ML16355A293

Millstone Power Station - Evaluation of Changes, Tests, and Experiments and Permanent Modifications Team Inspection Report 05000336/2016007 and 05000423/2016007

ML16355A293
Person / Time
Site:	Millstone
Issue date:	12/20/2016
From:	Dentel G T Engineering Region 1 Branch 2
To:	Stoddard D G Dominion Resources
Dentel G T
References
IR 2016007
Download: ML16355A293 (21)

See also: IR 05000336/2016007

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713

December 20, 2016 Mr. Daniel G. Stoddard

Senior Vice President and Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Blvd. Glen Allen, VA 23060-6711

SUBJECT: MILLSTONE POWER STATION - EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT MODIFICATIONS TEAM INSPECTION

REPORT 05000336/2016007 AND 05000423/2016007 Dear Mr. Stoddard:

On November 17, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an

inspection at your Millstone Power Station (Millstone), Units 2 and 3. On November 17, 2016,

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.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. In conducting the inspection, the team reviewed selected procedures, calculations, and records; observed activities; and interviewed station personnel.

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

D. Stoddard -2-

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding." Sincerely, /RA/ Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety

Docket Nos. 50-336 and 50-423

License Nos. DPR-65 and NPF-49

Enclosure: Inspection Report 05000336/2016007 and 05000423/2016007

w/Attachment: Supplementary Information

cc w/encl: Distribution via ListServ

ML16355A293 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME SPindale EDiPaolo via email GDentel DATE 12/15/16 12/15/16 12/20/16

1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I

Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Report Nos. 05000336/2016007 and 05000423/2016007

Licensee: Dominion Nuclear Connecticut, Inc. (Dominion)

Facility: Millstone Power Station, Units 2 and 3

Location: P.O. Box 128 Waterford, CT 06385 Inspection Period: October 31, 2016 through November 17, 2016 Inspectors: S. Pindale, Senior Reactor Inspector, Division of Reactor Safety (DRS),

Team Leader K. Mangan, Senior Reactor Inspector, DRS

L. Dumont, Reactor Inspector, DRS M. Orr, Reactor Inspector, DRS

Approved By: Glenn T. Dentel, Chief Engineering Branch 2

Division of Reactor Safety

2 SUMMARY IR 05000336/2016007 and 05000423/2016007; 10/31/2016 - 11/17/2016; Millstone Power Station, Units 2 and 3; Engineering Specialist Plant Modifications Inspection.

This report covers a two week inspection of the evaluations of changes, tests, or experiments

and permanent plant modifications. The inspection was conducted by four region-based

engineering inspectors. No findings were identified. The NRC's program for overseeing the

safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6, dated July 2016.

3 REPORT DETAILS 1. REACTOR SAFETY Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications (IP 71111.17) .1 Evaluations of Changes, Tests, and Experiments (36 samples) a. Inspection Scope The team reviewed 13 safety evaluations to evaluate whether the changes to the facility or procedures, as described in the Updated Final Safety Analysis Report (UFSAR), had been reviewed and documented in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.59 requirements. In addition, the team evaluated whether Dominion had been required to obtain U.S. Nuclear Regulatory Commission (NRC)

approval prior to implementing the changes. The team interviewed plant staff and reviewed supporting information including calculations, analyses, design change documentation, procedures, the UFSAR, technical specifications, and plant drawings to

assess the adequacy of the safety evaluations. The team compared the safety

evaluations and supporting documents to the guidance and methods provided in Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Evaluations," Revision 1, as

endorsed by NRC Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," to determine the adequacy of the safety evaluations. The team also reviewed 23 samples of 10 CFR 50.59 screenings and applicability

determinations for which Dominion had concluded that no safety evaluation was

required. These reviews were performed to assess whether Dominion's threshold for

performing safety evaluations was consistent with 10 CFR 50.59. The samples included

design changes, calculations, procedure changes, and setpoint changes. The

screenings and applicability determinations were selected based on the safety significance, risk significance, and complexity of the change to the facility. Finally, the team compared Dominion's administrative procedures used to control the screening, preparation, review, and approval of safety evaluations to the guidance in

NEI 96-07 to determine whether those procedures adequately implemented the requirements of 10 CFR 50.59. The documents reviewed for each section of this report are listed in the Attachment.

b. Findings No findings were identified.

4 .2 Permanent Plant Modifications (13 samples) .2.1 MP2-11-01079, Replacement of Pressurizer Spray Manual Isolation Gate Valves 2-RC-252 and 2-RC-253 a. Inspection Scope The team reviewed modification MP2-11-01079, which installed two Class 1 manual

isolation valves, replacing the existing valves. The valves are used to isolate the pressurizer spray nozzles. Dominion replaced two valves and a section of piping to correct bonnet leakage from the installed valves. The new piping and valves were installed on existing pipe supports in the containment. Dominion evaluated the seismic

qualifications of the valves to verify adequate structural margin existed for design basis

seismic events; and welded the new valves and piping into the system and performed associated post-maintenance testing to verify the integrity of the valves, piping, and associated welds.

The team reviewed the modification to determine if the design bases, licensing bases, or

performance capability of the pressurizer spray header had been degraded by the

modification. The team interviewed design engineers and reviewed design drawings and calculations to determine if the new piping and valves met applicable specifications and requirements. Additionally, the team reviewed the post-modification test (PMT)

results, welding certifications, and associated maintenance work orders to determine if

the modification was appropriately implemented. b. Findings No findings were identified.

.2.2 MP2-14-01009, Replace the Shutdown Cooling Isolation Valve 2-SI-652 Motor a. Inspection Scope The team reviewed modification MP2-14-01009, which replaced the motor for motor-

operated valve 2-SI-652 with a new style motor. The motor was replaced to address

industry operating experience related to corrosion issues identified with magnesium

rotors. Dominion replaced the original motor with a motor of similar electrical and torque characteristics and an aluminum rotor. As part of the modification, Dominion verified the motor's locked rotor amps, full load amps, and torque capability of the motor would meet

valve and electrical system design requirements. Dominion also verified that the motor

met seismic and environmental qualifications requirements; and motor weight and

dimensions did not impact the seismic qualifications of the safety injection system. Following installation of the motor, Dominion performed a PMT to ensure design, licensing, and American Society of Mechanical Engineers (ASME) Code requirements

were met.

The team reviewed the modification to determine if the design bases, licensing bases, or performance capability of the motor-operated valve, safety injection system, or electrical system had been degraded by the modification. The team interviewed design engineers and reviewed design drawings, vendor documentation, and calculations to determine if

the motor met the applicable specifications and requirements for the shutdown cooling

5 system. Additionally, the team reviewed PMT results and associated maintenance work orders to determine if the changes were appropriately implemented and the valve test

results were within the required ASME Code and licensing specifications. Finally, the team reviewed environmental qualification testing results to determine if the testing bounded the design basis post-accident containment atmosphere. b. Findings No findings were identified. .2.3 MP3-14-01187, Reactor Plant Closed Loop Cooling Water Heat Exchanger 3CCP*E1B Replacement a. Inspection Scope The team reviewed modification MP3-14-01187, which replaced one of three reactor

plant closed loop cooling water (RPCCW) heat exchangers. Dominion replaced the heat

exchanger to restore heat removal capacity and provide additional operating flow margin

to the RPCCW system. Dominion also upgraded the heat exchanger with a more corrosion/erosion resistant Monel material. As part of the modification, Dominion redesigned the structural supports for the new heat exchanger to ensure the heat

exchanger and associated RPCCW piping maintained the required Seismic I capability

as required by the licensing basis. Finally, Dominion performed a PMT to assess the

cooling capacity, flow velocity though the heat exchanger tubes, and the integrity of the

RPCCW system. The team reviewed the modification to determine if the design bases, licensing bases, or

performance capability of the RPCCW heat exchanger had been degraded by the

modification. The team interviewed design engineers and reviewed design drawings, vendor documentation, and calculations to determine if the heat exchanger met the specifications and requirements for the RPCCW system. Additionally, the team reviewed the PMT results and associated maintenance work orders to determine if the

changes were appropriately implemented; the heat removal capability of the heat

exchanger met design requirements; and post-modification leakage results were within

the required ASME Code and licensing specification. The team performed a walkdown

of the heat exchanger to determine if the modification was installed in accordance with the design, and to assess the overall material conditions of the systems following the modification work. Finally, the team reviewed the 10 CFR 50.59 screening associated with this modification as described in Section 1R17.1 of this report. b. Findings No findings were identified.

.2.4 MP3-12-01028, Reactor Vessel Head Vent Valve Replacements a. Inspection Scope The team reviewed modification MP3-12-01028, which replaced the reactor vessel head

vent valves and associated electrical connections. The valves provide the capability to vent non-condensable gasses from the reactor vessel following a design basis event.

6 Dominion performed the modification to correct degraded performance of the previously installed valves. Dominion performed pre-installation testing on the valves to ensure the

valves met ASME Code leak requirements and post-installation testing to verify the integrity of the valve flange connections and the correct operation of the valves.

The team reviewed the modification to determine if the design bases, licensing bases, or

performance capability of the valves and associated piping had been degraded by the

modification. The team interviewed design engineers and reviewed design drawings, calculations, and vendor specifications to determine if the valves met the applicable specifications and requirements of the reactor head vent system. Additionally, the team reviewed PMT results, associated maintenance work orders, and leakage test results to

determine if the changes were appropriately implemented. The team reviewed

environmental qualification testing results to determine if the testing bounded the

projected design basis post-accident containment atmosphere. Finally, the team reviewed the 10 CFR 50.59 screening associated with this modification as described in Section 1R17.1 of this report. b. Findings No findings were identified. .2.5 MP3-13-01127, Replacement of Service Water Valves 3SWP*AOV39A&B due to Material Change a. Inspection Scope

The team reviewed modification MP3-13-01127, which replaced service water air-

operated butterfly isolation valves. The valves' operation provided service water to the emergency diesel generator (EDG) heat exchangers. Dominion performed the

modification to address identified valve degradation due to de-alloying of the cast aluminum-bronze alloy valve material. Dominion installed the same style valves with improved metallurgical properties to minimize this salt water degradation mechanism.

Following installation, Dominion performed testing to verify the valves were properly

installed and the ASME Code requirements were met.

The team reviewed the modification to determine if the design bases, licensing bases, or performance capability of the valve and associated service water and/or air systems had been degraded by the modification. The team interviewed design engineers and reviewed design drawings, calculations, and vendor specifications to determine if the valves met the design and licensing requirements of the system. Additionally, the team reviewed PMT results and associated maintenance work orders to determine if the changes were appropriately implemented. Finally, the team performed a walkdown of the valves to determine if the modification was installed in accordance with the design,

and to assess the overall material conditions of the systems following the modification work. b. Findings No findings were identified.

7 .2.6 MP3-14-01156, 3HVK CHL 1B Relay Module Replacement a. Inspection Scope The team reviewed modification MP3-14-01157, which replaced an existing time delay relay module in the 19FA control building chiller with a time delay relay module conversion kit. The new installed time delay relay module conversion kit was a complete upgrade from the old relay module. However, the automatic chiller re-start feature after

a loss of power, which was built-in in the original relay, was not incorporated in the new

relay module design. Therefore, in order to maintain this operational feature, Dominion

added an additional timing relay to the 19FA control building chiller circuitry. The team reviewed the modification to verify that the design bases, licensing bases, and

performance capability of the control building chiller had not been degraded by the

modification and had been adequately implemented. The team reviewed the purchase

order and the certification of conformance associated with the relay module kit to verify

that quality requirements, including technical, administrative, regulatory, and reporting

requirements (e.g., specifications, codes, standards, tests, inspections) were specified in procurement documents. The team interviewed engineering staff to verify that the relay module design would function in accordance with its design requirements. The team

also reviewed the associated work order instructions and vendor documentation to

ensure that maintenance personnel had implemented the modification as designed. In

addition, the team verified that procedures, design documents, and drawings affected by the modification had been adequately updated. The team performed a walkdown to independently assess the performance of the 19FA control building chiller by visually

inspecting the local chiller control panel. The team reviewed the associated PMT results and the 3HVK CHL1B chiller operational performance to verify that the system

functioned as designed following the modification. Finally, the team reviewed the 10 CFR 50.59 screening associated with this modification as described in Section 1R17.1 of this report. b. Findings No findings were identified. 2.7 MP3-14-01148, Replacement of 48/15 Vdc Power Supplies for Solid State Protection System a. Inspection Scope

The team reviewed modification MP-14-01149, which installed four 48/15 Vdc power

supplies for the solid state protection system. There are two 48/15 Vdc power supplies

per train, and each power supply provides a 48 Vdc and 15 Vdc output to the solid state

protection system logic and output relays. This change was performed due to preventive

maintenance that required the existing power supplies to be replaced on a ten-year frequency. The originally installed Basler Electric dual output supply unit was no longer manufactured, therefore, an equivalent power supply module was procured as a

replacement.

The team reviewed the modification to verify that the design bases and licensing bases of the power supplies had been adequately implemented. The team reviewed the

8 equivalency change report to ensure that performance capability of the power supplies had not been degraded by the modification. The team reviewed the associated work

order instructions and documentation to verify that maintenance personnel had implemented the modification as designed. The team reviewed the associated PMT requirements and results of the new power supplies to confirm that the implementation

was properly executed and to verify that the system functioned as designed following the

modification. In addition, the team reviewed procedures, design documents, and

drawings affected by the changes to verify that these documents had been adequately

updated. b. Findings No findings were identified.

2.8 10000032204, MP3 Commercial Grade Dedication - Battery Charger Failure Relay a. Inspection Scope The team reviewed modification 10000032204, which replaced a relay associated with Millstone Unit 3 battery charger No. 1. This replacement relay was not designed nor

manufactured as a basic component. The relay was purchased as a commercial grade

item (CGI) and was dedicated by Dominion to be used as a safety-related component.

Dominion characterized this replacement as a like-for-like replacement. The safety function of the relay was to maintain electrical circuit continuity in the battery charger and to change states when energized or de-energized by allowing the relay contacts to pick

up or drop out. This change was performed because the original relay failed in service.

The team reviewed the modification to verify that the design bases, licensing bases, and

performance capability of the battery charger relay had not been degraded by the modification. The team verified that Dominion's process for dedicating the CGI provided reasonable assurance that the commercial grade relay would perform its intended safety

function. Specifically, the team verified that Dominion had established adequate controls

for acceptance of the CGI through its receipt inspection requirements. The team verified

that Dominion properly identified and verified that all critical characteristics associated with the replacement relay satisfied their respective acceptance criteria. The team reviewed the associated work order instructions and documentation to verify that

maintenance personnel had implemented the modification as designed. The team

reviewed the associated acceptance criteria and PMT requirements of the new relay to confirm that the implementation was properly executed and to verify that the battery charger would function as designed following the modification. Finally, the team reviewed procedures, design documents, and drawings affected by the changes to verify

that these documents had been adequately updated.

b. Findings No findings were identified.

9 .2.9 MP2-15-01097, Reactor Protection System Bistable Trip Unit, Auxiliary Trip Units, and Trip Test Cable Assemblies Replacement a. Inspection Scope The team reviewed design change package MP2-15-01097 for a planned modification

that will replace the reactor protection system (RPS) bistable trip units (BTU), the

auxiliary trip units (ATU), and the trip test cable assemblies (TTCA). This design change

is required to replace the obsolete BTUs, ATUs, and TTCAs for the Millstone Unit 2 RPS. This design change will replace eight BTUs, two ATUs, and a TTCA in RPS channel 'B' during the next Unit 2 outage (2R24), and the remaining three channels ('A',

'C', and 'D') will be replaced during 2R25.

The team reviewed the design work package to evaluate whether the design bases, licensing bases, and performance capability of the RPS can be degraded by the modification. The team reviewed Dominion's technical evaluation, design specifications, calculations, analysis, drawings, and logic control sheets to verify that design

assumptions were valid. The team reviewed the procurement specification to verify that

quality requirements, including technical, administrative, regulatory, and reporting requirements (e.g., specifications, codes, standards, tests, inspections) were specified in procurement documents. The team interviewed system engineers and technical staff to evaluate the adequacy of the modification. Additionally, the team reviewed the 10 CFR

50.59 screening associated with this modification as described in Section 1R17.1 of this

report. b. Findings No findings were identified.

2.10 Calculation 96-067, Auxiliary Feedwater System Comprehensive Flow Analysis, and Modification MP3-14-01107, MP3 TDAFW Pump Overspeed Margin Change a. Inspection Scope

The team reviewed Millstone Unit 3 Calculation 96-067, which was revised in support of

lowering the operating speed (from 4500 to 4400 rpm) of the turbine-driven auxiliary feedwater (TDAFW) pump to gain margin to the relief valve setpoint and to increase pump reliability. This change was implemented due to prior operating experience events

at Millstone Unit 3 involving TDAFW pump/turbine overspeed trips and challenging the

discharge relief valve. The change involved a reduction in auxiliary feedwater (AFW)

flow due to the speed reduction. In the calculation revision, Dominion evaluated the lower AFW flow on postulated events in the safety analysis. The team also reviewed the associated modification, MP3-14-01107, TDAFW Pump Overspeed Margin Change, for

which the above calculation supported.

The team reviewed the calculation change to determine if the design bases, licensing

bases, or performance capability of the AFW system had been degraded by reduction in TDAFW pump operating speed. The team interviewed design engineers and reviewed the revised calculation and associated design basis events to determine whether the

change met design and licensing requirements. Surveillance procedures, including test

results, were reviewed by the team to determine whether the results were bounded by

10 the modification and existing analyses. The 10 CFR 50.59 safety evaluation associated with this change was also reviewed as described in Section 1R17.1 of this report.

b. Findings No findings were identified.

2.11 MP3-14-01070, Replace Emergency Diesel Generator Air Cooler Service Water Relief Valves M33SWP*RV90A/RV90B a. Inspection Scope

The team reviewed modification MP3-14-01070 that Dominion implemented to replace the service water system thermal protection relief valves to the Unit 3 EDG air coolers. The function of the relief valves is to provide overpressure protection to the service water side of the safety-related EDG combustion air heat exchangers in the event of an

unintentional equipment isolation or a thermal transient during component lay-up

conditions. The original relief valves were configured with a metal-to-metal seat design that was susceptible to the effects of corrosion and debris, resulting in failure to lift within the specified tolerance of the set pressure. The modification allowed for a soft seat configuration for both of the system relief valves.

The team reviewed the modification to determine if the design and licensing bases, and

performance capability of the EDG system had been degraded by any of the associated

equipment, process, and/or procedure changes. The team interviewed design engineers, and reviewed evaluations, surveillance results, technical data sheets, and associated maintenance activities to verify that Dominion appropriately implemented the

design change in accordance with their design process and assumptions. The team

performed walkdowns of accessible portions of the EDG and service water systems to assess configuration control and the material condition of the associated components. The team also reviewed condition reports, completed preventive maintenance activities, and the EDG system operating logs to determine if there were reliability or performance

issues that may have resulted from the modification. b. Findings No findings were identified.

.2.12 MP3-14-01027, Motor-Driven Auxiliary Feed Pump Lube Oil Pump 3FWL*P6A Replacement a. Inspection Scope The team reviewed modification MP3-14-01027 that Dominion implemented to replace the direct drive (shaft-driven) lube oil pump 3FWL*P6A for AFW pump 3FWA*P1A, due

to unrepairable minor seal leakage and component obsolescence. The AFW pump's

lube oil pump is designed to provide the necessary lubricating oil to the motor-driven AFW pump. The replacement lube oil pump has slightly different suction and discharge piping connections, as well as different orientation, which required some minor piping

replacement and rerouting. The replacement lube oil pump was determined to be an

acceptable equivalent replacement pump for the existing 3FWL*P6A.

11 The team reviewed the modification to determine if the design bases, licensing bases, or performance capability of the motor-driven AFW pump had been degraded by the

modification. The team interviewed design and system engineers and reviewed installation procedures, surveillance results, and associated maintenance activities to determine if the new lube oil pump, piping, and configuration met design specifications

and requirements of the system. The team performed a walkdown of both motor-driven AFW pumps and the TDAFW pump rooms to assess configuration comparisons and

material conditions. b. Findings No findings were identified.

2.13 MP2-14-01001, Replace Emergency Diesel Generator M-7A Service Water Coolers Supply and Discharge Lines with AL-6XN Material a. Inspection Scope

The team reviewed modification MP2-14-01001 that replaced 6-inch and 8-inch lined carbon steel flanged pipe spools on the 'A' train service water supply header to the Unit 2 'A' EDG jacket water cooling, lube oil cooling, and air cooler heat exchangers.

The modification also included the replacing previously-installed AL6XN material pipe

spools to correct flange alignment issues, replacing check valve 2-SW-13A with an

AL6XN pipe spool, and replacing stainless steel flow restricting orifices. The

modifications were necessary to eliminate dissimilar metal galvanic interactions and corrosion issues.

The review was performed to determine if the design bases, licensing bases, or

performance capability of the 'A' EDG had been degraded by the modifications. Design

assumptions were reviewed to evaluate whether they were technically appropriate and consistent with the UFSAR. The team discussed the impact of the modification on the EDG operation with responsible engineers. Additionally, the team reviewed

maintenance work orders to confirm that the modifications were appropriately

implemented. The team performed walkdowns of the EDG to assess the quality of the

modification work and the overall material condition of the equipment. The adequacy of

the PMT was verified, and affected design documents and drawings were reviewed to ensure they had been properly updated. Additionally, the equivalent 10 CFR 50.59 screen associated with this modification was reviewed as described in Section 1R17.1 of

this report. b. Findings No findings were identified.

12 4. OTHER ACTIVITIES 4OA2 Identification and Resolution of Problems (IP 71152) a. Inspection Scope The team reviewed a sample of problems that Dominion had previously identified and entered into the corrective action program. The team reviewed these issues to verify an

appropriate threshold for identifying issues and to evaluate the effectiveness of

corrective actions. In addition, the team reviewed corrective action condition reports written on issues identified during the inspection to verify adequate problem identification and incorporation of the problem into the corrective action system.

b. Findings No findings were identified.

4OA6 Meetings, including Exit The team presented the inspection results to Mr. John Daugherty, Site Vice President, and other members of Dominion staff at an exit meeting on November 17, 2016. The

team returned the proprietary information reviewed during the inspection to Dominion

staff and verified that this report does not contain proprietary information. ATTACHMENT: SUPPLEMENTARY INFORMATION

A-1 Attachment SUPPLEMENTARY INFORMATION KEY POINTS OF CONTACT

Dominion Personnel D. Coleman, Nuclear Technical Specialist

E. Dundon, System Engineer

J. Farley, System Engineer T. Fecteau, Design Contractor J. Gardner, System Engineer

Z. Hoagland, System Engineer

R. Kasuga, Design Engineer

M. Legg, Nuclear Engineer S. O'Hearn, Nuclear Engineer F. Perkins, System Engineer

R. Perry, System Engineer

T. Raetz, Design Engineer

T. Ryan, System Engineer J. Scheeler, Electrical Engineer C. Thomas, System Engineering

R. Wells, Nuclear Engineer

P. Wynn, Procurement Engineer

NRC Personnel J. Ambrosini, Senior Resident Inspector

ITEMS OPENED, CLOSED AND DISCUSSED None

LIST OF DOCUMENTS REVIEWED

10 CFR 50.59 Evaluations E-14-00075-000, Retire-in-Place of MP2 De-icing Line for the Intake Structure, Revision 0 MP-EVAL-SAF-S2-EV-15-0001, OP 230J, Changes to Procedure for Boron Injection, Revision 0

MP-EVAL-SAF-SG-EV-15-0004, Time to Restore Offsite Power to a "Good Element," Revision 0 S2-EV-13-0001, Reanalysis of the MP2 LOCA and MSL Break Containment Analysis, Revision 0 S2-EV-14-0002, Procedure Change, Upender Vertical Input to Fuel Transfer System, 4/13/14

S3-EV-13-0002, MP3 Rod Withdrawal from Subcritical Analysis, 4/9/13

S3-EV-13-0003, Analytical Basis of MP3 LBLOCA Containment Response, 4/29/13 S3-EV-14-0001, SP 3622.9 (TDAFW Pump Full Flow Test) in Mode 1, Revision 1 S3-EV-14-0004, MP3 TDAFW Pump Operating Speed Change from 4500 to 4400 RPM, 12/2/15

A-2 S3-EV-14-0005, MP3 Compensatory Action to Control Rate of Opening and Closing TDAFW Pump Discharge Flow Control Valves, 10/15/14 SG-EV-15-0002, 345 kV Protective Relay Digital Upgrade, Revision 0 SG-EV-15-0002, 345 kV Switchyard Breaker Revised Close/Open Cycles, Revision 1 SG-EV-15-0005, 345 kV Switchyard Breaker-and-Half Configuration, 6/17/15

10 CFR 50.59 Screened-out Evaluations MPS2-SCRN-2016-0065-0, 'C' Service Water Discharge Strainer Motor Full Load Amps Greater than Nameplate, 4/22/16 MPS2-SCRN-2016-0087-0, Belzona Repair of MP2 Primary Water Transfer Pump Shaft, 5/3/16 MPS2-SCRN-2016-0124-0, Helecoil Installed in Bonnet Stud Hole of Valve 2-CN-52 to Repair Damaged Thread per ETE-MP-2011-0067, 7/19/16 MPS2-SCRN-2016-0143-1, Adjust Packing Load on 2-FW-51B to Eliminate Packing Leakage without Invalidating Stroke Time Results, 8/7/16 MPS2-SCRN-2016-0166-0, Replace Valve 2-SW-3.1B with AL-6XN Material, 12/30/15 MPS2-SCRN-2016-0190-0, Replace Hart Monitor LY-5030A-1 with Firmware Version, 10/19/16 MPS3-SCRN-2015-0006-0, TDAFW Governor Speed Control Switch Logic Change, 4/22/16

MPS3-SCRN-2016-0072-0, Change Trip Setpoint for MP3 Pressurizer Safety Valves Flow Monitoring Switches, 5/2/16 MPS3-SCRN-2016-0078-1, SLCRS Damper 3HVV*MOD51D Repair, 4/29/16 MPS3-SCRN-2016-0123-0, MP3 Diesel Instrument Air System, 7/28/16

MPS3-SCRN-2016-0161-0, SBO DG Vibration-Powered Hour Meter Installation, 10/4/16

MPS3-SCRN-2016-0164-0, Installation of Oversized Motor Termination Box, 9/6/16

Screen for AOP 3562, Loss of Instrument Air, 8/14/14

Screen for Changing MOV 2-SI-652 from Torque Switch to Limit Switch Control, 4/26/14 Screen for Construction of Permanent Scaffold Frames in MP2 Containment, 4/1/15 Screen for ETE-MP-2016-1097, Insulation around Yoke of Feedwater Control Valves, 6/14/16

Screen for IC 2418B/012-00, Revised TI-114 Alarm Setpoint for TCC-MP-2014-018, 8/13/14

Screen for Implementing Automatic Start Feature for the SBO Diesel Generator, 12/8/15

Screen for Installation of a Non-Safety-Related Positive Displacement Pump for Refill of the Safety Injection Accumulator, 8/17/15 Screen for OP 2204/025-10, Revise OP 2204 to Restore Functionality of RM-4296A/B, 7/11/14

Screen for Opening RHR Suction MOV breakers, 10/23/13

Screen for Rerate of MS3 Service Water Strainers to 100 psig at 100 degrees F, 5/9/14

Screen for Retire-in-Place of Millstone Unit 2 De-icing Line for the Intake Structure, 3/9/15

Modifications 10000032204, MP3 GDC Battery Charger Failure Relay, Revision, 00 Calculation 96-067, MP3 Auxiliary Feedwater System Comprehensive Flow Analysis, 10/22/14 MP2-11-01079, Replacement of Pressurizer Spray Manual Isolation Gate Valves 2-RC-252 and 2-RC-253, Revision 1 MP2-14-01001, EDG M-7A SW Coolers Supply/Discharge Lines with AL-6XN Material, 3/4/15 MP2-14-01009, Replace Shutdown Cooling Isolation Valve 2-SI-652 Motor, Revision 0

MP2-15-01097, MP2 RPS Bistable Trip Unit, Auxiliary Trip Units, and Trip Test Cable Assemblies Replacement, 9/14/16 MP3-12-01028, MP3 Reactor Vessel Head Vent Valve Replacements, Revision 1

MP3-13-01127, MP3 Replacement of Service Water Valves 3SWP*AOV39A&B due to Material Change, Revision 0 MP3-14-01027, Motor-Driven AFW Pump Lube Oil Pump 3FWL*P6A Replacement, 4/9/14

MP3-14-01070, Replace EDG Air Cooler SW Relief Valves M33SWP*RV90A/RV90B, 6/11/14

MP3-14-01107, MP3 TDAFW Pump Overspeed Margin Change, 12/2/15

A-3 MP3-14-01149, Replacement of 48/15 Vdc Power Supplies for SSPS, 10/8/14 MP3-14-01156, 3HVK CHL 1B Relay Module Replacement, 2/24/15

MP3-14-01187, MP3 RPCCW Heat Exchanger 3CCP*E1B Replacement, Revision 010 Calculations and Evaluations12-001, MP2 SW Model and Design Basis Analysis, Revision 2 12-350, MP3 Required SW Flow Rate to the CCP Heat Exchangers at 80 degrees F during LOOP and during an SIS, Revision 1 527012-189-EM, MP2 Pipe Support Calculation SW System Support No. 527012, Revision 4 90-069-01065M3, MP3 SW System, GL 89-13, Item IV, Design Basis Summary, Revision 2 95-052, Safety Grade Cold Shutdown Design Basis Analysis, Revision 6 96-001, Empirical Adjustment of the MP3 SW Model to 1995 Flow Test Data and Incorporation of the Latest SW System Design Change Notices, Revision 3 96-ENG-01279M3, MP3 - Thermal Performance Evaluation of Designated In-Service and Discretionary Components Subject to Elevated CCP Temperatures during SGCS, Revision 0 97-014, MP3 AFW System Determination of AFW Turbine and Pump Speed and AFW System Flows for Reduced Steam Generator Pressures, 10/6/14 97-129, CCP System Heat Exchangers - Process Side Temperatures Resulting from CCP System Operation at 33 F, Revision 1A CM-AA-CLC-301, SBO Calculation for NUMARC 87-00, Power Uprate to 3650 MW, 10/9/14

CR- M2-98-1764, Qualified Life of Agastat ETR/EGP/EML and E7000 Timer Delay and Control Relays, 6/18/98 DON-NAF-3-0.0-P-A, GOTHIC Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment, September 2006 EEQ-TRA-146.0, Qualification Extension Analysis Report for the Environmental Qualification of the Target Rock Solenoid Operated Globe Valves Model 12E-001, Revision 3 ETE-MP-2016-1066, Restore Sealing Capability of Damper 3HVV*MOD51D, Revision 1

ETE-MP-2016-1071, Repair of B Primary MU Water Transfer Pump Shaft (P22B), Revision 0

ETE-MP-2016-1096, MP2 Steam Generator Feedwater Regulating Valve (2-FW-51B) On-Line Packing Adjustment, Revision 2 ETE-MP-2016-1122, Oversize Motor Termination Box for 3CND-P11B, 9/6/16

ETE-NAF-2012-0152, Implementation of Revised MP2 Containment Analysis Results Required to Close OD000281 and to Support an Increase in the Ultimate Heat Sink to 80 F,

Revision 0 ETE-NAF-2013-0002, Implementation of LOCA Containment Analysis with Corrected LOCA Mass and Energy Releases for MP3, Revision 0 ETE-NAF-2013-0008, Implementation of the ABB-NV Rod Withdrawal from Subcritical Analysis for MP 3, Revision 0 ETE-NAF-3013-0106, Assessment of Operator Vital Area Actions Dose for Powering Residual Heat Removal System Motor-Operated Valves, Revision 0 Condition Reports 04-03344 235877 316440 346853 446496 451173 456066

467710 503721 506095 507788 524412 538015 542278

544616 549055 549422 551353 553558 555213 563418

563418 565191 575918 577364 578905 1030128 1030852 1035794 1036047 1037622 1053463* 1053479*

• Generated as result of this inspection

A-4 Design & Licensing Bases Safety Evaluation by the Office of Nuclear Reactor Regulation, in the Matter of Combustion Engineering, Incorporated CESSAR System 80 Docket No. STN 50-470, December 1975 Safety Evaluation by the Office of Nuclear Reactor Regulation, Related to Amendment No. 139 the Facility Operating License No. DPR-65, 3/20/89 MP2 UFSAR, Revision 34.1

MP3 UFSAR, Revision 29.1

Drawings 103225, Shts. 1 - 6, PC ASSY Bistable Trip Module, RPS, Revision B

1501042-M-25203-26008, Sht. 2, MP2 Service Water, Revision 0

25203-20182, Sht. 1, M-7A Cooling Heat Exchangers SW Supply/Discharge Piping, Revision 10

25203-26017, Sht. 1, Charging System, Revision 64

25203-26017, Sht. 2, Deborating and Purification System, Revision 38 25203-26017, Sht. 3, Boric Acid System, Revision 45 25212-23018, Sht. 207, Service Water Piping Diesel Generator Building, Revision 6

25212-23018, Sht. 208, Service Water Piping Diesel Generator Building, Revision 7

25212-26904, Sht. 1, Chemical and Volume Control, Revision 54

25212-26913, Sht. 1, High Pressure Safety Injection, Revision 32 25212-26933, Sht. 4, Service Water, Revision 48 25212-29041, Sht. 16, Lube Oil Piping - Motor Driven AFW Pump, Revision G

25212-29061, Sht. 15, Control Bldg Water Chill Electrical Diagram [3HVK*CHL1B], Revision 15

25212-29186, Sht. 10, Pressure Relief Valve, Revision A

25212-29186, Sht. 2, Pressure Relief Valve, Revision 2

25212-32001, Sht. 7KJ, 120 Vac Control Building Chiller Auxiliary Circuits, Revision 12 6822-34868A, Shts. 1 and 2, Reactor Protective System, Bistable Trip Unit Schematic, 4/8/79 D-18767-411-301, Auxiliary Trip Unit Schematic, Revision 2

NCB-1486-E, ARR130K200F, Summary Relay and ET-6 Alarm Light, 11/9/79

Miscellaneous 25203-29016, Sht. 23, Certified Test Curve for B&W Pump V2660-40, 11/7/72

45895745, Purchase Order for Module, Relay, Assembly, Conversion kit, 1/2/12

ANF-87-161, MP2 Plant Transient Analysis Report - Chapter 15 Events, September 1988

ANF-87-161, Supplement 1, MP2 Plant Transient Analysis Report - Chapter 15, October 1988

DCN DM3-00-0166-09, Change Alpha Service Water Relief Valves to Soft Seats, 11/15/09

DCN DM3-00-0167-09, Change Bravo Service Water Relief Valves to Soft Seats, 11/15/09 DCN MP2-15-01161, Replace Valve 2-SW-3.1B with AL-6XN Material, Revision 0 DCN MP3-16-01071, Install Non-Resettable Hour Meter on Station Blackout Diesel Generator Engine 3BGS-BG-A, Revision 0 DNES-AA-GN-1002, Document Impact Summary, Revision 13

DR-2994, Velan Design/Seismic Report for 3" 1500 Special Class Bolted Bonnet Gate Valve with Handwheel - Nuclear Class 1, Revision A MP2-13-01204, MP2 De-icing Line Retirement, Revision 1

MP3-13-01034, Ultimate Heat Sink Temperature, LCO Increase from 75 to 80 °F, 7/26/13

NEI 01-0, Guideline on Licensing Digital Upgrade, Revision 1

OP 3346A-14, EDG 'A' Operating Logs, 1/19/16 through 9/27/16

OP 3346A-15, EDG 'B' Operating Logs, 2/2/16 through 10/12/16 PO-MAT-0045938321, Curtiss Wright Flow Control Co, Supporting Documents for Receipt Inspection Report Package, 4/8/13 Receipt Inspection Report Package for the Battery Charger relay, 11/1/14

SO-14-017, Standing Order, Throttling TDAFW Pump Flow, Revision 1

Specification for Mechanical Refrigeration Unit, Control Building Water Chiller Cat. 1, 11/13/73

A-5 TCC-MP-2014-012, Manual Switch to Replace Fuel Transfer System Upender Vertical Position Proximity Switch, Reactor Side, Revision 0 Wyle Seismic Qualification Test Report on Two Battery Charger, 4/26/83 Procedures CEN 110, Post Repair/Replacement Leakage Test, Revision 4

CM-AA-400, 10 CFR 50.59 and 10 CFR 72.48 - Changes, Tests, and Experiments, Revision 8

CM-AA-DDC-201, Design Change, Revision 17

CM-AA-RSK-1001, Engineering Risk Assessment, Revision 14 DNES-AA-GN-1005, Failure Modes and Effects Analysis (FMEA), Revision 3 IC 2418B, RCS Temperature Instrument Calibration, Revision 015-00

MP 2703C3, I. R. Chemliner Pump, Revision 8

MP 3710AA-149E, Lubrication Maintenance Technique, Auxiliary Feedwater Pump Oil and Strainer Change, Revision 2 MP 3762WB, Generic Relief Valve Maintenance, Revision 8 MP-02-NO-GDL405, Determination of Inspection Requirements for Quality Activities, Revision 7 MP-20-WP-GDL40, Pre and Post Maintenance Testing, Revision 14

NC 1900.3B, Application of Belzona Products, Revision 1

OP 2204, Load Changes, Revision 034 OP 2304J, Boric Acid Addition to CVCS from a Temporary Borated Water Source, Revision 1 OP 3310B, Accumulator Low Pressure Safety Injection, Revision 17

OP 3314F, Control Building HVAC and Chill Water, Revision 033-00

OP 3322, Auxiliary Feedwater System, Revision 026

OP 3353.VP1C, Main Ventilation and AC Panel VP1C Annunciator Response, Revision 007-00

OPS-FH 202, Transfer Carriage and Upender Operations, Revision 4 PI-AA-200, Corrective Action, Revision 32 PT 31459A, MP# Timing Device Calibration Program, Revision 009

SP 2613A, Diesel Generator Operability Tests, Facility 1, Revision 25

SP 2613B, Diesel Generator Operability Tests, Facility 2, Revision 26

SP 3622.8, Auxiliary Feedwater Valve Operability Test, Revision 010-06 SP 3622.8-005, 3FWA*P2 Discharge Isolation Valves Stroke Time Test, Revision 000-06 SP 3622.8-012, TDAFW Pump Control Valves Stroke Time, Revision 02

SP 3626.13, Service Water Heat Exchangers Fouling Determination, Revision 22

SP 3626.14, RSS Heat Exchanger SW Supply Piping Flush, Revision 4

SP 3646A.1, Emergency Diesel Generator 'A' Operability Test, Revision 20

SP 3646A.2, Emergency Diesel Generator 'B' Operability Test, Revision 22 WM-AA-301, Operational Risk Assessment, Revision 13

Surveillance, Functional, and Modifications Acceptance Tests CBM 104, Vibration Data Acquisition and Overall Vibration Analysis, performed 11/13/14

CMP 715E, General Practices Flanges and Threaded Fasteners, performed 5/29/15 and 2/15/16 CMP 727A, Testing and Setting Pressure Relief Valves, performed 9/11/14 and 2/14/16 CMP 799D, Cutting of Installed Plant Piping, performed 10/28/14

MP 3762WB, Generic Relief Valve Maintenance, performed 2/15/16

MP-VE-9, Visual Weld Acceptance Criteria, Weldments and Brazed Joints, performed 10/28/14

OP 3346A, Emergency Diesel Generator, performed 1/19/16, 2/20/16, 6/7/16 and 9/27/16

SP 2613K, DG Slow Start Operability Test, Facility 1, performed 9/19/15 and 10/19/16 SP 2613L-001, Periodic DG Slow Start Operability Test, Facility 2 (Loaded Run), performed 10/07/15 and 10/02/16 SP 2670-007, Diesel Generator 'B' Heat Exchanger D/P Determination, performed 10/02/16

SP 3446F31-001, SSPS Refueling Tests, performed 4/22/16

SP 3622.1, AFW Pump 3FWA*P1A Operational Readiness Test, performed 11/13/14 SP 3622.3-001, TDAFW Pump Operational Readiness and Quarterly IST Group 'B' Pump Tests, performed 5/11/16 and 8/8/16

A-6 SP 3622.8-001, Auxiliary Feedwater Train 'A' Valve Stroke Time, performed 10/17/16 SP 3622.8-001, TDAFW Pump Control Valves Stroke Time, performed 8/8/16

SP 3622.8-005, 3FWA*P2 Discharge Isolation Valves Stroke Time Test, performed 5/18/16 SP 3622.8-009, Auxiliary Feedwater Train 'B' Valve Stroke Time, performed 9/5/16 SP 3622.9-001, TDAFW Pump Full Flow Test in Mode 1, performed 1/27/14

SP 3626.3, 3SWP*AOV39B, EDG B Service Water HX Outlet, Stroke Test, performed 4/17/16

Vendor Manuals, Standards, and Specifications 25212-041-001, Sulzer Bingham Pump - Installation, Operation and Maintenance of Motor-Driven Auxiliary Feedwater Pumps, Revision 9 25212-260-002, Installation, Operation & Maintenance of 200 AMP Battery Charger, Revision 1

Agastat Nuclear Qualified Time Delay Relays, Revision 1

Tyco Electronics GP/ML/TR Series 10 Amp Control Relay Non-lathing, Latching & Timing Versions, Revision 3-13 Work Orders 53102428795

53102437234

53102443647 53102633524 53102783755 53102785317 53102849166

53102351580 53102539957 53102618701 53102737935 53102737943

53102885049

LIST OF ACRONYMS 10 CFR Title 10 of the Code of Federal Regulations AFW auxiliary feedwater

ASME American Society of Mechanical Engineers

ATU auxiliary trip unit BTU bistable trip unit CGI commercial grade item

DRS Division of Reactor Safety

EDG emergency diesel generator

NEI Nuclear Energy Institute

NRC Nuclear Regulatory Commission PMT post-modification test RPCCW reactor plant closed cooling water

RPS reactor protection system

TDAFW turbine-driven auxiliary feedwater

TTCA trip test cable assembly UFSAR Updated Final Safety Analysis Report