IR 05000280/2020010: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
{{Adams
| number = ML20171A348
| number = ML20310A112
| issue date = 06/19/2020
| issue date = 11/05/2020
| title = Notification of Surry Power Station Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000280/2020010 and 05000281/2020010
| title = NRC Design Bases Assurance Inspection Report 05000280/2020010 and 05000281/2020010
| author name = Baptist J
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS/EB1
| author affiliation = NRC/RGN-II
| addressee name = Stoddard D
| addressee name = Stoddard D
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
| addressee affiliation = Virginia Electric & Power Co (VEPCO)
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = IR 2020010
| document report number = IR 2020010
| document type = Letter
| document type = Inspection Report, Letter
| page count = 6
| page count = 11
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:June 19, 2020
{{#Wiki_filter:November 5, 2020


==SUBJECT:==
==SUBJECT:==
NOTIFICATION OF SURRY POWER STATION DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000280/2020010 AND 05000281/2020010
SURRY POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000280/2020010 AND 05000281/2020010


==Dear Mr. Stoddard:==
==Dear Mr. Stoddard:==
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
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.
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Surry Power Station during the weeks of September 14-18, 2020, and September 28-October 2, 2020.


Mr. Theo Fanelli, a Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320).
No findings or violations of more than minor significance were identified during this inspection.


The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.
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.


During a telephone conversation on June 15, 2020, with Mr. Steve Newman, we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:
Sincerely,
* Information-gathering visit: Week of August 24, 2020
/RA/
* Onsite weeks: Weeks of September 14 and September 28, 2020 The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components and operator actions.
James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37


Information and documentation needed to support the inspection will also be identified.
===Enclosure:===
As stated


Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Fanelli during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the first onsite week, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios. The enclosure lists documents that will be needed prior to the information-gathering visit.
==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


Please provide the referenced information to the Region II Office by Friday, August 14, 2020.
=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.


Additional documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Wednesday, September 2, 2020, to support the inspection teams preparation week.
===List of Findings and Violations===


During the information-gathering trip, Mr. Fanelli will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector requests during the inspection; (3) licensee computer access; (4) working space; (5)
No findings or violations of more than minor significance were identified.
arrangements for site access; and (6) other applicable information.


In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
===Additional Tracking Items===
None.


Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Fanelli at 404-997-4433 or contact me at 404-997-4506.
=INSPECTION SCOPES=


Sincerely, James Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-280, 50-281 License Nos.: DPR-32, DPR-37 Enclosure:
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.
Notification of Surry Power Station Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv


ML20171A348 OFFICE RII:DRS RII:DRS SIGNATURE  EJS2 TNF1 FOR JBB1 NAME  T. Fanelli J. Baptist DATE  6/15/2020 6/15/2020
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.


INFORMATION REQUEST FOR SURRY POWER STATION DESIGN BASES ASSURANCE INSPECTION (TEAMS)
==REACTOR SAFETY==
Please provide the information electronically in .pdf files, Excel, or other searchable format on CDROM (or Certrec, FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*), should have a date range from February 1, 2017, until present.


1. *List and brief description of permanent plant modifications including permanent plant changes, design changes, set point changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications. Include an index of systems (system numbers/designators and corresponding names), the safety classification for each modification, and type of modification.
===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
* Updated Final Safety Analysis Report (UFSAR), including applicable design and licensing basis requirements
* Material condition and configuration (e.g. visual inspection during a walkdown)
* Time critical operator actions associated with internal flooding scenario
* 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.)
* Adequacy of corrective action activities Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
{{IP sample|IP=IP 71111.21|count=1}}
: (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
* Susceptibility to tornado missiles
* Component condition and walkdown
* System health reports


2. From your most recent probabilistic safety analysis (PSA) excluding external events and fires:
===Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance b. A list of the top 500 cut-sets c. A list of the top 500 LERF contributors 3. From your most recent PSA including external events and fires:
: (1) SU-18-00116, Stem and Disc Arm Replacement for 1-SI-MOV-1863A
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance b. A list of the top 500 cut-sets 4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items 5. List of time-critical operator actions with a brief description of each action 6. *List of components with low-design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.) and associated evaluations or calculations 7. *List and brief description of Root Cause Evaluations performed 8. *List and brief description of common-cause component failures that have occurred 9. List and brief description of equipment currently in degraded or nonconforming status.
: (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


10. *List and brief description of Operability Determinations and Functionality Assessments 11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status Enclosure
===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


12. *List of equipment on the sites Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s) along with dates added or removed from the issues list 13. List of current operator work arounds/burdens 14. Copy of Updated Final Safety Analysis Report 15. Copy of Technical Specification(s)
==INSPECTION RESULTS==
16. Copy of Technical Specifications Bases 17. Copy of Technical Requirements Manual(s)
No findings were identified.
18. Copy of the Quality Assurance Program Manual 19. Copy of Corrective Action Program Procedure(s)
20. Copy of Operability Determination Procedure(s)
21. Copy of Original SER with all Supplements 22. Copy of procedures addressing the following: Corrective Action Program (CAP),
Modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates.


23. List of motor operated valves and air operated valves in valve programs, and their associated design margin and risk ranking (Please Note JOG program commitments for MOVs and AOVs).
==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.


24. Primary AC and DC calculations for safety-related buses 25. One-line diagram of electrical plant (Electronic only)
=DOCUMENTS REVIEWED=
26. Index and legend for electrical plant one-line diagrams 27. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
28. Index and legend for P&IDs 29. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures 30. Copies of corrective action documents generated from previous CDBI / DBAI 31. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI


32. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address)
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
}}
}}

Latest revision as of 11:35, 15 December 2021

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

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000280/2020010&oldid=3381194"