Text

Integrated Inspection Report 05000280/2019003 and 05000281/2019003
	ML19311C688
Person / Time
Site:	Surry
Issue date:	11/07/2019
From:	Bradley Davis; Division Reactor Projects II
To:	Stoddard D; Virginia Electric & Power Co (VEPCO)
	Geanette D
References
	IR 2019003
	Download: ML19311C688 (29)
	v • d • e

November 7, 2019

SUBJECT:

SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2019003 AND 05000281/2019003

Dear Mr. Stoddard:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station and discussed the results of this inspection with F. Mladen and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Bradley J. Davis, Chief Reactor Projects Branch 4 Division of Reactor Projects

Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000280 and 05000281

License Numbers:

DPR-32 and DPR-37

Report Numbers:

05000280/2019003 and 05000281/2019003

Enterprise Identifier: I-2019-003-0030

Licensee:

Virginia Electric and Power Company

Facility:

Surry Power Station

Location:

Surry, VA

Inspection Dates:

July 01, 2019 to September 30, 2019

Inspectors:

R. Carrion, Senior Reactor Inspector

J. Diaz-Velez, Senior Health Physicist

S. Downey, Senior Reactor Inspector

C. Fontana, Emergency Preparedness Inspector

A. Johnson, Materials Engineer

W. Loo, Senior Health Physicist

M. Magyar, Reactor Inspector

L. McKown, Senior Resident Inspector

W. Pursley, Health Physicist

C. Read, Resident Inspector

F. Sacko, Electrical Engineer

S. Sanchez, Senior Emergency Preparedness Inspector

J. Walker, Emergency Response Inspector

Approved By:

Bradley J. Davis, Chief

Reactor Projects Branch 4

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Surry Power Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000280,05000281/20 14007-04 Qualification Basis for Safety-Related Molded Case Circuit Breakers 71152 Closed

INSPECTION SCOPES

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

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated readiness for impending adverse weather conditions for Hurricane Dorian on September 5, 2019.

71111.04Q - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Emergency Diesel Generators' fuel oil supply alignment following underground fuel oil tank sampling on July 11, 2019.

(2) Main Control Room air handling units' alignment after degradation of the 2-VS-AC-8 air handling unit on July 16, 2019.

(3) Spent Fuel Pool Cooling Pump and Heat Exchangers in advance of fall refueling outage on September 27, 2019.

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01) (5 Samples)

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

(1) Fire protection loop isolations and fire pumps following rupture of a segment of buried piping on July 15, 2019

(2) Unit 1 Emergency Switchgear Room, on August 21, 2019.

(3) Unit 1 Safeguards Basement, Elevation 11'-6" on September 24, 2019.

(4) Unit 1 Safeguards Valve Pit, Elevation 28'-6" on September 25, 2019.

(5)

2 Emergency Diesel Generator Room, Elevation 27'-6" on September 26, 2019.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during 1-OPT-RX-005, Control Rod Partial Movement Testing, on July 10, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a simulator requalification training session involving a ruptured steam generator and a loss of containment instrument air resulting in an Alert declaration, on July 17, 2019.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)

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

(1) Unit 1 and 2 Station Batteries 1A & 1B preventive maintenance strategies following discovery of unexpected sedimentation in Unit 1 battery 1A, cell 26, on August 26, 2019.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

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

(1) Unit 1 and Unit 2 elevated risk upon rupture of underground fire main and loss of fire protection system pressure on July 13, 2019.

(2) Unit 1 elevated risk of introducing foreign material into the reactor coolant system during pump disassembly of the '1C' charging pump casing on July 22, 2019.

(3) Emergent change in station risk due to engine failure to start during 2-OPT-EG-001,

2 Emergency Diesel Generator Monthly Start Exercise testing (CR1127834), on July 29, 2019.

(4) Elevated Trip risk associated with restoration of 531 Offsite Line sequenced with 0-PT-8.8, Canal Level Logic Testing, on August 6, 2019.

(5) Elevated Risk associated with Unit 2 condensate storage tank Internal Inspections and Level Instrument Calibrations, on August 20, 2019.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 02.02) (6 Samples)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) CR1125964, cross-tie valve between service water chemical injection pumps left open, on July 8, 2019.

(2) CR1126835, fire main rupture between 1-FP-86 and 1-FP-92 (yard fire main), on July 15, 2019.

(3) CR1127217, NRC identified apparent undersized fillet weld on service water piping in MER 4, on July 19, 2019.

(4) CR1127585, NRC identified cold recirculation pipe in 2-SI-P-1B, Unit 2 Low Head Safety Injection Pump, on July 29, 2019.

(5) CR1127851 and CR1127846, NRC identified debris in backflow preventers in Mechanical Equipment Rooms 3 and 4, July 29, 2019.

(6) CR1125899, CR1101522, & CR1128490 (CA7682619), FLEX Spent Fuel Pool Instrumentation uninterruptable power supply battery health alarms in on both channels on August 8, 2019.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Permanent shaft keyway modification for 1-CH-P-1C following identification of deformation on July 1, 2019

(2) Permanent piping modifications for the Unit 2 charging pump service water pump piping and supports in Mechanical Equipment Room 4, on July 16, 2019

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the following post maintenance tests:

(1)2-PT-18.8, 'B' charging pump service water pump performance testing following motor and strainer maintenance, on July 9, 2019 (2)0-OPT-SW-002, Emergency Service Water Pump 1-SW-P-1B, following repeat ejection of pump packing (38204200818 & 38204200862) on July 26, 2019 (3)2-OPT-EG-001, #2 Emergency Diesel Generator Monthly Start Exercise following start failure and start logic relay replacement (38204193912, 38204201123,

===38204201124, & 38204201125) on July 30, 2019

(4) OP-51.1, 'B' component cooling pump post-maintenance testing following motor electrical preventative maintenance and oil change, on July 31, 2019 (5)1-OPT-SI-005, Unit 1 Low Head Safety Injection Pump testing following suction and discharge valve preventive maintenance (38204195341) on August 29, 2019 (6)0-OSP-AAC-001, Alternate AC Station Blackout Diesel Generator governor replacement and emergency stop valve troubleshooting (38103735090, CR1130048, CR1130050, & CR1130086) on September 4, 2019 (7)1-IPT-CC-NI-N-42, Unit 1 Nuclear Instrumentation Power Range N-42 Channel Calibration, following failure and replacement of the N-42 isolation amplifier (38204203495) on September 30, 2019

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

Main article: IP 71111.22

(1)1-OPT-CS-002, Unit 1 '1A' and '1B' Containment Spray System Testing, on July 8, 2019 (2)2-OPT-EG-001, #2 Emergency Diesel Generator Monthly Start Exercise Test, on July 29, 2019 (3)2-OPT-FW-003, Unit 2 Turbine Driven Auxiliary Feedwater Pump 2-FW-P-2 quarterly testing (38204194609, 38204194608, 38103744570, & 3810374452), on August 5, 2019

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11)===

Main article: IP 38204

(1) The inspectors evaluated the biennial emergency plan exercise during the week of July 22, 2019. The exercise scenario simulated a loss of offsite power on Unit 1, with a failure of the #3 emergency diesel generator (EDG) to power the electrical bus. A subsequent fire in the #3 EDG room led to the declaration of an Alert. Four control rods unexpectedly drop into the reactor core, but the reactor fails to automatically or manually trip, thus creating conditions that met the threshold for declaring a Site Area Emergency. Then a large break loss of coolant accident was simulated, along with the failure of the only containment spray pump, and eventual leak in the containment hatch from pressurization. Once the reactor vessel level indication system reached a certain threshold, along with core exit thermocouples less than 700 degrees Fahrenheit, this then met the simulated conditions for a General Emergency and allowed the Offsite Response Organizations to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of July 22, 2019. This evaluation does not constitute NRC approval.

71114.08 - Exercise Evaluation Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

RADIATION SAFETY

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Inspectors evaluated licensee performance in ensuring that gaseous and liquid effluent processing systems are maintained to properly mitigate, monitor and evaluate radiological discharges to the public. Inspectors reviewed compensatory measures for out-of-service effluent monitors.

Walk Downs and Observations (IP Section 02.01) (1 Sample)

The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:

(1) Inspectors reviewed the following:

SRF Liquid Effluent Monitor (01-RRM-RITS-131), SRF Vent Filter Systems, Vent Stack #1 Monitor, and Process Vent Particulate Monitor (01-GW-RM-130A).

Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)

The inspectors reviewed gaseous and liquid effluent monitor instrument calibrations or tests by reviewing information not limited to but including alarm set points, periodicity, National Institute of Standards and Traceability for sources used.

(1) Inspectors reviewed the following:

U1 Process Vent Normal Range (1-GW-RM-130) dated 07/30/2019

U2 Vent Vent Normal Range (1-VG-RM-131) dated 08/31/2017

SRF Liquid Waste Disposal Rad. Monitor (1-RRM-RE-131) dated 06/03/2019

CW Discharge Tunnel Rad. Monitor (1/2-SW-120/220) dated 07/16/2019

Sampling and Analysis (IP Section 02.03) (1 Sample)

The inspectors reviewed radioactive effluent sampling and analysis activities.

(1) The inspectors reviewed the following:

Radioactive Effluent Sampling and Analysis

Ventilation Vent # 1 - Inspectors observed the weekly sample collection, lab.

sample preparation for analysis, reviewed lab. counting results, and observed the release permit generation process.

1-PT-50.4 Health Physics Sampling Ventilation Vent 1 dated June 4, 2019

1-PT-50.4 Health Physics Sampling Ventilation Vent 1 dated July 16, 2019

24-JUL-2017-0018 Liquid Effluent Sample (Laundry drain monitoring Tank B)

Effluent discharges with inoperable monitors

None occurred during this inspection period.

Instrumentation and Equipment (IP Section 02.04) (1 Sample)

The inspectors reviewed flow rates for effluent stack and related vent flow and surveillances.

Inspectors also reviewed maintenance and methodologies for one or two high-range effluent monitors (or other effluent/process monitor) relied on in emergency operating procedures for decision making.

(1) Inspectors reviewed the following:

Air Cleaning Systems

0-PT-24.17 Test of Gaseous Waste Charcoal for 1-GW-FL-1A/B (Work Order # 38203876270)

0-PT-24.17 Test of Gaseous Waste Charcoal for 1-GW-TS-100A/101A/100B/101B, 1-GWPDI-100, and 1-GW-PI-108/120 (Work Order #

===38204187579)

0-MCM-0620-12 Filter and Charcoal Replacement of 1-GW-FL-1A (Work Order # 38103259966)

0-MCM-0620-12 Filter and Charcoal Replacement of 1-GW-FL-1B (Work Order # 38103635285)

High-Range Effluent Monitor

1-GM-RM-130 Calibration (Work Order #38203876395)

1-GM-RM-130 Calibration (Work Order #38103779371)

1-GM-RM-120 Calibration (Work Order #38203871092)

1-GM-RM-120 Calibration (Work Order #38103745535)

Dose Calculations (IP Section 02.05)===

Main article: IP 38204

The inspectors reviewed required annual reports for changes, release permits and the offsite dose calculation manual for changes and results.

(1) The inspectors reviewed the following:

Liquid and Gaseous Discharge Permits

Liquid Release Permits #L-20190820-B and L20190828-180-B

Gas Release Permits #G-20180701-C and G-20180701-C

Abnormal Gaseous or Liquid Tank Discharge

None

Annual Radiological Effluent Release Reports

Annual Radiological Effluent Report CY2017

Annual Radiological Effluent Report CY2018

71124.07 - Radiological Environmental Monitoring Program

Site Inspection (IP Section 02.01) (1 Sample)

The inspectors evaluated the radiological environmental monitoring program implementation.

(1) The inspectors performed walkdowns of environmental sampling stations, direct radiation measurement locations and meteorological instrumentation. Inspectors also performed observations of preparation and collections of different environmental sample types. Inspectors reviewed sampling results and maintenance, calibration, quality control and ground water records.

Walkdowns, Calibrations, and Maintenance Record Review

Inspectors observed material condition of sampling and direct radiation measuring equipment at the following locations:

Surry Station (SS) 0.3 NNE

Hog Island Reserve (HIR) 2.0 NNE

Bacons Castle (BC) 4.5 SSW

Alliance (ALL) 5.1 WSW

Colonial Parkway (CP) 3.8 NNW

Environmental Sample Collections and Preparation Observation

Air particulate samples from locations listed above

Air Iodine samples from locations listed above

Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement

Milk not available CR 1085500

Kings Mill TLD missing CR 1080538

TLD #02(WNW) missing CR 1084393

Sampling Program for the Potential of Licensed Material Entering Groundwater

Spent Fuel Pool

U1&2 Containment

Yard Storm Drain System

Fuel Building

Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees continuing implementation of the voluntary Nuclear Energy Institute (NEI) Ground Water Protection Initiative.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (IP Section 02.12)===

Main article: IP 71151

(1) EP01: Drill & Exercise Performance for the period January 1, 2018, through March 31, 2019.

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) EP02: Emergency Response Organization Drill Participation for the period January 1, 2018, through March 31, 2019.

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) EP03: Alert & Notification System Reliability for the period January 1, 2018, through March 31, 2019.

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 (July 1, 2016 - June 30, 2019)

(2) Unit 2 (July 1, 2016 - June 30, 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (July 1, 2016 - June 30, 2019)

(2) Unit 2 (July 1, 2016 - June 30, 2019)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (July 1, 2016 - June 30, 2019)

(2) Unit 2 (July 1, 2016 - June 30, 2019)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (July 1, 2016 - June 30, 2019)

(2) Unit 2 (July 1, 2016 - June 30, 2019)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample.

(IP Section 02.16) (1 Sample)

(1)

10/01/2018 to 08/31/2019

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Partial)

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

(1)

(Partial)

URI 05000280/2014007-04; 05000281/2014007-04, Qualification Basis for Safety-Related Molded Case Circuit Breakers on September 25,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal

The NRC continued monitoring Dominions performance at Surry by conducting a Post-Approval Site Inspection for License Renewal - Phase 4 in accordance with the license renewal inspection program (LRIP). Per IMC 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs) and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.

The inspectors reviewed the licensees implementation of the Aging Management Programs (AMPs) shown below by selecting a sample of structures, systems, components (SSCs) within the scope of the respective AMPs. The inspectors performed the following activities, as applicable to each SSC, to determine that there is a reasonable assurance that the effects of aging are being adequately managed: walked down all accessible SSCs to observe their general condition and identify any signs of aging related degradation; interviewed plant personnel; reviewed completed work orders; reviewed applicable monitoring and trending data; and reviewed the acceptability of inspection and test results. For each AMP shown below, the inspectors also reviewed a sample of aging related issues entered into the licensees corrective action program to verify that age-related degradation is being identified at an appropriate threshold and corrected.

Post-Approval Site Inspection for License Renewal===

Main article: IP 71003

(1) Augmented Inspection Program a. Weld 1-08, Pipe to Weldolet Weld on line 12-RC-10, ASME Class 1 b. Weld 1-02, Reducer to Nozzle Weld on line 12-WFPD-117, ASME Class 1 c. Weld 2-15, Pipe to Pipe Weld on line 4-RC-15, ASME Class 1 d. Unit 2 High Energy Piping Outside Containment (Main Steam and Feedwater Piping)

(2) Buried Piping and Valve Inspection Program

36 Recirculating Spray Heat Exchanger service water pipe and transition to the 8 2C service water header.

Copper-Nickel piping in the Service Water System

Emergency Diesel Generator (EDG) Fuel Oil Piping in EDG Room #3

Fire water header piping between valves 1-FP-86 and 1-FP-92

Fire Protection System piping at fire hydrant 1-FP-512

Service water piping upstream of valve 1-SW-MOV-101A.

Service water piping at valve 1-SW-MOV-103C

(3) Chemistry Control Program for Primary Systems

Unit 1 & Unit 2 Primary Sample Sinks

Boric Acid Storage Tanks

Primary Grade Water Tanks

Spend Fuel Pool Demineralizer Ion Exchanger

Refueling Water Storage Tanks

Deborating Demineralizer

(4) Chemistry Control Program for Secondary Systems

Bearing Cooling System

Condensate Storage Tank

EDG Cooling System

Feedwater System

Steam Generators

(5) Civil Engineering Structural Inspection Program

Auxiliary Building

Containment

Fuel Building

Intake and Discharge Structures and Tunnels

Manholes

Masonry Walls

Turbine Building

(6) General Condition Monitoring

Various structures, systems, components, and items within the scope of the following program areas:

o Inspections of Radiologically Controlled Areas for Borated Water Leakage o Periodic focused inspections such as system walkdowns o Area inspections for condition of structural supports and doors

(7) Non-EQ Cable Monitoring Program

Intermediate Range Channel N36 Cables (01-NI-NE-36-DETECT, 02-NI-NE-36-DETECT)

Type E1 Cables in the Unit 1 & Unit 2 Auxiliary Building, Unit 2 Safeguards Room, and the Unit 2 Cable Spreading Room

Type E3 Underground Cables that supply power to the C Reservice Station Service Transformer

(8) Tank Inspection Program

EDG Coolant Expansion Tank (03-EG-TK-7)

EDG Fuel Oil Tank (03-EE-TK-3)

EDG Starting Air Receiver Tanks (03-EG-TK-1/2/3/4/5/6)

Unit 1 Fire Protection Tanks (01-FP-TK-1A, 01-FP-TK-1B)

Unit 2 Chemical Addition Tank (02-CS-TK-2)

Unit 2 Refueling Water Storage Tank (02-CS-TK-1)

(9) Work Control Process

96 Circulating Water Lines (1-CW-PP-96.00-WC-PIPE, 2-CW-PP-96.00-WC-PIPE)

Containment Instrument Air Compressor Heat Exchangers (1-IA-E-4A/4B, 2-IA-E-4A/4B)

Emergency Service Water Pump B (1-SW-P-1B)

High Level Intake Structure

Unit 1 Main Control Room Chillers (1-VS-E-4A, 1-VS-E-4D)

Unit 2 Feedwater Regulating Valve (2-FW-FCV-2488)

Unit 2 Main Steam Safety Valves (2-MS-SV-205A, 2-MS-SV-202C)

INSPECTION RESULTS

Unresolved Item (Closed)

Qualification Basis for Safety-Related Molded Case Circuit Breakers URI 05000280,05000281/2014007-04 71152

Description:

On November 10, 2014, the NRC issued Inspection Report 05000280/2014007 and 05000281/2014007 documenting Unresolved Item (URI)05000280/2014007-04; 05000281/2014007-04 associated with approximately 60 safety-related molded case circuit breakers (MCCBs) installed in mild environments for greater than 20 years. At that time, the inspectors observed that the licensee had not performed engineering evaluations to justify continued operation beyond the manufacturer design service life established in Westinghouse Electric Technical Bulletin TB-04-13, Replacement Solutions for Obsolete Classic MCCBs, UL [Underwriters Laboratory] Testing Issues, Breaker Design Life and Trip Band Adjustment, which was superseded in 2006 by TB-06-02, Aging Issues and Subsequent Operating Issues for Breakers That are at Their 20-Year Design/Qualified Lives; UL Certification/Testing Issues Update. Since then, the NRC undertook efforts, such as training, to assist inspectors in dispositioning issues related to how long safety-related components remain in service and to clarify the applicability of various regulations and industry standards. As part of this effort, the NRC determined current agency regulations require the establishment of quality assurance programs and supporting procedures that, among other things, set PM schedules for the inspection or replacement of parts having a specific lifetime.

During the NRC's previous inspection, the team identified the licensees failure to implement required preventive maintenance on safety related molded case circuit breakers (NCV 05000280/2014007-01; 05000281/2014007-01, Failure to Perform Required Preventative Maintenance on Class 1E Molded Case Circuit Breakers). The inspectors verified completion of corrective actions associated with this NCV during the Surry Power Station NRC Design Bases Assurance Inspection (Team) Report Number 05000280/2017007 and 05000281/2017007 issued on September 22, 2017 (CR560488 & CR560597). While the NRC undertook the training efforts previously described, the licensee replaced the MCCBs associated with the URI (CR553796 & CR558445). Because these actions reasonably ensured the continued quality of the MCCBs, the inspectors determined further efforts to evaluate the qualification basis in effect at the time the URI was issued were no longer needed to provide reasonable assurance of adequate protection of public health and safety.

Based on the above, no performance deficiency or violation of regulatory requirements was identified. This review did not represent an inspection sample.

Corrective Action Reference(s): CR553796, CR558445, CR560488, and CR560597

EXIT MEETINGS AND DEBRIEFS

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

On July 26, 2019, the inspectors presented the Emergency Preparedness Exercise inspection results to F. Mladen and other members of the licensee staff.

On August 16, 2019, the inspectors presented the License Renewal Phase IV Inspection Exit Meeting inspection results to Roy Simmons, Plant Manager and other members of the licensee staff.

On October 7, 2019, the inspectors presented the Third Quarter 2019 Integrated Baseline Inspection Program Exit inspection results to F. Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71003

Corrective Action

Documents

CA278275,

CA3043578,

CA3052253,

CA3057457,

CA7317266,

CA7643442,

CR1014025,

CR1015578,

CR1016519,

CR1016880,

CR1017433,

CR1035737,

CR1050808,

CR1052032,

CR1052038,

CR1052039,

CR1052040,

CR1052050,

CR1052051,

CR1052136,

CR1052141,

CR1052188,

CR1052195,

CR1052199,

CR1052205,

CR1052383,

CR1059013,

CR1061924,

CR1068192,

CR1068384,

CR1068648,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR1069157,

CR1075996,

CR1079710,

CR1087963,

CR1088833,

CR1093199,

CR1096915,

CR1097265,

CR1098557,

CR1101423,

CR1104723,

CR1105154,

CR1107843,

CR1109101,

CR1109103,

CR1109416,

CR1113848,

CR1120563,

CR1121216,

CR1123559,

CR1126168,

CR1125354,

CR1126835,

CR1128837,

CR1128894,

CR1128904,

CR435932,

CR476205,

CR496654,

CR496866,

CR496867,

CR514139,

CR514142,

CR540390

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Resulting from

Inspection

CR1128845

Requirement to provide certain information prior to start of

an NRC inspection not met

08/13/2019

CR1129011

ER-SU-AUG-101 Documentation of LR Compliance

08/15/2019

Drawings

11448-FE-32B

Duct Line Plan & Detail, Surry Power Station - Unit 1

Revision 10

Engineering

Evaluations

CE-0087

Guideline for Monitoring of Structures, SPS

Revision 7

CE-2014

Evaluation Concrete Beam at SPS High-Level Intake

Structure

Revision 0

ETE-CEP-2012-

1007

Non-EQ Cable Monitoring, License Renewal Aging

Management Program (LR-1772/LR-2772)

Revision 1

ETE-CEP-2017-

1002

Work Control Process, License Renewal Aging Management

Activities

Revision 0

ETE-CEP-2017-

1003

General Condition Monitoring Activities, License Renewal

Aging Management Activities (LR-1766/LR-2766)

Revision 0

ETE-CEP-2017-

1005

Civil Engineering Structural Inspection, License Renewal

Aging Management Activities (LR-1714/LR-2714)

Revision 0

ETE-CEP-2017-

1009

Augmented Inspection Activities, License Renewal Aging

Management Activities (LR-1731/LR-2731)

Revision 1

ETE-CEP-2017-

1015

Tank Inspection Activities, License Renewal Aging

Management Activities (LR-1756/LR-2756)

Revision 0

ETE-NAF-2018-

0002

Surry Units 1 and 2 Extended Steam Generator Feedwater

Nozzle Weld Examination Frequency

Revision 0

ETE-SLR-2018-

26

Surry Subsequent License Renewal Project - Aging

Management Program Evaluation Report - External

Surfaces Monitoring of Mechanical Components

Revision 4

ETE-SLR-2018-

1338

Surry Subsequent License Renewal Project - Aging

Management Program Evaluation Report - Masonry Walls

Revision 1

ETE-SLR-2018-

1339

Surry Subsequent License Renewal Project - Aging

Management Program Evaluation Report - Structures

Monitoring

Revision 2

ETE-SLR-2018-

1340

Surry Subsequent License Renewal Project - Aging

Management Program Evaluation Report - Inspection of

Water-Control Structures Associated with Nuclear Power

Revision 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Plants

ETE-SU-2011-

24

License Renewal Inspections for RWST and CAT

Revision 0

ETE-SU-2011-

0070

Summary of Tank Inspections for Surry License Renewal

Commitment Number 10

Revision 0

ETE-SU-2011-

0075

Component Cooling Pipe in Containment NDE Results 2009-

2013

Revision 2

ETE-SU-2011-

0103

License Renewal Tank Inspection Plans for the Period of

Extended Operations

Revision 3

ETE-SU-2012-

0046

Condition Assessment of Plant Structures (Third Five-Year

Inspection Interval)

Revision 0

ETE-SU-2014-

20

Evaluation of 2014 Inspection of 1-FP-TK-IA

Revision 0

ETE-SU-2014-

0080

Assessment of Additional Cathodic Protection and Site Soil

Analysis at Surry Power Station

Revision 1

ETE-SU-2014-

0081

Evaluation of 2014 Inspection of 1-FP-TK-IB

Revision 0

ETE-SU-2015-

0076

Evaluation and Repair of Degraded Concrete in the High-

Level Intake Bays

Revision 4

ETE-SU-2016-

1011

2016 Aging Management Review of NON-EQ Cable

Inspections

Revision 0

ETE-SU-2019-

0002

Condition Assessment of Plant Structures (Fourth Five-Year

Inspection Interval)

Revision 0

ETE-SU-2019-

0015

UPTI Condition Assessment and Asses Management Plan

(Surry Life Cycle Management Plan, Rev. 13)

Revision 0

Miscellaneous

B. Muirhead

Curtiss-Wright Personnel Certification Statement: UT II

2/04/2017

B. Muirhead

Curtiss-Wright Certification of Visual Acuity and Color Vision

01/10/2017

ER-AA-CBL-10

Cable Management Program

Revision 2

ER-SU-5909

SPS Program to Inspect Non-EQ Electrical Cables

Revision 4

ET-CEP-04-0021

Walkdown Visual Inspection of Non-EQ Cables at Surry

Power Station

Revision 1

M. Smith

Curtiss-Wright Personnel Certification Statement: UT II

09/26/2016

M. Smith

Curtiss-Wright Certification of Visual Acuity and Color Vision

07/26/2019

W. Steppe

Curtiss-Wright Personnel Certification Statement: PT II

01/21/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

W. Steppe

Curtiss-Wright Certification of Visual Acuity and Color Vision

09/01/2016

NDE Reports

PT-17-002

Liquid Penetrant Examination

05/14/2017

UT-16-021

UT Calibration/Examination

10/26/2016

UT-17-009

UT Calibration/Examination

05/11/2017

Procedures

0-CSP-PL-001

Subsurface Drain Chemistry

Revision 6

0-MCM-0203-02

Containment Instrument Air Compressor Maintenance

Revision 24

0-MPM-1900-01

Periodic Inspection of Flood and Spill Protection Dikes,

Dams, and Expansion Joint Shields

Revision 15

0-MPM-1901-01

High Level Intake Structure Screenwells and Associated

Piping Inspection

Revision 33

0-MPM-1901-02

Low Level Intake Structure Screenwells 1D, 2A, 2B Service

Water Inspection

Revision 9

0-NSP-BS-001

Erosion Control Inspection

Revision 2

0-NSP-BS-005

Monitoring of Structures

Revision 11

0-OSP-FP-010

0-OSP-FP-010, Daily Fire Door Inspection

Revision 8

0-STP-70.7

Annual Intake Canal Liner Visual Inspection/Acceptance

Test

Revision 4

1-NPT-LR-001

License Renewal General Condition Monitoring Review -

Unit 1 Containment

Revision 1

1-NPT-LR-002

License Renewal General Condition Monitoring Review -

Unit 1 Areas Outside of Containment

Revision 1

1-NPT-MS-001

Inservice Inspection System Pressure Test for Main Steam

System Components Outside Containment

Revision 3

1-OPT-MS-001

Operations Periodic Test

Revision 3

2-NPT-LR-001

License Renewal General Condition Monitoring Review -

Unit 2 Containment

Revision 1

2-NPT-LR-002

License Renewal General Condition Monitoring Review -

Unit 2 Areas Outside of Containment

Revision 1

2-NPT-MS-001

Inservice Inspection System Pressure Test for Main Steam

System Components Outside Containment

Revision 3

2-OPT-MS-001

Operations Periodic Test

Revision 3

38-01-ISI-INT5

Surry Power Station Unit 1, Inservice Inspection Plan

Components and Component Supports, 5th Interval

Revision 3

38-02-ISI-INT5

Surry Power Station Unit 2, Inservice Inspection Plan

Revision 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Components and Component Supports, 5th Interval

CH-93.400

Closed Cooling Water Chemistry Program

Revision 24

CH-99.500

Primary Chemistry Specifications and Action Levels

Revision 15

CH-99.600

Secondary Chemistry Specifications and Action Levels

Revision 16

CY-AP-SEC-200

Secondary System Chemistry

Revision 7

ER-AA-101

System Engineering Walkdowns

Revision 2

ER-AA-103

System Engineering Handbook

Revision 3

ER-AA-CBL-101

Evaluation and Testing of Low Voltage Cables

Revision 3

ER-AA-CBL-103

Evaluation and Testing of Medium Voltage Cables

Revision 3

ER-AA-CII-10

ASME Section XI Containment Inservice Inspection Program

Revision 2

ER-AA-CII-101

ASME Section XI Containment Inservice Inspection

(Concrete/IWL) Program Fleet Implementation

Requirements

Revision 3

ER-AA-CII-102

ASME Section XI Containment Inservice Inspection

(Metal/IWE) Program Fleet Implementation Requirements

Revision 3

ER-AA-MRL-10

Maintenance Rule Program

Revision 6

ER-AA-MRL-100

Implementing Maintenance Rule

Revision 12

ER-AA-NDE-PT-

300

ASME Section XI Liquid Penetrant Examination Procedure

Revision 7

ER-AA-NDE-UT-

801

Ultrasonic Examination of Ferritic Piping Welds in

Accordance with ASME Section XI, Appendix VIII

Revision 7

ER-AA-NDE-UT-

2

Ultrasonic Examination of Austenitic Piping Welds in

Accordance with ASME Section XI, Appendix VIII

Revision 5

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-AP-BAC-102

Boric Acid Corrosion Control Program (BACCP) Evaluations

Revision 13

ER-SU-AUG-101

Surry Augmented Inspection Program

Revision 17

MA-AA-1002

Leakage Management

Revision 6

OP-AA-100

Conduct of Operations

Revision 38

RP-AA-220

Radiological Survey Scheduling

Revision 2

RP-AA-221

Radiological Survey Records

Revision 7

RP-AA-222

Radiation Surveys

Revision 3

RP-AA-223

Contamination Surveys

Revision 4

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RP-SU-101-1000

Health Physics Operations: Department Standards

Revision 2

SU-PROC-0000-

CH-72.B70

Boron: Operation and Calibration of the Mettler T Series

Auto Titrator

Revision 6

WM-AA-100

Work Management

Revision 32

Self-Assessments Audit 18-13

Surry License Renewal

11-15-2018

Self-Assessment

Report (SAR)

3163

Informal License Renewal / Aging Management SA

2-10-2015

Work Orders

00470550-01,

38079565601,

38102528278,

38102566261,

38102921108,

38103187487,

38103249126,

38103275045,

38103320488,

38103601914,

38103710818,

38103710868,

38103717453,

38103738416,

38103788846,

38103765534,

204182589,

204186356,

204192142,

204192148,

204199602

71111.01

Procedures

Dominion Energy Hurricane Response Plan

(Nuclear)

0-AP-37.01

ABNORMAL ENVIRONMENTAL CONDITIONS

0-OP-ZZ-021

SEVERE WEATHER PREPARATION

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04Q Procedures

0-OP-EG-001A

EDG 3 System Alignment

0-OP-FC-001A

Spent Fuel Pit Cooling System Alignment

0-OP-FC-002

Spent Fuel Pit Cooler Operations

0-OP-VS-006

Control Room and Relay Room Ventilation System

1-OP-EG-001A

EDG 1 System Alignment

1-OP-SI-001A

Safety Injection System Alignment

2-OP-EG-001A

EDG 2 System Alignment

2-OP-SI-001A

Safety Injection System Alignment

71111.05Q Procedures

0-FS-FP-122

Diesel Generator Room Number 2 Elevation 27 Feet - 6

Inches

1-FS-FP-139

Safeguards Valve Pit - Unit 1 Elevation 28 Feet - 6 Inches,

Elevation 19 Feet - 6 Inches, and Elevation 12 Feet

1-FS-FP-140

Safeguards Basement - Unit 1 Elevation 11 Feet - 6 Inches

71111.11Q Procedures

1-E-3

Steam Generator Tube Rupture

1-ECA-3.3

SGTR Without Pressurizer Pressure Control

1-OPT-RX-005

Control Rod Assembly Partial Movement

71111.12

Corrective Action

Documents

Resulting from

Inspection

CR1131000

Procedures

1-EPT-0102-01

Monthly Station Battery 1A Cell Voltage Check

CM-SU-STI-101

Technical Specification Surveillance Test Interval List

71111.13

Miscellaneous