESULTS

Observations 71152

Annual Follow-up of Selected Issues

The inspectors assessed Dominions problem identification threshold, assessment and

operability determinations for each of the identified issues, maintenance rule applicability,

extent of condition reviews, and the prioritization and timeliness of corrective actions to

determine whether Dominion staff was appropriately identifying, characterizing, and correcting

problems associated with the chillers and whether the corrective actions were appropriate.

The prior failures in 2014 involved a failed card, several loose and/or broken connections and

an unexpected loose soldered connection (vice crimped), and spurious electrical signal spikes

on the bearing temperature module. The inspectors determined these conditions have not

recurred; and the subsequent failures have been properly evaluated and adequate corrective

actions have been completed and/or planned. Specifically, for each of the chiller failures

since 2014, Dominion conducted the appropriate level of cause evaluation and properly

identified and implemented appropriate applicable corrective actions. Included in these

corrective actions were developing modifications for both chillers to prevent spurious electrical

signal spike trips and for replacing the existing electromechanical timers with solid state

timers. Dominion also reviewed preventive maintenance activities and adjusted specific

activity frequencies to enhance the service life of the components.

Licensee Event Turbine Driven Auxiliary Feedwater Pump Room HELB 71153

Report (Closed) [High Energy Line Break] Door Left Open on April 27, 2016

LER 2016-001-00

Description: On April 27, 2016, with Millstone Power Station Unit 2 in MODE 1 at 100%

power, plant personnel inadvertently left the door to the turbine driven auxiliary feed purnp

room open. This condition existed for less than one hour. The door is a high energy line

break (HELB) barrier. With the door open there was no HELB protection for the motor driven

auxiliary feedwater pumps thus potentially rendering both trains of auxiliary feedwater

inoperable. The licensee determined that the cause was human performance error. The door

is conspicuously labeled on each side that it is a HELB boundary door and must be closed

except for entry and exit from the room. Corrective actions were taken in accordance with the

station's corrective action program, and condition report 1035792 was initiated to address this

issue.

Closure Basis: The inspectors determined that Dominion's immediate actions to close the

HELB door and subsequent corrective actions that created a computer based training,

assigned to current and future contractor personnel, to reinforce the requirements associated

with HELB doors were adequate. The inspectors determined that the failure to close and

latch the HELB door represented a Green licensee identified violation of 10 CFR Part 50,

Appendix B, Criterion V. This Green licensee identified violation is documented under

Inspection Results in Millstone's IR2018001. The inspectors did not identify any new issues

during the review of the LER. This LER is closed.

Licensee Identified Non-Cited Violation 71153

This violation of very low safety significant was identified by the licensee and has been

entered into the licensees corrective action program and is being treated as a non-cited

violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings,

requires that activities affecting quality shall be prescribed by documented instructions,

procedures, or drawings, of a type appropriate to the circumstances and shall be

accomplished in accordance with these instructions, procedures, or drawings.

Section 4.4 of Operating Procedure 2356, Doors, Revision 004, states in part, site

personnel are responsible for ensuring doors [high energy line break boundary doors] are

closed and latched after passage.

Contrary to the above, between 7:10 pm and 8:07 pm on April 27, 2016, with Millstone Unit 2

in Mode 1 at 100 percent power, Dominion personnel failed close and latch the HELB barrier

door between the steam driven and motor driven auxiliary feedwater pumps, which rendered

both trains of auxiliary feedwater inoperable for approximately 57 minutes.

Significance/Severity Level: The inspectors evaluated this finding using IMC 0609.04, Initial

Characterization of Findings, and IMC 0609, Appendix A, Exhibit 2, Mitigating Systems

Screening Questions. The inspectors determined that the finding was of very low safety

significance (Green).

Corrective Action Reference: CR 1035792

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On April 4, 2018, the inspectors presented the quarterly resident inspector inspection results

to Mr. John Daugherty, Site Vice President, and other members of the Millstone staff.

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

Miscellaneous

Surveillance Form SP 3665.2-001, Intake Structure Condition Determination with Vacuum in

Condenser, dated March 6, 2018

Surveillance Form SP 2654R-001, Intake Structure Condition Determination (With Vacuum in

Condenser), dated March 6, 2018

71111.04 - Equipment Alignment

Procedures

OP 3304A, Charging and Letdown

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-

01, performed January 31, 2018

SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed

January 31, 2018

SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B

Test, Revision 012-01

Condition Reports

CA3100943 CA3114923 1068440 1087819

1088497 1088897 1090041 1090044

1090717

Maintenance Orders/Work Orders

53103053362 53103079863 53103084426 53103104435

53103108717 53203153366

Miscellaneous

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49

212-26930, Sheet 3, PID Feed Water System, Revision 30

71111.05 - Fire Protection

Procedures

MP-PROC-ENG-U3-24-FFS-BAP01-ESF-MAP, Revision 0

Millstone Unit 2 Fire Fighting Strategy for Fire Areas: T-10, 13, and 14

Miscellaneous

U3-24-FFS, Millstone Unit 3 Fire Fighting Strategies, Revision 0

Millstone Unit 3 Fire Protection Evaluation Report, Revision 21.3

71111.06 - Flood Protection Measures

Condition Reports

CA277474 1087853

Miscellaneous

ETE-MP-2015-1057, Condition Monitoring of Structures, Revision 0

71111.11 - Licensed Operator Requalification Program

Procedures

SP 2651M, Combined Intermediate Valves Operability Test, Revision 005

SP 2651L, Main Stop Valve Operability Test, Revision 004-01

SP 2651N, Main Control Valve Operability Test, Revision 007

OP 2204, Load Changes, Revision 038

SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002

SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002

SP 2651N-001, Main Control Operability Test, Revision 003-01

AOP 2585, Immediate Operator Actions, Revision 003-00

AOP 2568, Reactor Coolant System Leak, Revision 016

AOP 2575, Rapid Down Power, Revision 010-00

EOP 2526, Reactor Trip Recovery, Revision 019-00

EOP 2525, Standard Post Trip Action, Revision 028-00

AOP 2586, RCP Malfunctions, Revision 004

SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01

SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025

Work Orders

53102961788 53103112699 53203157223

Condition Reports

1088243 1088260 1088261 1090369

1090404 1090469

Miscellaneous

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

LORP program # S18103, Simulator Exercise Guide Minimum manning/Secondary Malfunctions

course # 70260

LORP program # S18102, Simulator Exercise Guide RCS Leak AOP-2568 course # 70160

71111.12 - Maintenance Effectiveness

Procedures

SP 3626.10-001, Motor Control Center and Rod Control Booster Pump 3SWP*P3A Group B

Test, Revision 012-01

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

Work Orders

53102987484 53103053362 53103079863 53103084426

53103104183 53103104435 53103108717 53203153366

Condition Reports

CA3064516 CA3040023 CA3114923 CA3100943

1068440 1087819 1088497 1088897

1090041 1090044 1090717

Miscellaneous

Failure report number 361 for 'B DC SWGR room chiller, dated March 21, 2002

Radiation monitors Maintenance Rule Evaluations (MRE) Unit 2, since January 1 2016

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

212-26930, Sheet 2, PID B Auxiliary Feedwater System, Revision 49

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Procedures

IC2418D1, Setting Letdown Limiter LLM - 110 High and Low Limit Setpoints, Revision 001-03

C IC 400.05-002, Instrument/Loop Calibration Testing Guidelines, dated January 14, 2013

SP 2610CO, AFW system lineup, valve operability and operational readiness tests, operating,

Revision 001

SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure mode and stroke time IST, Revision 001

SP 2610CO-001, Auxiliary feedwater flow path lineup verification, Revision 001

SP 2402M, Functional test of steam generator level and auto-aux. feedwater initiation logic,

Revision 011

SP 3621.4, Main Feedwater Turbine Emergency Governor and Trip Lockout Test, Revision 001

SP 3448E41, Train B - Diesel Sequencer Actuation Logic Test, Revision 006-01

Condition Reports

1086031 1090369 1090404 1090469

Work Orders

53102961788 53103112699 53203149868 53203157223

Miscellaneous

Medium Risk Plan for CR1086138 dated January 17, 2018

Operator risk report unit 2 dated February 13, 2018

Operator risk report unit 2 dated February 12, 2018

WO# TMC80101

EOOS Version 4.1 for Millstone Unit 3 on February 9, 2018

EOOS Version 4.1 for Millstone Unit 3 on March 29, 2018

High Risk Plan, Eversource TOA 18-00852 and 18-00768

EOOS Version 4.1 for Millstone Unit 3 on January 31, 2018

EOOS Version 4.1 for Millstone Unit 3 on February 20, 2018

71111.15 - Operability Determinations and Functionality Assessments

Procedures

ER-M2-THM-201 attachment 1, Feed flow correction factor determination, Revision 0

ER-M2-THM-201, Determining feed flow correction factors for MP Unit 2, Revision 0

EN 21002, Core Heat Balance, Revision 017

SP 2601D-001, Power range channel and delta T power channel calibration, Revision 016-01

C SP 600.5, QA Diesel Fuel Oil Delivery Post - Offload Results, Revision 003, performed

February 28, 2018

Condition Reports

CA3061625 CA3114923 CA3100943 1078830

1087718 1087785 1087819 1088497

1088558 1088839 1089030 1090041

1090044 1090807

Maintenance Orders/Work Orders

203152143 53203153366

Miscellaneous

Periodic review of OD CR1073242/CA3061625 dated January 11, 2018

Prompt operability determination documentation for CR1073242 dated July 14, 2017

P&ID 6822-34868A, Reactor Protective System Bistable Trip Unit Schematic, Revision dated

December 1, 2004

Unit 2 Control room narrative logs, dated January 25, 2018

Unit 2 Control room narrative logs, dated March 2, 2018

Unit 2 Control room narrative logs, dated February 5-8, 2018

Unit 2 Control room narrative logs, dated January 30, 2018

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

ETE-MP-2017-1144, Code Case N-513-3 Limit Load Planer Flaw Evaluation on Line 6-HCD-3,

Return to RWST, Revision 0

203-26015, PID

L.P. Safety Injection System, Revision 50

71111.18 - Plant Modifications

Procedures

SP 3612B.5, Primary Coolant Leakage Outside Containment - Summary Sheet, Revision 001-

01, performed January 31, 2018

SP 3604A.1, Charging Pump A Leaktightness Verification Check, Revision 005-04, performed

January 31, 2018

Condition Reports

1088897 1090717

Miscellaneous

3C19-CHS01-0002, Alternate Plant Configuration for Isolation of A Charging Pump due to Seal

Leakage

212-26904, Sheet 1, PID Charging and Letdown System, Revision 54

71111.19 - Post-Maintenance Testing

Procedures

SP 3447B01A-001R, Containment Sump Wide Range Level Rack Channel Calibration Train A,

Revision 000, performed February 12, 2018

SP 3441A10, Power Range Neutron Flux Monitor 41 Channel Calibration, Revision 004

Condition Reports

CA3114923 565360 1087675 1087718

1088410 1088418 1088497 1089726

1089754 1089767 1090369 1090404

Maintenance Orders/Work Orders

53102748541 53102756227 53102916491 53102987484

53103104183 53103123688 53203149868 53203152142

203152143 53203153366 53203156607 53203156690

203156704 53203157223

Miscellaneous

Trouble shooting plan for CR 1087675 M2 Control Element Drive System (CEDS), dated

January 11, 2018

Failure report number 361 for B DC SWGR room chiller, dated March 21, 2002

P&ID 25203-39045 SH 78, Rear Panel Wiring Diagram Engineered Safeguards Section CO-1,

Revision 17

212-26916, Sheet 4, PID B Emergency Diesel Generator Air Start System, Revision 20

71111.22 - Surveillance Testing

Procedures

SP 2610BO-004, Auxiliary Feedwater Pump Turbine Trip Throttle Valve Exercise Test, Revision

2

SP 2610BO-002, Turbine Driven Auxiliary Feedwater Pump and Recirculation Check Valve In-

Service Inspection Testing (IST), Revision 002

SP 2610BO-001, 2-MS-201, 2-MS-202, and 2-MS-464 (SV-4188) Stroke and Timing In-Service

Inspection Testing (IST), Revision 002

SP 2651M, Combined Intermediate Valves Operability Test, Revision 005

SP 2651L, Main Stop Valve Operability Test, Revision 004-01

SP 2651N, Main Control Valve Operability Test, Revision 007

OP 2204, Load Changes, Revision 038

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

SP 2651L-002, Quarterly Main Stop Valve Operability Test, Revision 002

SP 2651M-002, Combined Intermediate Valves Operability Test, Revision 002

SP 2651N-001, Main Control Operability Test, Revision 003-01

CM-M2-STI-101, Millstone Unit 2 Technical Specification Surveillance Test Interval (STI0 List,

Revision 7

SP 3622.3, Auxiliary Feedwater Pump 3FWA*P2 Operational Readiness Test, Revision 027

SP 3622.3-001 Surveillance Form - TDAFW Pump Operational Readiness and Quarterly IST

Group B Pump Tests, dated January 10, 2018

SP 2619G, AC Electrical Sources Inoperability, Revision 005

SP 2613K, Diesel Generator Slow Start Operability Test Facility 1, Revision 007

SP 2670, Saltwater Cooled HX D/P Determination, Revision 016

OP 2346A, A Emergency Diesel Generator, Revision 034

OP 2346A-002, A DG Pre-start Checklist, Revision 021

OP 2346A-004, A DG Data Sheet, Revision 024-03

SP 2613K-001, Periodic DG Slow Start Operability Test, Facility 1 (Loaded Run), Revision 005

SP 2670-004, Diesel Generator A HX D/P Determination, Revision 001-05

OP 2346A-009, A DG Air Roll, Revision 000-04

SP 2619G-002, TS 3.8.1.1.b - One EDG Inoperable, Revision 002-01

SP 2610CO, AFW System Lineup, Valve Operability and Operational Readiness Tests,

Operating, Revision 001

SP 2610CO-002, 2-FW-43A and 2-FW-43B Failure Mode and Stroke Time IST, Revision 001

SP 2610CO-001, Auxiliary Feedwater Flow Path Lineup Verification, Revision 001

SP 2402M, Functional Test of Steam Generator Level and Auto-Aux. Feedwater Initiation Logic,

Revision 011

SP 3646A.2, Emergency Diesel Generator B Operability Test, Revision 025

SP 3604A.1, Charging Pump A Operational Readiness Test, Revision 017

Work Orders

53102961788 53103053362 53103079863 53103084426

53103096824 53103104435 53103104903 53103104933

53103104942 53103108717 53103112699 53203157223

Condition Reports

1068440 1088243 1088260 1088261

1088557 1088897 1090369 1090404

1090469 1090717 1090807

Miscellaneous

ER-AA-RXE- Attachment 4, Reactivity Plan, Dated January 19, 2018

212-26933, Sheet 2, PID Service Water System, Revision 90

212-26933, Sheet 4, PID Service Water System, Revision 54

71114.06 - Drill Evaluation

Miscellaneous

EP-AA-103 Attachment 3, Classification Opportunity, for LORTSE55 on January 9, 2018

SERO Log Sheet, dated February 28, 2018

Drill Incident Response Forms

EOF Protective Action Recommendations for Drill dated February 28, 2018

Unit 3 Rehearsal Drill Objectives and Critique dated February 28, 2018

71151 - Performance Indicator Verification

Procedures

SP 3601F.6, Reactor Coolant System Water Inventory Measurement, Revision 008-00

SP 3855, Reactor Coolant Analysis for Dose Equivalent, Rev. 8

SP3670.1, Mode 1-4 Daily and Shiftly Control Room Rounds

SP 2602A, Reactor Coolant Leakage, Revision 10

C OP 200.15, RCS Leakage Trending and Investigation, Revision 3

SP 2619A, Control Room Daily Surveillance, Mode 1 & 2, Revision 56

Surveillance Test Reports

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated December 4, 2017

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated October 9, 2017

SP3855-001, Reactor Coolant Analysis for Dose Equivalent I-131, dated September 11, 2017

Miscellaneous

2017 Monthly Leakage Spreadsheet for Units 2 and 3

2017 RCS Activity Spreadsheet for Units 2 and 3

71152 - Problem Identification and Resolution

Condition Reports

570737 571897 578532 1001480

1005259 1044700 1054758 1057865

1057896 1073086 1076228 1083510

Miscellaneous

ACE 019884, Green NCV Finding 3HVK*CHL1A Chiller Trips, September 26, 2014 -

December 13, 2014, Revision 0

CA3004488, Root Cause Evaluation, CR1005259, Significant Level 2 Multiple Unit 3 A Control

Building Chiller Trips, dated September 11, 2015

ETE-MP-2017-1009, Classification of MPS Systems Using the Tiered Approach to System

Selection, Revision 0

Modification

MP3-15-01158, Chiller M33HVK*CHL 1B Bearing and Motor Module Time Delay, January 13,

2016

Work Orders

53102695494 53102906138

71153 - Follow-up of Events and Notices of Enforcement Discretion

Procedures

OP 2356, Doors, Revision 004

Condition Reports

CR1035792

Apparent Cause Evaluation #3030473 (2016)

Apparent Cause Evaluation #019415 (2013)