IR 05000387/2019011

Design Basis Assurance Inspection (Teams) Inspection Report 05000387/2019011 and 05000388/2019011

ML19317D574
Person / Time
Site:	Susquehanna
Issue date:	11/12/2019
From:	Mel Gray Engineering Region 1 Branch 1
To:	Berryman B Susquehanna
Gray M
References
IR 2019011
Download: ML19317D574 (11)

Text

ber 12, 2019

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000387/2019011 AND 05000388/2019011

Dear Mr. Berryman:

On October 10, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2 and discussed the results of this inspection with Mr. Kevin Cimorelli, Site Vice President 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/

Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000387 and 05000388 License Nos. NPF-14 and NPF-22

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000387 and 05000388 License Numbers: NPF-14 and NPF-22 Report Numbers: 05000387/2019011 and 05000388/2019011 Enterprise Identifier: I-2019-011-0023 Licensee: Susquehanna Nuclear, LLC Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, PA Inspection Dates: September 15, 2019 to October 5, 2019 Inspectors: E. Burket, Senior Reactor Inspector J. Kulp, Senior Reactor Inspector M. Orr, Reactor Inspector S. Pindale, Senior Reactor Inspector M. Yeminy, NRC Mechanical Contractor W. Hopf, NRC Electrical Contractor Approved By: Mel Gray, 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 design basis assurance inspection (teams) inspection at Susquehanna Steam Electric Station, 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.

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.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams)

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience during the weeks of September 16, 2019, and September 30, 2019.

For the components, the team reviewed the attributes listed in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.

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

=

(1) 125 Vdc Load Center, 1D622 (EP-BS-1D622)

Material condition and configuration (reviewed periodic inspection results)

Normal, abnormal, and emergency operating procedures Environmental qualification classification Protection against seismic events Surveillance testing and recent results Maintenance effectiveness Consistency between station documentation (e.g., procedures) and vendor specifications Translation of vendor specifications Electrical design calculations System health report and operational history Component health, corrective maintenance records, and corrective action history The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System

(2) 'A' Emergency Diesel Generator (Electrical), 0G501A Material condition and installed configuration (e.g., visual inspection/walkdown)

Normal, abnormal, and emergency operating procedures Consistency among design and licensing bases and other documents and procedures System health report, maintenance effectiveness and records, and corrective action history Control logic Design calculations Surveillance testing and recent test results Adequacy of electrical power supply for motor and controls Protection coordination; Load in-rush and full load current Range, accuracy, and setpoint of installed instrumentation Equipment protection from fire, flood, and water intrusion or spray Heat removal cooling water and ventilation Energy sources, fuel and air (e.g., engine start, operation, and control)

Contactor and fuse ratings; Component adequacy for minimum voltage The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System.

(3) B Emergency Service Water Pump, 0P504B Material condition and installed configuration (e.g., visual inspection/walkdown)

Normal, abnormal, and emergency operating procedures Consistency among design and licensing bases and other documents and procedures System health report, maintenance effectiveness and records, and corrective action history Control logic Equipment/environmental controls and qualification Operator actions Design calculations Surveillance testing and recent test results Range, accuracy, and setpoint of installed instrumentation Equipment protection from fire, flood, and water intrusion or spray Heat removal cooling water and ventilation Pump Net positive Suction Head and Vortex considerations Pump interaction with sister pumps The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System.

(4) Unit 1 Reactor Core Isolation Cooling Pump and Turbine Material condition and installed configuration (e.g., visual inspection/walkdown)

Normal, abnormal, and emergency operating procedures Consistency among design and licensing bases and other documents and procedures System health report, maintenance effectiveness and records, and corrective action history Equipment/environmental controls and qualification Operator actions Design calculations Surveillance testing and recent test results Range, accuracy, and setpoint of installed instrumentation Equipment protection from fire, flood, and water intrusion or spray Heat removal cooling water and ventilation Energy sources, fuel and air (e.g., engine start, operation, and control)

The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System.

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (2 Samples)

(1) Unit 1 Tie Bus 0A106 Material condition and configuration (review periodic inspection results)

Normal, abnormal, and emergency operating procedures Environmental qualification classification Surveillance testing and recent results Maintenance effectiveness Consistency between station documentation (e.g., procedures) and vendor specifications Translation of vendor specifications Electrical design calculations System health report and operational history Component health, corrective maintenance records, and corrective action history The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System.

(2) Unit 1 Residual Heat Removal Suppression Pooling Cooling/Test Control Valve, HV151F024A Material condition and installed configuration (e.g., visual inspection/walkdown)

Normal, abnormal, and emergency operating procedures Consistency among design and licensing bases and other documents and procedures System health report, maintenance effectiveness and records, and corrective action history Control logic Equipment/environmental controls and qualification Operator actions Design calculations Surveillance testing and recent test results Range, accuracy, and setpoint of installed instrumentation Equipment protection from fire, flood, and water intrusion or spray Heat removal cooling water and ventilation The team used Appendix B guidance for Valves, Instrumentation, Electric Loads, and As-Built System.

Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)

(1) EC 1923863, Replace Unit 1 Service Water Valves, HV11024A3 and HV11024B3

(2) EC 2002457, Instrument Air Design Pressure Increase

(3) EC 1865356, 2x210 ESS Load Center Transformer Replacement

(4) EC-023-1007, Fuel Oil Consumption Rates for 'A' - 'D' and 'E' Emergency Diesel Generators Review of Operating Experience Issues (IP Section 02.06) (2 Samples)

(1) OpESS 2007/02, Revision 3, Analysis of Flooding Vulnerabilities

(2) OpESS 2008-01, Negative Trend and Recurring Events involving Emergency Diesel Generators

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 4, 2019, the team presented the preliminary results of the Design Bases Assurance Inspection to Mr. Kevin Cimorelli, Site Vice President, and other members of the licensee staff. After further in-office review, the final results of this inspection were presented to Mr. Cimorelli and other licensee staff via telephone on October 10, 2019.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations EC-023-1012 Evaluate Impact of Use of Biodiesel (B5) and Ultra-Low Revision 3

Sulfur Diesel Fuel on the Diesel Generator Fuel Oil Storage

and Transfer System

EC-024-0012 Modify Emergency Diesel Generator Over-Voltage Relays Revision 0

EM1,

EC-024-0629 SSES FSAR 8.3 Diesel Generator Loading Tables Updates Revision 18

EC-024-1029 Evaluation of EDG Frequency Response During Design Revision 0

Basis LOOP/LOCA Transient Loading with Replacement

Woodward 2301A Governor

EC-028-0010 ESW Pump Structure Heat Gain Revision 2

EC-054-0538 NPSH Calculation for ESW Pumps Revision 0

EC-FLOD-0001 Internal Flooding Evaluations for Moderate Energy Pipe Revision 0

Cracks and Sprinkler System Actuations

EC-FLOD-0001 Internal Flooding Evaluations for Moderate Energy Pipe Revision 3

Cracks and Sprinkler System Actuations

EC-FLOD-0001 Internal Flooding Evaluations for Moderate Energy Pipe Revision 4

Cracks and Sprinkler System Actuations

EC-FLOD-0001 Internal Flooding Evaluations for Moderate Energy Pipe Revision 5

Cracks and Sprinkler System Actuations

EC-PUPC-20309 EPU Task Report T0309, Reactor Core Isolation Cooling Revision 0

System

EC-SOPC-0597 Relay Setting Calculations for Diesel Generator ABCD Sync Revision 1

Corrective Action AR-2016-09219

Documents AR-2016-09451

AR-2016-12920

AR-2017-01015

CR 2016-08441

CR 2017-13061

CR 2018-06820

CR 2019-11984

CR 2019-11994

CR-2016-08172

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-2016-12235

CR-2016-12238

CR-2018-17000

Corrective Action CR-2019-11742

Documents CR-2019-11752

Resulting from CR-2019-11801

Inspection CR-2019-11816

CR-2019-11918

CR-2019-11926

CR-2019-11993

CR-2019-12188

CR-2019-12283

CR-2019-12357

CR-2019-12362

CR-2019-12410

CR-2019-12525

CR-2019-12698

Drawings E-148 Unit 1 RBCCW Transfer SOVs Revision 16

E106216, Sh. 1 Emergency Service Water System Revision 51

E107158, Sh. 1 Unit 1 and 2 Single Line Diagram Station Revision 40

FF105801, Sh. Common DG Control Schematic, Shutdown and Alarm Revision 15

2411 System for OC521A

M-110 Unit 1 Service Water Revision 45

P-25-5, Sheet 1 Drainage Reactor Building Unit #1 Area 25 Plan Of Elevation Revision 13

749

P-27-5, Sheet 1 Drainage Reactor Building Unit #1 Area 25 Plan Of Elevation Revision 10

749

P-28-5, Sheet 1 Drainage Reactor Building Unit #1 Area 25 Plan Of Elevation Revision 9

749

P-29-5, Sheet 1 Drainage Reactor Building Unit #1 Area 25 Plan Of Elevation Revision 8

749

Engineering EC-002-0500 125 VDC System 1D620 Master Battery Calculation Revision 38

Changes EC-088-0530 Evaluation of Overvolt-250/125 VDC 1E Equip Revision 6

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering CR Evaluation/Action Plan Report for CR 923407 Revision 2

Evaluations

Miscellaneous BMR E121 Material Requisition Direct Current Control Centers and Revision 23

Load Centers

DBD-10 Design Basis Document for HELB/MELC/Internal Flooding Revision 3

IOM 1282 Tricentric Service Manual Revision 7

M1441-29 Flush/Check Floor Drains (Pre-Outage), dated

February 15,

2018

M2139-01 RCIC Turbine, 1S212 005 for Turbine Internal Inspection dated

4/14/16

SO-150-002 Quarterly RCIC flow verification dated 5/2/18

Procedures NDAP-QA-0343 Time Critical and Time Sensitive Operator Actions Revision 4

OP-003-001 13.8 kV Common Electrical Equipment Revision 20

OP-102-001 125V DC System Revision 27

OP-111-001 Unit 1 Service Water System Revision 52

OP-150-001 RCIC System Revision 50

OT-150-004 RCIC Turbine overspeed trip testing Revision 1

Work Orders 1837564

1863850

2108859

9