IR 05000280/2020010

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NRC Design Bases Assurance Inspection Report 05000280/2020010 and 05000281/2020010
ML20310A112
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/05/2020
From: James Baptist
NRC/RGN-II
To: Stoddard D
Virginia Electric & Power Co (VEPCO)
References
IR 2020010
Download: ML20310A112 (11)
v • d • e


Text

November 5, 2020

SUBJECT:

SURRY POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000280/2020010 AND 05000281/2020010

Dear Mr. Stoddard:

On October 2, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station and discussed the results of this inspection with Mr. Doug Lawrence, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

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

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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety 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: 05000280/2020010 and 05000281/2020010 Enterprise Identifier: I-2020-010-0045 Licensee: Virginia Electric and Power Company Facility: Surry Power Station Location: Surry, VA Inspection Dates: September 14, 2020 to October 02, 2020 Inspectors: P. Braxton, Reactor Inspector W. Deschaine, Senior Resident Inspector A. Lerch, Reactor Inspector R. Patterson, Senior Reactor Inspector B. Pinson, Reactor Inspector M. Riley, Senior Reactor Inspector T. Su, Reactor Inspector M. Yeminy, Contractor Approved By: James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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

None.

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 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)

(1) Unit 1 Motor Driven Auxiliary Feedwater Pump 1-FW-P-3A
  • Calculation for system flow rates, vortex limits, and net positive suction head for each pump
  • Calculation for emergency condensate storage tank size, including high and low water levels
  • Suction flow rates, including combined pump suction capabilities and transfer of flow rate to another source when tank level is low
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Operating procedures
  • Maintenance effectiveness
  • Component health reports, corrective maintenance records, and corrective action history
  • Operator actions
  • Surveillance and calibration testing and recent test results
  • Modifications performed
(2) Unit 2 Auxiliary Building Backflow Preventers
  • Calculations for expected internal flood heights in turbine and auxiliary buildings
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Maintenance effectiveness
  • Corrective action and corrective maintenance history
  • Preventive maintenance history
  • Component modification history
(3) Unit 2 4160V 2H Emergency Bus
  • Operating Environment
  • Compliance with UFSAR, Technical Specifications (TS), and TS Bases
  • Conformance with manufacturer instructions for installation, maintenance, and operation
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Verification that system health reports accurately reflect current system conditions
  • Design requirements (rating, loading, short circuit analysis, etc.)
  • Protective relays and coordination
  • Adequacy of corrective action activities
(4) Emergency Diesel Generator #3 Output Breaker 25J3
  • Operating Environment
  • Compliance with UFSAR, TS and TS Bases
  • Conformance with manufacturer instructions for installation, maintenance, and operation
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Identification and follow-up of issues identified in system health reports
  • Verification of system design requirements (Rating, loading, etc.)
Main article: IP 71111.21
(1) Unit 2 Main Steam Safety Valve (MSSV) 2-MS-SV-201A
  • UFSAR, TS, and other design and licensing basis requirements
  • MSSV capacity and system steam flow (normal and accident)
  • MSSV seismic qualification
  • Corrective actions
  • In-service test requirements and required maintenance
  • Component condition and walkdown
  • System health reports

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) SU-18-00116, Stem and Disc Arm Replacement for 1-SI-MOV-1863A
(2) SU-19-01068, Replacement of 01-FW-LT-1495-IXMITR
(3) SU-19-00113, 1-RC-P-1A Abeyance Seal Upgrade
(4) SU-17-00104, MOV Hot Short MCC Wiring Modification
(5) SU-19-01001, Replacement of Service Water Transmitter, 01-SW-FT-106A
(6) SU-PTE-000, Fuel Oil Day Tank ASCO SOV Series 8210

Review of Operating Experience Issues (IP Section 02.06) (3 Samples)

(1) NRC Information Notice 09-11, Configuration Control Errors
(2) NRC Information Notice 15-01, Degraded Ability to Mitigate Flooding Events
(3) NRC Information Notice 16-08, Inadequate Work Practices Resulting in Faulted Circuit Breaker Connections

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On October 2, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Doug Lawrence, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations ME-0747 MOV Differential Pressure Calculation for the LHSI Supply Revision 0

Isolation Valves to the Charging Pump

ME-3330 JOG Calculation of Required Thrust Settings for MOV 1-SI- Revision 4

MOV-1863A

14937.44-C-11 Main Steam Relief Valve Capacity Limits at 110% Revision 1

DCP-00-20 Miscellaneous NSSS Protection and Control System 09/13/2001

Setpoints

EE-0339 Relay Setting Calculations for the Protection of Safety Bus Revision 0

2H at Surry Power Station

EE-0879 SPS 4160V and 480 V Short-Circuit Analysis Revision 0

ME-0277 North Anna 1&2 / Surry 1&2 Secondary- Side Design Revision 2

Thermal Performance and Heat Balances

ME-0637 PEPSE Heat Balance Model for Surry Power Station Core Revision 0

Uprate and Turbine Retrofit Projects

SM-796 Surry SGTR Analysis for Core Uprate Condition Revision 0

SU-CALC-EEP- Protective Relay Setting Revision 0

EE-0336

SU-CALC-EEP- Protective Relay Settings Revision 0

EE-0336

Corrective Action CRs 570285, Various Corrective Action Reports Various

Documents 1098552,

1109856,

1148513, 360054,

518985

Corrective Action CR 1155555 JOG Classification Documented in a Superseded 09/16/2020

Documents Engineering Technical Evaluation (ETE)

Resulting from CR 1155602 Error in Calculation SU-CALC-ICC-EE-0111 09/17/2020

Inspection CR 1156028 Calculation Error in PQE 09/22/2020

CR 1156261 PQE Review for 3152N Rosemount Transmitter 09/24/2020

CR 1156667 Non-Safety Classification of Backflow Preventers 09/29/2020

CR 1156851 Periodic Testing of Circuit Breaker 25J3 Undervoltage Relay 10/01/2020

Drawings 11448-FE-1A2 Electrical Power Distribution - One Line Integrated Revision 44

Inspection Type Designation Description or Title Revision or

Procedure Date

Schematic

SU-DWG-000- AFW System Flow Diagrams Revision 65

11448-FM-068A

SU-DWG-000- Safety Injection Flow Diagram Revision 54

11448-FM-089A

SU-DWG-000- Safety Injection Flow Diagram Revision 35

11448-FM-089B

Engineering 81-050 EDG Transfer Bus Mod 2 Second Delay 10/09/81

Changes DCP 00-049 EDG Output Breaker Circuit Modification and Relay Setpoint 07/12/01

Change/Surry/Unit 1 & 2

SU-19-00113 1-RC-P-1A Abeyance Seal Upgrade 08/29/2019

SU-19-01001 Replacement of Service Water Flow Transmitters Revision 1

SU-19-01068 Replacement of 01-FW-LT-1495-IXMITR Revision 0

SU-PTE-000 Fuel Oil Day Tank ASCO SOV Series 8210 Version 01

Engineering CT-EQUAL-000- 3154N Pressure Transmitters Revision 2

Evaluations PQE-08.27-P01

D2013003 IEEE Qualification Report of Rosemount 3154N Pressure Revision B

Transmitters

EE-0116 Allowable Custom Values for North Anna Improved Revision 17

Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1

and Setting Limits for Surry Technical Specifications (CTS),

Sections 2.3 and 3.7

EE-0432 CSA Calculation for Surry Power Station, Steam Generator Revision 5

Narrow Range Level, Units 1 & 2

ET-NAF-07-0092 Evaluation of Main Steam Exhaust Piping Vulnerability to Revision 0

Tornado Generated Missiles at North Anna and Surrv

ETE-CEE-2016- Performance Specification for Rosemount 3153N and Revision 0

0006 3154N Series Transmitters

ETE-SU-2015- Design Basis for Backflow Preventers in Charging Pump Revision 0

0069 Cubicles, MER 3, MER 4, and MER 5

ETE-SU-2020- Main Steam Safety Valves and Pressurizer Safety Valves Revision 0

0037 repaired/refurbished without SCM Vendor Surveillance

PA3035300 Evaluate IN 16-08 08/21/16

SU-EQUAL-000- 3154N Pressure Transmitters EQ Evaluation Revision 2

Inspection Type Designation Description or Title Revision or

Procedure Date

PQE-08.27-P01

Miscellaneous Surry EQML 09/17/2020

CT-EQUAL-000- 3154N Series Transmitters Rosemount Report Revision 0

GQE-08.27-G01

D2013003 IEEE Qualification Report for Rosemount 3154N Pressure Revision B

Transmitters

ET-CEM-99-0009 Spectral Peaks and Zero Period Accelerations (ZPA) - OBE Revision 0

and DBE Surry Power Station - Units 1 and 2

ME-0009 Design Specification for Reactor Coolant Pump N-9000 Seal Revision 001

Assembly

OEE000707 OPEX002248: IN 2009-11 Configuration Control Errors 04/05/2010

PI-AA-100-1007- NRC Information Notice 2016-08 08/10/16

Attachmentt 9

PIR 1040648 IN 16-08, Inadequate Work Practices Resulting in Faulted 06/30/16

Circuit Breaker Connections

SDBD-SPS-EG System Design Basis Document for Emergency Diesel Revision 24

Generator System, Surry Power Station

SDBD-SPS-FW System Design Basis Document for Feedwater System Revision 18

Surry Power Station

SU-EQUAL-000- Surry Environmental Zone Description Units 1 & 2 Revision 29

38-EZD

Procedures 0-AP-13.00 Turbine Building or MER 3 Flooding Revision 33

0-AP-13.01 Uncontrollable Turbine Building Flooding Revision 10

0-AP-13.02 Loss of ESGR Cooling Revision 11

0-DRP-049 Time Critical Operator Actions Revision 19

0-OSP-TCA-001 Time Critical Operator Action Validation Revision 22

1-AP-9.02 Loss of RCP Seal Cooling Revision 14

1-AP-9.02 Loss of RCP Seal Cooling Revision 14

2-DRP-006 Protective Relay Setpoints Revision 28

2-MPT-0427-02 Main Steam Safety Setpoint Verification Revision 12

CM-AA-400 10 CFR 50.59 and 10 CFR 72.48 - Changes, Tests, and Revision 13

Experiments

DNES-AA-MEL- Determining the Safety Classification of Structures, Revision 3

4001 Systems, and Components

Inspection Type Designation Description or Title Revision or

Procedure Date

ER-AA-IST-103 ASME IST Program - Inservice Testing of Pressure Relief Revision 3

Devices

ER-AA-IST-PRD- ASME IST Program - Inservice Testing of Pressure Relief Revision 1

103 Devices Implementation

PI-AA-100-1007 Operating Experience Program Revision 2

Work Orders 38203877019,

38103441574,

38103791010,

204185642,

204185670,

204209440,

204209678,

204210949,

38102151703,

204036719,

203920040,

38103690022,

381021411743,

38102166449,

38103724130,

203871047

9

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