IR 05000280/2019010

NRC Evaluation of Changes, Tests, and Experiments Report 05000280/2019010 and 05000281/2019010

ML19123A172
Person / Time
Site:	Surry
Issue date:	05/03/2019
From:	Jonathan Montgomery NRC/RGN-II/DRS/EB1
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2019010
Download: ML19123A172 (8)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION May 3, 2019

SUBJECT:

SURRY UNITS 1, 2 -NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT 05000280/2019010 AND 05000281/2019010

Dear Mr. Stoddard:

On April 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Surry Units 1, 2 and discussed the results of this inspection with Mr. Fred 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/

Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000280 and 05000281 License Nos.: DPR-32 and DPR-37

Enclosure:

Inspection Report 05000280/2019010 and 05000281/2019010

Inspection Report

Docket Number(s): 05000280 and 05000281 License Number(s): DPR-32 and DPR-37 Report Number(s): 05000280/2019010 and 05000281/2019010 Enterprise Identifier: I-2019-010-0028 Licensee: Virginia Electric & Power Co.

Facility: Surry, Units 1 and 2 Location: Surry, VA 23060 Inspection Dates: April 22, 2019 to April 25, 2019 Inspectors: B. Davis, Sr. Reactor Inspector N. Morgan, Reactor Inspector M. Schwieg, Reactor Inspector Approved By: Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a 10 CFR 50.59 inspection at Surry Units 1 and 2 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations No findings were identified.

INSPECTION SCOPE

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 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

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from March 2015 to February 2019.

(1) DCP 07-046, Replacement of 1-FP-P-2 Diesel Driven Fire Pump, Units 1 & 2

(2) DCP SU-15-01144, 2-SI-MOV-2869A Motor Replacement, Unit 2

(3) DCP SU-16-01101, Reactor Coolant Loop Flow Transmitter 1-RC-FT-1414 Rosemount Model 1153HA5 Replacement with Rosemount Model 3152ND3, Unit 1

(4) DCP 04-088, Replacement of the Emergency Diesel Temperature Switches, Unit 1

(5) DCP SU-13-00006, Emergency Diesel Generator #1 Cable Replacement, Unit 1

(6) DCP 04-076, Oversized Breakers and Undersized Cables Replacement, Units 1 & 2

(7) DCP SU-09-0017, Mechanical Equipment Room 3 & 4 Service Water Chemical Injection, Units 1 & 2

(8) DCP SU-15-01046, Replacement of Pressurizer Spray Bypass Valve 1-RC-139, Unit

(9) DCP SU-15-01056, Mechanical Equipment Room 4 Service Water Material Evaluation, Unit 2

(10) DCP SU-15-01074, Reactor Coolant Pump 1-RC-P-1B Seal Face Change, Unit 1

(11) DCP SU-15-01123, Refueling Water Storage Tank Controller Replacement, Units 1 &

(12) DCP SU-18-00105, Ventilation System Set Point Changes (1-VS-PS-128A, 128A-1, 128B & 128B-1), Unit 1

(13) DCP 98-043, Turbine Driven Auxiliary Feedwater Pump Steam Supply Circuit Upgrades, Unit 1

(14) DCP SU-14-01153, "C" Safety Injection Accumulator Discharge Motor Operated Valve Modification, Unit 1

(15) DCP SU-14-01083, Replacement Flow Switch for 1-VS-FS-117A/B and Setpoint Change, Units 1 & 2

(16) DCP SU-15-01014, Thermal Overload Replacement for Safety Related Motor Operated Valves, Units 1 & 2

(17) DCP 05-048, Circulating Water Inlet Motor Operated Valve Modification, Units 1 & 2

(18) DCP SU-15-01063, Reconfiguration of Direct Current Circuit Breakers, Units 1 & 2

(19) DCP SU-15-01075, Reconfiguring Reactor Protection Trip Breaker Ladder Logic Wiring, Units 1 & 2

(20) DCP SU-09-0008, Motor Operated Valve Stem Cuts, Unit 2

(21) DCP SU-10-01041, High Head Safety Injection Motor Operated Valve Pressure Locking Modifications, Units 1 & 2

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On April 25, 2019, the inspector presented the inspection results to Mr. Fred Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations EE-0183 CSA Calculation for Surry Power Station Units 1 and 2 Rev. 5

Reactor Coolant Flow

ME-0615 Auxiliary Ventilation System Flow/Pressure Model Rev. 0

ME-0977 Hydraulic Calculation of Fire Main Loop Rev. 0

ME-0977 Hydraulic Calculation of Fire Main Loop Rev. A

SM-1323 Pressurizer Spray Bypass Flow Rate Calculation, Surry Rev. 0

Power Station, Units 1 and 2

Corrective Action 1002002

Documents 1017294

2165

2632

553409

554091

2198

Corrective Action 1121608 Missing Record for 0-NSP-RC-001 Vibration Testing 4/23/2019

Documents

Resulting from

Inspection

Drawings 11448-FB-47A Flow/Valve Operating Numbers Diagram Fire Protection & Rev. 34

Domestic Water System Surry Power Station - Unit 1

Miscellaneous ET-S-04-0018 Evaluate SW Pipe Spool for IEER Rev. 0

MOV 2-SI-2869A Motor Current Evaluation 11/18/2015

Procedures 0-ECM-1403-01 Electrical Corrective Maintenance Rev. 40

0-NSP-RC-001 Reactor Coolant Pump Vibration and Balancing Data Rev. 2

ET-CEE-08-0015 Motor Operated Valve (MOV) Overcurrent Issue Six Sigma Rev. 1

Project Results

Work Orders 38102423911

38102423911

38102586663

71111.17T Work Orders 38103521042

38103564388

38103584837

38103584844

38103631355

38103631403

38103635555

38103638419

38103676443