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| issue date = 11/08/2018 | | issue date = 11/08/2018 | ||
| title = Integrated Inspection Report 05000219/2018003 | | title = Integrated Inspection Report 05000219/2018003 | ||
| author name = Young M | | author name = Young M | ||
| author affiliation = NRC/RGN-I/DRP/PB6 | | author affiliation = NRC/RGN-I/DRP/PB6 | ||
| addressee name = Hanson B | | addressee name = Hanson B | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:mber 8, 2018 | ||
==SUBJECT:== | ==SUBJECT:== | ||
OYSTER CREEK NUCLEAR GENERATING STATION | OYSTER CREEK NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000219/2018003 | ||
==Dear Mr. Hanson:== | |||
-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, | On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oyster Creek Nuclear Generating Station. On October 10, 2018, the NRC inspectors discussed the results of this inspection with Mr. Jeffrey Dostal, Site Decommissioning Director and other members of your staff. The results of this inspection are documented in the enclosed report. | ||
The NRC inspectors did not identify any findings or violations 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, | Sincerely, | ||
/RA/ Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Number: 50-219 License Number: DPR-16 | /RA/ | ||
Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Number: 50-219 License Number: DPR-16 | |||
===Enclosure:=== | ===Enclosure:=== | ||
Inspection Report | Inspection Report 05000219/2018003 | ||
==Inspection Report== | ==Inspection Report== | ||
Docket Number: 50-219 License Number: DPR-16 Report Number: | Docket Number: 50-219 License Number: DPR-16 Report Number: 05000219/2018003 Enterprise Identifier: I-2018-002-0078 Licensee: Exelon Nuclear Facility: Oyster Creek Nuclear Generating Station Location: Forked River, New Jersey Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: E. Andrews, Senior Resident Inspector J. Kulp, Senior Reactor Inspector E. Allen, Project Engineer J. Ambrosini, Senior Emergency Preparedness Inspector B. DeBoer, Health Physicist J. DeBoer, Emergency Preparedness Inspector S. Horvitz, Beaver Valley Resident Inspector A. Patel, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector A. Turlin, Project Engineer K. Warner, Health Physicist Approved By: Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure | ||
I- | |||
E. Andrews, Senior Resident Inspector J. Kulp, Senior Reactor Inspector E. Allen, Project Engineer J. Ambrosini, Senior Emergency Preparedness Inspector B. DeBoer, Health Physicist J. DeBoer, Emergency Preparedness Inspector S. Horvitz, Beaver Valley Resident Inspector A. Patel, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector A. Turlin, Project Engineer K. Warner, Health Physicist Approved By: | |||
Matthew R. Young | |||
, Chief Reactor Projects Branch 6 Division of Reactor Projects | |||
=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. | |||
The | |||
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. | |||
No findings or more-than-minor violations were identified. | No findings or more-than-minor violations were identified. | ||
Additional Tracking Items Type Issue number Title Inspection Results Section | Additional Tracking Items Type Issue number Title Inspection Status Results Section LER 05000219/2017-004- Reactor Protection 71153 Closed 00/01 System Channel Disabled during RPS Test Box Use LER 05000219/2018-001-00 EMRV Pressure 71153 Closed Sensor As-Found Setting Exceeded Limiting Safety System Settings | ||
-004-00/01 | |||
-001-00 EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings | |||
=PLANT STATUS= | =PLANT STATUS= | ||
Oyster Creek began the inspection period at 98 percent power, coasting down in power as it approached the end of the operating cycle. Operators lowered power to 70 percent on July 29, 2018 | Oyster Creek began the inspection period at 98 percent power, coasting down in power as it approached the end of the operating cycle. Operators lowered power to 70 percent on July 29, 2018, to remove the B feedwater string from service due to an internal leak in the high pressure feedwater heater. On September 17, 2018, operators commenced a plant shutdown, took the unit offline, and entered a defueling outage (1D27) where the unit remained for the remainder of the inspection period. On September 25, 2018, Oyster Creek certified that all fuel had been permanently removed from the reactor vessel and placed in the spent fuel pool. As stated in the Termination of Reactor Oversight Process for Oyster Creek Nuclear Generating Station and Commencement of Decommissioning Inspection Program letter (ADAMS Accession Number ML18274A221), beginning October 1, 2018, the NRCs oversight of Oyster Creek will no longer be performed in accordance with the operating power reactor inspection program and will instead be conducted in accordance with the decommissioning power reactor inspection program. | ||
, to remove the | |||
==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. | |||
==INSPECTION | |||
-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, | |||
-Water Reactor Inspection Program - Operations Phase. | |||
The inspectors performed plant status activities described in IMC 2515 , Appendix D, | |||
, | |||
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess | |||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
==71111.01 - Adverse Weather Protection | ==71111.01 - Adverse Weather Protection Seasonal Extreme Weather== | ||
Seasonal Extreme Weather | |||
{{IP sample|IP=IP 71111.01|count=1}} | {{IP sample|IP=IP 71111.01|count=1}} | ||
The inspectors evaluated operator response to a high drywell temperature condition caused by seasonal extreme weather on | The inspectors evaluated operator response to a high drywell temperature condition caused by seasonal extreme weather on July 24 and July 25, 2018. | ||
==71111.04 - Equipment Alignment== | ==71111.04 - Equipment Alignment Partial Walkdown== | ||
{{IP sample|IP=IP 71111.04|count=3}} | |||
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains: | |||
: (1) B isolation condenser during A isolation condenser testing on July 9, 2018 | |||
: | : (2) A isolation condenser on August 14, 2018 | ||
: (1) | : (3) Spent fuel pool cooling system on September 20, 2018 | ||
: (2) | |||
: (3) Spent fuel pool cooling system on September 20, 2018 | |||
== | ===Complete Walkdown (1 Sample)=== | ||
The inspectors evaluated system configurations during a complete walkdown of core spray system 1 on August 15, 2018. | |||
== | ==71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection== | ||
Quarterly Inspection | |||
{{IP sample|IP=IP 71111.05A/Q|count=6}} | {{IP sample|IP=IP 71111.05A/Q|count=6}} | ||
The inspectors evaluated fire protection program implementation in the following selected areas: | The inspectors evaluated fire protection program implementation in the following selected areas: | ||
: (1) | : (1) A 480V switchgear room on July 10, 2018 | ||
: (2) | : (2) B 480V switchgear room on July 10, 2018 | ||
: (3) | : (3) A and B battery room on July 23, 2018 | ||
: (4) Lower cable spreading room on July 24, 2018 | : (4) Lower cable spreading room on July 24, 2018 | ||
: (5) | : (5) C and D 4160V emergency switchgear vaults on July 25, 2018 | ||
: (6) Fresh water fire pump house on July 27, 2018 | : (6) Fresh water fire pump house on July 27, 2018 | ||
== | ===Annual Inspection (1 Sample)=== | ||
The inspectors evaluated fire brigade performance on July 12, 2018. | |||
== | ==71111.06 - Flood Protection Measures Internal Flooding== | ||
Internal Flooding | |||
{{IP sample|IP=IP 71111.06|count=1}} | {{IP sample|IP=IP 71111.06|count=1}} | ||
The inspectors evaluated internal flooding mitigation protections in the northeast corner room on July 3, 2018. | The inspectors evaluated internal flooding mitigation protections in the northeast corner room on July 3, 2018. | ||
==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance | ==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Performance== | ||
Operator Performance | |||
{{IP sample|IP=IP 71111.11|count=1}} | {{IP sample|IP=IP 71111.11|count=1}} | ||
The inspectors observed operator performance during reactor shutdown for the 1D27 defueling outage on September 17, 2018. | |||
== | ==71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness== | ||
Routine Maintenance Effectiveness | |||
{{IP sample|IP=IP 71111.12|count=1}} | {{IP sample|IP=IP 71111.12|count=1}} | ||
The inspectors evaluated the effectiveness of routine maintenance activities associated with the spent fuel pool cooling and augmented spent fuel cooling systems during the week of July 30, 2018. | |||
== | ==71111.13 - Maintenance Risk Assessments and Emergent Work Control== | ||
Control | |||
{{IP sample|IP=IP 71111.13|count=3}} | {{IP sample|IP=IP 71111.13|count=3}} | ||
The inspectors evaluated the risk assessments for the following planned and emergent work activities | |||
: | The inspectors evaluated the risk assessments for the following planned and emergent work activities: | ||
: (1) Protection of the | : (1) Protection of the A, B, C, and D reactor recirculation motor generator sets and associated breakers following trip of the E reactor recirculation pump during the week of July 23, 2018 | ||
: (2) Emergent unavailability of the 1-1 service air compressor on July 24, 2018 | |||
: (3) Yellow risk due to high decay heat generation rate during the defueling outage (1D27)on September 17, 2018 | |||
: (2) Emergent unavailability of the 1 | |||
-1 service air compressor on July 24, 2018 | |||
: (3) Yellow risk due to high decay heat generation rate during the defueling outage (1D27) on September 17, 2018 | |||
==71111.15 - Operability Determinations and Functionality Assessments== | ==71111.15 - Operability Determinations and Functionality Assessments== | ||
{{IP sample|IP=IP 71111.15|count=4}} | |||
The inspectors evaluated the following operability determinations and functionality assessments: | The inspectors evaluated the following operability determinations and functionality assessments: | ||
: (1) Seismic adequacy of the | : (1) Seismic adequacy of the A1 and A2 24V battery racks on July 25, 2018 | ||
: (2) Degraded condition on station blackout 4160V switchgear breaker on July 31, 2018 | : (2) Degraded condition on station blackout 4160V switchgear breaker on July 31, 2018 | ||
: (3) Air leak from diaphragm of CV 127 on hydraulic control unit 42-11 on | : (3) Air leak from diaphragm of CV-305-127 on hydraulic control unit 42-11 on July 31, 2018 | ||
: (4) Torus to drywell vacuum breaker delay relay out of specification on August 22, 2018 | : (4) Torus to drywell vacuum breaker delay relay out of specification on August 22, 2018 | ||
==71111.18 - Plant Modifications== | ==71111.18 - Plant Modifications== | ||
{{IP sample|IP=IP 71111.18|count=2}} | |||
The inspectors evaluated the following temporary or permanent modifications: | |||
: (1) TCC-1805-821, Temporary supplemental feed pump motor cooling | : (1) TCC-1805-821, Temporary supplemental feed pump motor cooling | ||
: (2) Engineering Change 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill | : (2) Engineering Change 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill | ||
==71111.19 - Post Maintenance Testing== | ==71111.19 - Post Maintenance Testing== | ||
{{IP sample|IP=IP 71111.19|count=4}} | |||
The inspectors evaluated post maintenance testing for the following maintenance and repair activities: | |||
: | : (1) B spent fuel pool pump preventative maintenance on July 16, 2018 | ||
: (1) | |||
: (2) 1-1 fire diesel following annual preventive maintenance on July 26, 2018 | : (2) 1-1 fire diesel following annual preventive maintenance on July 26, 2018 | ||
: (3) 1-1 air compressor troubleshooting and Q 2 auto blow down valve replacement on August 3, 2018 | : (3) 1-1 air compressor troubleshooting and Q-6-2 auto blow down valve replacement on August 3, 2018 | ||
: (4) Average power range monitor power supply replacement on August 7, 2018 | : (4) Average power range monitor power supply replacement on August 7, 2018 | ||
==71111.20 - Refueling and Other Outage Activities== | ==71111.20 - Refueling and Other Outage Activities== | ||
{{IP sample|IP=IP 71111.20|count=1}} | {{IP sample|IP=IP 71111.20|count=1}} | ||
==71111.22 - Surveillance Testing | The inspectors evaluated the Oyster Creek defueling outage (1D27) activities from September 17, 2018, to September 25, 2018. The inspectors verified the fuel was removed from the core on September 25, 2018. | ||
The inspectors evaluated the following surveillance tests: | |||
Containment Isolation Valve | ==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Containment Isolation Valve== | ||
{{IP sample|IP=IP 71111. | {{IP sample|IP=IP 71111.22|count=1}} | ||
: (1) 678.4.001, Primary containment isolation valve operability and in | : (1) 678.4.001, Primary containment isolation valve operability and in-service testing, on both Drywell vent valves and both Drywell purge valves July 6, 2018 | ||
-service testing, on both Drywell vent valves and both Drywell purge valves July 6, 2018 | |||
==71114.02 - Alert and Notification System Testing== | ==71114.02 - Alert and Notification System Testing== | ||
{{IP sample|IP=IP 71114.02|count=1}} | |||
The inspectors evaluated the maintenance and testing of the alert and notification system from September 2016 to July 2018. | The inspectors evaluated the maintenance and testing of the alert and notification system from September 2016 to July 2018. | ||
==71114.03 - Emergency Response Organization Staffing and Augmentation System== | ==71114.03 - Emergency Response Organization Staffing and Augmentation System== | ||
{{IP sample|IP=IP 71114.03|count=1}} | {{IP sample|IP=IP 71114.03|count=1}} | ||
The inspectors conducted a review of Exelons Emergency Response Organization augmentation staffing requirements and the process for notifying and augmenting the Emergency Response Organization. | |||
and Emergency Plan Changes | ==71114.04 - Emergency Action Level and Emergency Plan Changes== | ||
{{IP sample|IP=IP 71114.04|count=1}} | |||
{{IP sample|IP=IP 71114. | |||
The inspectors verified that the changes made to the Emergency Plan were done in accordance with 10 CFR 50.54(q)(3), and any change made to the Emergency Action Levels, Emergency Plan, and its lower | The inspectors verified that the changes made to the Emergency Plan were done in accordance with 10 CFR 50.54(q)(3), and any change made to the Emergency Action Levels, Emergency Plan, and its lower-tier implementing procedures, had not resulted in any reduction in effectiveness to the plan. This evaluation does not constitute NRC approval. | ||
-tier implementing procedures, had not resulted in any reduction in effectiveness to the plan. This evaluation does not constitute NRC approval. | |||
==71114.05 - Maintenance of Emergency Preparedness== | ==71114.05 - Maintenance of Emergency Preparedness== | ||
{{IP sample|IP=IP 71114.05|count=1}} | |||
The inspectors reviewed activities to evaluate Exelons efforts to maintain Oyster Creeks emergency preparedness programs. | |||
The inspectors reviewed activities to evaluate | |||
==71114.06 - Drill Evaluation== | ==71114.06 - Drill Evaluation Emergency Planning Drill== | ||
{{IP sample|IP=IP 71114.06|count=1}} | |||
The inspectors evaluated the conduct of a routine Exelon decommissioning emergency planning drill on August 15, | |||
==OTHER ACTIVITIES - BASELINE== | |||
The inspectors evaluated the conduct of a | |||
===71151 - Performance Indicator Verification The inspectors verified Exelons performance indicator submittals listed below. | |||
== | === | ||
{{IP sample|IP=IP 71151|count=10}} | |||
: (1) Reactor Coolant System Leak Rate from July 2017 to June 2018 | : (1) Reactor Coolant System Leak Rate from July 2017 to June 2018 | ||
: (2) Reactor Coolant System Activity from July 2017 to June 2018 | : (2) Reactor Coolant System Activity from July 2017 to June 2018 | ||
Line 226: | Line 184: | ||
: (5) Emergency Response Organization Drill Participation from July 2017 to June 2018 | : (5) Emergency Response Organization Drill Participation from July 2017 to June 2018 | ||
: (6) Emergency Alternating Current Power System from October 2017 to June 2018 | : (6) Emergency Alternating Current Power System from October 2017 to June 2018 | ||
: (7) High Pressure Injection System | : (7) High Pressure Injection System - Core Spray from October 2017 to June 2018 | ||
- Core Spray from October 2017 to June 2018 | : (8) Heat Removal - Isolation Condensers from October 2017 to June 2018 | ||
: (8) Heat Removal | : (9) Residual Heat Removal - Containment Spray from October 2017 to June 2018 | ||
- Isolation Condensers from October 2017 to June 2018 | |||
: (9) Residual Heat Removal | |||
- Containment Spray from October 2017 to June 2018 | |||
: (10) Cooling Water System from October 2017 to June 2018 | : (10) Cooling Water System from October 2017 to June 2018 | ||
==71152 - Problem Identification and Resolution== | ==71152 - Problem Identification and Resolution Semiannual Trend Review== | ||
{{IP sample|IP=IP 71152|count=1}} | |||
The inspectors reviewed Exelons corrective action program for trends that might be indicative of a more significant safety issue. The inspectors determined that, in most cases, issues were appropriately evaluated by Exelon staff for potential trends and resolved within the scope of the corrective action program. However, the inspectors reviewed Issue Report | |||
The inspectors reviewed | |||
===4130797, which documented a potential trend for six instances of foreign material found on fuel bundles in April 2018. The inspectors identified four more issue reports regarding instances of foreign material identified on fuel bundles since April 2018. Although the individual issues were addressed through the corrective action program, the inspectors did not see evidence that Exelon collectively evaluated the additional instances of foreign material identified on fuel bundles between April 2018 and August 2018 for a potential adverse trend. | |||
The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues. | The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues. | ||
Annual Follow | Annual Follow-up of Selected Issues === | ||
-up of Selected | {{IP sample|IP=IP 41307|count=3}} | ||
The inspectors reviewed the Exelons implementation of its corrective action program related to the following issues: | |||
: (1) Issue Report 3989025, PMC: #2 EDG Normally Full Sight Glass Less than Half Full | : (1) Issue Report 3989025, PMC: #2 EDG Normally Full Sight Glass Less than Half Full | ||
: (2) Issue Report 2421521, SFP Badger Testing Results | : (2) Issue Report 2421521, SFP Badger Testing Results | ||
: (3) Issue Report 4048016, Results from Fermi RPS Test Box OE Review | : (3) Issue Report 4048016, Results from Fermi RPS Test Box OE Review | ||
The inspectors also concluded that a violation of NRC requirements occurred, but that the violation is of minor safety significance | ===71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports === | ||
{{IP sample|IP=IP 71153|count=2}} | |||
-routine evolutions or transients. | The inspectors evaluated the following licensee event reports (LERs): | ||
: (1) Operators entered ABN 35, | : (1) LER 2017-004-00 and -01, Reactor Protection System Channel Disabled during RPS Test Box Use (ADAMS Accession Number: ML18046A076) | ||
: (2) | The circumstances surrounding this LER are documented in Section 71152, Problem Identification and Resolution. | ||
: (2) LER 2018-001-00, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings (ADAMS Accession Number: ML18220A877) | |||
The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that a violation of NRC requirements occurred, but that the violation is of minor safety significance. | |||
===Personnel Performance (2 Samples)=== | |||
The inspectors evaluated response during the following non-routine evolutions or transients. | |||
: (1) Operators entered ABN 35, Loss of Instrument Air, due to rapidly lowering air pressure on July 25, 2018 | |||
: (2) B feedwater string removed from service due to tube leak in the B feedwater heater on July 30, | |||
==INSPECTION RESULTS== | ==INSPECTION RESULTS== | ||
Observations 71152 Follow-up of Selected Issues The inspectors determined that, in most cases, issues were appropriately evaluated by Exelon staff for potential trends and resolved within the scope of the corrective action program. However, the inspectors reviewed Issue Report 4130797, which documented a potential trend for six instances of foreign material found on fuel bundles in April 2018. The inspectors identified four more issue reports regarding instances of foreign material identified on fuel bundles since April 2018. Although the individual issues were addressed through the corrective action program, the inspectors did not see evidence that Exelon collectively evaluated the additional instances of foreign material identified on fuel bundles between April 2018 and August 2018 for a potential adverse trend. | Observations 71152 Follow-up of Selected Issues The inspectors determined that, in most cases, issues were appropriately evaluated by Exelon staff for potential trends and resolved within the scope of the corrective action program. | ||
However, the inspectors reviewed Issue Report 4130797, which documented a potential trend for six instances of foreign material found on fuel bundles in April 2018. The inspectors identified four more issue reports regarding instances of foreign material identified on fuel bundles since April 2018. Although the individual issues were addressed through the corrective action program, the inspectors did not see evidence that Exelon collectively evaluated the additional instances of foreign material identified on fuel bundles between April 2018 and August 2018 for a potential adverse trend. | |||
The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues. | The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues. | ||
Observations 71152 Follow-up of Selected Issues The inspectors reviewed the work group evaluation, the proposed and implemented corrective actions, and the past operability regarding the deficiencies on the No. 2 emergency diesel generator return fuel oil sight glass. The inspectors concluded that the work group evaluation was | Observations 71152 Follow-up of Selected Issues The inspectors reviewed the work group evaluation, the proposed and implemented corrective actions, and the past operability regarding the deficiencies on the No. 2 emergency diesel generator return fuel oil sight glass. The inspectors concluded that the work group evaluation was thorough, the extent of condition was reasonable, and the corrective actions were timely and adequate. | ||
Observations 71152 Follow-up of Selected Issues On April 7, 2016, the NRC issued Generic Letter 2016 | Observations 71152 Follow-up of Selected Issues On April 7, 2016, the NRC issued Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools, to address degradation of neutron-absorbing materials in wet storage systems for reactor fuel at power and non-power reactors. In response to Generic Letter 2016-01, Exelon submitted information to demonstrate that credited neutron-absorbing materials in the spent fuel pool were in compliance with the licensing and design basis and with applicable regulatory requirements; and that there were measures in place to maintain this compliance. The inspectors reviewed Exelons operability determination, technical evaluation, the proposed and implemented corrective actions, and the past operability regarding the neutron-absorbing materials in the spent fuel pool. The inspectors concluded that the operability determination was thorough, the extent of condition was reasonable, and the corrective actions were timely and adequate. | ||
-01, | |||
, | |||
-absorbing materials in wet storage systems for reactor fuel at power and non | |||
-power reactors. In response to Generic Letter 2016 | |||
-01, Exelon submitted information to demonstrate that credited neutron | |||
-absorbing materials in the spent fuel pool were in compliance with the licensing and design basis and with applicable regulatory requirements; and that there were measures in place to maintain this compliance. The inspectors reviewed | |||
-absorbing materials in the spent fuel pool. The inspectors concluded that the operability determination was thorough, the extent of condition was reasonable, and the corrective actions were timely and adequate. | |||
Minor Violation | Minor Violation 71152 Follow-up of Selected Issues This violation of minor significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a minor violation, consistent with the NRC enforcement Policy Minor Violation. On August 31, 2017, Exelon Generation Company, LLC (the licensee)performed a review of industry operating experience from Fermi, Unit 2 (LER 2017-001-00 under ADAMS Accession Number ML17065A226). During their review, Exelon determined that the prior use of a reactor protection system test box at Oyster Creek during periodic surveillance testing (associated with the turbine trip reactor protection system trip function)resulted in bypassing multiple contacts in parallel circuits. The use of the reactor protection system test box rendered two of four instrument channels for the turbine trip function inoperable. | ||
In 2013, the licensee revised their surveillance procedures for reactor protection system logic testing to implement the use of a reactor protection system test box in order to minimize unwanted scrams that may occur. However, the licensee did not recognize that use of the reactor protection system test box during testing of the turbine trip function would not satisfy the requirements of the technical specification limiting condition for operation. Specifically, Table 3.1.1, Function 11, turbine trip scram, in the | In 2013, the licensee revised their surveillance procedures for reactor protection system logic testing to implement the use of a reactor protection system test box in order to minimize unwanted scrams that may occur. However, the licensee did not recognize that use of the reactor protection system test box during testing of the turbine trip function would not satisfy the requirements of the technical specification limiting condition for operation. Specifically, Table 3.1.1, Function 11, turbine trip scram, in the licensees technical specifications, specifies that the minimum number of instrument channels needed to remain operable (four channels), and with fewer than that number, various technical specification actions statements are applicable. With the reactor protection system test box installed, two of the four required turbine trip scram inputs were bypassed. Technical Specifications Table 3.1.1, note (nn)requires the licensee to verify within one hour that the remaining channels were operable. | ||
The action to verify sufficient channels remained operable was not completed within one hour, and therefore, a violation of technical specifications occurred. The ability to initiate a full scram due to turbine stop valve closures among valve combinations (turbine stop valve closures in 3 of 4 different steam lines) when the reactor protection system test box is installed was not inhibited since the other trip system within the reactor protection system protection logic was unaffected. | |||
The inspectors reviewed the apparent cause analysis, the corrective actions taken, and the past operability regarding the deficiencies discovered on reactor protection system testing issues. The inspectors concluded that the cause analysis was thorough, the extent of condition was reasonable, and the corrective actions were timely. | The inspectors reviewed the apparent cause analysis, the corrective actions taken, and the past operability regarding the deficiencies discovered on reactor protection system testing issues. The inspectors concluded that the cause analysis was thorough, the extent of condition was reasonable, and the corrective actions were timely. | ||
Screening. This issue is similar to example 1.c of IMC 0612, Appendix E, | Screening. This issue is similar to example 1.c of IMC 0612, Appendix E, Examples of Minor Issues, in that, subsequent testing of reactor protection system did verify the remaining channels were operable and therefore this issue is minor. | ||
=====Enforcement.===== | =====Enforcement.===== | ||
This failure to comply with Technical Specification Table 3.1.1, note | This failure to comply with Technical Specification Table 3.1.1, note (nn)constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy. | ||
Minor Violation 71153 Minor Violation. During the performance of Procedure 602.3.004, Electromatic Relief Valve Pressure Sensor Test and Calibration, on June 5, 2018, the as-found set point for the A electromatic relief valve (EMRV) was found to be 1095 psig. Technical Specification 2.3.D, Limiting Safety System Settings, Reactor High Pressure, Relief Valve Initiation, states that the maximum allowable set point for the A EMRV is 1085 psig, 1094.15 psig when corrected for height. Exelon calibrated the A EMRV pressure sensor and retested it satisfactorily on the same day. Exelon entered the issue into the corrective action program as Issue Report 4144437. | |||
The inspectors reviewed design basis documentation, the Final Safety Analysis Report, historical calibration data for the A EMRV pressure switch, Oyster Creek accident analysis, and corrective action program documentation. The inspectors determined that the automatic depressurization system and manual operation functions were not affected by this issue. | |||
, and corrective action program documentation. The inspectors determined that the automatic depressurization system and manual operation functions were not affected by this issue | |||
The inspectors determined that the as | Following a review of the historical calibration test data from the A EMRV pressure switch, the inspectors did not identify a trend in set point measurements that would have indicated that Exelon should have taken any corrective actions to adjust the pressure switch prior to the June 5, 2018, calibration and determined that a performance deficiency did not exist. The inspectors determined that the observed actuation value did not challenge the integrity of the reactor coolant pressure boundary because overpressure protection is provided by the nine installed safety valves and did not rely on the EMRVs. The inspectors determined that the observed value for the A EMRV pressure switch actuation did not challenge the integrity of the fuel cladding as it did not affect the results of the most limiting abnormal operating transient analysis where the EMRVs are relied upon to operate. The inspectors determined that the observed value for the A EMRV pressure switch actuation did not challenge the integrity of primary containment as the analysis of record for the mark one containment bounded the observed test result. | ||
3.D and is a violation of the Oyster Creek Technical Specifications. | The inspectors determined that the as-found set point for the A EMRV exceeded the maximum set point set forth in Technical Specification 2.3.D and is a violation of the Oyster Creek Technical Specifications. | ||
Screening. The inspectors concluded that the observed result of the | Screening. The inspectors concluded that the observed result of the A EMRV pressure switch calibration did not pose a significant safety or regulatory impact and was not indicative of a programmatic issue. The inspectors considered that risk impact from the high set point was minor, and that the violation was similar to examples of minor violations of licensee administrative requirements described in the NRC Enforcement Manual, Appendix E, Examples of Minor Issues. Therefore, the violation is characterized as minor. | ||
Enforcement | =====Enforcement.===== | ||
. | Violation: Oyster Creek Technical Specification 2.3.D states, in part, that the limiting safety system setting for the A EMRV is less than or equal to 1085 psig, 1094.15 psig when corrected for height. | ||
Violation: | |||
Contrary to the above, on June 5, 2018, the limiting safety system setting for the | Contrary to the above, on June 5, 2018, the limiting safety system setting for the A EMRV was not less than or equal to 1085 psig, 1094.15 psig when corrected for height. Specifically, during calibration and testing of the A EMRV, Exelon determined that the opening set point was 1095 psig. | ||
Exelon entered the issue into the corrective action program as Issue Report 4144437 | Exelon entered the issue into the corrective action program as Issue Report 4144437. | ||
Exelons corrective actions included calibrating the A EMRV pressure sensor, performed a post maintenance test, and placed the pressure sensor in service on June 5, 2018, to restore compliance with Technical Specification 2.3.D. Although the issue was corrected, it constitutes a violation of minor significance that is not subject to enforcement action in accordance with Section 2 of the Enforcement Policy. | |||
On October 10 , 2018, the | ==EXIT MEETINGS AND DEBRIEFS== | ||
The inspectors verified no proprietary information was retained or documented in this report. | |||
* On October 10, 2018, the inspectors presented the resident inspector quarterly inspection results to Mr. Jeffrey Dostal, Site Decommissioning Director, and other members of the Oyster Creek staff. | |||
=DOCUMENTS REVIEWED= | =DOCUMENTS REVIEWED= | ||
71111.01: | 71111.01: Adverse Weather Protection | ||
Adverse Weather Protection | |||
Procedures | Procedures | ||
2.1 , Power Operation , Revision | 2.1, Power Operation, Revision 157 | ||
Equipment Alignment | 71111.04: Equipment Alignment | ||
Condition Reports | Condition Reports | ||
2456609 2724119 | 2456609 2724119 | ||
Procedures | |||
307, Isolation Condenser System, Revision 127 | 307, Isolation Condenser System, Revision 127 | ||
308, Emergency Core Cooling System Operation, Revision 99 | 308, Emergency Core Cooling System Operation, Revision 99 | ||
Line 333: | Line 279: | ||
OP-OC-108-1003, Oyster Creek Locked Equipment and Key Control, Revision 33 | OP-OC-108-1003, Oyster Creek Locked Equipment and Key Control, Revision 33 | ||
OP-OC-108-103, Locked Equipment Program, Revision 2 | OP-OC-108-103, Locked Equipment Program, Revision 2 | ||
Drawings GE148F262, Emergency Condenser Flow Diagram, Sheet 1, Revision 56 | Drawings | ||
GE148F262, Emergency Condenser Flow Diagram, Sheet 1, Revision 56 | |||
GE237E756, Spent Fuel Pool Cooling Flow Diagram, Sheet 1, Revision 60 | GE237E756, Spent Fuel Pool Cooling Flow Diagram, Sheet 1, Revision 60 | ||
GE885D781, Core Spray System Flow Diagram, Sheet 1, Revision 76 | GE885D781, Core Spray System Flow Diagram, Sheet 1, Revision 76 | ||
GU3C-735-11-001, 125V Station DC System Panel Schedule DC-D, Sheets 1 and 2, Revision 3 | |||
-D, Sheets 1 and 2, Revision 3 | GU3C-735-11-003, 125V Station DC System Panel Schedule DC-F, Revision 6 | ||
71111.05: Fire Protection | |||
-F, Revision 6 | |||
71111.05: | |||
Fire Protection | |||
Condition Reports | Condition Reports | ||
4015425 4159522 | 4015425 4159522 | ||
Procedures | |||
101.2, Oyster Creek Site Fire Protection Program, Revision 73 | 101.2, Oyster Creek Site Fire Protection Program, Revision 73 | ||
ABN 29, Plant Fires, Revision 32 | ABN 29, Plant Fires, Revision 32 | ||
Line 349: | Line 294: | ||
OP-OC-201-008, Oyster Creek Pre-fire Plans, Revision 27 | OP-OC-201-008, Oyster Creek Pre-fire Plans, Revision 27 | ||
OP-OC-201-008-1041, Hazardous Materials Storage Area, Revision 2 | OP-OC-201-008-1041, Hazardous Materials Storage Area, Revision 2 | ||
OP-OC-201-012-1001 , On-line Fire Risk Management, Revision 4 | OP-OC-201-012-1001, On-line Fire Risk Management, Revision 4 | ||
71111.06: | 71111.06: Flood Protection Measures | ||
Miscellaneous | Miscellaneous | ||
OP-PSA-012, Internal Flood Evaluation Summary Notebook, dated May 2014 | OP-PSA-012, Internal Flood Evaluation Summary Notebook, dated May 2014 | ||
OC-PSA-022, Internal Flood Walkdown Notebook, dated May 2014 | OC-PSA-022, Internal Flood Walkdown Notebook, dated May 2014 | ||
71111.11: Licensed Operator Requalification Program and Licensed Operator | |||
71111.11: | Performance | ||
Procedures | Procedures | ||
203, Plant Shutdown, Revision 90 | 203, Plant Shutdown, Revision 90 | ||
203.4, Plant Cooldown Following Reactor Scram, Revision 58 | 203.4, Plant Cooldown Following Reactor Scram, Revision 58 | ||
2.9, Primary Containment Control, Revision 66 | 2.9, Primary Containment Control, Revision 66 | ||
ABN 1, Reactor Scram, Revision 18 | ABN 1, Reactor Scram, Revision 18 | ||
Maintenance Effectiveness | 71111.12: Maintenance Effectiveness | ||
Completed Surveillance and Functional Tests | Completed Surveillance and Functional Tests | ||
614.4.001, Fuel Pool Cooling Pump Test, performed March 17, 2016, September 8, 2016, | 614.4.001, Fuel Pool Cooling Pump Test, performed March 17, 2016, September 8, 2016, | ||
614.4.002, Augmented Fuel Pool Cooling Pumps Functional Test , performed August 6, 2014 | April 1, 2017, and September 28, 2017 | ||
614.4.002, Augmented Fuel Pool Cooling Pumps Functional Test, performed August 6, 2014 | |||
and August 5, 2016 | and August 5, 2016 | ||
Condition Reports | Condition Reports | ||
1549751 1559056 1609824 1699097 1716809 2384275 2391141 2421897 2450559 2464619 2528787 2551655 2553374 2666910 2687755 2706652 2708891 2711124 2718850 2719288 2719539 2720569 3970146 3992422 3992425 4111933 4115252 4133576 4133917 4147536 4158080 4159422 4159553 4159554 4160354 Engineering Evaluations | 1549751 1559056 1609824 1699097 1716809 2384275 | ||
3970146-06, Excessive Reactor Cavity | 2391141 2421897 2450559 2464619 2528787 2551655 | ||
Leakage After Flood | 2553374 2666910 2687755 2706652 2708891 2711124 | ||
-up for 1R26 Work Group Evaluation, Revision 0 | 2718850 2719288 2719539 2720569 3970146 3992422 | ||
3992425 4111933 4115252 4133576 4133917 4147536 | |||
4158080 4159422 4159553 4159554 4160354 | |||
Engineering Evaluations | |||
3970146-06, Excessive Reactor Cavity Leakage After Flood-up for 1R26 Work Group | |||
Evaluation, Revision 0 | |||
Maintenance Orders/Work Orders | Maintenance Orders/Work Orders | ||
4581721 | 4581721 | ||
311, Fuel Pool Cooling System, Revision | Procedures | ||
311, Fuel Pool Cooling System, Revision 124 | |||
ER-AA-310-1004, Maintenance Rule | ABN 16, Loss of Fuel Pool Cooling, Revision 6 | ||
- Performance Monitoring, Revision 14 | ER-AA-310, Implementation of the Maintenance Rule, Revision 11 | ||
71111.13: | ER-AA-310-1004, Maintenance Rule - Performance Monitoring, Revision 14 | ||
71111.13: Maintenance Risk Assessments and Emergent Work Controls | |||
Condition Reports | Condition Reports | ||
4153483 4158227 4158460 4160883 4160887 | 4153483 4158227 4158460 4160883 4160887 | ||
OYS-0-2018-0253, ODM: | Miscellaneous | ||
OYS-0-2018-0253, ODM: E Reactor Recirc Pump, dated July 11, 2018 | |||
Procedures | Procedures | ||
301.2 , Reactor Recirculation System , Revision 95 | 301.2, Reactor Recirculation System, Revision 95 | ||
71111.15: | 71111.15: Operability Evaluations | ||
Calculations | Calculations | ||
C-1302-243-E170-087, Wetwell to Drywell Vacuum Breaker Sizing, Revision 4 | C-1302-243-E170-087, Wetwell to Drywell Vacuum Breaker Sizing, Revision 4 | ||
Condition Reports | Condition Reports | ||
0751551 2559925 2680591 2680993 2741850 4160551 | |||
751551-03, 24VDC Battery banks DC | 4161224 4161227 4161229 4161249 4162333 | ||
-A1 and DC-A2 Seismic Technical Evaluation, dated March 24, 2008 | Engineering Evaluations | ||
SQ-OC-DC-A1, DC-A1 / 24V DC | 751551-03, 24VDC Battery banks DC-A1 and DC-A2 Seismic Technical Evaluation, dated | ||
Batteries for Power Panel DC | March 24, 2008 | ||
-A, Revision 1 | SQ-OC-DC-A1, DC-A1 / 24V DC Batteries for Power Panel DC-A, Revision 1 | ||
Maintenance Orders/Work Orders | Maintenance Orders/Work Orders | ||
4787751 | 4787751 | ||
Miscellaneous | |||
Technical Specification 3.2.B.2.(b), Control Rod System, Amendment 178 | Technical Specification 3.2.B.2.(b), Control Rod System, Amendment 178 | ||
Procedures | Procedures | ||
ABN 36, Loss of Offsite Power & Station Blackout (Plant Control), Revision 34 ABN 37, Combustion Turbine Operation , Revision 33 | ABN 36, Loss of Offsite Power & Station Blackout (Plant Control), Revision 34 | ||
ABN 37, Combustion Turbine Operation, Revision 33 | |||
71111.18: Plant Modifications | |||
Condition Reports | Condition Reports | ||
248105 3787918 4113200 4123383 4133520 4135987 4140026 4159993 4161601 4162650 | 248105 3787918 4113200 4123383 4133520 4135987 | ||
460V Unit Substation 1A2 & 1B2, Sheet 2, | 4140026 4159993 4161601 4162650 | ||
Drawings | |||
BR 3002, 480V System One Line Diagram 460V Unit Substation 1A2 & 1B2, Sheet 2, | |||
Revision 14 | |||
Engineering Evaluations | Engineering Evaluations | ||
A2063866-01, Supplemental Feed Pump Cooling Design Attributes Review Technical Evaluation, dated June 13, 2003 | A2063866-01, Supplemental Feed Pump Cooling Design Attributes Review Technical | ||
A2063866- | Evaluation, dated June 13, 2003 | ||
EC 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill , Revision 2 | A2063866-04, Technical Evaluation for Installation of Additional Feed Pump Cooling, dated | ||
June 7, 2007 | |||
EC 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill, Revision 2 | |||
OC-700-03-013, Feed Pump Temporary Cooling Electrical Loading Analysis, Revision 1 | OC-700-03-013, Feed Pump Temporary Cooling Electrical Loading Analysis, Revision 1 | ||
OC-2003-S-0250, Temporary Configuration Change for Supplemental Feed Pump Motor Cooling 50.59 Screening, dated June 12, 2003 | OC-2003-S-0250, Temporary Configuration Change for Supplemental Feed Pump Motor | ||
Cooling 50.59 Screening, dated June 12, 2003 | |||
Procedures | Procedures | ||
28, Turbine Building Heating and Ventilation System, Revision 68 | 28, Turbine Building Heating and Ventilation System, Revision 68 | ||
338, 480 Volt Electrical System , Revision | 338, 480 Volt Electrical System, Revision 63 | ||
71111.19: | RAP J-8-F, COND/FD PMP BRG TEMP HI, Revision 10 | ||
Post Maintenance Testing | 71111.19: Post Maintenance Testing | ||
Condition Reports | Condition Reports | ||
4156090 4158227 4158460 4158875 4159507 4160552 | 4156090 4158227 4158460 4158875 4159507 4160552 | ||
4384791 4682635 4755283 4810711 4812742 | Maintenance Orders/Work Orders | ||
4384791 4682635 4755283 4810711 4812742 | |||
71114.02: Alert and Notification System Evaluation | |||
Condition Reports | Condition Reports | ||
2731947 3971345 4018930 | 2731947 3971345 4018930 | ||
EP-AA-1010, Exelon Nuclear Radiological Emergency Plan Annex for Oyster Creek Station, Revision 11 | Procedures | ||
EP-AA-1010, Exelon Nuclear Radiological Emergency Plan Annex for Oyster Creek Station, | |||
Revision 11 | |||
EP-MA-121-1002, Alert and Notification System (ANS) Program, Revision 13 | EP-MA-121-1002, Alert and Notification System (ANS) Program, Revision 13 | ||
EP-MA-121-1003, Alert and Notification System (ANS) Monitoring, Troubleshooting, and Testing Program, Revision 8 | EP-MA-121-1003, Alert and Notification System (ANS) Monitoring, Troubleshooting, and Testing | ||
Program, Revision 8 | |||
EP-MA-121-1004, Alert and Notification System (ANS) Maintenance Program, Revision 11 | EP-MA-121-1004, Alert and Notification System (ANS) Maintenance Program, Revision 11 | ||
71114.03: | 71114.03: Emergency Response Organization Staffing and Augmentation System | ||
Miscellaneous | Miscellaneous | ||
10CFR50.54(q) Evaluation 17 | 10CFR50.54(q) Evaluation 17-131 | ||
EP-AA-1010, Table OCGS 2-1, Minimum Staffing Requirements | |||
-1, Minimum Staffing Requirements | |||
Procedures | Procedures | ||
EP-AA-122, Drills and Exercise Program, Revision 19 | EP-AA-122, Drills and Exercise Program, Revision 19 | ||
EP-AA-122-100, Drill and Exercise Planning and Scheduling, Revision 8 | EP-AA-122-100, Drill and Exercise Planning and Scheduling, Revision 8 | ||
TQ-AA-113, ERO Training and Qualification, Revision 33 | TQ-AA-113, ERO Training and Qualification, Revision 33 | ||
71114.04: | 71114.04: Emergency Action Level and Emergency Plan Changes | ||
Emergency Action Level and Emergency Plan Changes | |||
Procedures | Procedures | ||
EP-AA-110-200, Dose Assessment, Revision 11 | EP-AA-110-200, Dose Assessment, Revision 11 | ||
TQ-OC-113, Training and Qualification for Decommissioning Oyster Creek ERO, Revision 0 | TQ-OC-113, Training and Qualification for Decommissioning Oyster Creek ERO, Revision 0 | ||
71114.05: | 71114.05: Maintaining Emergency Preparedness | ||
Condition Reports | Condition Reports | ||
3974714 4003001 4008476 4018636 4112969 | 3974714 4003001 4008476 4018636 4112969 | ||
Maintenance Orders/Work Orders | |||
R2187212 | R2187212 | ||
Miscellaneous | Miscellaneous | ||
2017-2018 Drill Reports | 2017-2018 Drill Reports | ||
ERO Memorandum | ERO Memorandum 2018-01, Oyster Creek Nuclear Generating Station, January 6, 2018 Notice. | ||
2018-01, Oyster Creek Nuclear Generating Station, January | of Unusual Event, dated February 5, 2018 | ||
KLD TR-924, Oyster Creek Generating Station, 2017 Population Update Analysis, dated | KLD TR-924, Oyster Creek Generating Station, 2017 Population Update Analysis, dated | ||
September 9, 2017 | September 9, 2017 | ||
Line 454: | Line 419: | ||
: [[contact::X. Building Isolation Calibration)]], Revision 59 | : [[contact::X. Building Isolation Calibration)]], Revision 59 | ||
EP-AA-121-F-10, Oyster Creek Equipment Matrix, Revision 1 | EP-AA-121-F-10, Oyster Creek Equipment Matrix, Revision 1 | ||
71151: | 71151: Performance Indicator Verification | ||
Condition Reports | Condition Reports | ||
3958850 4017602 4030606 4056733 4060631 4094634 4112416 4127990 | 3958850 4017602 4030606 4056733 4060631 4094634 | ||
4112416 4127990 | |||
Miscellaneous | |||
Increase in Unidentified Leakage Adverse Condition Monitoring Plan, Revisions 5 and 6 | Increase in Unidentified Leakage Adverse Condition Monitoring Plan, Revisions 5 and 6 | ||
OYS-0-2017-0015, UILR Post 1R26, Revision 3 | OYS-0-2017-0015, UILR Post 1R26, Revision 3 | ||
Line 463: | Line 430: | ||
EP-AA_125-1001, EP Performance Indicator Guidance, Revision 10 | EP-AA_125-1001, EP Performance Indicator Guidance, Revision 10 | ||
ER-AA-600-1047, Mitigating Systems Performance Index Basis Document, Revision 11 | ER-AA-600-1047, Mitigating Systems Performance Index Basis Document, Revision 11 | ||
ER-AB-331-1006, BWR Reactor Coolant System Leakage Monitoring and Action Plan, | ER-AB-331-1006, BWR Reactor Coolant System Leakage Monitoring and Action Plan, | ||
Revision 2 | |||
LS-AA-2200, Mitigating System Performance Index Data Acquisition & Reporting, Revision 6 | LS-AA-2200, Mitigating System Performance Index Data Acquisition & Reporting, Revision 6 | ||
71152: | 71152: Problem Identification and Resolution | ||
Condition Reports | Condition Reports | ||
0651716 0986129 1296791 1353678 1513542 2421521 | 0651716 0986129 1296791 1353678 1513542 2421521 | ||
4572692 4600295 4615010 4725780 4743398 4756912 | 2516275 2537533 2624595 2632135 2658614 2665499 | ||
2713415 2714215 2723641 3971336 3986629 3989025 | |||
3989621 3989985 3990330 4029965 4048016 4071396 | |||
4096785 4094768 4111910 4128124 4128205 4130122 | |||
4130797 4131121 4133650 4140383 4157254 4158080 | |||
4166605 | |||
Maintenance Orders/Work Orders | |||
4572692 4600295 4615010 4725780 4743398 4756912 | |||
4778790 | |||
Miscellaneous | Miscellaneous | ||
Bubble in EDG | Bubble in EDG-2 Normally Full Sight Glass Adverse Condition Monitoring Plan, Revision 5 | ||
-2 Normally Full Sight Glass Adverse Condition Monitoring Plan, Revision 5 | EC 399975, Oyster Creek 2014 RACKLIFE Update Engineering Evaluation, Revision 0 | ||
EC 399975, Oyster Creek 2014 RACKLIFE | |||
Update Engineering Evaluation, Revision 0 | |||
EC 400120, Oyster Creek Boraflex Degradation Limits, Revision 2 | EC 400120, Oyster Creek Boraflex Degradation Limits, Revision 2 | ||
EC 405644, Boraflex Degradation Limits by Fuel Type, Revision 1 | EC 405644, Boraflex Degradation Limits by Fuel Type, Revision 1 | ||
EC 618059, RACKLIFE Model Update and Projection for Oyster Creek Boraflex Spent Fuel Pool Racks | EC 618059, RACKLIFE Model Update and Projection for Oyster Creek Boraflex Spent Fuel | ||
- January 2017, Revision 0 | Pool Racks - January 2017, Revision 0 | ||
EC 619348, Emergency Diesel Generator Priming Acceptability Technical Evaluation, | EC 619348, Emergency Diesel Generator Priming Acceptability Technical Evaluation, | ||
EC 620515, EDG | Revision 1 | ||
-1 Fuel System Pump Mod, Revision 0 | EC 620515, EDG-1 Fuel System Pump Mod, Revision 0 | ||
EC 620516, EDG-2 Fuel System Priming Pump Mod, Revision 2 | EC 620516, EDG-2 Fuel System Priming Pump Mod, Revision 2 | ||
NET-356-03, Criticality Analysis of the Oyster Creek Boraflex Spent Fuel Racks, Revision 2 | NET-356-03, Criticality Analysis of the Oyster Creek Boraflex Spent Fuel Racks, Revision 2 | ||
NET-28097-000-01, 2017 BADGER Test Campaign at Oyster Creek, Revision 2 | NET-28097-000-01, 2017 BADGER Test Campaign at Oyster Creek, Revision 2 | ||
NRC Information Notice 2018 | NRC Information Notice 2018-08: Failure to Enter the Required Technical Specifications Action | ||
-08: Failure to Enter the Required Technical Specifications Action Statement for Operation during Recent Surveillance Testing While Using a Reactor Protection System Test Box | Statement for Operation during Recent Surveillance Testing While Using a Reactor | ||
Protection System Test Box | |||
OC-2014-OE-0005, Degraded Boraflex Fuel Rack Operability Evaluation, Revision 4 | OC-2014-OE-0005, Degraded Boraflex Fuel Rack Operability Evaluation, Revision 4 | ||
OYS-0-2017-0286, Simple Risk Issue Assessment, Revision 0 | OYS-0-2017-0286, Simple Risk Issue Assessment, Revision 0 | ||
OYS-0- | OYS-0-2016-0171, Emergency Diesel Generator System Reliability Issues, Revision 2 | ||
Various Operations Logs from March 26, 2017 to July 12, 2018 | Various Operations Logs from March 26, 2017 to July 12, 2018 | ||
Procedures | Procedures | ||
341, Emergency Diesel Generator Operation, Revision 117 | 341, Emergency Diesel Generator Operation, Revision 117 | ||
619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% load), Revision 29 | 619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% load), Revision 29 | ||
20.4.002, APRM Surveillance Test Front Panel Check | 20.4.002, APRM Surveillance Test Front Panel Check - RPS System 1, Revision 36 | ||
- RPS System 1, Revision 36 | 20.4.003, APRM Surveillance Test Front Panel Check - RPS System 2, Revision 15 | ||
20.4.003, APRM Surveillance Test Front Panel Check | 1002.6, Oyster Creek Spent Fuel Rack In-Service Surveillance and Management Program for | ||
- RPS System 2, Revision 15 | Boraflex Racks, Revision 16 | ||
1002.6, Oyster Creek Spent Fuel Rack In | |||
-Service Surveillance and Management Program for Boraflex Racks, Revision 16 | |||
ER-AA-2003, System Performance Monitoring and Analysis, Revision 14 | ER-AA-2003, System Performance Monitoring and Analysis, Revision 14 | ||
NF-AA-610-1000, Creation of RACKLIFE Input Files and Statepoints, Revision 6 | NF-AA-610-1000, Creation of RACKLIFE Input Files and Statepoints, Revision 6 | ||
Line 506: | Line 479: | ||
PI-AA-101-1001, Performance Monitoring and Analysis Manual, Revision 1 | PI-AA-101-1001, Performance Monitoring and Analysis Manual, Revision 1 | ||
PI-AA-125, Corrective Action Program Procedure, Revision 6 | PI-AA-125, Corrective Action Program Procedure, Revision 6 | ||
71153: | 71153: Follow-up of Events and Notices of Enforcement Discretion | ||
Condition Reports | Condition Reports | ||
4158875 4158919 4158934 4159175 4159208 4159223 4159808 4159609 4159673 4159853 4159677 4159760 4159807 4159811 4159853 4144437 4059763 2534463 2631107 3962818 3962822 3998369 | 4158875 4158919 4158934 4159175 4159208 4159223 | ||
4755262 | 4159808 4159609 4159673 4159853 4159677 4159760 | ||
4159807 4159811 4159853 4144437 4059763 2534463 | |||
2631107 3962818 3962822 3998369 | |||
Maintenance Orders/Work Orders | |||
4755262 R2270139 R2265252 | |||
Procedures | |||
318, Main Steam System and Reheat Steam, Revision 77 | 318, Main Steam System and Reheat Steam, Revision 77 | ||
ABN 35, Loss of Instrument Air , Revision 14 | ABN 35, Loss of Instrument Air, Revision 14 | ||
Relief Valve Pressure Sensor Test and Calibration, Revision 59 | 2.3.004, Electromatic Relief Valve Pressure Sensor Test and Calibration, Revision 59 | ||
Miscellaneous | Miscellaneous | ||
LER 2018-001-00, EMRV Pressure Sensor As | LER 2018-001-00, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System | ||
-Found Setting Exceeded Limiting Safety System Settings, dated July 31, 2018 | Settings, dated July 31, 2018 | ||
SE-210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure Switches and ID13 Level Transmitters, Revision 0 | SE-210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure Switches and ID13 Level | ||
EGS-DP-E23-01, Generic Dedication/Seismic Procedure for Pressure Switches, dated September 9, 1999 | Transmitters, Revision 0 | ||
C-1302-622-E510-060, PS-IA-0083 EMRV High Pressure Relief Calibration and Instrument Loop Error, Revision 0 | EGS-DP-E23-01, Generic Dedication/Seismic Procedure for Pressure Switches, dated | ||
September 9, 1999 | |||
C-1302-622-E510-060, PS-IA-0083 EMRV High Pressure Relief Calibration and Instrument | |||
Loop Error, Revision 0 | |||
SE 315-403-027, Technical Specification Amendment 165, Revision 0 | SE 315-403-027, Technical Specification Amendment 165, Revision 0 | ||
C-1302-212-E610-104, Impact to Peak Clad Temperature with Reduced EMRV flow Rate, Revision 1 | C-1302-212-E610-104, Impact to Peak Clad Temperature with Reduced EMRV flow Rate, | ||
Revision 1 | |||
SE-212-029-029, EMRV Set Point and Tolerance, Revision 0 | SE-212-029-029, EMRV Set Point and Tolerance, Revision 0 | ||
MPR-1434, Oyster Creek Nuclear Generating Station Evaluation of Proposed Increase in Technical Specification Limits for EMRV Setpoint Pressure on Mark 1 Containment | MPR-1434, Oyster Creek Nuclear Generating Station Evaluation of Proposed Increase in | ||
Technical Specification Limits for EMRV Setpoint Pressure on Mark 1 Containment | |||
Long-Term Program Analyses, Revision 0 | Long-Term Program Analyses, Revision 0 | ||
SE 315403-028, Technical Specification Change for EMRV Setpoints, Revision 0 | SE 315403-028, Technical Specification Change for EMRV Setpoints, Revision 0 | ||
2N6964, Oyster Creek Unit 1 Cycle 26 Reload Licensing Reports | 2N6964, Oyster Creek Unit 1 Cycle 26 Reload Licensing Reports - Supplemental Reload | ||
- Supplemental Reload Licensing Report (SRLR), Revision 0 | Licensing Report (SRLR), Revision 0 | ||
}} | }} |
Latest revision as of 16:53, 18 December 2019
ML18317A340 | |
Person / Time | |
---|---|
Site: | Oyster Creek |
Issue date: | 11/08/2018 |
From: | Matt Young NRC/RGN-I/DRP/PB6 |
To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
References | |
IR 2018003 | |
Download: ML18317A340 (20) | |
Text
mber 8, 2018
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000219/2018003
Dear Mr. Hanson:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oyster Creek Nuclear Generating Station. On October 10, 2018, the NRC inspectors discussed the results of this inspection with Mr. Jeffrey Dostal, Site Decommissioning Director and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any findings or violations 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 05000219/2018003
Inspection Report
Docket Number: 50-219 License Number: DPR-16 Report Number: 05000219/2018003 Enterprise Identifier: I-2018-002-0078 Licensee: Exelon Nuclear Facility: Oyster Creek Nuclear Generating Station Location: Forked River, New Jersey Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: E. Andrews, Senior Resident Inspector J. Kulp, Senior Reactor Inspector E. Allen, Project Engineer J. Ambrosini, Senior Emergency Preparedness Inspector B. DeBoer, Health Physicist J. DeBoer, Emergency Preparedness Inspector S. Horvitz, Beaver Valley Resident Inspector A. Patel, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector A. Turlin, Project Engineer K. Warner, Health Physicist Approved By: Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure
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.
Additional Tracking Items Type Issue number Title Inspection Status Results Section LER 05000219/2017-004- Reactor Protection 71153 Closed 00/01 System Channel Disabled during RPS Test Box Use LER 05000219/2018-001-00 EMRV Pressure 71153 Closed Sensor As-Found Setting Exceeded Limiting Safety System Settings
PLANT STATUS
Oyster Creek began the inspection period at 98 percent power, coasting down in power as it approached the end of the operating cycle. Operators lowered power to 70 percent on July 29, 2018, to remove the B feedwater string from service due to an internal leak in the high pressure feedwater heater. On September 17, 2018, operators commenced a plant shutdown, took the unit offline, and entered a defueling outage (1D27) where the unit remained for the remainder of the inspection period. On September 25, 2018, Oyster Creek certified that all fuel had been permanently removed from the reactor vessel and placed in the spent fuel pool. As stated in the Termination of Reactor Oversight Process for Oyster Creek Nuclear Generating Station and Commencement of Decommissioning Inspection Program letter (ADAMS Accession Number ML18274A221), beginning October 1, 2018, the NRCs oversight of Oyster Creek will no longer be performed in accordance with the operating power reactor inspection program and will instead be conducted in accordance with the decommissioning power reactor inspection program.
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection Seasonal Extreme Weather
The inspectors evaluated operator response to a high drywell temperature condition caused by seasonal extreme weather on July 24 and July 25, 2018.
71111.04 - Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) B isolation condenser during A isolation condenser testing on July 9, 2018
- (2) A isolation condenser on August 14, 2018
- (3) Spent fuel pool cooling system on September 20, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of core spray system 1 on August 15, 2018.
71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) A 480V switchgear room on July 10, 2018
- (2) B 480V switchgear room on July 10, 2018
- (3) A and B battery room on July 23, 2018
- (4) Lower cable spreading room on July 24, 2018
- (5) C and D 4160V emergency switchgear vaults on July 25, 2018
- (6) Fresh water fire pump house on July 27, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance on July 12, 2018.
71111.06 - Flood Protection Measures Internal Flooding
The inspectors evaluated internal flooding mitigation protections in the northeast corner room on July 3, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Performance
The inspectors observed operator performance during reactor shutdown for the 1D27 defueling outage on September 17, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the spent fuel pool cooling and augmented spent fuel cooling systems during the week of July 30, 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) Protection of the A, B, C, and D reactor recirculation motor generator sets and associated breakers following trip of the E reactor recirculation pump during the week of July 23, 2018
- (2) Emergent unavailability of the 1-1 service air compressor on July 24, 2018
- (3) Yellow risk due to high decay heat generation rate during the defueling outage (1D27)on September 17, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Seismic adequacy of the A1 and A2 24V battery racks on July 25, 2018
- (2) Degraded condition on station blackout 4160V switchgear breaker on July 31, 2018
- (3) Air leak from diaphragm of CV-305-127 on hydraulic control unit 42-11 on July 31, 2018
- (4) Torus to drywell vacuum breaker delay relay out of specification on August 22, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following temporary or permanent modifications:
- (1) TCC-1805-821, Temporary supplemental feed pump motor cooling
- (2) Engineering Change 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill
71111.19 - Post Maintenance Testing
The inspectors evaluated post maintenance testing for the following maintenance and repair activities:
- (1) B spent fuel pool pump preventative maintenance on July 16, 2018
- (2) 1-1 fire diesel following annual preventive maintenance on July 26, 2018
- (3) 1-1 air compressor troubleshooting and Q-6-2 auto blow down valve replacement on August 3, 2018
- (4) Average power range monitor power supply replacement on August 7, 2018
71111.20 - Refueling and Other Outage Activities
The inspectors evaluated the Oyster Creek defueling outage (1D27) activities from September 17, 2018, to September 25, 2018. The inspectors verified the fuel was removed from the core on September 25, 2018.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Containment Isolation Valve
- (1) 678.4.001, Primary containment isolation valve operability and in-service testing, on both Drywell vent valves and both Drywell purge valves July 6, 2018
71114.02 - Alert and Notification System Testing
The inspectors evaluated the maintenance and testing of the alert and notification system from September 2016 to July 2018.
71114.03 - Emergency Response Organization Staffing and Augmentation System
The inspectors conducted a review of Exelons Emergency Response Organization augmentation staffing requirements and the process for notifying and augmenting the Emergency Response Organization.
71114.04 - Emergency Action Level and Emergency Plan Changes
The inspectors verified that the changes made to the Emergency Plan were done in accordance with 10 CFR 50.54(q)(3), and any change made to the Emergency Action Levels, Emergency Plan, and its lower-tier implementing procedures, had not resulted in any reduction in effectiveness to the plan. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
The inspectors reviewed activities to evaluate Exelons efforts to maintain Oyster Creeks emergency preparedness programs.
71114.06 - Drill Evaluation Emergency Planning Drill
The inspectors evaluated the conduct of a routine Exelon decommissioning emergency planning drill on August 15,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified Exelons performance indicator submittals listed below.
=
- (1) Reactor Coolant System Leak Rate from July 2017 to June 2018
- (2) Reactor Coolant System Activity from July 2017 to June 2018
- (3) Alert and Notification Reliability from July 2017 to June 2018
- (4) Drill and Exercise Performance from July 2017 to June 2018
- (5) Emergency Response Organization Drill Participation from July 2017 to June 2018
- (6) Emergency Alternating Current Power System from October 2017 to June 2018
- (7) High Pressure Injection System - Core Spray from October 2017 to June 2018
- (8) Heat Removal - Isolation Condensers from October 2017 to June 2018
- (9) Residual Heat Removal - Containment Spray from October 2017 to June 2018
- (10) Cooling Water System from October 2017 to June 2018
71152 - Problem Identification and Resolution Semiannual Trend Review
The inspectors reviewed Exelons corrective action program for trends that might be indicative of a more significant safety issue. The inspectors determined that, in most cases, issues were appropriately evaluated by Exelon staff for potential trends and resolved within the scope of the corrective action program. However, the inspectors reviewed Issue Report
===4130797, which documented a potential trend for six instances of foreign material found on fuel bundles in April 2018. The inspectors identified four more issue reports regarding instances of foreign material identified on fuel bundles since April 2018. Although the individual issues were addressed through the corrective action program, the inspectors did not see evidence that Exelon collectively evaluated the additional instances of foreign material identified on fuel bundles between April 2018 and August 2018 for a potential adverse trend.
The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues.
Annual Follow-up of Selected Issues ===
The inspectors reviewed the Exelons implementation of its corrective action program related to the following issues:
- (1) Issue Report 3989025, PMC: #2 EDG Normally Full Sight Glass Less than Half Full
- (2) Issue Report 2421521, SFP Badger Testing Results
- (3) Issue Report 4048016, Results from Fermi RPS Test Box OE Review
71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2017-004-00 and -01, Reactor Protection System Channel Disabled during RPS Test Box Use (ADAMS Accession Number: ML18046A076)
The circumstances surrounding this LER are documented in Section 71152, Problem Identification and Resolution.
- (2) LER 2018-001-00, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings (ADAMS Accession Number: ML18220A877)
The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that a violation of NRC requirements occurred, but that the violation is of minor safety significance.
Personnel Performance (2 Samples)
The inspectors evaluated response during the following non-routine evolutions or transients.
- (1) Operators entered ABN 35, Loss of Instrument Air, due to rapidly lowering air pressure on July 25, 2018
- (2) B feedwater string removed from service due to tube leak in the B feedwater heater on July 30,
INSPECTION RESULTS
Observations 71152 Follow-up of Selected Issues The inspectors determined that, in most cases, issues were appropriately evaluated by Exelon staff for potential trends and resolved within the scope of the corrective action program.
However, the inspectors reviewed Issue Report 4130797, which documented a potential trend for six instances of foreign material found on fuel bundles in April 2018. The inspectors identified four more issue reports regarding instances of foreign material identified on fuel bundles since April 2018. Although the individual issues were addressed through the corrective action program, the inspectors did not see evidence that Exelon collectively evaluated the additional instances of foreign material identified on fuel bundles between April 2018 and August 2018 for a potential adverse trend.
The inspectors continued to monitor trends in issue report generation to ensure the reduction is a result of the transition to decommissioning and not indicative of a lack of worker engagement. Exelon had previously identified and evaluated a decreasing trend in issue report generation. Based on the overall results of the semiannual trend review, the inspectors determined that Exelon was appropriately identifying and entering issues into the corrective action program and adequately evaluating the issues.
Observations 71152 Follow-up of Selected Issues The inspectors reviewed the work group evaluation, the proposed and implemented corrective actions, and the past operability regarding the deficiencies on the No. 2 emergency diesel generator return fuel oil sight glass. The inspectors concluded that the work group evaluation was thorough, the extent of condition was reasonable, and the corrective actions were timely and adequate.
Observations 71152 Follow-up of Selected Issues On April 7, 2016, the NRC issued Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools, to address degradation of neutron-absorbing materials in wet storage systems for reactor fuel at power and non-power reactors. In response to Generic Letter 2016-01, Exelon submitted information to demonstrate that credited neutron-absorbing materials in the spent fuel pool were in compliance with the licensing and design basis and with applicable regulatory requirements; and that there were measures in place to maintain this compliance. The inspectors reviewed Exelons operability determination, technical evaluation, the proposed and implemented corrective actions, and the past operability regarding the neutron-absorbing materials in the spent fuel pool. The inspectors concluded that the operability determination was thorough, the extent of condition was reasonable, and the corrective actions were timely and adequate.
Minor Violation 71152 Follow-up of Selected Issues This violation of minor significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a minor violation, consistent with the NRC enforcement Policy Minor Violation. On August 31, 2017, Exelon Generation Company, LLC (the licensee)performed a review of industry operating experience from Fermi, Unit 2 (LER 2017-001-00 under ADAMS Accession Number ML17065A226). During their review, Exelon determined that the prior use of a reactor protection system test box at Oyster Creek during periodic surveillance testing (associated with the turbine trip reactor protection system trip function)resulted in bypassing multiple contacts in parallel circuits. The use of the reactor protection system test box rendered two of four instrument channels for the turbine trip function inoperable.
In 2013, the licensee revised their surveillance procedures for reactor protection system logic testing to implement the use of a reactor protection system test box in order to minimize unwanted scrams that may occur. However, the licensee did not recognize that use of the reactor protection system test box during testing of the turbine trip function would not satisfy the requirements of the technical specification limiting condition for operation. Specifically, Table 3.1.1, Function 11, turbine trip scram, in the licensees technical specifications, specifies that the minimum number of instrument channels needed to remain operable (four channels), and with fewer than that number, various technical specification actions statements are applicable. With the reactor protection system test box installed, two of the four required turbine trip scram inputs were bypassed. Technical Specifications Table 3.1.1, note (nn)requires the licensee to verify within one hour that the remaining channels were operable.
The action to verify sufficient channels remained operable was not completed within one hour, and therefore, a violation of technical specifications occurred. The ability to initiate a full scram due to turbine stop valve closures among valve combinations (turbine stop valve closures in 3 of 4 different steam lines) when the reactor protection system test box is installed was not inhibited since the other trip system within the reactor protection system protection logic was unaffected.
The inspectors reviewed the apparent cause analysis, the corrective actions taken, and the past operability regarding the deficiencies discovered on reactor protection system testing issues. The inspectors concluded that the cause analysis was thorough, the extent of condition was reasonable, and the corrective actions were timely.
Screening. This issue is similar to example 1.c of IMC 0612, Appendix E, Examples of Minor Issues, in that, subsequent testing of reactor protection system did verify the remaining channels were operable and therefore this issue is minor.
Enforcement.
This failure to comply with Technical Specification Table 3.1.1, note (nn)constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Minor Violation 71153 Minor Violation. During the performance of Procedure 602.3.004, Electromatic Relief Valve Pressure Sensor Test and Calibration, on June 5, 2018, the as-found set point for the A electromatic relief valve (EMRV) was found to be 1095 psig. Technical Specification 2.3.D, Limiting Safety System Settings, Reactor High Pressure, Relief Valve Initiation, states that the maximum allowable set point for the A EMRV is 1085 psig, 1094.15 psig when corrected for height. Exelon calibrated the A EMRV pressure sensor and retested it satisfactorily on the same day. Exelon entered the issue into the corrective action program as Issue Report 4144437.
The inspectors reviewed design basis documentation, the Final Safety Analysis Report, historical calibration data for the A EMRV pressure switch, Oyster Creek accident analysis, and corrective action program documentation. The inspectors determined that the automatic depressurization system and manual operation functions were not affected by this issue.
Following a review of the historical calibration test data from the A EMRV pressure switch, the inspectors did not identify a trend in set point measurements that would have indicated that Exelon should have taken any corrective actions to adjust the pressure switch prior to the June 5, 2018, calibration and determined that a performance deficiency did not exist. The inspectors determined that the observed actuation value did not challenge the integrity of the reactor coolant pressure boundary because overpressure protection is provided by the nine installed safety valves and did not rely on the EMRVs. The inspectors determined that the observed value for the A EMRV pressure switch actuation did not challenge the integrity of the fuel cladding as it did not affect the results of the most limiting abnormal operating transient analysis where the EMRVs are relied upon to operate. The inspectors determined that the observed value for the A EMRV pressure switch actuation did not challenge the integrity of primary containment as the analysis of record for the mark one containment bounded the observed test result.
The inspectors determined that the as-found set point for the A EMRV exceeded the maximum set point set forth in Technical Specification 2.3.D and is a violation of the Oyster Creek Technical Specifications.
Screening. The inspectors concluded that the observed result of the A EMRV pressure switch calibration did not pose a significant safety or regulatory impact and was not indicative of a programmatic issue. The inspectors considered that risk impact from the high set point was minor, and that the violation was similar to examples of minor violations of licensee administrative requirements described in the NRC Enforcement Manual, Appendix E, Examples of Minor Issues. Therefore, the violation is characterized as minor.
Enforcement.
Violation: Oyster Creek Technical Specification 2.3.D states, in part, that the limiting safety system setting for the A EMRV is less than or equal to 1085 psig, 1094.15 psig when corrected for height.
Contrary to the above, on June 5, 2018, the limiting safety system setting for the A EMRV was not less than or equal to 1085 psig, 1094.15 psig when corrected for height. Specifically, during calibration and testing of the A EMRV, Exelon determined that the opening set point was 1095 psig.
Exelon entered the issue into the corrective action program as Issue Report 4144437.
Exelons corrective actions included calibrating the A EMRV pressure sensor, performed a post maintenance test, and placed the pressure sensor in service on June 5, 2018, to restore compliance with Technical Specification 2.3.D. Although the issue was corrected, it constitutes a violation of minor significance that is not subject to enforcement action in accordance with Section 2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 10, 2018, the inspectors presented the resident inspector quarterly inspection results to Mr. Jeffrey Dostal, Site Decommissioning Director, and other members of the Oyster Creek staff.
DOCUMENTS REVIEWED
71111.01: Adverse Weather Protection
Procedures
2.1, Power Operation, Revision 157
71111.04: Equipment Alignment
Condition Reports
2456609 2724119
Procedures
307, Isolation Condenser System, Revision 127
308, Emergency Core Cooling System Operation, Revision 99
311, Fuel Pool Cooling System, Revision 125
OP-OC-108-1003, Oyster Creek Locked Equipment and Key Control, Revision 33
OP-OC-108-103, Locked Equipment Program, Revision 2
Drawings
GE148F262, Emergency Condenser Flow Diagram, Sheet 1, Revision 56
GE237E756, Spent Fuel Pool Cooling Flow Diagram, Sheet 1, Revision 60
GE885D781, Core Spray System Flow Diagram, Sheet 1, Revision 76
GU3C-735-11-001, 125V Station DC System Panel Schedule DC-D, Sheets 1 and 2, Revision 3
GU3C-735-11-003, 125V Station DC System Panel Schedule DC-F, Revision 6
71111.05: Fire Protection
Condition Reports
4015425 4159522
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 27
OP-OC-201-008-1041, Hazardous Materials Storage Area, Revision 2
OP-OC-201-012-1001, On-line Fire Risk Management, Revision 4
71111.06: Flood Protection Measures
Miscellaneous
OP-PSA-012, Internal Flood Evaluation Summary Notebook, dated May 2014
OC-PSA-022, Internal Flood Walkdown Notebook, dated May 2014
71111.11: Licensed Operator Requalification Program and Licensed Operator
Performance
Procedures
203, Plant Shutdown, Revision 90
203.4, Plant Cooldown Following Reactor Scram, Revision 58
2.9, Primary Containment Control, Revision 66
ABN 1, Reactor Scram, Revision 18
71111.12: Maintenance Effectiveness
Completed Surveillance and Functional Tests
614.4.001, Fuel Pool Cooling Pump Test, performed March 17, 2016, September 8, 2016,
April 1, 2017, and September 28, 2017
614.4.002, Augmented Fuel Pool Cooling Pumps Functional Test, performed August 6, 2014
and August 5, 2016
Condition Reports
1549751 1559056 1609824 1699097 1716809 2384275
2391141 2421897 2450559 2464619 2528787 2551655
2553374 2666910 2687755 2706652 2708891 2711124
2718850 2719288 2719539 2720569 3970146 3992422
3992425 4111933 4115252 4133576 4133917 4147536
4158080 4159422 4159553 4159554 4160354
Engineering Evaluations
3970146-06, Excessive Reactor Cavity Leakage After Flood-up for 1R26 Work Group
Evaluation, Revision 0
Maintenance Orders/Work Orders
4581721
Procedures
311, Fuel Pool Cooling System, Revision 124
ABN 16, Loss of Fuel Pool Cooling, Revision 6
ER-AA-310, Implementation of the Maintenance Rule, Revision 11
ER-AA-310-1004, Maintenance Rule - Performance Monitoring, Revision 14
71111.13: Maintenance Risk Assessments and Emergent Work Controls
Condition Reports
4153483 4158227 4158460 4160883 4160887
Miscellaneous
OYS-0-2018-0253, ODM: E Reactor Recirc Pump, dated July 11, 2018
Procedures
301.2, Reactor Recirculation System, Revision 95
71111.15: Operability Evaluations
Calculations
C-1302-243-E170-087, Wetwell to Drywell Vacuum Breaker Sizing, Revision 4
Condition Reports
0751551 2559925 2680591 2680993 2741850 4160551
4161224 4161227 4161229 4161249 4162333
Engineering Evaluations
751551-03, 24VDC Battery banks DC-A1 and DC-A2 Seismic Technical Evaluation, dated
March 24, 2008
SQ-OC-DC-A1, DC-A1 / 24V DC Batteries for Power Panel DC-A, Revision 1
Maintenance Orders/Work Orders
4787751
Miscellaneous
Technical Specification 3.2.B.2.(b), Control Rod System, Amendment 178
Procedures
ABN 36, Loss of Offsite Power & Station Blackout (Plant Control), Revision 34
ABN 37, Combustion Turbine Operation, Revision 33
71111.18: Plant Modifications
Condition Reports
248105 3787918 4113200 4123383 4133520 4135987
4140026 4159993 4161601 4162650
Drawings
BR 3002, 480V System One Line Diagram 460V Unit Substation 1A2 & 1B2, Sheet 2,
Revision 14
Engineering Evaluations
A2063866-01, Supplemental Feed Pump Cooling Design Attributes Review Technical
Evaluation, dated June 13, 2003
A2063866-04, Technical Evaluation for Installation of Additional Feed Pump Cooling, dated
June 7, 2007
EC 545008, Permanent USS 1A1 and 1A2 Transformer Nitrogen Keepfill, Revision 2
OC-700-03-013, Feed Pump Temporary Cooling Electrical Loading Analysis, Revision 1
OC-2003-S-0250, Temporary Configuration Change for Supplemental Feed Pump Motor
Cooling 50.59 Screening, dated June 12, 2003
Procedures
28, Turbine Building Heating and Ventilation System, Revision 68
338, 480 Volt Electrical System, Revision 63
RAP J-8-F, COND/FD PMP BRG TEMP HI, Revision 10
71111.19: Post Maintenance Testing
Condition Reports
4156090 4158227 4158460 4158875 4159507 4160552
Maintenance Orders/Work Orders
4384791 4682635 4755283 4810711 4812742
71114.02: Alert and Notification System Evaluation
Condition Reports
2731947 3971345 4018930
Procedures
EP-AA-1010, Exelon Nuclear Radiological Emergency Plan Annex for Oyster Creek Station,
Revision 11
EP-MA-121-1002, Alert and Notification System (ANS) Program, Revision 13
EP-MA-121-1003, Alert and Notification System (ANS) Monitoring, Troubleshooting, and Testing
Program, Revision 8
EP-MA-121-1004, Alert and Notification System (ANS) Maintenance Program, Revision 11
71114.03: Emergency Response Organization Staffing and Augmentation System
Miscellaneous
10CFR50.54(q) Evaluation 17-131
EP-AA-1010, Table OCGS 2-1, Minimum Staffing Requirements
Procedures
EP-AA-122, Drills and Exercise Program, Revision 19
EP-AA-122-100, Drill and Exercise Planning and Scheduling, Revision 8
TQ-AA-113, ERO Training and Qualification, Revision 33
71114.04: Emergency Action Level and Emergency Plan Changes
Procedures
EP-AA-110-200, Dose Assessment, Revision 11
TQ-OC-113, Training and Qualification for Decommissioning Oyster Creek ERO, Revision 0
71114.05: Maintaining Emergency Preparedness
Condition Reports
3974714 4003001 4008476 4018636 4112969
Maintenance Orders/Work Orders
R2187212
Miscellaneous
2017-2018 Drill Reports
ERO Memorandum 2018-01, Oyster Creek Nuclear Generating Station, January 6, 2018 Notice.
of Unusual Event, dated February 5, 2018
KLD TR-924, Oyster Creek Generating Station, 2017 Population Update Analysis, dated
September 9, 2017
KLD TR-1010, Oyster Creek Generating Station, 2018 Population Update Analysis, dated
September 8, 2018
NOSA-CAL-17-03, 2017 Emergency Preparedness Audit Report
NOSA-CAL-18-03, 2018 Emergency Preparedness Audit Report
Procedures
21.3.005, High Radiation Monitor (R
- X. Building Isolation Calibration), Revision 59
EP-AA-121-F-10, Oyster Creek Equipment Matrix, Revision 1
71151: Performance Indicator Verification
Condition Reports
3958850 4017602 4030606 4056733 4060631 4094634
4112416 4127990
Miscellaneous
Increase in Unidentified Leakage Adverse Condition Monitoring Plan, Revisions 5 and 6
OYS-0-2017-0015, UILR Post 1R26, Revision 3
Various Operations Logs from July 1, 2017 to June 30, 2018
Procedures
EP-AA_125-1001, EP Performance Indicator Guidance, Revision 10
ER-AA-600-1047, Mitigating Systems Performance Index Basis Document, Revision 11
ER-AB-331-1006, BWR Reactor Coolant System Leakage Monitoring and Action Plan,
Revision 2
LS-AA-2200, Mitigating System Performance Index Data Acquisition & Reporting, Revision 6
71152: Problem Identification and Resolution
Condition Reports
0651716 0986129 1296791 1353678 1513542 2421521
2516275 2537533 2624595 2632135 2658614 2665499
2713415 2714215 2723641 3971336 3986629 3989025
3989621 3989985 3990330 4029965 4048016 4071396
4096785 4094768 4111910 4128124 4128205 4130122
4130797 4131121 4133650 4140383 4157254 4158080
4166605
Maintenance Orders/Work Orders
4572692 4600295 4615010 4725780 4743398 4756912
4778790
Miscellaneous
Bubble in EDG-2 Normally Full Sight Glass Adverse Condition Monitoring Plan, Revision 5
EC 399975, Oyster Creek 2014 RACKLIFE Update Engineering Evaluation, Revision 0
EC 400120, Oyster Creek Boraflex Degradation Limits, Revision 2
EC 405644, Boraflex Degradation Limits by Fuel Type, Revision 1
EC 618059, RACKLIFE Model Update and Projection for Oyster Creek Boraflex Spent Fuel
Pool Racks - January 2017, Revision 0
EC 619348, Emergency Diesel Generator Priming Acceptability Technical Evaluation,
Revision 1
EC 620515, EDG-1 Fuel System Pump Mod, Revision 0
EC 620516, EDG-2 Fuel System Priming Pump Mod, Revision 2
NET-356-03, Criticality Analysis of the Oyster Creek Boraflex Spent Fuel Racks, Revision 2
NET-28097-000-01, 2017 BADGER Test Campaign at Oyster Creek, Revision 2
NRC Information Notice 2018-08: Failure to Enter the Required Technical Specifications Action
Statement for Operation during Recent Surveillance Testing While Using a Reactor
Protection System Test Box
OC-2014-OE-0005, Degraded Boraflex Fuel Rack Operability Evaluation, Revision 4
OYS-0-2017-0286, Simple Risk Issue Assessment, Revision 0
OYS-0-2016-0171, Emergency Diesel Generator System Reliability Issues, Revision 2
Various Operations Logs from March 26, 2017 to July 12, 2018
Procedures
341, Emergency Diesel Generator Operation, Revision 117
619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% load), Revision 29
20.4.002, APRM Surveillance Test Front Panel Check - RPS System 1, Revision 36
20.4.003, APRM Surveillance Test Front Panel Check - RPS System 2, Revision 15
1002.6, Oyster Creek Spent Fuel Rack In-Service Surveillance and Management Program for
Boraflex Racks, Revision 16
ER-AA-2003, System Performance Monitoring and Analysis, Revision 14
NF-AA-610-1000, Creation of RACKLIFE Input Files and Statepoints, Revision 6
NF-OC-310-2000, Special Nuclear Material and Core Component Movement, Revision 16
OP-AA-108-108, Unit Restart Review, Revision 19
OP-AA-108-115, Operability Determinations, Revision 21
PI-AA-101-1001, Performance Monitoring and Analysis Manual, Revision 1
PI-AA-125, Corrective Action Program Procedure, Revision 6
71153: Follow-up of Events and Notices of Enforcement Discretion
Condition Reports
4158875 4158919 4158934 4159175 4159208 4159223
4159808 4159609 4159673 4159853 4159677 4159760
4159807 4159811 4159853 4144437 4059763 2534463
2631107 3962818 3962822 3998369
Maintenance Orders/Work Orders
4755262 R2270139 R2265252
Procedures
318, Main Steam System and Reheat Steam, Revision 77
ABN 35, Loss of Instrument Air, Revision 14
2.3.004, Electromatic Relief Valve Pressure Sensor Test and Calibration, Revision 59
Miscellaneous
LER 2018-001-00, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System
Settings, dated July 31, 2018
SE-210-001, Evaluation of EQ Master List Inclusion of IA83 Pressure Switches and ID13 Level
Transmitters, Revision 0
EGS-DP-E23-01, Generic Dedication/Seismic Procedure for Pressure Switches, dated
September 9, 1999
C-1302-622-E510-060, PS-IA-0083 EMRV High Pressure Relief Calibration and Instrument
Loop Error, Revision 0
SE 315-403-027, Technical Specification Amendment 165, Revision 0
C-1302-212-E610-104, Impact to Peak Clad Temperature with Reduced EMRV flow Rate,
Revision 1
SE-212-029-029, EMRV Set Point and Tolerance, Revision 0
MPR-1434, Oyster Creek Nuclear Generating Station Evaluation of Proposed Increase in
Technical Specification Limits for EMRV Setpoint Pressure on Mark 1 Containment
Long-Term Program Analyses, Revision 0
SE 315403-028, Technical Specification Change for EMRV Setpoints, Revision 0
2N6964, Oyster Creek Unit 1 Cycle 26 Reload Licensing Reports - Supplemental Reload
Licensing Report (SRLR), Revision 0