IR 05000245/2016002

Millstone Power Station - Integrated Inspection Report 05000336/2016002 and 05000423/2016002, 04/01/2016 - 06/30/2016

ML16210A104
Person / Time
Site:	Millstone
Issue date:	07/25/2016
From:	Dentel G T Reactor Projects Branch 2
To:	Heacock D Dominion Resources
Dentel G T
References
IR 2016002
Download: ML16210A104 (44)

Text

July 25, 2016

Mr. David Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT: MILLSTONE POWER STATION - INTEGRATED INSPECTION REPORT 05000336/2016002 AND 05000423/2016002

Dear Mr. Heacock:

On June 30, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Millstone Power Station (Millstone), Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on July 25, 2016, with Mr. John Daugherty, Site Vice President, and other members of your staff.

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

This report documents one violation of NRC requirements which was of very low safety significance (Green). However, because of the very low safety significance, and because it is entered into your corrective action program, the NRC is treating this finding as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy. If you contest the non-cited violation in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Millstone. In addition, if you disagree with the cross-cutting aspect assigned to the finding, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Resident Inspector at Millstone. In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Glenn T. Dentel, 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 05000336/2016002 and 05000423/2016002

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ

SUMMARY

Inspection Report 05000336/2016002 and 05000423/2016002; 04/01/2016 - 06/30/2016; Millstone Power Station (Millstone), Units 2 and 3; Operability Determinations and Functionality Assessments.

This report covered a three-month period of inspection by resident inspectors and announced baseline inspections performed by regional inspectors. The inspectors identified one non-cited violation (NCV), which was of very low safety significance (Green). The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process," dated April 29, 2015. Cross-cutting aspects are determined using IMC 0310, "Aspects Within Cross-Cutting Areas," dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy, dated February 4, 2015. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.

Cornerstone: Barrier Integrity

Green.

The inspectors documented a self-revealing Green NCV of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," because Dominion did not develop a Unit 3 supplementary leak collection and release system (SLCRS) damper procedure that was adequate to prevent the inoperability of the system. Specifically, deficiencies in procedure SP 3614I.3A,

"Supplementary Leak Collection and Release System Boundary Isolation Damper Test," as well as the SLCRS damper monitoring program and preventative maintenance strategy, led to both trains of the Unit 3 SLCRS failing their respective surveillance tests resulting in the inoperability of secondary containment. After the issue was identified, Dominion entered the condition into their corrective action program (CAP) as condition report (CR)1033408, declared the secondary containment inoperable until the plant entered a mode of technical specifications non-applicability, and conducted walkdowns and repairs to the system to restore it to compliance. This performance deficiency was considered to be more than minor because it adversely affected the system, structure, and component (SSC) and barrier performance attribute of the Barrier Integrity cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, inadequate maintenance of the SLCRS system led to a system differential pressure during operation that was not adequate to meet its design basis surveillance requirement and thus rendered the system inoperable. Additionally, the performance deficiency was similar to IMC 0612, Appendix E, minor example 2.a. The finding was evaluated in accordance with IMC 0609, Appendix A, "The Significance Determination Process for Findings At-Power," and determined to be of very low safety significance (Green) since it only represented a degradation of the radiological barrier function provided for the auxiliary building. The finding is related to the cross-cutting aspect of Human Performance, Design Margins, because Dominion did not operate and maintain equipment within design margins. Specifically, Dominion did not appropriately monitor and maintain the SLCRS system in such a way that declining damper performance trends were identified and prevented prior to the inoperability of the system. [H.6] (Section 1R15)4

REPORT DETAILS

Summary of Plant Status Unit 2 began the inspection period at 100 percent power and remained at or near there for the duration of the inspection period.

Unit 3 began the inspection period at 100 percent power. On April 9, Unit 3 began refueling outage 3R17 which concluded on May 13. On May 15, during power ascension, operators declared a Notice of Unusual Event (NOUE) due to a main generator hydrogen gas leak into the turbine building. Unit 3 operators manually tripped the reactor in accordance with procedures.

On May 17, during power ascension following restoration from the NOUE, the main turbine tripped due to high water level in the moisture separators. Because power level at the time of the turbine trip was less than 51 percent, the reactor remained online. Dominion completed the necessary repairs and resumed power ascension. Unit 3 returned to 100 percent power on May 20. On June 12, operators identified a reactor coolant system (RCS) leak greater than allowed by technical specifications (TSs) coming from the 'A' reactor coolant pump (RCP) seal and performed a rapid downpower to take the unit offline. During the downpower, Unit 3 experienced feedwater system oscillations and operators manually tripped the reactor due to high steam generator water levels. Unit 3 returned to 100 percent power on June 25 and remained there for the duration of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

.1 External Flooding

a. Inspection Scope

On June 23, the inspectors performed an inspection of the external flood protection measures for Millstone Unit 2. The inspectors reviewed TSs, procedures, design documents, and Updated Final Safety Analysis Report (UFSAR), Chapter 2.5.4, which depicted the design flood levels and protection areas containing safety-related equipment to identify areas that may be affected by external flooding. The inspectors conducted a general site walkdown of all external areas of the plant to observe the condition of the flood gates and water flood doors. The inspectors also reviewed operating procedures for mitigating external flooding during severe weather to confirm that, overall, Dominion had established adequate measures to protect against external flooding events and, more specifically, that credited operator actions were adequate. Documents reviewed for each section of this inspection report are listed in the

.

b. Findings

No findings were identified.

.2 Summer Readiness of Offsite and Alternate Alternating Current (AC) Power Systems

a. Inspection Scope

On June 23, the inspectors performed a review of plant features and procedures for the operation and continued availability of the offsite and alternate AC power system to evaluate readiness of the systems prior to seasonal high grid loading. The inspectors reviewed Dominion's procedures affecting these areas and the communications protocols between the transmission system operator and Dominion. This review focused on changes to the established program and material condition of the offsite and alternate AC power equipment. The inspectors assessed whether Dominion established and implemented appropriate procedures and protocols to monitor and maintain availability and reliability of both the offsite AC power system and the onsite alternate AC power system. The inspectors evaluated the material condition of the associated equipment by interviewing the responsible system manager, reviewing CRs and open work orders, and walking down portions of the offsite and AC power systems including the 500 kilovolt (kV) and 220 kV switchyards.

b. Findings

No findings were identified

1R04 Equipment Alignment

.1 Partial System Walkdowns

a. Inspection Scope

The inspectors performed partial walkdowns of the following systems:

Unit 2 Reactor building closed loop cooling water pump and heat exchanger trains following attempt to isolate 'C' reactor building closed loop cooling water pump on April 15 'A' low pressure safety injection during 'B' train surveillance testing on April 28 Emergency buses 24C, 24D, and 24E on May 16 Unit 3 'B' train reactor plant closed cooling water following return to service on May 9 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the UFSAR, TSs, work orders, CRs, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted the system's performance of its intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether Dominion staff had properly identified equipment issues and entered them into the CAP for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

.2 Full System Walkdown

a. Inspection Scope

On April 20, the inspectors performed a complete system walkdown of systems pertaining to cold leg and hot leg recirculation operations to verify the existing equipment lineup would allow for successful implementation of Dominion's emergency operating procedures. The inspectors reviewed emergency operating procedures, drawings, and the UFSAR to verify that the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hanger and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify as-built system configuration matched plant documentation. The inspectors confirmed that systems and components were aligned correctly, environmentally qualified and protected against external threats. The inspectors also examined the material condition of the components for degradation and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related CRs to ensure Dominion appropriately evaluated and resolved any deficiencies.

b. Findings

No findings were identified.

1R05 Fire Protection

.1 Resident Inspector Quarterly Walkdowns

a. Inspection Scope

The inspectors conducted tours of the areas listed below to assess the material condition and operational status of fire protection features. The inspectors verified that Dominion controlled combustible materials and ignition sources in accordance with administrative procedures. The inspectors verified that fire protection and suppression equipment was available for use as specified in the area pre-fire plan, and passive fire barriers were maintained in good material condition. The inspectors also verified that station personnel implemented compensatory measures for out of service, degraded, or inoperable fire protection equipment, as applicable, in accordance with procedures.

Unit 2 Intake structure (I-1A, I-1B, I-1C) on May 25 Unit 3 Containment 3', -24' (RC-1) on April 12 Containment 51', 24' (RC-1) on April 12 Control building east and west switchgear (CB-1, CB-2) on May 10 Engineered safety features building north and south air conditioning cubicles (ESF-10, ESF-11) on May 19

b. Findings

No findings were identified.

1R07 Heat Sink Performance

(711111.07A - 1 sample)

a. Inspection Scope

The inspectors reviewed the Unit 2 'B' emergency diesel generator (EDG) heat exchangers on May 18 to determine its readiness and availability to perform its safety functions. The inspectors reviewed the design basis for the component and verified Dominion's commitments to NRC Generic Letter 89-13, "Service Water System Requirements Affecting Safety-Related Equipment." The inspectors discussed the results of the most recent inspection with engineering staff and verified that Dominion initiated appropriate corrective actions for identified deficiencies. The inspectors also verified that the number of tubes plugged within the heat exchanger did not exceed the maximum amount allowed.

b. Findings

No findings were identified.

1R08 In-service Inspection

Unit 3

a. Inspection Scope

From April 18 - 27, 2016, the inspectors conducted an inspection of the Dominion's third period, third interval in-service inspection activities during the Millstone Unit 3 refueling outage (3R17). Inspection samples were chosen based on the procedure objectives and where degradation would result in a significant increase in the risk of core damage. The inspectors observed in-process non-destructive examinations (NDEs), reviewed documentation, and interviewed Dominion personnel to verify that the NDE activities were conducted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 2004 Edition, no addenda.

Non-Destructive Examination and Welding Activities (IMC Section 02.01) The inspectors performed direct observations of NDE activities in process and reviewed records of NDEs listed below:

ASME Code Required Examinations Remote observation of a sample of automated phased array ultrasonic test (UT), volumetric examinations, of four 29-inch diameter RCS hot leg reactor vessel outlet nozzle to safe-end dissimilar metal welds (302-121-A, 302-121-B, 302-121-C, 302-121-D), four 27.5 inch diameter RCS cold leg reactor vessel inlet safe-end to nozzle dissimilar metal welds (301-121-A, 301-121-B, 301-121-C, and 301-121-D), and documentation review of all UT examination data records; A sample of remote visual (VT-3) observation of reactor internals including the baffle plates, top former plate, and bolting; Direct observation of UT examination, RCS hot leg bypass line weld (component ID RCS-504B-FW-4); Record review of UT examination reports, auxiliary and main feedwater pipe welds (component ID FWS-25-5-SW-D, FWS-25-5-SW-E and FWA-509-6-SW-2); Record review of UT, magnetic particle test, and radiographic film examination of feedwater piping replacement due to flow accelerated corrosion (component ID FWS-11-FW-88, FWS-11-FW-87, FWS-11-FW-93, FWS-11-FW-5-BM, FWS-11-FW-5-CM and FWS-11-FW-8); Record review of radiographic film of main feedwater 18 inch diameter 3321A pipe to 20-inch reducer weld (3-FWS-018-83-2 / 3321A); Direct observation of UT examination of the safety injection line welds (component ID SIL-25-FW-1-6M and SIL-25-FW-1-7M); Record review of UT examination of pressurizer surge nozzle inner radius, weld overlays, surge nozzle to lower head weld, and pressurizer relief nozzle weld overlay (component ID 03-007-SW-S(IR), 03-X-5551-X-T, RCS-SL-FW-4 and 03-007-SW-S) and pressurizer relief nozzle weld overlay (component ID 03-X5650-D-T); Direct observation of UT examination of the 'D' steam generator main and auxiliary feedwater system welds (component ID FWS-25-5-SW-E, FWS-25-5-SW-D and FWA-509-6-SW-2); and, Record review of UT examination of pressurizer relief line, pipe to safe end weld overlay (component ID RCS-513-FW-1).

The inspectors reviewed certifications of the NDE technicians performing the examinations to verify the examinations were performed by qualified individuals in accordance with approved procedures and the results reviewed and evaluated by certified Level III NDE personnel.

Other Augmented or Industry Initiative Examinations The inspectors reviewed inspections conducted to implement an industry initiative in accordance with the MRP-146, "Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines," to verify the examinations were conducted in conformance with the guidelines. The inspectors reviewed UT examination data records of 'A' and 'B' loop reactor coolant drain lines in the crossover leg piping sections 408002-FW-8 and 408001-Elbow to verify that the activities were performed in accordance with applicable examination procedures and industry guidance.

Review of Originally Rejectable Indications Accepted by Evaluation The inspectors reviewed surface examinations (M3-PT-14-025 pipe to elbow and M3-PT-14-022 pipe to tee) reports from the previous outage with relevant indications that were evaluated and accepted by Dominion for continued service. The inspectors verified that Dominion's acceptance criteria was in accordance with the ASME Section XI Code, 2004 Edition requirements and confirmed the indications were examined for acceptability for continued service.

Modification/Repair/Replacements Consisting of Welding on Pressure Boundary Risk Significant Systems Millstone Unit 3 repair/replacement activity associated with the repair of a pipe replacement due to flow accelerated corrosion (3FWS-3321A). The inspectors reviewed the ASME Section XI Repair/Replacement Program procedure, work order 53102838022, welding procedure, weld data record, welding program weld map, welding technique sheet for welding technique 109, UT examination report, and radiographic inspection reports. The inspectors reviewed the repair activity to verify the welding and applicable NDE activities were performed in accordance with ASME Section XI Code, 2004 Edition requirements. Pressurized Water Reactor Vessel Upper Head Penetration Inspection Activities (IMC Section 02.02) The inspectors reviewed the bare metal visual examination data record of the bare metal visual examination completed of the exterior surface of the reactor vessel upper head to verify that no boric acid leakage or wastage was present, noting that there was not a requirement to perform a volumetric NDE of the control rod drive mechanism welds to the reactor pressure vessel head during 3R17.

The inspectors reviewed the bare metal visual examination data records of the reactor vessel lower head in-core instrument nozzle penetration welds. The inspectors assessed the acceptability of the as-found conditions to ensure the integrity of the reactor coolant pressure boundary.

Boric Acid Corrosion Control Inspection Activities The inspectors discussed the boric acid control program with the boric acid corrosion control program owner. The inspectors also sampled photographic inspections of boric acid found on safety significant piping and components inside containment during the Mode 3 walkdowns conducted by Dominion personnel on April 10, 2016. Selected walkdowns were directly observed by the resident inspectors to verify that the visual inspections were performed in accordance with the Millstone Boric Acid Corrosion Control Program inspection procedure and checklists. The boric acid corrosion control inspection program emphasized the areas and locations where boric acid leaks could cause degradation of safety significant components and required that deficient conditions were identified and documented in the CAP.

A sample of engineering evaluations/corrective actions associated with the boric acid deficiencies were reviewed by the inspectors and verified that CRs were assigned corrective actions consistent with the requirements of the ASME Code and 10 CFR 50, Appendix B, Criterion XVI.

Steam Generator Tube Inspection Activities (IMC Section 02.04) The inspectors reviewed the Millstone Unit 3 steam generator (SG) eddy current testing (ECT) tube examinations and the applicable procedures for monitoring degradation of the SG tubes. The inspectors verified that the SG examination activities were performed in accordance with the rules and regulations of the Dominion Steam Generator Program; Unit 3 Eddy Current Data Analysis Reference Manual, U3-24-SIP-REF01; NRC generic letters; 10 CFR 50; TSs for Millstone Unit 3; Nuclear Energy Institute 97-06, "Steam Generator Program Guidelines"; Electric Power Research Institute Pressurized-Water Reactor Steam Generator Examination Guidelines; and the ASME Boiler and Pressure Vessel Code, Sections V and XI. The inspectors reviewed the Millstone Unit 3 SG inspection plan, Millstone Unit 3 Steam Generator Integrity Degradation Assessment, and Millstone Unit 3 Steam Generator Condition Monitoring and Operational Assessment for refueling outage 3R17. The SG inspection plan included ECT of all in-service tubes in SG 'B' and 'D' during this outage.

The inspectors observed a sample of ECT of the tubes in the 'B' and 'D' SGs, reviewed ECT data of various tubes, and observed data analysis and resolution activities. During the previous operating cycle no tube leakage was reported and during inspections this outage no tubes required in-situ pressure testing or plugging.

The inspectors verified that the examinations satisfied the Millstone Unit 3 TSs and the Electric Power Research Institute Pressurized-Water Reactor Steam Generator Examination Guidelines by directly observing in-process SG tube examination activity and discussing the eddy current data and results with the Dominion technical specialist responsible for the SG examinations. Identification and Resolution of Problems (IMC Section 02.05) The inspectors reviewed a sample of Millstone Unit 3 CRs, which identified flaws and other nonconforming conditions since the previous outage and during the current outage. The inspectors verified that nonconforming conditions were properly identified, characterized, evaluated, corrective actions were identified, and appropriately entered and dispositioned in the CAP.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program and Licensed Operator Performance

.1 Quarterly Review of Licensed Operator Requalification Testing and Training (3 samples)

a. Inspection Scope

The inspectors observed the following Unit 2 and Unit 3 licensed operator simulator training scenarios: Unit 2 June 3 feed regulating valve packing steam leak, a fire in the west 480 volts alternating current switchgear room, and a loss of plant process computer Unit 3 June 7 isolable RCS leak and a station blackout June 19 intervention training given to remediate gaps in operator control of the feedwater system identified during the June 12 reactor trip following the 'A' RCP seal failure The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency classifications made by the shift manager and the TS action statements entered by the unit supervisor.

Additionally, the inspectors assessed the ability of the crew and training staff to identify and document crew performance problems.

b. Findings

No findings were identified.

.2 Quarterly Review of Licensed Operator Performance in the Main Control Room

(3 samples)

a. Inspection Scope

Unit 2 The inspectors observed Unit 2 operator performance during control element assembly partial movement testing on May 24 as well as a planned downpower and quarterly turbine valve testing on May 26. The inspectors observed crew briefings and focus briefings to verify that the briefings met the criteria specified in Dominion's Operations Section Expectations Handbook. Additionally, the inspectors observed test performance to verify that procedure use, crew communications, and coordination of activities between work groups similarly met established expectations and standards.

Unit 3 The inspectors observed Unit 3 operator performance during the transition to shutdown cooling during 3R17 on April 10 and the reactor startup following an unplanned reactor trip on May 16. The inspectors observed crew briefings and focus briefings to verify that the briefings met the criteria specified in Dominion's Operations Section Expectations Handbook. Additionally, the inspectors observed performance to verify that procedure use, crew communications, and coordination of activities between work groups similarly met established expectations and standards.

b. Findings

No findings were identified.

1R12 Maintenance Effectiveness

a. Inspection Scope

The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on SSC performance and reliability. The inspectors reviewed system health reports, CAP documents, maintenance work orders, and maintenance rule basis documents to ensure that Dominion was identifying and properly evaluating performance problems within the scope of the maintenance rule. For each sample selected, the inspectors verified that the SSC was properly scoped into the maintenance rule in accordance with 10 CFR 50.65 and verified that the (a)(2) performance criteria established by Dominion staff was reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and corrective actions to return these SSCs to (a)(2). Additionally, the inspectors ensured that Dominion staff was identifying and addressing common cause failures that occurred within and across maintenance rule system boundaries.

Unit 2 Charging pump piston seal leakage on May 5 Unit 3 Pressurizer relief valves flow alarm on February 10

b. Findings

No findings were identified.

1R13 Maintenance Risk Assessments and Emergent Work Control

a. Inspection Scope

The inspectors reviewed station evaluation and management of plant risk for the maintenance and emergent work activities listed below to verify that Dominion performed the appropriate risk assessments prior to removing equipment for work. The inspectors selected these activities based on potential risk significance relative to the reactor safety cornerstones. As applicable for each activity, the inspectors verified that Dominion personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When Dominion performed emergent work, the inspectors verified that operations personnel promptly assessed and managed plant risk. The inspectors reviewed the scope of maintenance work and discussed the results of the assessment with the station's probabilistic risk analyst to verify plant conditions were consistent with the risk assessment. The inspectors also reviewed the TS requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid and applicable requirements were met. Unit 2 Electro-hydraulic control system troubleshooting following failure of the 'R' control card on April 1 'A' EDG heat exchanger maintenance window on June 1 High risk contingency plan actions for packing adjustment on 2-FW-51B on June 29 Unit 3 Decreased RCS inventory on April 13 34D 4160V bus outage on April 20 Decreased RCS inventory on May 3 Yellow risk due to decay heat removal during forced outage on June 16

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

a. Inspection Scope

The inspectors reviewed operability determinations for the following degraded or non-conforming conditions:

Unit 2 Motor control center vital area cooler electrical environmental qualification non-conformance on April 1 Reserve station service transformer to north bus disconnect switch 15G-22S1-4 position detection error on April 20 Unit 3 CR1033408, SLCRS negative pressure surveillance failed to meet acceptance criteria on April 9 Crosby service water relief valve ASME III non-conformance on April 12 Pressurizer safety valve tailpipe temperature differences on May 15 The inspectors selected these issues based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the operability determinations to assess whether TS operability was properly justified and the subject component or system remained available such that no unrecognized increase in risk occurred. The inspectors compared the operability and design criteria in the appropriate sections of the TSs and UFSAR to Dominion's evaluations to determine whether the components or systems were operable. The inspectors confirmed, where appropriate, compliance with bounding limitations associated with the evaluations.

Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were properly controlled by Dominion.

b. Findings

Introduction.

The inspectors documented a self-revealing Green NCV of 10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," because Dominion did not develop a Unit 3 SLCRS damper preventative maintenance procedure that was adequate to prevent the inoperability of the system. Specifically, deficiencies in procedure SP 3614I.3A, "Supplementary Leak Collection and Release System Boundary Isolation Damper Test," as well as the SLCRS damper monitoring program and preventative maintenance strategy, led to both trains of the Unit 3 SLCRS failing their respective surveillance tests resulting in the inoperability of secondary containment.

Description.

The Unit 3 SLCRS is a safety-related system that mitigates the radiological consequences of postulated accidents by filtering the exhaust from the secondary containment, an area that includes the containment enclosure building, engineered safety features building, auxiliary building, main steam valve building, and hydrogen recombiner building. The SLCRS consists of two redundant trains of exhaust fans, dampers, and their associated filter units. The safety function of the SLRCS is to maintain a negative pressure in the secondary containment to ensure there is no unfiltered leakage to the outside environment from these areas in the event of an accident. The SLCRS is not normally in operation, and starts upon receipt of a signal from the reactor protection system. The TS operability of the system is verified, in part, by a negative pressure surveillance test performed every refueling outage on both trains.

The surveillance verifies that the system can maintain a minimum vacuum pressure for a specified period of time (-0.40 inches water gauge or better for 120 seconds).

On April 9, 2016, Dominion conducted the Unit 3 TS required 18-month surveillance procedure 3614I.3, "SLCRS Negative Pressure Verification," and determined that the 'B' train of SLCRS did not meet the surveillance criteria acceptance criteria of -0.40 inches of water gauge negative vacuum pressure for 120 seconds. Dominion subsequently conducted the same surveillance on the 'A' train of SLCRS and determined that it too did not meet the surveillance procedure acceptance criteria. As a result of both trains of SLCRS failing their TS required surveillance criteria, Dominion declared the Unit 3 secondary containment inoperable and entered the applicable TS action statement -

3.6.6.2, "Secondary Containment." This action statement requires secondary containment to be restored to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. During the time of the conduct of the surveillance procedures, Millstone Unit 3 was in the process of conducting a plant shutdown for refueling outage 3R17 and entered Mode 5 (cold shutdown) prior to the required TS action time expiration.

A subsequent root cause evaluation conducted by Dominion (CR1033408) determined that the cause of both trains of SLCRS to not meeting their respective surveillance requirements was the failure to develop a Unit 3 SLCRS damper preventative maintenance procedure that was adequate to prevent the inoperability of the system.

Specifically, deficiencies in procedure SP 3614I.3A, "Supplementary Leak Collection and Release System Boundary Isolation Damper Test," led to Dominion personnel using SLCRS damper position indicator lights, rather than a visual observation of actual damper position, to determine the condition of the associated dampers. This directly led to the degradation of dampers such that a leakage bypass flowpath was established that degraded the ability of the system to maintain its required vacuum pressure.

Additionally, the SLCRS damper monitoring program and preventative maintenance strategies were cited as contributing causes to the degradation of the systems.

Specifically, there was no engineering program in place to monitor for damper performance and direct the performance of a specific maintenance strategy despite a history of damper performance issues that included twelve instances of auxiliary building damper degradation and three instances of main steam valve building damper degradation.

After discovery of the system degradation, Dominion personnel conducted extensive walkdowns and analysis to determine the cause of the degradation. Repairs were conducted on all components of the system where degradation was observed.

Surveillance procedure SP 3614I.3 was conducted again on both trains of SLCRS prior to the plant reaching a TS required mode of applicability. Both trains of SLCRS meet the acceptance criteria with a significant margin.

Analysis.

The inspectors determined that failing to conduct adequate maintenance on the SLCRS system was a performance deficiency within Dominion's ability to foresee and correct. This performance deficiency was considered to be more than minor because it adversely affected the SSC and barrier performance attribute of the Barrier Integrity cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events.

Specifically, inadequate maintenance of the SLCRS system led to a system differential pressure during operation that was not adequate to meet its design basis surveillance requirement and thus rendered the system inoperable. Additionally, the performance deficiency was similar to IMC 0612, Appendix E. minor example 2.a. The finding was evaluated in accordance with IMC 0609, Appendix A, "The Significance Determination Process for Findings At-Power," and determined to be of very low safety significance (Green) since it only represented a degradation of the radiological barrier function provided for the auxiliary building. The finding is related to the cross-cutting aspect of Human Performance, Design Margins, because Dominion did not operate and maintain equipment within design margins. Specifically, Dominion did not appropriately monitor and maintain the SLCRS system in such a way that declining damper performance trends were identified and prevented prior to the inoperability of the system. [H.6]

Enforcement.

10 CFR 50, Appendix B, Criterion V states, in part, "Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished." Contrary to the above, from September 12, 2012, to present, Dominion procedure SP 3614I.3A has not included appropriate quantitative or qualitative acceptance criteria for determining that positioning of the SLCRS dampers has been satisfactorily accomplished. After the issue was identified, Dominion entered the condition into their CAP (CR1033408), declared the secondary containment inoperable until the plant entered a mode of tech Spec non-applicability, and conducted walkdowns and repairs to the system to restore it to compliance. Because this issue is of very low safety significance (Green) and Dominion has entered this issue into their CAP, this finding is being treated as an NCV consistent with the NRC Enforcement Policy Section 2.3.2.a. (NCV-05000423/2016002-01: Secondary Containment Inoperability Due to Inadequate Procedures)

1R18 Plant Modifications

.1 Temporary Modifications

a. Inspection Scope

The inspectors reviewed the temporary modification listed below to determine whether the modification affected the safety functions of systems that are important to safety. The inspectors reviewed 10 CFR 50.59 documentation and post-modification testing results, and conducted field walkdowns of the modifications to verify that the temporary modification did not degrade the design bases, licensing bases, and performance capability of the affected systems.

Unit 3 reactor vessel level monitoring system sensor A2 jumpers on May 16

b. Findings

No findings were identified.

.2 Permanent Modifications

a. Inspection Scope

The inspectors evaluated the following permanent modifications to verify that the design bases, licensing bases, and performance capability of the affected systems were not degraded by the modification. In addition, the inspectors reviewed modification documents associated with the design changes, observed installation activities where possible, and reviewed revisions to control room alarm response procedures as necessary.

Unit 3 RCP seal replacement ('B' and 'C') on April 20 Unit 3 service water piping replacement for a throughwall leak on inlet header to 'D' recirculation spray system (RSS) heat exchanger on April 25 Unit 3 turbine driven auxiliary feedwater pump refueling outage 3R17 permanent modifications, May 19

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

a. Inspection Scope

The inspectors reviewed the post-maintenance tests for the maintenance activities listed below to verify that procedures and test activities ensured system operability and functional capability. The inspectors reviewed the test procedure to verify that the procedure adequately tested the safety functions that may have been affected by the maintenance activity, that the acceptance criteria in the procedure were consistent with the information in the applicable licensing basis and/or design basis documents, and that the test results were properly reviewed and accepted and problems were appropriately documented. The inspectors also walked down the affected job site, observed the pre-job brief and post-job critique where possible, confirmed work site cleanliness was maintained, and witnessed the test or reviewed test data to verify quality control hold point were performed and checked, and that results adequately demonstrated restoration of the affected safety functions.

Unit 2 'C' charging pump overhaul on May 24 Packing adjustment on 2-FW-51B feedwater regulating valve on June 30 Unit 3 'B' EDG governor replacement on April 25 Service water piping throughwall leak on inlet header to 'D' RSS heat exchanger on April 25 SLCRS negative pressure verification following surveillance test failure on May 8 'B' feedwater regulating valve positioner replacement on May 31 Steam flow instrument (FI-512) not indicating at low powers due to installation of new isolation valve in a different orientation than the previous valve on May 13 'A' EDG two year preventative maintenance window on June 10

b. Findings

No findings were identified.

1R20 Refueling and Other Outage Activities

a. Inspection Scope

The inspectors reviewed the station's work schedule and outage risk plan for the Unit 3 maintenance and refueling outage (3R17), which was conducted April 10 through May 13 and the Unit 3 forced outage from June 12 through June 25. The inspectors reviewed Dominion's development and implementation of outage plans and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed portions of the shutdown and cooldown processes and monitored controls associated with the following outage activities:

Configuration management, including maintenance of defense-in-depth, commensurate with the outage plan for the key safety functions and compliance with the applicable TSs when taking equipment out of service Implementation of clearance activities and confirmation that tags were properly hung and that equipment was appropriately configured to safely support the associated work or testing Installation and configuration of reactor coolant pressure, level, and temperature instruments to provide accurate indication and instrument error accounting, particularly during activities associated with the highest level of shutdown risk, which occurred during the RCS drain-down for reactor vessel head de-tensioning and lift activities, as well as the drain-down to reinstall and tension the reactor vessel head Status and configuration of electrical systems and switchyard activities to ensure that TSs were met Monitoring of decay heat removal operations during initial transition to shutdown cooling, as well as activities associated with spent fuel pool cooling following full core off-load Impact of outage work on the ability of the operators to operate the spent fuel pool cooling system Reactor water inventory controls, including flow paths, configurations, alternative means for inventory additions, and controls to prevent inventory loss Activities that could affect reactivity Maintenance of secondary containment as required by TSs Refueling activities, including fuel handling and fuel receipt inspections Fatigue management that involved covered workers and review of work hour controls Final containment closeout walkdown to verify that debris or equipment had not been left inside, particularly in areas that could impact operability of the containment recirculation sumps Reactor start-up, plant heat-up, and power ascension activities; and Identification and resolution of problems related to refueling outage activities

b. Findings

No findings were identified.

1R22 Surveillance Testing

a. Inspection Scope

The inspectors observed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR, and Dominion procedure requirements. The inspectors verified that test acceptance criteria were clear, tests demonstrated operational readiness and were consistent with design documentation, test instrumentation had current calibrations and the range and accuracy for the application, tests were performed as written, and applicable test prerequisites were satisfied. Upon test completion, the inspectors considered whether the test results supported that equipment was capable of performing the required safety functions. The inspectors reviewed the following surveillance tests:

Unit 2 SP 2604D-002, 'B' low pressure safety injection pump and valve test on April 28 SP 2620A, control element assembly partial movement test on May 24 SP 2651N, main turbine control valve operability test on May 26 SP 2601H, 'C' charging pump comprehensive test on May 27 (IST) Unit 3 Train 'B' emergency safeguards feature with loss of power test on April 29 'A' RCP seal supply isolation 3CHS*MV8109A local leak rate test on May 10 (containment isolation valve) RCS leakage on May 24 Power operated relief valve block valve cycling on June 10

b. Findings

No findings were identified.

RADIATION SAFETY

Cornerstone:

Occupational and Public Radiation Safety

2RS1 Radiological Hazard Assessment and Exposure Controls

a. Inspection Scope

The inspectors reviewed Dominion's performance in assessing and controlling radiological hazards in the workplace. The inspectors used the requirements contained in 10 CFR 20, TSs, applicable regulatory guides (RGs), and the procedures required by TSs as criteria for determining compliance.

Inspection Planning

The inspectors reviewed radiation protection program audits and reports of operational occurrences in occupational radiation safety since the last inspection.

Radiological Hazard Assessment The inspectors conducted independent radiation measurements during walkdowns of the facility and reviewed the radiological survey program, air sampling and analysis, continuous air monitor use, recent plant radiation surveys for radiological work activities, and any changes to plant operations since the last inspection to verify survey adequacy of any new radiological hazards for onsite workers or members of the public. Instructions to Workers (1 sample) The inspectors reviewed high radiation area radiation work permit controls and use, and observed containers of radioactive materials and assessed whether the containers were labeled and controlled in accordance with requirements.

The inspectors reviewed several occurrences where a worker's electronic personal dosimeter alarmed. The inspectors reviewed Dominion's evaluation of the incidents, documentation in the corrective action program, and whether compensatory dose evaluations were conducted when appropriate. The inspectors verified follow-up investigations of actual radiological conditions for unexpected radiological hazards were performed. Radiological Hazards Control and Work Coverage (1 sample) The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors assessed whether posted surveys, radiation work permits, worker radiological briefings and radiation protection job coverage, continuous air monitoring use, air sampling and engineering controls, and dosimetry monitoring were consistent with the present plant conditions. The inspectors examined the control of highly activated or contaminated materials stored within the spent fuel pools and the posting and physical controls for selected high radiation areas, locked high radiation areas, and very high radiation areas to verify conformance with the occupational performance indicator. Radiation Worker Performance and Radiation Protection Technician Proficiency (1 sample) The inspectors evaluated radiation worker performance with respect to radiation protection work requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage.

b. Findings

No findings were identified.

2RS2 Occupational ALARA Planning and Controls

a. Inspection Scope

The inspectors assessed Dominion's performance with respect to maintaining occupational individual and collective radiation exposures as low as is reasonably achievable (ALARA). The inspectors used the requirements contained in 10 CFR 20, applicable RGs, TSs, and procedures required by TSs as criteria for determining compliance.

Inspection Planning

The inspectors conducted a review of Millstone's ongoing and planned radiological work activities and radiological source term history and trends. Source Term Reduction and Control The inspectors observed radiological work activities and evaluated the use of shielding and other engineering work controls based on the radiological controls and ALARA plans for those activities.

Radiation Worker Performance (1 sample)

The inspectors observed radiation worker and radiation protection technician performance during radiological work to evaluate worker ALARA performance according to specified work controls and procedures. Workers were interviewed to assess their knowledge and awareness of planned and/or implemented radiological and ALARA work controls.

b. Findings

No findings were identified.

2RS3 In-Plant Airborne Radioactivity Control and Mitigation

a. Inspection Scope

The inspectors reviewed the control of in-plant airborne radioactivity and the use of respiratory protection devices in these areas. The inspectors used the requirements in 10 CFR 20, RG 8.15, RG 8.25, NUREG/CR-0041, TS, and procedures required by TS as criteria for determining compliance. Inspection Planning The inspectors reviewed the UFSAR to identify ventilation and radiation monitoring systems associated with airborne radioactivity controls and respiratory protection equipment staged for emergency use. The inspectors also reviewed respiratory protection program procedures and current performance indicators for unintended internal exposure incidents.

Engineering Controls (1 sample) The inspectors reviewed operability and use of both permanent and temporary ventilation systems, and the adequacy of airborne radioactivity radiation monitoring in the plant based on location, sensitivity, and alarm set-points.

Use of Respiratory Protection Devices (1 sample) The inspectors reviewed the adequacy of Dominion's use of respiratory protection devices in the plant to include applicable ALARA evaluations, respiratory protection device certification, respiratory equipment storage, air quality testing records, and individual qualification records.

Self-Contained Breathing Apparatus (SCBA) for Emergency Use (1 sample) The inspectors reviewed the following: the status and surveillance records for three SCBAs staged in-plant for use during emergencies; Dominion's SCBA procedures and maintenance and test records; the refilling and transporting of SCBA air bottles; SCBA mask size availability; and the qualifications of personnel performing service and repair of this equipment.

Problem Identification and Resolution (1 sample) The inspectors evaluated whether problems associated with the control and mitigation of in-plant airborne radioactivity were identified at an appropriate threshold and addressed by Dominion's CAP.

b. Findings

No findings were identified.

4OA1 Performance Indicator Verification

.1 Unplanned Scrams, Unplanned Power Changes, and Unplanned Scrams with Complications (6 samples)

a. Inspection Scope

The inspectors reviewed Dominion's submittals for the following Initiating Events Cornerstone performance indicators for the period of April 1, 2015, through March 31, 2016:

Unit 2 Unplanned scrams per 7000 critical hours Unplanned scrams with complications Unplanned transients per 7000 critical hours Unit 3 Unplanned scrams per 7000 critical hours Unplanned scrams with complications Unplanned transients per 7000 critical hours To determine the accuracy of the performance indicator data reported during those periods, inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, and NUREG-1022, "Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73."

The inspectors reviewed Dominion's operator narrative logs, maintenance planning schedules, CRs, event reports, and NRC integrated inspection reports to validate the accuracy of the submittals.

b. Findings

No findings were identified.

4OA2 Problem Identification and Resolution

.1 Routine Review of Problem Identification and Resolution Activities

a. Inspection Scope

As required by Inspection Procedure 71152, "Problem Identification and Resolution," the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that Dominion entered issues into the CAP at an appropriate threshold, gave adequate attention to timely corrective actions, and identified and addressed adverse trends. In order to assist with the identification of repetitive equipment failures and specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into the CAP and periodically attended CR screening meetings.

b. Findings

No findings were identified.

.2 Annual Sample:

Performance Issues with Units 2 and 3 Control Room Simulators

a. Inspection Scope

The inspectors performed an in-depth review of Dominion's evaluations and corrective actions associated with degraded simulator performance during the first half of calendar year 2015. An in-depth review was performed of Common Cause Analysis CR582505 / CCA000338 and Apparent Cause Analysis CR1005914, assessing Dominion's evaluation and corrective actions to determine whether the corrective actions were appropriate. Additionally, the inspectors reviewed two completed Unit 2 simulator deficiency report (DR) packages associated with simulator enhancement modifications for modeling of events similar to the shutdown cooling relief valve 2-SI-468 lift event of October 4, 2015.

b. Findings and Observations

No findings were identified. The inspectors determined Dominion's evaluation appropriately identified the causes and that corrective actions were adequate to resolve the simulator performance issues.

DR 2015-2-0040 was generated to create a new simulator malfunction feature to model a failure of shutdown cooling relief valve 2-SI-468. In addition to creating the new malfunction, code changes were implemented under this DR to have the relief valve more accurately model actual plant valve response. The inspector determined that a variable in the code was incorrectly named, such that the accuracy of valve modeling was not improved by these changes. This undesired result should have been identified and corrected by Dominion's simulator modification validation and verification process. CR1039577 and DR 2016-2-0050 were initiated to correct this condition.

DR 2016-2-0003 was generated to create a new simulator malfunction feature to simulate failure of charging system relief valve 2-CH-986. This variable severity malfunction was tested by facility staff at a partial severity, simulating the valve failing partially open, prior to testing at its 100 percent severity (valve fully open). The inspector, while observing simulation of the malfunction with one of the facility's simulator software engineers, determined the valve remained full open when malfunction severity was reduced, after first initiating the malfunction at 100 percent severity. This undesired result should have been identified and corrected by Dominion's simulator modification validation and verification process. CR1039577 and DR 2016-2-0049 were initiated to correct this condition.

Both of these issues screened to minor in accordance with IMC 0612, Appendix B, because the issues did not adversely affect any of the cornerstone objectives.

4OA3 Follow-up of Events and Notices of Enforcement Discretion

.1 Plant Events

a. Inspection Scope

For the plant events listed below, the inspectors reviewed and/or observed plant parameters, reviewed personnel performance, and evaluated performance of mitigating systems. The inspectors communicated the plant events to appropriate regional personnel, and compared the event details with criteria contained in IMC 0309, "Reactive Inspection Decision Basis for Reactors," for consideration of potential reactive inspection activities. As applicable, the inspectors verified that Dominion made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR Parts 50.72 and 50.73. The inspectors reviewed Dominion's follow-up actions related to the events to assure that Dominion implemented appropriate corrective actions commensurate with their safety significance.

Unit 3 reactor trip and NOUE on May 15 Unit 3 turbine trip on May 17 Unit 3 unplanned downpower for 'A' RCP seal failure and subsequent reactor trip on June 12

b. Findings

No findings were identified.

.2 (Closed) Licensee Event Report (LER) 05000423/2016-002-00:

Feedwater Isolation Signal Defeated Due to Wiring Error On January 25, 2016, an automatic reactor trip occurred at Millstone Unit 3 due to a loss of the 'B' RCP. While operators were performing feedwater isolation actuation verification steps, it was identified that the 'C' feedwater isolation valve (FWIV),

3FWS*CTV41C, did not auto close as expected. Operators subsequently closed the 'C' FWIV from the control room. The automatic closure of the 'C' FWIV is required by TS 3.3.2 and Table 3.3-3. Its failure to automatically close therefore represents a condition that is prohibited by TSs. The ability to automatically isolate main feedwater was maintained due to redundant valves in series with the 'C' FWIV that operated correctly during the event. The cause of the 'C' FWIV failure to close was determined to be a temporary jumper being inadvertently left installed in November 2014 during maintenance due to human error. The inspectors identified a self-revealing Green NCV associated with this event that was dispositioned in Inspection Report 05000336/2016001 and 05000423/2001601, Section 1R19 (Agencywide Documents Access and Management System Accession No. ML16125A122). This LER is closed.

.3 (Closed) Licensee Event Report (LER) 05000423/2016-003-00:

Loss of Safety Function - Supplementary Leak Collection and Release System On April 9, 2016, Dominion conducted the Unit 3 TS required 18-month surveillance procedure 364I.3, "SLCRS Negative Pressure Verification," and determined that the 'B' train of SLCRS did not meet the surveillance criteria acceptance criteria of -0.40 inches of water gauge negative vacuum pressure for 120 seconds. Dominion subsequently conducted the same surveillance on the 'A' train of SLCRS and determined that it too did not meet the surveillance procedure acceptance criteria. As a result of both trains of SLCRS failing their TS required surveillance criteria, Dominion declared the Unit 3 secondary containment inoperable and entered the applicable TS action statement -

3.6.6.2, "Secondary Containment." This action statement requires secondary containment to be restored to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. During the time of the conduct of the surveillance procedures, Millstone Unit 3 was in the process of conducting a plant shutdown for refueling outage 3R17 and entered Mode 5 (cold shutdown) prior to the required TS action time expiration. The enforcement aspects of this issue are discussed in Section 1R15. The inspectors did not identify any new issues during the review of the LER. This LER is closed.

4OA6 Meetings, Including Exit

On July 25, 2016, the inspectors presented the inspection results to Mr. John Daugherty, Site Vice President, and other members of the Millstone staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

J. Daugherty, Site Vice President

C. Olsen, Plant Manager

L. Armstrong, Director, Performance Recovery

R. Borchart, Senior Reactor Engineer

B. Bowen, Shift Supervisor, Health Physics

M. Bradley, Supervisor Health Physics Operations

J. Brookmiller, U-3 Outage Coordinator

J. Burkirk, Outage Control Center Health Physics Representative

S. K. Chang, Simulator Support Engineer

T. Cleary, Supervisor, Licensing

G. Closius, Licensing

G. Cochran, Supervisor, Nuclear Site Safety

M. Cote, Supervisor - Nuclear Training S, Doboe, Unit 2 Shift Manager

D. DelCore, Shift Supervisor, Health Physics

D. Dodson, Manager of Programs

M. Dunivan, Supervisor, Health Physics Auxiliary Building

S. Galbo, Fire Safety Technician

K. Gannon, Supervisor, Health Physics

M. Garza, Refueling Team (OCC)

W. Gorman, RMS Supervisor

B. Graber, Supervisor Exposure Control and Instrumentation

M. Hall, Dominion Corporate Welding Engineer

K. Hacker, Dominion Corporate Level III

K. Miles, Shift Supervisor, Health Physics

L. Hahn, Supervisor - IT Business Accounts

C. Karpinski, Senior Nuclear Instructor

L. Lebaron, System Engineer

J. Lebruto, Design Engineering

A. Leone, Shift Manager

D. Mello, Senior Fire Instructor

B. Pinkowitz. Operations Instructor L. Salyards, Licensing

L. Seplak, Regulatory Assurance

D. Smith, Site Emergency Preparedness Manager

T. Spakowski, Senior Nuclear Training Instructor

P. Sucholet, Manager - IT Process Systems

M. Sweet, Shift Supervisor, Health Physics

M. Stark, Nuclear Technical Specialist, ISI/NDE - Steam Generators

C. Tan, Simulator Support Engineer

J. Taylor, Supervisor, Health Physics Outage Containment

T. Thull, Boric Acid Program Manager

S. Turowski, Manager, Radiation Protection and Chemistry

K. Underwood, Operations Instructor

C. Walsh, Superintendent - Nuclear Operations Training

R. Wesley, Director - Nuclear Training

S. Williams, Lead Nuclear Chemistry Technician

M. Wynn, Supervisor, Radiological Analysis

R. Zieber, Nuclear Technical Specialist, ISI/NDE

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened/Closed

05000336/2016002-01 NCV Secondary Containment Inoperability Due to Inadequate Procedures (Section 1R15)

Closed

05000423/LER-2016-002-00 LER Feedwater Isolation Signal Defeated Due to Wiring Error (Section 4OA3)

05000423/LER-2016-003-00 LER Loss of Safety Function - Supplementary Leak Collection and Release System (Section 4OA3)

Section 1R01: Adverse Weather Protection

Procedures

OP 2356, Doors, Revision 004

AOP 2560, Storms, High Winds, High Tides, Revision 016

MP 2701E, Unit 2 Flood Gates Installation and Removal, Revision 000-01

SP 2665, Building Flood Gate Inspections, Revision 005-05

MP-01-SM-GDL01.03, Power Change, Outage Notification, and Communication Protocol, Revision 003

AOP 3569, Severe Weather Conditions, Revision 022

AOP 2508, Loss of 23kV Off-Site Power, Revision 001-06 Millstone Switchyard NEIL Weekly Insurance Inspection, Revision 4

AOP3577, Loss of Normal and Off-Site Power to a 4.16kV Emergency Bus, Revision 3

OP 2508, Loss of 23kV Off-Site Power, Revision 001-06

SP 2619G, Surveillance Form TS 3.8.1.1 action a.-One Off-Site Circuit Inoperable, Revision 002-03

SP 3646A.7-003, Surveillance Form TS 3.8.1.1 action a. - One Off-site Circuit and One EDG Inoperable, Revision 006

SP 3646A.7-001, Surveillance Form TS 3.8.1.1 action a. - One Off-site Circuit Inoperable, Revision 009

Condition Reports

370289

581747

1018031

1009399

1008618

1004750

1002348

582671

22660

Work Orders

53102864599 53102527483

Section 1R04: Equipment Alignment

Procedures

EOP 35

ES-1.4, Transfer to Hot Leg Recirculation, Revision 011

EOP 35

FR-C.2, Response to Degraded Core Cooling, Revision 013-01

EOP 35

FR-C.1, Response to Inadequate Core Cooling, Revision 017-01

EOP 35

ECA-3.2, SGTR with Loss of Reactor Coolant - Saturated Recovery Desired, Revision 015

EOP 35

ECA-3.1, SGTR with Loss of Reactor Cooling - Subcooled Recovery Desired, Revision 020

EOP 35

ES-1.3, Transfer to Cold Leg Recirc, Revision 016

EOP 35

ES-1.2, Post LOCA Cooldown and Depressurization, Revision 019

EOP 35 E-1, Loss of Reactor or Secondary Coolant, Revision 026

MA-AA-105, Scaffolding, Revision 16

Drawings

1279-EM-121A, Reactor Plant Component Cooling System, Revision 32 25212-26902, Reactor Coolant System, Revision 32

212-26912, Low Pressure Safety Injection, Revision 22

212-26912, Low Pressure Safety Injection, Revision 50

212-29013, High Pressure Safety Injection, Revision 41

SKM-CMC-SFTINJ, Updated 5-28-02 25203-30001, Main Single Line Diagram, Revision 40

203-30005, Single Line Meter and Relay Diagram 4.16kV Emergency Buses 24C and 24D, Revision 21 25203-30008, Single Line Diagram 480V Unit Substation Emergency 22E and 22F, Revision 21 25203-26015, Sheet 1, P&ID Low Pressure Safety Injection System, Revision 46 25203-26022, Sheet 1, P&ID RBCCW System, RBCCW Pumps and Heat Exchangers,

Revision 45

Condition Reports

576668

576660

704830

1037635

1037768

Maintenance Orders/Work Orders 53M30707306

53102352419 53M20303868

Miscellaneous

Millstone Unit 3 Updated Final Safety Analysis Report

Section 1R05: Fire Protection

Procedures

MP-PROC-ENG-U2-24-FFS-BAP01-INT, MSP2 Fire Fighting Strategies Intake Structure,

Revision 0

MP-PROC-ENG-U3-24-FFS-BAP01-RC, MSP3 Fire Fighting Strategies Containment Structure,

Revision 0

MP-PROC-ENG-U3-24-FFS-BAP01-RC-MAP, Containment Building Fire Strategy Map,

Revision 0

MP-PROC-ENG-U3-24-FFS-BAP01-CB-MAP, Control Building Fire Strategy Map, Revision 0

Miscellaneous

Millstone Unit 3 Updated Final Safety Analysis Report

Section 1R06: Heat Sink Performance

Condition Reports

575328

538282

Work Orders

53102842743

53102725788

53102842745

53102958249

53102842747

Miscellaneous

Calculation 94-DES-1111-M2, MP2 SWS Maximum Allowable Temperature to EDG Heat Exchangers at 1800KW and 2750KW Electrical Load Levels with 5% Tubes Plugged in Each Unit, Revision 00 Calculation Change Notice 1 to Calculation 94-DES-1111-M2, MP2 SWS Maximum Allowable Temperature to EDG Heat Exchangers at 1800KW and 2750KW Electrical Load Levels with 5% Tubes Plugged in Each Unit, Revision 00 Calculation 12-328, Equivalent Thermal Performance of Unit 2 EDG Heat Exchangers for UHS Temperature Increase, Revision 0

Section 1R08: In-service Inspection Activities

Procedures

ER-AA-ISI-10, ASME Section XI Inservice Inspection Program, Revision 4

ER-AA-ISI-100, Dominion Inservice Inspection Program, Revision 8

ER-AA-NDE-133, Performance of Phased Array Instrument Screen Height and Amplitude Control Linearity Checks, Revision 0

ER-AA-NDE-140, Processing of Dominion NDE Data, Revision 5

ER-AA-NDE-MT-200, ASME Section XI Magnetic Particle Examination Procedure, Revision 4

ER-AA-NDE-PT-300, ASME Section XI Liquid Penetrant Examination Procedure, Revision 7

ER-AA-NDE-RT-400, Radiographic Examination Procedure, Revision 0

ER-AA-NDE-VT-601,

VT-1 Visual Examination Procedure, Revision 3

ER-AA-NDE-VT-602,

VT-2 Visual Examination Procedure, Revision 4

ER-AA-NDE-VT-603,

VT-3 Visual Examination Procedure, Revision 4

ER-AA-NDE-VT-607, VE Visual Examination of Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Revision 1

ER-AA-NDE-UT-701, Ultrasonic Thickness Measurement Procedure, Revision 6

ER-AA-NDE-UT-702, Ultrasonic Examination of Ferritic Vessel Welds Greater Than 2.0" in Thickness, Revision 4

ER-AA-NDE-UT-705, Ultrasonic Examination Procedure of Vessel Nozzle Inside Radius Sections, Revision 0

ER-AA-NDE-UT-706,

Ultrasonic Examination for the Detection of Laminar Indications, Revision 0

ER-AA-NDE-UT-722,

Ultrasonic Examination of Pressure Vessel Repair Welds in Accordance with ASME Section VIII Requirements, Revision 1

ER-AA-NDE-UT-740, Encoded Phased Array Ultrasonic Examination of Ferritic Piping Welds, Revision 0

ER-AA-NDE-PT-301, Balance of Plant Liquid Penetrant Examination Procedure, Revision 7

ER-AA-NDE-800, Appendix VIII Qualified Equipment Tables for PDI Generic Procedures, Revision 4

ER-AA-NDE-UT-802, Ultrasonic Examination of Austenitic Piping Welds in Accordance with ASME Section XI, Appendix VIII, Revision 4

ER-AA-NDE-UT-804, Bore Probe Ultrasonic Examination of Studs and Bolts in Accordance with ASME Section XI, Appendix VIII, Revision 2

ER-AA-NDE-UT-805, Straight Beam Ultrasonic Examination of Studs and Bolts in Accordance with ASME Section XI, Appendix VIII, Revision 3

ER-AA-NDE-UT-806, Ultrasonic Examination of Reactor Vessel Welds in Accordance with ASME Section XI, Appendix VIII, Revision 1

ER-AA-NDE-810, Ultrasonic Examination of Dissimilar Metal Welds in Accordance with ASME Section XI, Appendix VIII, Revision 2

ER-AA-FAC-1002, Flow-Accelerated Corrosion (FAC) Inspection and Evaluation Activities, Revision 10

ER-AP-BAC-10, Boric Acid Corrosion Control Program, Revision 12

ER-AP-BAC-101, Boric Acid Corrosion Control Program (BACCP) Inspections, Revision 12

ER-MP-BAC-101, Millstone Boric Acid Corrosion Control Planned Inspections, Revision 1

ER-AA-RRM-100, ASME Section XI Repair/Replacement Program Fleet Implementation Requirements, Revision 6 VPROC ENG16-001, Remote Underwater Visual Examination of Reactor Pressure Vessels, Vessel Internals and Components in Pressurized Water Reactors (54-ISI-364-007), Revision 000 VPROC ENG16-002, Automated Phased Array Ultrasonic Examination of Large Diameter Austenitic and Dissimilar Metal Piping Welds from the Inside Surface For Depth Sizing (54-ISI-875-000), Revision 000 VPROC ENG16-003, Automated Phased Array Ultrasonic Examination of Large Diameter Austenitic and Dissimilar Metal Piping Welds from the Inside Surface For Detection and Length Sizing, Revision 000 VPROC ENG16-004, 3D Inside Surface Profiling of Piping Welds With Immersion Phased Array, Revision 000 U3-24-SIP-REF01, Unit 3 Steam Generator Eddy Current Data Analysis Reference Manual, Revision 8

WTS 109, Welding Technique Sheet, Manual Welding Gas Tungsten Arc Welding, Revision 11

NDE Records M3-VT-16-070, Visual Examination System Leakage (VT-2) data record, Reactor vessel lower head (58) in-core instrument nozzle penetration welds, dated April 20, 2016 M3-UT-16-026, UT Examination Report, reducer to pipe, component ID

FWS-11-FW-5-CM, dated April 26, 2016 M3-UT-16-031, UT Examination Report, reactor coolant drain line loop A BM elbow between

FW-2 and

FW-3 extrados and flanks, component

ID 408001-Elbow, dated April 20, 2016 M3-UT-16-034, UT Examination Report, reactor coolant drain line loop B elbow to pipe, component

ID 408002-FW-8, dated April 20, 2016

M3-UT-16-052, UT Examination data record, pressurizer relief nozzle to safe end weld overlay at 278 Az., component

ID 03-X-5650-D-T, dated April 24, 2016 M3-UT-16-054, UT Indication Report, pressurizer relief line pipe to safe end weld overlay, component ID

RCS-513-FW-1, dated April 26, 2016 M3-UT-16-063, UT Examination Report, feedwater pipe to reducer, component ID

FWS-11-FW-88, dated April 22, 2016 M3-UT-16-064, UT Examination data record, pressurizer surge nozzle inner radius, component

ID 03-007-SW-S(IR), dated April 23, 2016 M3-UT-16-065, UT Examination data record, pressurizer surge nozzle to lower head, component

ID 03-007-SW-S, dated April 25, 2016 M3-UT-16-070, UT Examination data record, safety injection elbow to pipe, component ID

SIL-25-FW-1-6M, dated April 25, 2016 M3-UT-16-071, UT Examination data record, safety injection elbow to pipe, component ID

SIL-25-FW-1-7M, dated April 25, 2016 M3-UT-16-072, UT Examination data record, pressurizer surge nozzle pipe to safe end weld overlay, component ID

RCS-SL-FW-4, dated April 24, 2016 M3-UT-16-073, UT Examination data record, pressurizer surge nozzle to safe end weld overlay, component

ID 03-X-5551-X-T, dated April 24, 2016 M3-UT-16-074, UT Examination data record of D steam generator auxiliary feedwater pipe to elbow, dated April 22, 2016 M3-UT-16-077, UT Examination data record, D steam generator main feedwater pipe to elbow, component ID

FWS-25-5-SW-D, dated April 24, 2016 M3-UT-16-078, UT Indication Report, D steam generator main feedwater elbow to pipe, component ID

FWS-25-5-SW-E, dated April 24, 2016 M3-UT-16-081, UT Indication Report, Loop B Bypass, pipe to valve V-4, component ID

RCS-504B-FW-4, dated April 24, 2016 M3-UT-16-104, UT Examination Report, feedwater pipe to valve (V-15), component ID

FWS-11-FW-8, dated May 7, 2016 M3-UT-16-106, UT Examination Report, feedwater pipe to reducer, component ID

FWS-11-FW-5-BM, dated May 7, 2016 M3-UT-16-108, UT Examination Report, feedwater valve to pipe, component ID

FWS-11-FW-93, dated May 8, 2016 M3-UT-16-110, UT Examination Report, reducer to pipe, component ID

FWS-11-FW-88, dated April 22, 2016 M3-MT-16-006, MT data record, feedwater reducer to pipe, component ID

FWS-11-FW-5-CM, dated April 17, 2016 M3-MT-16-015, MT data record, feedwater pipe to reducer, component ID

FWS-11-FW-88, dated April 20, 2016 M3-MT-16-024, MT data record, feedwater pipe to valve (V-15), component ID

FWS-11-FW-8, dated May 7, 2016 M3-MT-16-025, MT data record, feedwater pipe to reducer, component ID

FWS-11-FW-5-BM, dated May 7, 2016 M3-MT-16-026, MT data record, feedwater reducer to pipe, component ID

FWS-11-FW-93, dated May 7, 2016 M3-MT-16-027, MT data record, feedwater valve to pipe, component ID

FWS-11-FW-87, dated May 7, 2016 M3-VT-16-119, Visual Examination System Leakage (VT-2) RPV closure Nozzle to Head (79) penetrations, dated April 24, 2016 M3-1243, RT Inspection Report, feedwater piping FAC replacement, component

ID 16" / 18" Reducer to Pipe

FW-5C-M, dated May 10, 2016

M3-1244, RT Inspection Report, feedwater piping FAC replacement, component

ID 18" Pipe to 20" Reducer, dated May 7, 2016 M3-1249, RT Inspection Report, feedwater piping FAC replacement, component

FWS-11-FW-5B-M, dated May 7, 2016 M3-1250, RT Inspection Report, feedwater piping FAC replacement, component

FWS-11-FW-8, dated May 7, 2016 M3-1251, RT Inspection Report, feedwater piping FAC replacement, component ID

FWS-11-FW-87, dated May 7, 2016 M3-1252, RT Inspection Report, feedwater piping FAC replacement, component

FWS-11-FW-93, dated May 7, 2016 M3-1253, RT Inspection Report, feedwater piping FAC replacement, component

FWS-11-FW-8 R1, dated May 7, 2016 M3-1254, RT Inspection Report, feedwater piping FAC replacement, component

FWS-11-FW-5B-M R1, dated May 7, 2016 M3-1255, RT Inspection Report, feedwater piping FAC replacement, component ID

FWS-11-FW-87 final post PWHT, dated May 7, 2016 M3-1256, RT Inspection Report, feedwater piping FAC replacement, component ID

FWS-11-FW-93 R1, dated May 7, 2016 M3-PT-14-022, Liquid Penetrant Examination Report, pipe to tee, component ID

RHS-9-2-SW-F, dated October 14, 2014 M3-PT-14-025, Liquid Penetrant Examination Report, pipe to elbow, component ID

RSS-15-4-SW-C, dated October 14, 2014

ETE-MP-2016-1083, RCS Loop Isolation Valve 3RCS*MV8002A and 3RCS*MV8001C, Packing Gland Leak-Off Line Through Wall Leakage Engineering Disposition

Condition Reports

563995

1034686

1033776

1024651

1033863

564231

Miscellaneous

Millstone Unit 3, 3R17 RPV Nozzle to Safe-end DM Weld UT Examination Report, Document No. 180-9256102-000 Millstone MPS3R17 Reactor Vessel Internals Visual Examinations Report, Document No. 180-9256525-000 Millstone Unit 3 Steam Generator Integrity Condition Monitoring and Operational Assessment Refueling Outage 3R17, Revision 0 Millstone Unit 3 Steam Generator Integrity Degradation Assessment (R17), Revision 0 Audit 11-07, Inservice Inspection/Inservice Testing, September 26, 2011

Millstone Unit 3, 3R17 ECT Field Report, April 25, 2016

Section 1R11: Licensed Operator Requalification Program

Procedures

OP 3201, Plant Heatup, Revision 025

OP 3203, Plant Startup, Revision 021

OP 3202, Reactor Startup (ICCE), Revision 022

AOP 3575, Rapid Downpower, Revision 020-01

EOP 35 ES 0.1, Reactor Trip Response, Revision 027-00

EOP 35 E-0, Reactor Trip or Safety Injection, Revision 31

Reactivity Plan, Turbine Valve Testing - Revision 0

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

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

SP 2651N, Main Control Valve Operability Test, Revision 006

AOP 2518, Loss of Plant Process Computer, Revision 001

AOP 2559, Fire, Revision 009

AOP 2503E, Loss of Non-Vital 480 VAC Bus 22E, Revision 004

SP 2411A, CEA Motion Inhibit Verification (Deviation), Revision 003-02

SP 2620A, CEA Partial Movement, Revision 017

Work Orders

53102904619

53102904623

53102904625

53102869928

53102901830

Section 1R12: Maintenance Effectiveness

Procedures

OP 3353.MB4A, Pressurizer Safety Valve Discharge Flow, Revision 002-20

Condition Reports

1032843

1032924

1039447

1005482

1005257

CA3024354

CA3024204

CA3016038 CA3015132

CA3011482

Miscellaneous

Unit 3 Reactor System Leakage Report dated February 9, 2016 at 1704:43

Unit 2 Reactor System Leakage Report dated April 7, 2016 at 07:20:45 System Health Report, 1Q16, Millstone Unit 2, 2304A, B, C, CVCS, Letdown and Boric

Section 1R13: Maintenance Risk Assessments and Emergent Work Control

Procedures

NF-AA-PRA-370, Probabilistic Risk Assessment Procedures and Methods: MRule (a)(4) Risk

Monitor Guidance, Revision 16

OP-MP-6-1, Protected Equipment, Revision 21

OP 3216, Reactor Coolant System Drain (ICCE), Revision 011

OU-AA-200, Shutdown Risk Management, Revision 10

OU-M3-201, Shutdown Safety Assessment Checklist, Revision 17

WM-AA-301, Operational Risk Assessment, Revision 11

OP 2385, Feedwater Control System Operation, Revision 013

OP 2321, Main Feedwater System, Revision 023

SA-AA-109, Heat Stress Management, Revision 6

Condition Reports

1033665

Work Orders

53102973500

53102927320

Miscellaneous

Shutdown Safety Assessment for June 15, 2016

High Risk Contingency Plan Actions, dated June 15 and June 30

NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 2

ETE-MP-2016-1096, MP2 S/G Feedwater Regulating Valve (2-FW-51B) On-Line Packing Adjustment EOOS Version 4.1 for Millstone Unit 2 on 4/1/2016 EOOS Version 4.1 for Millstone Unit 2 on 6/1/2016

Section 1R15: Operability Determinations and Functionality Assessments

Procedures

SP 2614I.3, SLCRS Negative Pressure Verification - Train A, Revision 6

SP 3614I.3A, Supplementary Leak Collection and Release System Boundary Isolation Damper Test, Revision 0

Condition Reports

1033408

1033425

1033436

1033437

1036103

1035012

1033466

1036054

1034530

1033510

1032070

Miscellaneous

Millstone Nuclear Power Station Calculation No. 98-ENG-01595, Revision 0

Dwg. No. 12179-EM-152A, ESF and MSV Buildings Ventilation, Revision 21

Dwg. No. 12179-EM-152B, ESF and MSV Buildings Ventilation, Revision 15

Dwg. No. 12179-EM-152C, ESF and MSV Buildings Ventilation, Revision 18

Dwg. No. 12179-EM-102C, No. 25212-26902, P&ID Reactor Coolant System, Revision 24

Section 1R18: Plant Modifications

Procedures

Unit 3 Technical Specifications, addendum 229, 46, 258, & 224

SP 3622.3-001, TDAFW Pump Operational Readiness and Quarterly IST Group B Pump Tests, Revision 015

SP 3622.3-005, TDAFW Pump IST Comprehensive Pump and Check Valve Test, Revision 005

Condition Reports

1034089

1036680

1037316

1037258

Work Orders

53102970084

53102966711

53102789879

53102632690 53102478369

53102764110

53102776593

53102819384

53102792637

53102798689

53102957056

Miscellaneous

MP3-14-01022, Unit 3 Reactor Coolant Pump Seal Replacement (B&C), Revision 004

TCC-MP-2016-012, Bypass Damaged RVLMS Sensors A2, A5, & A6, Revision 1

MP3-15-01124-004, TDAFW Governor Speed Control Switch Logic Change, Revision 4

MP3-UCR-2015-030, SAR Change Request for Design Change

MP3-15-01124

PROTO-FLO, Version 4.60

SVVR-93948-01, Software Verification and Validation Report for

PROTO-FLO, Version 4.60, Revision N Calculation Change Notice 96-056, MP3 Auxiliary Feedwater System Determination of Degraded and Maximum Pump Curves, Revision 0

MP3-15-01124, TDAFW Governor Control Selector Switch Logic Change

MP3-14-01107, MP3 TDAFW Pump Overspeed Margin Change Calculation 96-067, Auxiliary Feed Water System Comprehensive Flow Analysis, Revision 3 DC

MP3-14-01188 - Repair of 18" Service Water Supply Line 3-SWP-018-082-3 to Containment Recirculation Cooler 3RSS*E1D

Section 1R19: Post-Maintenance Testing

Procedures

MP 3720CD, Slow Speed Start and Run-In of EDG Following Maintenance, Revision 12

OP 3250.21, Removing One Main Feed Pump From Service for Maintenance, Revision 7

PT 31416H1, MP3 Woodward Digital Reference Unit (DRU) and 2301A Installation and Field Adjustments, Revision 2

SP 3614I.3, Supplementary Leak Collection and Release System Negative Pressure Verification, Revision 12

SP 3614I.3-001, SLCRS Negative Pressure Verification - Train A, Revision 6

SP 3614I.3-002, SLCRS Negative Pressure Verification - Train B, Revision 7

SP 3670.4, Routine PMs, Revision 24

SPROC OPS16-3-002, EDG B Governor Replacement Testing, Revision 1

OP 2385, Feedwater Control System Operation, Revision 013

OP 2321, Main Feedwater System, Revision 023

SA-AA-109, Heat Stress Management, Revision 6

AOP 3571, Instrument Failure Response, Revision 011-01

SP 3646A.1-001, EDG A Operability Tests, Revision 018-08

SP 3646A.1-003, EDG A Air Start Valves Independence Test, Revision 010

SP 3448E31, Train A - Diesel Sequencer Actuation Logic Test Data Sheet, Revision 006-01

Condition Reports

1031545

1032371

1032768

1033525

1033660

1033682

1033700

1033701

1033808

1034487

1035966

1036001

1038685

1037325

1037464

1027716

27722

1027701

Work Orders

53102949897

5310297460

5310297350

53102970121 53102546606

53102770335

53102762832

53102464845 53102547041

53102464862

53102464825

53102390268

53102590077

53M30401200

53102464698

53102464814

53102837206

53102851842

53102933088

53102547035

53102465981

53102466404

53102546616

53102933112 53102547052

53102675529

53102675529

53102900329 53102675253

53102836296

53102836306

53M30703497

53102675281

53102648170

53102630270

53M30604846

53102465716

53M30703498

53102770341

53102770335

53102280745

53102870154

53M3040120

53102659739

53M3050193

5310273627

5310281991

53102705279

5310265971

5310273793

5310283628

5310254661

5310267551

5310275400

5310254702

53102464989

5310265766

5310265972

5310279650

53102910062

5310267703

5310278431

5310291378

53102586047

53M3080680

53M3071286

53M3060386

53M30806801

5310254668

5310267555

5310254735

53102746937

5310230310

5310290578

5310279868

53102957056

Miscellaneous

Dwg. No. 12179-EM-130C, Feedwater System, Revision 3

Dwg. No. 12179-ESK-7HQ, S.G. Main Fdwtr Flow Cont. Vv, Revision 8

NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 2

ETE-MP-2016-1096, MP2 S/G Feedwater Regulating Valve (2-FW-51B) On-Line Packing Adjustment

MP3-14-01188 - Repair of 18" Service Water Supply Line 3-SWP-018-082-3 to Containment Recirculation Cooler 3RSS*E1D

Section 1R20: Refueling and Other Outage Activities

Procedures

C

OP 200.14, Containment Entry, Revision 8

OP 3201, Plant Heatup, Revision 25

OP 3202, Reactor Startup (ICCE), Revision 22

OP 3203, Plant Startup, Revision 21

OP 3216, Reactor Coolant System Drain (ICCE), Revision 11

OP-MP-601, Protected Equipment, Revision 21

OU-AA-200, Shutdown Risk Management, Revision 10

OU-M3-201, Shutdown Safety Assessment Checklist, Revision 17

Condition Reports

1036502

1036511

1036541

1036923

1036941

1037028

1037060

1037084

1037278

Work Orders

53102967639 53102968741

Miscellaneous

ETE-MP-2016-1083, RCS Loop Isolation Valves #RCS*MV8002A & 3RCS*MV8001C, Packing Gland Leak-Off Line Through Wall Leakage Engineering Disposition

Section 1R22: Surveillance Testing

Procedures

MP24-APPJ-PRG, Appendix J Program, Revision 2

SP 3612B.4, Type C LLRT - penetration No. 16(o) [3CHS*MV8109A, Revision 4

SP 3646A.18, Train B ESF With LOP Test (ICCE), Revision 20

SP 3601F.5, Reactor Coolant Valve Operability, Revision 011

SP 3646A.8, Slave Relay Testing - Train A, Revision 025

SP 3601F.6-001, RCS Inventory Balance, Revision 003-02

SP 2604D-002, 'B' LPSI Pump and Valve IST Test, Revision 004

SP 2620A, CEA Partial Movement, Revision 017

SP 2651N, Main Control Valve Operability Test, Revision 006

SP 2601H, 'C' Charging Pump Comprehensive Test, Revision 000-02

Condition Reports

1034690

1034691

1035108

1036071

1038185

1038645

1038653

1026771

Work Orders

53102901830

53102904625

53102746937

Miscellaneous

NEI 99-04, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Revision 3-A

Section 2RS1: Access Control to Radiologically Significant Areas

Procedures

HP Checklist, "3R17 Core Barrel Movement", Revision 000

MP 3790AH, "Reactor Vessel Lower Internal Assembly Removal and Installation (ICCE)", Revision 008-00

MP-21-RPM-GDL10, "RCA Drinking Water Guideline", Revision 000

RP-MP-201-2001, "Unit 3 MIDS and Under-vessel Area Controls", Revision 4

MP-PROC-000-RP-AA-124, "Dosimetry Investigation and Processing", Revision 5

MP-PROC-000-RP-AA-201, "Access Controls for High and Very High Radiation Areas", Revision 8

MP-PROC-000-RP-AA-270, "Providing HP Coverage During Work", Revision 2

MP-PROC-OPS-OPS-FH 310, "MP3 Spent Fuel Pool Operations", Revision 001-05

Condition Reports

1010720

1018616

1018783

1018819

1018986

1019453

1019474

1029988

1030499

1033459

1034026

1034589

1034458

Miscellaneous

Alarm Trending Report, 5/1/15 to 3/30/16

Briefing Attendance Roster,

RP-AA-274 - Attachment 5, 5/21/15

Briefing Attendance Roster,

RP-AA-274 - Attachment 5, 10/29/15 Electronic Dosimeter Dose / Dose Rate Alarm Report,

EID 36420, dated 10/30/15 Electronic Dosimeter Dose / Dose Rate Alarm Report,

EID 54934, dated 10/30/15

Electronic Dosimeter Dose / Dose Rate Alarm Report,

EID 88108, dated 6/5/15

High Risk Contingency Plan Actions,

WM-AA-301 - Attachment 14, "3R17 MIDS VHRA Entry", dated 4/4/16 High Risk Contingency Plan Actions,

WM-AA-301 - Attachment 14, "Reactor Core Barrel Lift", dated 4/4/16 Log, Unit 2 Radiation, for 10/29/2015

Radiological Survey, Figure 00, 10/18/14 At 1100

Radiological Survey, Figure 00, 4/19/16 At 0810

Radiological Survey, Figure 00, 4/20/16 At 0650 Radiological Survey, Figure 01, 4/13/16 At 1330 Radiological Survey, Figure 1A, 5/21/15 At 0900

Radiological Survey, Figure 16, 4/15/16 At 2000

Radiological Survey, Figure 16D, 4/6/16 Aat 0200

Radiological Survey, Figure 19, 4/8/16 At 0105 Radiological Survey, Figure 26, 5/21/15 At 1030

Radiological Survey, Figure 35, 10/29/15 At 0230 Radiological Survey, Figure 35, 10/29/15 At 0615 Radiological Survey, Figure 35, 10/29/15 At 1710

Radiological Survey, Figure 46A, 4/11/16 At 1200

Radiological Survey, Figure 46B, 4/10/16 At 1200

Radiological Survey, Figure 48C, 4/10/16 At 1400

Radiological Survey, Figure 47, 4/17/16 At 1950 Radiological Survey, Figure 49, 4/20/16 At 0300 Radiological Survey, Figure 49, 4/20/16 At 0630

Radiological Surveys, Unit-3 Containment, dated 4/10/16 (initial entry)

Radiation Work Permit

2150305, Revision 1

Radiation Work Permit

3160311, Revision 1 Radiation Work Permit

3160324, Revision 0 Radiation Work Permit

3160327, Revision 0

Radiation Work Permit

3160392, Revision 0

Radiation Work Permit

4150102, Revision 0

Very High Radiation Area Entry Checklist, "24' Seal Table & -11' MIDS Area". Dated 4/10/16 Very High Radiation Area Entry Checklist, "MIDS Undervessel Unit-3", dated 4/11/16 Very High Radiation Area Key Log, dated 4/10 to 4/11/16

Section 2RS2: Occupational

ALARA Planning and Controls

Miscellaneous

TEDE ALARA Review for

RWP 327, dated 4/1/16

Station ALARA Committee, Agenda Package, 4/19/16

Section 2RS3: In-plant Airborne Radioactivity Control and Mitigation

Procedures

CP 3806K, Containment Air Sampling for Breathing Air, Revision 006

CP 3804L, PASS Containment Air Sample, Revision 003

EN 31153, Millstone Unit 3 Radiation Monitor High Radiation Set-points, Revision 005-06

FPTI-1, Attachment 18, Fire Training Simulator Air Compressor Training Requirements, Revision 1

MP-26-EPA-FAP05, EP Facility Maintenance, Revision 013

OP 3341F, Breathing Air and Air Monitoring Systems, Revision 001-02

RP-AA-110, Radiological Respiratory Protection Program, Revision 3

RP-AA-111-1010, Radiological Respiratory Protection Program Review, Revision 1

RP-AA-160, Donning and Removal of Respiratory Protection Equipment, Revision 0

RP-AA-161, Qualitative Fit Testing for Industrial Face Masks / Dust Masks / N95 Masks Using 3-M Qualitative Fit Testing Equipment, Revision 0

RP-AA-162, Issue and Control of Respiratory Protection Equipment, Revision 3

RP-AA-163, Inspection and Inventory of Respiratory Protection Equipment, Revision 5

RPM 2.2.6, Continuous Air Monitors, Revision 017

RPM 2.3.1, Quantitative Respirator Fit Testing Using TSA Porta-Count, Revision 010 RPM 2.3.11, Operation of Respirator Wash System, Revision 003 RPM 2.4.3, Performance Challenge of Portable HEPA Filtered Ventilation and vacuum Units, Revision 008

RPM 2.4.3, Performance Challenge of Portable HEPA Filtered Ventilation and vacuum Units, Revision 008 RPM 4.8.5, Emergency Radiological Equipment Maintenance and Inspection, Revision 008-01 RPM 5.4.3, Supplied Breathing Air, Revision 011

SA-AA-117, Industrial Respiratory Protection, Revision 1

SFP 24, Inspection and Inventory of Self Contained Breathing Apparatus, Revision 003-02

SP 2654Q, Main Exhaust System HEPA Filtration Testing, Revision 002-00

SP 3614A.2, Auxiliary Building Filter Testing, Revision 009-04

SP 3614C.2, Fuel Building Filter Testing, Revision 006-04

SP 3666.1, Technical Support Center Ventilation test, Revision 006-02 VPROC OPS15-001, In-Place Testing of HEPA Filters and Carbon Adsorbers (NCS 375 Rev. 9), Revision 000

Other Documents

Millstone Power Station Emergency Plan, Revision 53

Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 1/22/2014

Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 3/31/2014

Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 6/25/2014

Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 9/24/2014 Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 1/15/2015 Breathing air test result, Trace Analytics, LLC, Bauer UNI II S/N 77541, dated 3/13/2015

Lesson Plan

FB-00185 "Self-Contained Breathing Apparatus Scott 4.5 with Duration Extending Accessory Hose

MP-HPO-16020, "3R17 Airflow Study to Verify Previous 3R16 Study", dated 4/18/2016 Respirator medical, fit test, and training qualification records for various selected workers Self-Assessment Report, SAR002511, "Respiratory Protection Program", not dated

Condition Reports

CR1013210

CR1040433

CR1041776

CR440103

CR468120

CR576756

CR571278

CR570982

CR553474

CR551407

CR549963

CR546560

CR538702

CR533365

CR530286

CR528158

CR521328

CR519773

CR505655

CR495918

CR492378

CR491017

Work Orders

53102390295

53102390586

53102419146

53102448322

53102468558

53102493863

53102520810

53102590692

53102605166

53102652792

53102717311

53102897291

53M30411990

53M30612853

53M30704998

53M30714219

53M30803317

Miscellaneous

Air Activity Log, Unit-3, 4/19 to 4/20/16

Air Sample Report No. 2694

Air Sample Report No. 2702

Air Sample Report No. 2704 Air Sample Report No. 2727 Air Sample Report No. 2728

Air Sample Report No. 2729

Air Sample Report No. 2730

Air Sample Report No. 2731 Air Sample Report No. 2732

Air Sample Report No. 2733 Air Sample Report No. 2734 Air Sample Report No. 2735

Air Sample Report No. 2736

Personal Internal Dosimeter Record,

EID 67615, dated 4/19/16

Personal Internal Dosimeter Record,

EID 84103, dated 4/19/16

Section 4OA2: Problem Identification and Resolution

Procedures

OP-2207, Plant Cooldown, Revision 039

Condition Reports

1039577

1039453

1005914

1017078

1011898

582505

Miscellaneous

PI submittals 2Q2015 - 1Q2016

Nuclear Energy Institute Documents 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7

LER 2015-003, Valid Actuation of the Reactor Protection System

Section 4OA3: Follow-up of Events and Notices of Enforcement Discretion

Procedures

OP-AA-1500, Operational Configuration Control, Revision 12

OP-AA-200, Equipment Clearance, Revision 23

OP 3203, Plant Start up, Revision 021

OP 3323A, Main Turbine Start up, Revision 015-06

OP 3317, Reheat and Moisture Separator start up, Revision 017

EOP 35

ES-0.1, Reactor Trip Response, Revision 027-00

EOP 35 E-0, Reactor Trip or Safety Injection, Revision 31

MP-26-EPI-FAP06-003, Emergency Action Levels, Revision 003

OP-AP-105-Attachment 4, Post Trip Review Report, Revision June 2015

Condition Reports

1037818

1037586

1038363

1037601

1039762

Work Orders

53102971347

Miscellaneous

Tagout MSS00-0001, 3HRS-PS35 Reheat steam drains to Low Pressure Turbine pressure switch Apparent Cause Evaluation

3031934, Turbine tripped from 18% Reactor Power due to MSR high levels

LIST OF ACRONYMS

10 CFR Title 10 of the Code of Federal Regulations

AC alternating current

ALA [[]]

RA as low as is reasonably achievable

AS [[]]

ME American Society of Mechanical Engineers

CAP corrective action program

CR condition report

DR deficiency report

ECT eddy current testing EDG emergency diesel generator

FW [[]]

IV feedwater isolation valve

IMC Inspection Manual Chapter

LER licensee event report

NCV non-cited violation NDE non-destructive examination

NO [[]]

UE Notice of Unusual Event

NRC Nuclear Regulatory Commission, U.S.

RCP reactor coolant pump

RCS reactor coolant system RG regulatory guide

RSS recirculation spray system

SC [[]]

BA self-contained breathing apparatus

SG steam generator

SLCRS supplementary leak collection and release system

SSC structure, system, or component TS technical specification

UFSAR Updated Final Safety Analysis Report

UT ultrasonic test