IR 05000387/2019002

Integrated Inspection Report 05000387/2019002 and 05000388/2019002

ML19224A288
Person / Time
Site:	Susquehanna
Issue date:	08/09/2019
From:	Jon Greives Reactor Projects Region 1 Branch 4
To:	Berryman B Susquehanna
Greives J
References
IR 2019002
Download: ML19224A288 (22)

Text

ust 9, 2019

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -

INTEGRATED INSPECTION REPORT 05000387/2019002 AND 05000388/2019002

Dear Mr. Berryman:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On July 11, 2019, the NRC inspectors discussed the results of this inspection with you 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 E. Greives, Chief Reactor Projects Branch 4 Division of Reactor Projects 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: 05000387/2019002 and 05000388/2019002 Enterprise Identifier: I-2019-002-0035 Licensee: Susquehanna Nuclear, LLC Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, PA Inspection Dates: April 1, 2019 to June 30, 2019 Inspectors: L. Micewski, Senior Resident Inspector M. Rossi, Resident Inspector D. Beacon, Resident Inspector T. Daun, Resident Inspector E. Dipaolo, Senior Reactor Inspector J. Furia, Senior Health Physicist J. Kulp, Senior Reactor Inspector A. Turilin, Reactor Inspector Approved By: Jonathan E. Greives, 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 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.

PLANT STATUS

Unit 1 began the inspection period at 100 percent power. On May 1, 2019, operators reduced power to approximately 80 percent for a control rod pattern adjustment, condenser waterbox cleaning, and scram time testing. Operators returned the unit to 100 percent on May 4, 2019.

On May 22, 2019, operators reduced power to approximately 78 percent after a loss of power to a breaker for a 480-volt motor control center (MCC) caused the unit to enter Technical Specification Limiting Condition for Operation (LCO) 3.0.3, which required a shutdown to Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Operators commenced the shutdown, however exited LCO 3.0.3 after restoring power to the affected MCC, when the unit was at about 78 percent. Operators returned the unit to 100 percent power later that same day. On May 31, 2019, operators reduced power to approximately 66 percent to perform a control rod sequence exchange.

Operators returned the unit to 100 percent on June 2, 2019, and remained at or near 100 percent power for the remainder of the inspection period.

Unit 2 began the inspection period shutdown in Mode 5 for a planned refueling outage. Following the completion of refueling and maintenance activities, operators commenced a reactor startup on April 20, 2019, and achieved full power on April 30, 2019. On May 6, 2019, a recirculation pump rundown was automatically initiated following an electrical fault that tripped reactor building cooling water and chillers. The rundown reduced power to 78 percent. Operators subsequently reduced power to approximately 70 percent to stay within rod line operating limits. Following repairs and restoration from the electrical fault, operators returned the unit to 100 percent on May 7, 2019. On May 22, 2019, operators reduced power to approximately 79 percent after a loss of power to a breaker for a 480-volt MCC caused the unit to enter Technical Specification LCO 3.0.3, which required a shutdown to Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Operators commenced the shutdown, however exited LCO 3.0.3 after restoring power to the affected MCC, when the unit was at about 79 percent. Operators returned the unit to 100 percent power later that same day. On June 28, 2019, operators reduced power to approximately 57 percent to perform a control rod sequence exchange. Operators returned the unit to 100 percent on June 30, 2019, and remained at or near 100 percent power for the remainder of the inspection period.

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.

71111.01 - Adverse Weather Protection Summer Readiness Sample (IP Section 03.01)

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current power systems on May 30, 2019.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, core spray prior to division swap on April 4, 2019

(2) Unit 2, snubbers inside containment on April 16, 2019

(3) Unit 1 and Unit 2, spent fuel pool cooling during Unit 2 residual heat removal (RHR)common system outage window on April 22, 2019

(4) Unit 1, standby liquid control quarterly flow surveillance on April 23, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 high pressure injection system on April 9, 2019.

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

(1) The inspectors evaluated fire brigade performance on May 23, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 1, division 2, 250V and 125V battery rooms (fire zones 0-28M, 0-28N, 0-28J) on April 3, 2019

(2) Unit 2, equipment access area elevation 683' (fire zone 2-3C) on April 16, 2019

(3) Unit Common, 'E' emergency diesel generator (EDG) while swapped in during air compressor upgrades (fire zone 0-41E) on June 5, 2019

(4) Unit 2, load center and switchgear rooms (fire zones 2-4C/D and 2-5F/G) on June 17, 2019

(5) Unit 1, low pressure coolant injection equipment elevation 645' (fire zones 1-1B/D/E/F) on June 19, 2019

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 2, division 1 RHR room while aligned for shutdown cooling while flood doors obstructed on April 8, 2019

71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)

The inspectors evaluated readiness and performance of:

(1) Unit 2, division 2 RHR heat exchanger on April 22, 2019

===71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) ===

(1) The inspectors verified that the reactor coolant system (RCS) boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the following activities during the Susquehanna Unit 2 2R19 refueling outage from April 1, 2019, to April 5, 2019:

03.01.a - Nondestructive Examination and Welding Activities 1. Manual encoded phased array ultrasonic examination of standby liquid control system weld (SPDCA239-1 W3) for license renewal commitment to examination small bore piping welds 2. Ultrasonic examination of reactor vessel bottom head meridional weld DC 3. Magnetic particle examination of high pressure coolant Injection piping support weld (HBB2081-HW-1)4. Visual examination (VT-1) of N2B jet pump riser support weld A 5. Visual examination (EVT-1) of core shroud horizontal weld H4 6. ASME IWE visual examination of drywell liner and penetrations elevation 738-752

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) The inspectors observed and evaluated licensed operator performance in the Control Room during reactor startup operations on April 20, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a simulation of a seismic event resulting in multiple system failures on May 23, 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 2, reactor pressure vessel/pressure boundary flow accelerated corrosion program on April 15, 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 2, spent fuel pool cooling system during common shutdown cooling work window on April 10, 2019

(2) Unit Common, yellow risk during 'B' emergency service water outage on May 21, 2019

(3) Unit Common, elevated risk while 'C' and 'E' EDG inoperable on June 7, 2019

(4) Unit 1, breaker 1B22023 swap at power on June 11, 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) Unit 2, 250 VDC molded case circuit breaker failure on April 10, 2019

(2) Unit 2, high pressure injection snubber inoperable due to missing parts on May 13, 2019

(3) Units 1 and 2, ACT-01-CR-2019-07154, MCC 0B136 prompt operability determination, dated May 24, 2019

(4) Unit 2, local power range monitor connection swapped 48-33 B/D on June 11, 2019

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 2, EC 2203222, replace obsolete Mallory M200 PK potentiometer with Bourns 3400S-1-201L on April 10, 2019

(2) Unit Common, 'D' EDG starting air compressor modification on May 13, 2019

71111.19 - Post Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Unit 2, division 2 RHR following maintenance during refueling outage on April 4, 2019

(2) Unit 2, 125V battery charger 2D633 following maintenance and installation of engineering change on April 9, 2019

(3) Unit 2, 125VDC molded case circuit breaker 2D614 on April 11, 2019

(4) Unit 2, snubber replacement inside containment on April 16, 2019

(5) Unit 2, reactor vessel leak check on April 18, 2019

(6) Unit 2, safety relief valve replacement on April 18, 2019

(7) Unit Common, HS-0041B synchroscope selector switch replacement on April 20, 2019

(8) Unit 2, reactor core isolation cooling 150# test on April 20, 2019

(9) Unit 2, high pressure coolant injection exhaust vacuum breaker checked on May 3, 2019

(10) Unit Common, 'B' emergency system water discharge isolation and check valve repair on May 22, 2019

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) The inspectors evaluated Unit 2 refueling outage 2R19 activities from April 1, 2019, to April 20, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Containment Isolation Valve Testing (IP Section 03.01)

(1) Unit 2, main steam isolation valve 28 D test after maintenance on May 3, 2019

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 1, standby liquid control quarterly flow surveillance on April 23, 2019

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) Unit 2, division 2 automatic depressurization system logic system functional test on April 16, 2019

(2) Unit 2, RCS pressure test on April 18, 2019

(3) Unit Common, 'A' EDG analyzer run on April 29,

71124.01 - Radiological Hazard Assessment and Exposure Controls Instructions to Workers (IP Section 02.02)

The inspectors evaluated instructions to workers, including radiation work permits, used to access high radiation areas.

(1) The inspectors reviewed high radiation area work permit controls and use; and observed containers of radioactive materials and assessed whether the containers were labeled and controlled in accordance with requirements.

Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors examined the physical controls for selected high radiation areas, locked high radiation areas, and very high radiation areas to verify conformance with the occupational performance indicator.

High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

(1) The inspectors reviewed the procedures and controls for high radiation areas, very high radiation areas, and radiological transient areas in the plant.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)

(1) The inspectors evaluated radiation worker performance with respect to radiation protection work requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage.

71124.02 - Occupational ALARA Planning and Controls Implementation of ALARA and Radiological Work Controls (IP Section 02.03)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls.

(1) The inspectors reviewed radiological work controls and as low as reasonably achievable (ALARA) practices during the observation of in-plant work activities. The inspectors reviewed the results achieved against the intended ALARA estimates to confirm adequate implementation and oversight of radiological work controls.

71124.07 - Radiological Environmental Monitoring Program Groundwater Protection Initiative Implementation (IP Section 02.02)

(1) The inspectors reviewed: groundwater monitoring results; changes to the Groundwater Protection Initiative program since the last inspection; anomalous results or missed groundwater samples; leakage or spill events including entries made into the decommissioning files (10 CFR 50.75(g)); evaluations of surface water discharges; and evaluation of any positive groundwater sample results including appropriate stakeholder notifications and effluent reporting requirements.

Site Inspection (IP Section 02.01) (1 Sample)

The inspectors evaluated the radiological environmental monitoring program implementation.

(1) The inspectors walked down various thermoluminescent dosimeter and air and water sampling locations and reviewed associated calibration and maintenance records. The inspectors observed the sampling of various environmental media as specified in the Offsite Dose Calculation Manual. The inspectors reviewed the groundwater monitoring program as it applies to selected potential leaking structures, systems, and components; and 10 CFR 50.75(g) records of leaks, spills, and remediation since the previous inspection.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:

BI01: RCS Specific Activity Sample (IP Section 02.10) ===

(1) Unit 1 (January 1, 2018 - December 31, 2018)

(2) Unit 2 (January 1, 2018 - December 31, 2018)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (January 1, 2018 - December 31, 2018)

(2) Unit 2 (January 1, 2018 - December 31, 2018)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

The inspectors reviewed the licensees implementation of its corrective action program (CAP) related to the following issues:

(1) Essential service water (ESW) piping erosion

(2) Non-Cited Violation (NCV) 05000387;05000388/2018001-01, Failure to Proper Testing of 125VDC Molded Case Circuit Breakers to Confirm their Design Adequacy Long-Term

(3) Compensatory measures associated with fire barrier impairments

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed Susquehannas CAP for trends that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Observation: Annual Follow-Up of Selected Issues- Essential service water 71152 (ESW) piping erosion CR-2017-13423 The inspectors reviewed Susquehannas evaluation and corrective actions to address corrosion of safety-related ESW piping located in vault VA021 as documented in CR 2017-13423. Susquehanna staff performed a causal evaluation and determined the corrosion was a result of original construction pipe wrap failure and standing water in the vault.

Susquehanna staff performed an extent of condition evaluation which included all other vaulted ESW piping. The extent of condition identified similar but less extensive pipe wrap degradation and piping corrosion in vaults VA022 to VA026. Susquehanna staff implemented or scheduled corrective actions to drain the vaults and repair the degraded areas of the pipe wrap. Additionally, the inspectors determined that Susquehanna staff conducted an extent of cause evaluation and determined that the water intrusion resulted from rain water permeating the original deteriorated vault lid gasket. Susquehanna staff developed and implemented corrective actions to prevent rain water intrusion into the vaults. The corrective actions included assessing the vault lid gasket condition after each opening as well as caulking around the vault lid after the vault is closed. Furthermore the inspectors determined that corrective actions are scheduled to evaluate the inner and outer surface condition of the portion of the pipe that is embedded in the ground with non-destructive inspection methods to determine whether the water is intruding into the vaults from the ground. Corrective actions to eliminate standing water in safety-related vaults, which include installation of automatic sump pumps, have also been implemented or scheduled. Additionally, as part of their In-service Inspection program, Susquehanna staff initiated periodic inspections of the vaults to monitor the piping condition and effectiveness of the implemented corrective actions.

Inspectors reviewed Susquehannas evaluation and implemented and scheduled corrective actions and did not identify any issues of concern. The inspectors determined that Susquehannas corrective actions involving extent of condition review, extent of cause, subsequent cleaning and repair of the pipe coating, installation of the automatic sump pumps in the vaults, and periodic vault inspections by the in-service inspection program were commensurate with the safety significance of the issue.

Observation: Annual Follow-Up of Selected Issues- Failure to Conduct Proper 71152 Testing of 125VDC Molded Case Circuit Breakers (MCCBs) to Confirm their Design Adequacy Long Term The inspectors performed an in-depth review of Susquehannas evaluations and corrective actions associated with NCV 05000387;05000388/2018001-01 (ADAMS Accession No.

ML18241A044) for failing to adequately exercise and test safety-related 125 VDC MCCBs. Issues related to verifying the adequacy of the design for 125VDC MCCBs were previous identified in NCV 05000387;05000388/2013010-01 (ADAMS Accession No.

ML13275A074), and in a licensee-identified violation documented in NRC Inspection Report 05000387; 05000388/2016007 (ADAMS Accession No. ML16328A097) for failure to implement corrective actions to establish a preventive maintenance program for MCCBs associated with containment penetration conductors.

The inspectors performed a review of Susquehannas corrective action to address the adequacy of testing 125VDC MCCBs as documented in condition report (CR)-2018-09952, CR-2018-11415, and other related CRs. The inspectors verified that Susquehanna properly evaluated the issue and performed or planned appropriate corrective actions. The inspectors verified that Susquehanna conducted adequate testing of the Unit 2 125VDC MCCBs associated with containment penetration conductors during the Spring 2019 refueling outage and planned to complete similar testing during the next Unit 1 refueling outage.

The inspectors observed incomplete documentation of actions performed and/or planned to correct the issue within individual CAP documents. For example, the population of 125VDC MCCBs associated with containment penetration conductors had to be re-verified by engineering and actual work orders performed during the Unit 2 refueling outage had to be reviewed by the inspectors to conclude that Susquehannas actions were adequate. These issues were determined to be minor because the appropriate population of 125VDC MCCBs associated with containment penetration conductors was subsequently verified, all the associated MCCBs on Unit 2 were tested during the Spring 2019 refueling outage, and all the associate MCCBs on Unit 1 were planned to be tested during the next scheduled refueling outage.

Observation: Annual Follow-Up of Selected Issues- Alternate Compensatory 71152 Measures for Firewatches Associated with High Radiation Areas The inspectors performed a review of Susquehannas corrective action to address the adequacy of compensatory measures documented in CR-2019-00739, CR-2019-03992, and other related CRs. The inspectors verified that Susquehanna properly evaluated the issue and performed or planned appropriate corrective actions. The inspectors verified that Susquehanna implemented appropriate corrective actions to perform a fire hazards analysis prior to authorizing alternate compensatory actions to ensure an adequate level of fire protection is maintained when fire impairments are identified in high radiation areas.

The inspectors identified that Susquehannas fire protection procedure, NDAP-QA-0443, allowed for an hourly firewatch to check around the fire door for smoke and to touch the door to verify no heat was present. After the inspectors questioned whether this practice was evaluated as an alternate compensatory action, Susquehanna initiated CR-2019-03992 and determined that this practice required an area-specific engineering evaluation to ensure an adequate level of fire protection is maintained.

While the ability of procedurally allowing an alternate compensatory action existed for greater than ten years, the inspectors were only able to identify the one instance described in CR-2019-00739 where the practice was used. Additionally, the station performed an engineering analysis for the affected fire zone as part of their past operability process and determined that the alternate compensatory action provided an adequate level of fire protection. Though this evaluation was done after the alternate compensatory action was established, the inspectors determined this conclusion was reasonable.

The immediate and planned corrective actions are appropriate to ensure that an engineering evaluation in the form of a zone-specific fire hazard analysis is performed prior to implementing alternate compensatory actions. While other methods such as installing portable camera(s) could enable the required firewatch actions to be accomplished, the inspectors acknowledged that other factors such as radiation dose concerns must be considered and that establishing an alternate compensatory action following an engineering evaluation can provide for an adequate level of fire protection.

Observation: Semi-Annual Trend Review - Issues not appropriately entered into 71152 station processes The inspectors performed a semi-annual review of site issues to identify trends that might indicate the existence of more significant safety concerns. As part of this review, the inspectors included repetitive or closely-related issues documented by Susquehanna in the CAP database, trend reports, site performance indicators, major equipment problem lists, system health reports, maintenance rule assessments, and maintenance or CAP backlogs. The inspectors also reviewed how Susquehannas CAP evaluated and responded to individual issues identified by the NRC inspectors during routine plant walkdowns and daily CR reviews.

The inspectors noted an example where a condition adverse to quality (CAQ) was not entered promptly into the CAP, as required by station procedure LS-120, Issue Identification and Screening Process. LS-120 defines a CAQ as any condition identified with a quality related function which is determined to be in conflict with design documents, regulatory commitments, Final Safety Analysis Report (FSAR) commitments, or applicable state or federal codes. When Susquehanna discovered that a small water leak was wetting a fire barrier beneath it, hourly firewatches were instituted. However, since the location was a locked high radiation area, Susquehanna allowed the firewatch to look at the door for smoke or discolored paint, and feel the outside of the door for heat. When the inspectors questioned whether a more intrusive check was required, such as using a remote camera or opening the door and looking in, Susquehanna documented the question as DI-2019-01497, which is a non-CAP process, and stated that the current practice as described in procedure NDAP-QA-0443, Fire Watch, needed to be evaluated against the Fire Protection Review Report (FPRR). After further assessment of the question, Susquehanna staff concluded that NDAP-QA-0443 did not meet standards as defined in the FPRR, which is a CAQ. The inspectors observed that upon recognition that a CAQ existed, and that actions needed to be taken to correct the condition, Susquehanna staff did not enter the issue into the CAP. After the inspectors shared this observation, Susquehanna staff initiated CR-2019-03992 to document the CAQ. The inspectors determined that the failure to properly document this issue in station programs, as required by procedures LS-120, was a performance deficiency. The inspectors evaluated the deficiency using IMC 0612, Appendix B, "Issue Screening," and IMC 0612, Appendix E, "Examples of Minor Issues," and determined it was of minor significance because the failure to enter the issue into the formal station process did not have any adverse impact on the cornerstone objectives. The underlying technical issue was reviewed and documented separately.

EXIT MEETINGS AND DEBRIEFS

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

On July 11, 2019, the inspectors presented the integrated inspection results to Mr. Brad Berryman and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action CR-2019-07504 Indicating lights if shorted in the SSES KV switchyard could 05/30/2019

Documents possibly trip Unit 2 off-line

Miscellaneous Certification Letter for 2019 Summer Readiness 05/15/2019

71111.04 Corrective Action CR-2019-03868 Two nuts found in U2 drywell 03/27/2019

Documents CR-2019-03942 Snubber failed on high drag 03/26/2019

CR-2019-03971 MSRV cable number did not match procedure 03/26/2019

CR-2019-04249 L MSRV contacted airlock while in transport 03/30/2019

CR-2019-05197 Paint not reapplied to snubber 04/13/2019

Drawings E105952 Unit 2 Division 2 Core Spray P&ID Revision 31

E106253 Unit 1 Standby Liquid Control System P&ID Revision 40

Procedures CL-251-0012 Unit 2 Core Spray System Division 1 Mechanical Revision 12

CL-251-0013 Unit 2 Core Spray System Division 2 Mechanical- Revision 5

Containment

CL-251-0015 Unit 2 Core Spray System Division 2 Mechanical Revision 13

71111.04S Drawings E105956 Unit 2 HPCI P&ID Revision 31

Procedures CL-252-0011 Unit 2 HPCI System Electrical Revision 11

CL-252-0012 Unit 2 HPCI System Mechanical Revision 17

CL-252-0013 Unit 2 HPCI System Mechanical-Containment Revision 5

71111.05A Fire Plans FP-213-238 HPCI Pump Room (II-11) Fire Zone 2-1C Elevation 645'-0" Revision 5

Miscellaneous TQ-171-0105 Unit 2 HPCI Revision 0

71111.05Q Corrective Action CR-2019-07537 PA-015 FP in E EDG bay has packing leak 06/03/2019

Documents

Fire Plans FP-013-236 'E' Diesel Generator Building Fire Zone 0-41E Elevation Revision 7

656'-6", 675-6", 708'-0"

FP-113-104 RCIC Pump Room (I-12) Fire Zone 1-1D Elevation 645'-0" Revision 5

FP-113-105 RHR Pump Room "B" (I-13) Fire Zone 1-1E Elevation 645'- Revision 3

0"

FP-113-106 RHR Pump Room "A" (I-14) Fire Zone 1-1F Elevation 645'-0" Revision 5

FP-113-1102 Core Spray Pump Room "B" (1-10) Fire Zone 1-1B Elevation Revision 4

645'-0"

FP-213-247 Equipment Access Area (II-202,204,205) Fire Zones 2-3C-N, Revision 5

Inspection Type Designation Description or Title Revision or

Procedure Date

2-3C-W, 2-3C-S, Elevation 683'-0"

FP-213-250 Switchgear Rooms (II-406, II-407) Fire Zones 2-4C, 2-4D, Revision 7

Elevation 719'-1"

FP-213-258 Load Center Room (II-510) Load Center Room (II-507) Fire Revision 5

Zone 2-5F, 2-5 G, Elevation 749'1"

71111.07A Corrective Action CR-2018-05387 RHR heat exchanger pressure relief valve failed lift test 04/07/2018

Documents CR-2018-06358 Documentation of plugging in RHR heat exchanger 04/19/2018

Procedures MT-116-002 RHR Heat Exchanger Cleaning, Inspection, and Repair Revision 15

MT-GM-025 Heat Exchanger Cleaning and Inspection Revision 22

MT-GM-031 Immersed Component/Heat Exchanger Internals Epoxy Revision 22

Lining/Cladding

MT-GM-078 SSES Heat Exchanger Tube Plugging Revision 8

71111.11Q Corrective Action CR-2019-05411 Simulator response not as expected during start up Just-In- 04/16/2019

Documents Time Training

Procedures GO-200-002 Plant Startup, Heatup and Power Operation Revision 96

71111.12 Corrective Action CR-2019-05079 Wall thinning trend identified in bottom head drain piping 04/11/2019

Documents

71111.13 Calculations EC-049-0655 RHR fuel pool cooling mode heat capacity Revision 0

EC-THDY-1069 Excel program for calculating fuel pool heat-up during Revision 8

refueling operations

Corrective Action AR-2015-07176 Confirm time after shutdown when fuel pool cooling assist 03/12/2015

Documents can be credited for decay heat removal

AR-2015-09056 Update shutdown EOOS model to reflect availability of fuel 04/01/2015

pool cooling and FPC assist

Miscellaneous TM-OP-054-ST Emergency Service Water Revision 8

71111.15 Calculations EC-PIPE-2569 Piping analysis of Unit 2 HPCI inside containment Revision 0

EC-SOPC-0554 Relay Setting Calculation for Motor Control Center 0B136 Revision 2

Circuit Breaker at Load Center 1B230

Corrective Action AR-2019-04083 Missing rings, washers, and retaining pins on snubber 03/28/2019

Documents CR-2019-04020 Missing pin, washers, and retaining rings on snubber 03/27/2019

CR-2019-04879 AK breaker fails as-found testing 04/07/2019

CR-2019-04935 Removed AK breaker failed to meet acceptance criteria 04/08/2019

CR-2019-07089 Loss of 0B136 05/22/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-2019-07122 Troubleshooting revealed an issue with 0EP01 05/22/2019

Corrective Action CR-2019-07153 NRC question regarding breaker coordination 05/22/2019

Documents

Resulting from

Inspection

Miscellaneous EPRM 1447078 Perform Preparation of 480 Volt Overhauled Spare Load 07/25/2013

Center Breaker Returned from Vendor for use in 1B23023

EPRM 1802920 Perform Preventive Maintenance of 480 Volt Motor Control 12/14/2016

Center Breaker 0B136033

ST-200-001 Snubber visual inspection Revision 2

UFSAR Table Affiliated and Non-Class 1E Circuits that Connect to Class Revision 69

8.1-2 1E Power Supplies

71111.18 Calculations 2033998 Replace the Compressors and Air Dryers in Diesel Revision 2

Generator Air Start System

Miscellaneous 2203222 Mallory M200PK is obsolete is being replaced by Bourns Revision 0

3400S-1-201L

Work Orders 2150074 Remove existing EDG air compressor equipment 02/12/2018

71111.19 Corrective Action CR-2015-27535 B ESW pump discharge valve has leakby ~10 gpm 10/12/2015

Documents CR-2019-04153 Electrical questioning the effectiveness of not using lock ring 03/29/2019

on new sync switches

CR-2019-04683 CR to document resolution of 125 VDC electrical testing 04/04/2019

CR-2019-04732 EC-1 failed to trip breaker during testing 04/05/2019

CR-2019-04758 Breaker failed to reset during testing 04/06/2019

CR-2019-04822 Could not build pressure while testing accumulator 04/07/2019

CR-2019-04935 Removed AK breaker failed to meet acceptance criteria 04/08/2019

CR-2019-04957 O-ring leak found 04/08/2019

CR-2019-05260 Casting of new disc arm will not fit in valve body 04/14/2019

CR-2019-05491 40dpm leak found during vessel leak check 04/18/2019

CR-2019-05502 CRDM leaking during RPV hydro test 04/18/2019

CR-2019-05507 CRDM leaking during RPV hydro test 04/18/2019

CR-2019-05529 Packing leak identified 04/18/2019

Drawings E105955 HPCI system P&ID Revision 46

Procedures MT-GM-003A Swing check valve disassembly, inspection, and reassembly Revision 2

Inspection Type Designation Description or Title Revision or

Procedure Date

SE-249-301 RHR system leakage test Revision 11

SE-249-400 RHR system leakage quantification test Revision 15

SM-202-C04 48 Month Channel C 2D630 125VDC Battery Discharge Revision 25

Modified Performance Test and Battery Charger Capability

Test

SO-054-B03 Quarterly ESW Flow Verification LOOP B Revision 20

SO-249-014B RHR cold shutdown valve exercising, Division II Revision 0

SO-249-018 RHR Division II, 2 year RPI checks Revision 0

SO-249-B02 92 day RHR flow verification B loop Revision 27

SO-250-005 24 Month RCIC Flow Verification Revision 23

Work Orders 1938604 B ESW pump discharge valve has ~10 gpm leakby 10/13/2015

2177800 HPCI exhaust vacuum breaker check valve repair 04/13/2019

211054 125 VDC electrical testing 10/11/2018

242551 92 day RHR flow verification Loop B 03/05/2019

71111.22 Corrective Action AR-2019-04097 Revise TP-259-030 for relief valve set pressure 03/28/2019

Documents CR-2019-04137 Outboard D MSIV exceeded TS leakage limit 03/28/2019

CR-2019-05012 Unexpected results for SO-283-005, test aborted 04/10/2019

CR-2019-05398 Simulator does not respond correctly during RPV hydrostatic 04/14/2019

pressurization/depressurization

Procedures MT-024-024 Diesel Engine Analysis and Load Bearing Revision 21

OP-024-001 Diesel Generators Revision 87

SE-259-024 LLRT of main steam isolation valves penetration number X- Revision 21

7D

SO-024-001A Monthly Diesel Generator 'A' Operability Test Revision 28

SO-153-004 Unit 1 Quarterly SBLC Flow Verification Revision 45

SO-200-023 ASME Class I Boundary System Leakage Test Revision 4

71152 Calculations EC-013-1081 Generic Letter 86-10 to Determine Raceway Fire Revision 1

EC-013-1910 Calculation to Determine CO2 Room Concentrations for the Revision 1

Rooms Protected with an Automatic CO2 System

Corrective Action AR-2019-00903 Evaluate impacts to degraded fire wraps 01/15/2019

Documents AR-2019-01849 Engineering evaluation of wetted versa-wrap on conduit 02/06/2019

C1P107 in fire zone 1-6I in support of Operab

CR-2014-04167 A re-review of IN-2007-06 revealed the original evaluation 02/06/2014

Inspection Type Designation Description or Title Revision or

Procedure Date

did not address ESW/RHRSW manhole pipes

CR-2014-07344 External corrosion discovered on safety related piping and 03/06/2014

supports in vaults

CR-2016-04833 Gaps in corrective actions from CDBI inspection 02/26/2016

CR-2016-23373 Issues identified during CDBI with 125VDC MCCBs 10/14/2016

CR-2017-13423 ISI inspection of A ESW piping VA021 07/18/2017

CR-2017-14366 The scope of the safety related vault inspections needs to be 08/04/2017

expanded to five additional vaults

CR-2017-18437 ISI inspection of ESW/RHRSW piping in VA022 10/27/2017

CR-2018-09952 Understand why actions were not taken to address 2013 06/29/2018

NCV

CR-2018-11415 Electrical testing of 125VDC molded case circuit breakers 08/01/2018

may be necessary

CR-2018-12271 Minor surface corrosion found on flange bolting 08/23/2018

CR-2018-12276 Minor surface corrosion found on flange bolting 08/23/2018

CR-2018-12564 Minor surface corrosion found on flange bolting 08/29/2018

CR-2018-12566 Minor surface corrosion found on flange bolting and minor 08/29/2018

coating loss on flange surface

CR-2018-12598 NRC Green NCV for 2018 PIR 09/28/2018

CR-2018-16967 U1 Entry into ON-FLOOD-101 due to flooding in the reactor 12/17/2018

building

CR-2018-16972 Floor drain slow to accept influent on RW 646' 12/17/2018

CR-2018-17000 U1 RB 749' floor drain blockage requires resolution 12/18/2018

CR-2019-00452 RTSV 2142569 (SI-213-241) fuel pool heat exchanger room 01/08/2019

fire protection not able to be performed

CR-2019-00524 Unable to repressurize PA-223 from air supply 01/09/2019

CR-2019-00739 New Leak identified in U1 Fuel Pool Cooling Hold Pump 01/15/2019

Room, Elev 779'. Leak is 15 dpm.

CR-2019-01495 Fire damper FPD-3-21-3-1 did not pass the inspection 01/30/2019

CR-2019-04113 The fire seal in penetration X-12-5-185 is less than the 03/28/2019

minimum required depth

CR-2019-04683 CR to document resolution of 125VDC MCCB electrical 04/04/2019

testing

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-2019-04758 Had breaker fail to reset during testing 04/06/2019

Corrective Action CR-2019-01497 Question on Firewatch methodology for inaccessible areas 01/30/2019

Documents meeting the intent of our FPRR

Resulting from CR-2019-07066 NRC walk down observation 05/21/2019

Inspection CR-2019-07153 NRC Question regarding beaker coordination of 1B23023 05/22/2019

CR-2019-07380 Penetrations X-27-4-18 and X-27-4-19 (Unit 1 RB Elev 719') 05/29/2019

leaking gel

CR-2019-07537 PA-015 FP in E DG Bay has packing leak dripping roughly 1 05/31/2019

drop every 2 minutes

CR-2019-07541 Housekeeping issue in Unit 1 Reactor Building Elevation 05/31/2019

719' Identified by the NRC Resident

Drawings C-1725 Reactor Building Fire Zone Plan of Protected Tray Raceway Revision 2

Elevation 779' 1"

C-1725 Reactor Building Fire Protection Plan Elevation 779' 1' Revision 5

C-1725 Unit 1 Reactor Building Fire Doors and Fire Dampers Revision 6

Elevation 779' 1"

C-1725 Unit 1 Reactor Building Fire Zone Plan Elevation 779' 1" Revision 9

C-1725 Unit 1 Reactor Building Fire Detector Location Plan Elevation Revision 6

779' 1" to 799' 1"

C-1725 Reactor Building Fire Zone Plan of Protected Conduit Revision 2

Raceway Elevation 779' 0"

C-1726 Reactor Building Fire Detector Location Plan Elevation 799' Revision 4

1" to 818' 1"

FF62009 Fire Barrier Upgrade A1P075, A1P105, C1P107 & E1P005 Revision 0

Wrapped Raceways and JB2068

HRC-10-1 Isometric - Yard Emergency Service Water - Unit 1 & 2 Revision 4

HRC-2-53 Isometric - Yard RHR Service Water - Units 1 & 2 Revision 7

Fire Plans FP-113-125 Access Area (I-604) Adjoining Rooms (I-621, 620, 619, 606, Revision 5

601) Fire Zones 1-6A, 1-61, 0-6G Elevation 779'-1"

FP-113-125 Access Area (I-604) Adjoining Rooms (I-621, 620, 619, 606, Revision 5

601) Fire Zones 1-6A, 1-61, 0-6G Elevation 779'-1'

Miscellaneous Fire Endurance Test Acceptance Criteria for Fire barrier 03/25/1994

Systems Used to Separate Redundant Safe Shutdown

Trains Within the Same Fire Area

Inspection Type Designation Description or Title Revision or

Procedure Date

2149189 Design Change Package, Install Sump Pumps in Vaults Revision 2

VA011 and VA012

8856-M-208 Technical Specification for External Surface Treatment of Revision 2

Underground Steel Pipe for the Susquehanna Steam Electric

Station Units 1 and 2

EG263 Transient Combustibles in Crimp Revision 1

EPRM 2211054 Unit 2 Division I 125VDC Siemens/ITE Molded Case Circuit 04/06/2019

Breaker Electrical Testing

EPRM 2231580 Unit 2 Division II Siemens/ITE Molded Case Circuit Breaker 03/27/2019

Electrical Testing

ML042360547 NRC Regulatory Issue Summary 2005-07 Compensatory 04/19/2005

Measures to Satisfy the Fire Protection Program

Requirements

NRC Information Periodic Testing and Preventive Maintenance of Molded 08/22/1993

Notice 93-64 Case Circuit Breakers

NUREG/CR-7135 Compensatory and Alternative Regulatory Measures for August 2015

Nuclear Power Plant Fire Protection

Procedures NDAP-QA-0443 Firewatch Procedure Revision 14

NDAP-QA-0446 Fire Barrier Program Revision 8

NSEI-AD-418 Miscellaneous Buildings Structural Monitoring Revision 4

SI-113-245 Annual Functional Test of Fire Protection Smoke Detectors Revision 9

for Fire Zones 1-6I and 1-6A

20