IR 05000280/2019003

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Integrated Inspection Report 05000280/2019003 and 05000281/2019003
ML19311C688
Person / Time
Site: Surry  Dominion icon.png
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)


Text

{{#Wiki_filter:ber 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 Enclosure

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 Qualification Basis for 71152 Closed 14007-04 Safety-Related Molded Case Circuit Breakers

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) 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)

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)

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) 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)

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)

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)

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)

[[IP sample::=

=IP 71111.18|count=7}}

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)

(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)

(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) 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) 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)==

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) ===

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) ===

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)

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) ===

(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==

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

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 Type Designation Description or Title Revision or Procedure 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 Type Designation Description or Title Revision or Procedure 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 Type Designation Description or Title Revision or Procedure Date Corrective Action CR1128845 Requirement to provide certain information prior to start of 08/13/2019 Documents an NRC inspection not met Resulting from CR1129011 ER-SU-AUG-101 Documentation of LR Compliance 08/15/2019 Inspection Drawings 11448-FE-32B Duct Line Plan & Detail, Surry Power Station - Unit 1 Revision 10 Engineering CE-0087 Guideline for Monitoring of Structures, SPS Revision 7 Evaluations CE-2014 Evaluation Concrete Beam at SPS High-Level Intake Revision 0 Structure ETE-CEP-2012- Non-EQ Cable Monitoring, License Renewal Aging Revision 1 1007 Management Program (LR-1772/LR-2772) ETE-CEP-2017- Work Control Process, License Renewal Aging Management Revision 0 1002 Activities ETE-CEP-2017- General Condition Monitoring Activities, License Renewal Revision 0 1003 Aging Management Activities (LR-1766/LR-2766) ETE-CEP-2017- Civil Engineering Structural Inspection, License Renewal Revision 0 1005 Aging Management Activities (LR-1714/LR-2714) ETE-CEP-2017- Augmented Inspection Activities, License Renewal Aging Revision 1 1009 Management Activities (LR-1731/LR-2731) ETE-CEP-2017- Tank Inspection Activities, License Renewal Aging Revision 0 1015 Management Activities (LR-1756/LR-2756) ETE-NAF-2018- Surry Units 1 and 2 Extended Steam Generator Feedwater Revision 0 0002 Nozzle Weld Examination Frequency ETE-SLR-2018- Surry Subsequent License Renewal Project - Aging Revision 4 26 Management Program Evaluation Report - External Surfaces Monitoring of Mechanical Components ETE-SLR-2018- Surry Subsequent License Renewal Project - Aging Revision 1 1338 Management Program Evaluation Report - Masonry Walls ETE-SLR-2018- Surry Subsequent License Renewal Project - Aging Revision 2 1339 Management Program Evaluation Report - Structures Monitoring ETE-SLR-2018- Surry Subsequent License Renewal Project - Aging Revision 1 1340 Management Program Evaluation Report - Inspection of Water-Control Structures Associated with Nuclear Power Inspection Type Designation Description or Title Revision or Procedure Date Plants ETE-SU-2011- License Renewal Inspections for RWST and CAT Revision 0 24 ETE-SU-2011- Summary of Tank Inspections for Surry License Renewal Revision 0 0070 Commitment Number 10 ETE-SU-2011- Component Cooling Pipe in Containment NDE Results 2009- Revision 2 0075 2013 ETE-SU-2011- License Renewal Tank Inspection Plans for the Period of Revision 3 0103 Extended Operations ETE-SU-2012- Condition Assessment of Plant Structures (Third Five-Year Revision 0 0046 Inspection Interval) ETE-SU-2014- Evaluation of 2014 Inspection of 1-FP-TK-IA Revision 0 20 ETE-SU-2014- Assessment of Additional Cathodic Protection and Site Soil Revision 1 0080 Analysis at Surry Power Station ETE-SU-2014- Evaluation of 2014 Inspection of 1-FP-TK-IB Revision 0 0081 ETE-SU-2015- Evaluation and Repair of Degraded Concrete in the High- Revision 4 0076 Level Intake Bays ETE-SU-2016- 2016 Aging Management Review of NON-EQ Cable Revision 0 1011 Inspections ETE-SU-2019- Condition Assessment of Plant Structures (Fourth Five-Year Revision 0 0002 Inspection Interval) ETE-SU-2019- UPTI Condition Assessment and Asses Management Plan Revision 0 0015 (Surry Life Cycle Management Plan, Rev. 13) Miscellaneous B. Muirhead Curtiss-Wright Personnel Certification Statement: UT II 02/04/2017 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 Revision 1 Power Station 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 Type Designation Description or Title Revision or Procedure 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, Revision 15 Dams, and Expansion Joint Shields 0-MPM-1901-01 High Level Intake Structure Screenwells and Associated Revision 33 Piping Inspection 0-MPM-1901-02 Low Level Intake Structure Screenwells 1D, 2A, 2B Service Revision 9 Water Inspection 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 Revision 4 Test 1-NPT-LR-001 License Renewal General Condition Monitoring Review - Revision 1 Unit 1 Containment 1-NPT-LR-002 License Renewal General Condition Monitoring Review - Revision 1 Unit 1 Areas Outside of Containment 1-NPT-MS-001 Inservice Inspection System Pressure Test for Main Steam Revision 3 System Components Outside Containment 1-OPT-MS-001 Operations Periodic Test Revision 3 2-NPT-LR-001 License Renewal General Condition Monitoring Review - Revision 1 Unit 2 Containment 2-NPT-LR-002 License Renewal General Condition Monitoring Review - Revision 1 Unit 2 Areas Outside of Containment 2-NPT-MS-001 Inservice Inspection System Pressure Test for Main Steam Revision 3 System Components Outside Containment 2-OPT-MS-001 Operations Periodic Test Revision 3 38-01-ISI-INT5 Surry Power Station Unit 1, Inservice Inspection Plan Revision 3 Components and Component Supports, 5th Interval 38-02-ISI-INT5 Surry Power Station Unit 2, Inservice Inspection Plan Revision 3 Inspection Type Designation Description or Title Revision or Procedure 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 Revision 3

                             (Concrete/IWL) Program Fleet Implementation

Requirements ER-AA-CII-102 ASME Section XI Containment Inservice Inspection Revision 3

                             (Metal/IWE) Program Fleet Implementation Requirements

ER-AA-MRL-10 Maintenance Rule Program Revision 6 ER-AA-MRL-100 Implementing Maintenance Rule Revision 12 ER-AA-NDE-PT- ASME Section XI Liquid Penetrant Examination Procedure Revision 7 300 ER-AA-NDE-UT- Ultrasonic Examination of Ferritic Piping Welds in Revision 7 801 Accordance with ASME Section XI, Appendix VIII ER-AA-NDE-UT- Ultrasonic Examination of Austenitic Piping Welds in Revision 5 2 Accordance with ASME Section XI, Appendix VIII 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 Type Designation Description or Title Revision or Procedure Date RP-SU-101-1000 Health Physics Operations: Department Standards Revision 2 SU-PROC-0000- Boron: Operation and Calibration of the Mettler T Series Revision 6 CH-72.B70 Auto Titrator WM-AA-100 Work Management Revision 32 Self-Assessments Audit 18-13 Surry License Renewal 11-15-2018 Self-Assessment Informal License Renewal / Aging Management SA 12-10-2015 Report (SAR) 3163 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 14

                                           (Nuclear)

0-AP-37.01 ABNORMAL ENVIRONMENTAL CONDITIONS 72 0-OP-ZZ-021 SEVERE WEATHER PREPARATION 23 Inspection Type Designation Description or Title Revision or Procedure Date 71111.04Q Procedures 0-OP-EG-001A EDG 3 System Alignment 16 0-OP-FC-001A Spent Fuel Pit Cooling System Alignment 7 0-OP-FC-002 Spent Fuel Pit Cooler Operations 5 0-OP-VS-006 Control Room and Relay Room Ventilation System 74 1-OP-EG-001A EDG 1 System Alignment 14 1-OP-SI-001A Safety Injection System Alignment 19 2-OP-EG-001A EDG 2 System Alignment 14 2-OP-SI-001A Safety Injection System Alignment 16 71111.05Q Procedures 0-FS-FP-122 Diesel Generator Room Number 2 Elevation 27 Feet - 6 2 Inches 1-FS-FP-139 Safeguards Valve Pit - Unit 1 Elevation 28 Feet - 6 Inches, 2 Elevation 19 Feet - 6 Inches, and Elevation 12 Feet 1-FS-FP-140 Safeguards Basement - Unit 1 Elevation 11 Feet - 6 Inches 2 71111.11Q Procedures 1-E-3 Steam Generator Tube Rupture 51 1-ECA-3.3 SGTR Without Pressurizer Pressure Control 45 1-OPT-RX-005 Control Rod Assembly Partial Movement 38 71111.12 Corrective Action CR1131000 Documents Resulting from Inspection Procedures 1-EPT-0102-01 Monthly Station Battery 1A Cell Voltage Check 5 CM-SU-STI-101 Technical Specification Surveillance Test Interval List 13 71111.13 Miscellaneous PHOENIX Scheduler's Evaluation for Surry Power Station, 07/22/2019 Units 1 and 2 PHOENIX Scheduler's Evaluation for Surry Power Station, 07/29/2019 Units 1 and 2 PHOENIX Scheduler's Evaluation for Surry Power Station, 08/06/2019 Units 1 and 2 PHOENIX Scheduler's Evaluation for Surry Power Station, 08/20/2019 Units 1 and 2 PHOENIX Scheduler's Evaluation for Surry Power Station, 07/13/2019 Units 1 and 2 71111.15 Corrective Action CR1125964 Documents Inspection Type Designation Description or Title Revision or Procedure Date Corrective Action CR1128490 Documents Resulting from Inspection Drawings 11448-FM-071D, Flow/Valve Operating Numbers Diagram Circulating and 8 Sheet 3 Service Water System 11548-FM-089A Flow/Valve Operating Numbers Diagram Safety Injection 54 and 55 System Sheets 1 and 2 Miscellaneous Weld Record for 7/16/2019 2-SW-PP-2.00- WS-PIPE-171- 9107 Operability Welding 11 Evaluations Technique Sheet 109 71111.18 Corrective Action CR1127217 Documents Resulting from Inspection Drawings 11448-MKS- 2"-WS-171-21X 2 21A36 Engineering SU-18-00109 MER-3&4 Charging Service Water Improvements 3 Changes Miscellaneous Weld Data July 16, Record for 02- 2019 SW-PP-2.00-WS- PIPE-171-9107 Welding 0 Technique Sheet 3404 Procedures 0-MCM-1801-01 Welding Safety-Related, Seismic-Related and Fire 17 Protection Equipment Welding 11 Technique Sheet Inspection Type Designation Description or Title Revision or Procedure Date 109 Welding 0 Technique Sheet 3404 Work Orders 38204192939 204192942 7/15/2019 71111.19 Procedures 0-ECM-1401-06 Component Cooling Water Motor Maintenance 14 1-IPT-CC-NI-N-42 Nuclear Instrumentation Power Range N-42 Channel 5 Calibration 2-PT-18.8 Charging Pump Service Water Performance 36 OP-51.1 Component Cooling Subsystem 11 Work Orders 38103841715 7/31/2019 38103841756 204203495 71111.22 Procedures 1-OPT-CS-002 Containment Spray System Test 19 71124.06 Calibration HP-3010.040 Effluent Radiation Monitor Setpoint Record 12/02/2015 Records (Attachment 2) for RM-RRM-131 Monitor HP-3010.040 Liquid Effluent Monitor Setpoint Worksheet 12/01/2015

                            (Attachment 5) for

RM-RRM-131 Monitor Corrective Action CRs 1124974, Corrective Action Documents Documents 1124995, 1117307, 1110189, 1110241, 1110305, 1110714, 1111542, 1118609, 27391, 27558, Inspection Type Designation Description or Title Revision or Procedure Date 1130517, 1130514, 1115287, and 24749. Miscellaneous 17-SEP-2019- Gamma Spectrum Analysis 09/17/2019 0008 Gaseous Effluent Sample

                        (Vent. Vent. #1

250 Marinelli Gas Chamber) 17-SEP-2019- Gamma Spectrum Analysis 09/17/2019 0009 Gaseous Effluent Sample

                        (Vent. Vent. #1

Charcoal Filter) 17-SEP-2019- Gamma Spectrum Analysis 09/17/2019 0010 Gaseous Effluent Sample

                        (Vent. Vent. #1

Particulate Filter) G-20190910-233- Gas Permit Post-Release Data Ventilation Vent # 1 (VG- 09/17/2019 C 104) Work Orders 38204196211 7 Day Freq. PT:HP Sampling - Vent. Vent. #1 71124.07 Calibration C-HP-1033.620, Portable Air Sampler Calibration 08/27/2018 Records Attachment 2, Calibration Certificate - Portable Air Sampler #22124, 08/27/2018 C-HP-1033.620, Portable Air Sampler Calibration 01/15/2019 2, Calibration Certificate - Inspection Type Designation Description or Title Revision or Procedure Date Portable Air Sampler #22126 C-HP-1033.620, Portable Air Sampler Calibration 10/23/2018 2, Calibration Certificate - Portable Air Sampler #27314 C-HP-1033.620, Portable Air Sampler Calibration 10/23/2018 2, Calibration Certificate - Portable Air Sampler #27316 C-HP-1033.620, Portable Air Sampler Calibration 01/15/2019 2, Calibration Certificate - Portable Air Sampler #28187 W/O PM/CAL PRIMARY MET TOWER INSTRUMENTATION 10/10/2018 203875765 Miscellaneous AREOR Report Dominion Energy, Surry Power Station, 2017 & 2018 Radiological Environmental Monitoring Program Report Procedures 0-HSP-GPP-001 GROUNDWATER PROTECTION PROGRAM REVIEWS Revision 3 AND ASSESSMENTS 0-HSP-REMP- LAND USE CENSUS REVISION 001 NO:12 0-HSP-SS-002 Well Sampling Instructions Revision 8 HP-3051.020 GROUNDWATER PROTECTION PROGRAM REVISION NO: 12 RP-AA-504 Remediation Process for the Groundwater Protection Revision 4 Program Inspection Type Designation Description or Title Revision or Procedure Date VPAP-2103S Offsite Dose Calculation Manual (Surry) Revision 21 Self-Assessments GWPI Risk Surry Groundwater Protection Program Risk Assessment Assessment 2019 2019 71151 Miscellaneous 2Q2017, 2Q2018, & 2Q2019 Derivation and Margin Reports for Surry Power Station Unit 1 Mitigating System Performance Index Performance Indicator Emergency AC, High Pressure Injection, Heat Removal, Residual Heat Removal, and Cooling Water System inputs 2Q2017, 2Q2018, & 2Q2019 Derivation and Margin Reports for Surry Power Station Unit 2 Mitigating System Performance Index Performance Indicator Emergency AC, High Pressure Injection, Heat Removal, Residual Heat Removal, and Cooling Water System inputs 27| ]]