IR 05000219/2018002

Integrated Inspection Report 05000219/2018002 and Independent Spent Fuel Storage Installation Report 0700015/2018001

ML18218A407
Person / Time
Site:	Oyster Creek, 07000015
Issue date:	08/02/2018
From:	Matt Young NRC Region 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2018001, IR 2018002
Download: ML18218A407 (17)

Text

UNITED STATES ust 2, 2018

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000219/2018002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 0700015/2018001

Dear Mr. Hanson:

On June 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oyster Creek Nuclear Generating Station. On July 18, 2018, the NRC inspectors discussed the results of this inspection with Mr. Timothy Moore, 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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Number: 50-219 License Number: DPR-16 Enclosure:

Inspection Report 05000219/2018002 cc w/encl: Distribution via ListServ

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Oyster Creek Nuclear Generating Station by conducting the baseline inspections described in this report 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.

No findings or more-than-minor violations were identified.

PLANT STATUS

Oyster Creek began the inspection period at 80 percent power due to a rod power adjustment.

Operators returned the unit to 100 percent power the same day. On June 29, 2018, operators lowered power to 60 percent power for condenser backwashing. Operators returned the unit to 100 percent power the same day. The unit 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 Exelons performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection Summer Readiness

The inspectors evaluated summer readiness of offsite and alternate AC power systems on

===June 28, 2018.

Seasonal Extreme Weather (1 Sample)===

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the hot weather alerts on June 30 and July 1, 2018.

71111.04 - Equipment Alignment Partial Walkdown

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

(1) No. 1 reactor building closed cooling water system during the No. 2 reactor building closed cooling water heat exchanger cleaning on April 9 through April 12, 2018

(2) No. 2 core spray system during the No. 1 core spray system testing on May 30, 2018

(3) No. 2 emergency diesel generator during the No. 1 emergency diesel generator maintenance outage on June 13, 2018

71111.05Q - Fire Protection Quarterly Quarterly Inspection

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

(1) Reactor building 95 elevation on April 7, 2018

(2) Control room on April 8, 2018

(3) Main transformer area on May 3, 2018

(4) Emergency diesel generator areas on June 5, 2018

71111.06 - Flood Protection Measures Cables

The inspectors evaluated cable submergence protection in MH-743-4 and MH-731-1 on May 2, 2018.

71111.07 - Heat Sink Performance Heat Sink

The inspectors evaluated Exelons monitoring and maintenance of the No. 2 reactor building closed cooling water heat exchanger on April 16, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated a crew of licensed operators in the plants simulator during licensed operator requalification training on April 17, 2018.

Operator Performance (1 Sample)

The inspectors observed licensed operator performance during a reduction in power and return to full power for a rod pattern adjustment on April 24, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Main steam system on April 8, 2018

Quality Control (2 Samples)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:

(1) Emergency service water pump expansion joint on May 7, 2018

(2) No. 2 emergency diesel generator fuel oil filter relief valve on May 25, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) No. 2 emergency diesel generator battery service check on April 23, 2018

(2) No. 1 emergency diesel generator battery service check on April 30, 2018

(3) No. 1 instrument air compressor maintenance outage on May 1, 2018

(4) Startup transformer Bank 6 maintenance outage on May 8, 2018

(5) Startup transformer Bank 5 voltage regulator controller replacement on May 14, 2018

(6) No. 1 core spray system testing on May 30, 2018

(7) No. 2 emergency diesel generator maintenance outage on June 13, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Emergency diesel generator battery spacer material on April 9, 2018

(2) Core spray over current relay test results on April 10, 2018

(3) B containment spray pump restart after stop signal on May 7, 2018

(4) No. 1 reactor building closed cooling water motor temperature readings on May 10, 2018

(5) D emergency service water pump protective relay test results on May 25, 2018

(6) No. 2 emergency diesel generator starter motor low megger readings on June 26, 2018

71111.18 - Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change 618715, swap fuel zone level power supplies

(2) Engineering Change 622758, 1-8 sump circuit mod to improve reliability

71111.19 - Post Maintenance Testing

The inspectors evaluated post maintenance testing for the following maintenance and repair activities:

(1) B control room heating, air, and ventilation system battery replacement on April 11, 2018

(2) No. 2 reactor building closed cooling water heat exchanger cleaning and anode replacement on April 12, 2018

(3) A emergency service water pump relay replacement on April 16, 2018

(4) No. 1 emergency diesel generator battery service checks on May 1, 2018

(5) B containment spray pump repairs on May 31, 2018

(6) No. 1 emergency diesel generator starting motor replacement on June 13, 2018

(7) No. 1 emergency diesel generator lower driveshaft replacement on June 13, 2018

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) 636.4.003, Diesel generator No. 1 load test on April 16, 2018

(2) 636.2.012, Diesel generator No. 1 battery service test on April 30, 2018

(3) 602.3.004, Electromatic relief valve pressure sensor test and calibration on June 5, 2018

Inservice (2 Samples)

(1) 610.4.021, Core spray system No. 1 pump operability and quarterly inservice test on May 30, 2018

(2) 612.4.001, Standby liquid control pump and valve inservice test on June 19, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) 312.9, Primary containment control on April 30, 2018

71114.06 - Drill Evaluation Drill/Training Evolution

The inspectors evaluated a simulator training evolution for licensed operators on April 17,

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment

The inspectors conducted independent radiation measurements during walkdowns of the facility and reviewed:

• the radiological survey program;

• any changes to plant operations since the last inspection;

• recent plant radiation surveys for radiological work activities;

• air sampling and analysis; and

• continuous air monitor use.

Instructions to Workers (1 Sample)

The inspectors reviewed high radiation area work permit controls and use, reviewed electronic alarming dosimeter alarms and setpoints, observed worker briefings on radiological conditions, and observed containers of radioactive materials and assessed whether the containers were labeled and controlled in accordance with requirements.

Contamination and Radioactive Material Control (1 Sample)

The inspectors observed the monitoring of potentially contaminated material leaving the radiologically controlled area and inspected the methods and radiation monitoring instrumentation used for control, survey, and release of that material. The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination. The inspectors evaluated whether any recent transactions involving nationally tracked sources were reported in accordance with requirements. The inspectors reviewed Exelons compliance with the national source tracking system annual inventory reconciliation requirement (10 CFR 20.2207(g)).

Radiological Hazards Control and Work Coverage (1 Sample)

The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walkdowns and observation of radiological work activities. The inspectors assessed whether posted surveys; radiation work permits; worker radiological briefings and radiation protection job coverage; and the use of continuous air monitoring, air sampling and engineering controls, and dosimetry monitoring were consistent with the present conditions. The inspectors examined the control of highly activated or contaminated materials stored within the spent fuel pool and the posting and physical controls for selected high radiation areas, locked high radiation areas, and very high radiation areas.

High Radiation Area and Very High Radiation Area Controls (1 Sample)

The inspectors reviewed the procedures and controls for high radiation areas, very high radiation areas, and radiological transient areas in the plant. The inspectors observed the locked high radiation area key control inventory and verified a sampling of locked high radiation area closures.

Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)

The inspectors evaluated radiation worker performance with respect to radiation protection work permit requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage. The inspectors observed radiation worker performance and radiation protection job coverage activities on the operating turbine floor and on the refuel floor.

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Implementation of ALARA and Radiological Controls

The inspectors reviewed radiological work controls and ALARA practices during the observation of in-plant work activities. The inspectors verified use of shielding, contamination controls, airborne controls, radiation work permit controls, and other work controls were consistent with ALARA plans. The inspectors ensured that work-in-progress reviews were performed in a timely manner and adjustments made to the ALARA estimates were appropriate. The inspectors reviewed the results achieved against the intended ALARA estimates to confirm adequate implementation and oversight of radiological work controls. The inspectors also verified that the ALARA staff was involved with emergent work activities and were revising both dose estimates and ALARA controls in the associated radiation work permits and ALARA plans, as appropriate.

Radiation Worker Performance (1 Sample)

The inspectors observed radiation worker and radiation protection technician performance during radiological work to evaluate worker ALARA performance according to specified work controls and procedures.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified Exelons performance indicator submittals listed below for the period from April 1, 2017 through March 31, 2018.

(1) Unplanned Scrams per 7,000 Critical Hours

(2) Unplanned Scrams with Complications

(3) Unplanned Power Changes

(4) Safety System Functional Failures

71152 - Problem Identification and Resolution Semiannual Trend Review

No findings were identified.

The inspectors reviewed Exelons corrective action program for trends that might be indicative of a more significant safety issue. The inspectors identified and assessed a trend in the condition report generation rate over the first and second quarter inspection periods of 2018. The inspectors noted a decrease in the number of condition reports being written, and this was also identified by Exelon and documented in issue report 4106609. In response to this trend, Exelon performed a work group evaluation and discussed the results with station personnel. Exelon continues to track daily, weekly, and monthly condition report generation rates and communicates these rates to station personnel via station ownership committee and management review committee meetings. The trend continues to be closely monitored by the inspectors to ensure the reduction in condition report generation is a result of the transition to decommissioning and not indicative of the lack of worker engagement.

Based on the overall results of the semi-annual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program, adequately evaluating the issues, and properly identifying adverse trends before they became more safety significant problems.

Annual Follow-up of Selected Issues (2 Samples)

The inspectors reviewed Exelons implementation of its corrective action program related to the following issues:

(1) C emergency service water pump flow below alert limit during comprehensive inservice test

(2) Isolation condenser steam line rupture relay deficiencies

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT, AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation The inspectors evaluated Oyster Creeks independent spent fuel storage installation cask loading on April 23 through August 27, 2018. Specifically, the inspectors observed the following activities:

• Fuel selection and fuel loading

• Heavy load movement of transfer cask and loaded dry shielded canister

• Closure welding and non-destructive weld evaluations

• Final helium leak test

• Radiological field surveys

INSPECTION RESULTS

Observation 71152 Follow-up of Selected Issues On October 25, 2017, Exelon initiated corrective action issue report 4067838 for as-found C emergency service water pump flow below the comprehensive alert limit during an inservice test. The inspectors determined that Exelons associated engineering evaluations and trending were sufficiently thorough and based on the best available information, demonstrated sound judgment, and considered relevant operating experience. Exelons assigned corrective actions were aligned with engineering evaluations, adequately tracked, appropriately documented, and completed as scheduled. Based on the documents reviewed, emergency service water system walkdowns, and discussions with engineering personnel, the inspectors noted that Exelon personnel identified problems and entered them into the corrective action program at a low threshold.

Observation 71152 Follow-up of Selected Issues The inspectors reviewed the apparent cause analysis, the corrective actions taken, and the past operability regarding the deficiencies discovered on the isolation condenser steam line rupture relays. The inspectors concluded that the cause analysis was thorough, the extent of condition was reasonable, and the corrective actions were timely.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

On July 18, 2018, the inspectors presented the resident inspector quarterly inspection results to Mr. Timothy Moore, Site Vice President, and other members of the Oyster Creek staff.

DOCUMENTS REVIEWED

71111.01 - Adverse Weather Protection

Procedures

ABN 60, Grid Emergency, Revision 19

EN-OC-402-0005, Extreme Heat Implementation Plan, Revision 0

OP-OC-108-109-1001, Severe Weather Preparation T&RM for Oyster Creek, Revision 39

OP-AA-108-111-1001, Severe Weather and Natural Disaster Guidelines, Revision 17

71111.04 - Equipment Alignment

Procedures

308, Emergency Core Cooling System Operations, Revision 99

309.2, Reactor Building Closed Cooling Water System, Revision 100

71111.05 - Fire Protection

Procedures

101.2, Oyster Creek Site Fire Protection Program, Revision 73

ABN 29, Plant Fires, Revision 32

ER-AA-600-1069, High Risk Fire Area Identification, Revision 4

OP-OC-201-008, Oyster Creek Pre-fire Plans, Revision 26

OP-OC-201-012-1001, On-line Fire Risk Management, Revision 4

71111.06 - Flood Protection Measures

Procedure

ER-AA-300-150, Cable Condition Monitoring Program, Revision 5

Maintenance Orders/Work Orders

4390804 4594592 4613856 4675451

71111.07 - Heat Sink Performance

Maintenance Order/Work Order

4657094

71111.11 - Licensed Operator Requalification Program

Procedures

2.1, Power Operation, Revision 157

203, Plant Shutdown, Revision 90

71111.12 - Maintenance Effectiveness

Procedures

2400-SMM-3900.08, General Hydrostatic Test, Initial Service Leak Test, and Pneumatic Test

Procedure, Revision 10

ER-AA-310-1004, Maintenance Rule - Performance Monitoring, Revision 14

ER-AA-310-1005, Maintenance Rule - Dispositioning Between (a)(1) and (a)(2), Revision 7

SM-AA-300-1001, Procurement Engineering Process and Responsibilities, Revision 23

Miscellaneous

Oyster Creek Maintenance Rule Database, updated March 29, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Controls

Procedures

ER-AA-600-1042, On-Line Risk Management, Revision 11

OP-OC-108-117-1000, Oyster Creek Protected Equipment Program, Revision 13

WC-AA-101-1006, On-Line Risk Management and Assessment, Revision 2

71111.15 - Operability Determinations and Functionality Assessments

Procedure

MA-OC-741-101, Diesel Generator Inspection (24 Month) - Electrical, Revision 17

Calculations

C-1302-700-5350-003, OC-1E Protective Relay Set Points, Revision 5

C-1302-741-5320-010, Seismic Adequacy of EDG Batteries, Revision 0

Condition Reports

1368035 1658897 2573206 2678084 4119115

Maintenance Orders/Work Orders

R2111556 R2151927 R2191838 R2229008

71111.18 - Plant Modifications

Miscellaneous

EC 618715, Swap Fuel Zone Level Power Supplies IPS-622-1015 and IPS-622-1016, dated

March 17, 2017

EC 622758, 1-8 Sump Circuit Mod to Improve Reliability, dated April 12, 2018

71111.19 - Post Maintenance Tests

Maintenance Orders/Work Orders

1393747 4383584 4383903 4657094 4683153 4773974

71111.22 - Surveillance Testing

Procedures

2.9, Primary Containment Control, Revision 66

2.3.004, Electromatic Relief Valve Pressure Sensor Test and Calibration, Revision 59

610.4.021, Core Spray System 1 Pump Operability and Quarterly In-service Test, Revision 35

2.4.001, Standby Liquid Control Pump and Valve Operability and In-service Test, Revision 54

OP-AA-111 Attachment 1, Adverse Condition Monitoring Plan, Revision 10

71124.01 - Radiological Hazard Assessment and Exposure Controls

Procedures

NISP-RP-005, Access Controls for High Radiation Areas, Revision 0

NISP-RP-010, Radiological Job Coverage, Revision 0

RP-AA-300, Radiological Survey Program, Revision 16

RP-AA-301, Radiological Air Sampling Program, Revision 11

RP-AA-376-1001, Radiological Posting, Labeling, and Marking Standard, Revision 16

RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 32

RP-AA-460-001, Controls for Very High Radiation Areas, Revision 6

Condition Reports

24919 4050860 4063917 4071303

Radiation Work Permits

OC-1-18-00202 OC-1-18-00204 OC-1-18-00307

Dose Rate and Contamination Surveys

2018-20114-32 2018-20503-1761

Air Sample Surveys18-393 18-455 18-509

71152 - Problem Identification Resolution

Procedures

607.4.005, Containment Spray and Emergency Service Water Pump System 2 Operability and

Comprehensive/Preservice/Post-Maintenance Inservice Test, Revision 85

607.4.005, Containment Spray and Emergency Service Water Pump System 2 Operability and

Comprehensive/Preservice/Post-Maintenance Inservice Test, performed

October 9, 2015 and November 20, 2017

607.4.015, Containment Spray and ESW Pump System 2 Operability, IST and Containment

Spray Pumps Trip, Revision 51

607.4.015, Containment Spray and ESW Pump System 2 Operability, IST and Containment

Spray Pumps Trip, performed October 25, 2017

607.4.017, Containment Spray and Emergency Service Water Pump System 2 Operability and

Quarterly Inservice Test, Revision 48

607.4.017, Containment Spray and Emergency Service Water Pump System 2 Operability and

Quarterly Inservice Test, performed August 18, 2017, January 17, 2018, and

April 27, 2018

609.3.012, Isolation Condenser Isolation Test and Calibration, Revision 18

2400-SMM-3531.01, ESW Pump and Motor Maintenance, Revision 15

ER-AA-321, Administrative Requirements for Inservice Testing, Revision 12

OP-AA-108-115, Operability Determinations, Revision 21

OP-AA-108-115-1002, Supplemental Consideration for On-Shift Immediate Operability

Determinations, Revision 3

PI-AA-120, Issue Identification and Screening Process, Revision 8

PI-AA-125, Corrective Action Program Procedure, Revision 6

Condition Reports

29980 2725206 2730024 4009112 4067838 4069291

4070615 4081918 4090708 4106609 4126312 4137471

4137479 4138294 4138321

Maintenance Orders/Work Orders

4369921 4627966 4663130 4672287 4713159 C2035003

R2058773 R2094429

Engineering Evaluations

25-1 File No. 0053-96, Evaluation of ESW Pump 52A Lift Adjustment, dated February 17, 1996

4069291-02, IST Trends and Gaps Work Group Evaluation, Revision 0

A0700381-05, ESW Pump/Motor Replacement PM Frequency Change Evaluation, dated

April 20, 2009

OYS-0-2017-0646, ODM: ESW Pumps 52B & 52C, Revision 0

Drawings

3E-611-17-005, Electrical Elementary Diagram Control Panel 1F/2F-Annunicator, Revision 21

BR 3029, Emergency Condenser System Electrical Elementary Diagram, Revision 28

GE 719E211, Main Control Room Panels Electrical Connection Diagram, Revision 20

Miscellaneous

ECR 16-00392, MCR Unexpected Alarm: C-3-B Cond B Flow Hi Possible Rupture, Revision 0

IST-OC-BDOC-V-5, Oyster Creek - Inservice Testing Bases Document (Emergency Service

Water Pump 1-3(52C)), dated April 18, 2018

NRC IMC 0326, Operability Determinations & Functionality Assessments for Conditions

Adverse to Quality or Safety, dated November 20, 2017

NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 2

Performance Trend Data for P-3-3C, for the period January 19, 2012 - April 26, 2018

SDBDOC-532, Design Basis Document for Emergency Service Water System, Revision 4

60855.1 - Operation of an Independent Spent Fuel Storage Installation

Procedures

614.1.003, Independent Spent Fuel Storage Installation Technical Specification Surveillance

Testing, Revision 3

OU-OC-641, Transport and Loading of Transfer Cask and Dry Shielded Canister, Revision 4

OU-OC-642, 61 BTH Dry Shielded Canister Welding, Vacuum Drying, and Helium Fill,

Revision 5

Miscellaneous

ALARA Plan Number 18-204, 2018 Dry Cask Storage Campaign 7 Casks

Fuel Selection Package, OYC-0033