IR 05000321/2022004
| ML23031A043 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/01/2023 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2022004 | |
| Download: ML23031A043 (21) | |
Text
February 1, 2023
SUBJECT:
EDWIN I. HATCH PLANT - INTEGRATED INSPECTION REPORT 05000321/2022004 AND 05000366/2022004
Dear Cheryl A. Gayheart:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Plant. On January 19, 2023, the NRC inspectors discussed the results of this inspection with Johnny Weissinger and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Edwin I. Hatch Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Edwin I. Hatch Plant.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Alan J. Blamey, Chief Reactor Projects Branch2 Division of Reactor Projects Docket Nos. 05000321 and 05000366 License Nos. DPR57 and NPF5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366
License Numbers:
Report Numbers:
05000321/2022004 and 05000366/2022004
Enterprise Identifier:
I2022004-0018
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch Plant
Location:
Baxley, GA
Inspection Dates:
October 01, 2022, to December 31, 2022
Inspectors:
M. Bates, Senior Operations Engineer
B. Caballero, Senior Operations Engineer
P. Gresh, Emergency Preparedness Inspector
J. Hickman, Resident Inspector
D. Lanyi, Senior Operations Engineer
T. Morrissey, Senior Resident Inspector
S. Sanchez, Senior Emergency Preparedness Insp
R. Smith, Senior Resident Inspector
J. Walker, Emergency Response Inspector
Approved By:
Alan J. Blamey, Chief
Reactor Projects Branch2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Maintain an Emergency Plan Risk Significant Planning Standard Implementing Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness Green NCV 05000321,05000366/202200401 Open/Closed
[H.3] - Change Management 71114.04 On December 15, 2022, the inspectors identified a Green finding and associated NCV of Title 10 Code of Federal Regulations (CFR) Part 50, Appendix E, and the planning standards of Title 10 CFR 50.47(b)(9) when the licensee failed to maintain the effectiveness of the sites emergency plan. Specifically, the licensee failed to ensure adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency were in place for performing manual dose assessment.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On November 19, 2022, the unit was down powered to 65 percent RTP to perform a rod pattern adjustment, the unit was returned to 100 percent RTP on November 20, 2022, and remained at or near RTP for the remainder of the inspection period.
Unit 2 began the inspection period at 100 percent RTP. On October 10, 2022, the unit was shut down to replace the E safety relief valve and perform other maintenance activities. On October 15, 2022, the unit was started up and reached 100 percent RTP on October 18, 2022. The unit was down powered to between 80 to 85 percent RTP multiple times (e.g., October 29, 2022, November 5, 2022, November 12, 2022, and November 18, 2022) for rod pattern adjustment. In each instance the unit was returned to 100 percent RTP the same day following the rod pattern adjustment. On November 21, 2022, the unit was down powered to 82 percent RTP to repair the mechanical seal on C condensate booster pump, the unit was returned to 100 percent RTP on November 22, 2022. On November 29, 2022, the unit reached maximum core flow and began the initial coast down in power for the 2023, winter refueling outage. On December 14, 2022, the unit was down powered to 85 percent RTP to perform final feedwater temperature reduction and returned to 100 percent RTP the same day. On December 22, 2022, the unit reached maximum core flow and began the final coast down in power for the 2023, winter refueling outage, and remained in coast down in power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of below freezing temperatures for the following systems on November 21, 2022:
1. Plant Service Water (PSW)
2. Residual Heat Removal Service Water (RHRSW)
3. Emergency Diesel Generators (EDGs)
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Alignment of the Unit 1 reactor core isolation cooling (RCIC) system following RCIC system outage, using procedure 34SO-E51001-1, on October 7, 2022.
- (2) Alignment of the Unit 2 residual heat removal (RHR) system in a shutdown cooling mode following reactor shutdown for the replacement of the E safety relief valve (SRV), using procedure 34SO-E11010-2, on October 12, 2022.
- (3) Alignment of the Unit 1 'A' EDG while the 'C' EDG was out of service for a maintenance outage, using procedure 34SO-R43001-1, on October 2627, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Control building 164-foot elevation on October 7, 2022.
- (2) Unit 2 Reactor Building 185-foot elevation on November 13, 2022.
- (3) Unit 1 Reactor Building 203-foot elevation on November 13, 2022.
- (4) Unit 2 Radwaste Building 132-foot elevation on November 18, 2022.
- (5) Unit 2 Condensate Storage Tank on December 23, 2022.
- (6) Unit 1 Turbine Building 112-foot elevation on December 28, 2022.
71111.11 A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)
- (1) Annual Review of Licensee Requalification Examination Results: On October 26, 2022, the facility licensee completed the annual requalification operating tests required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. During the week of December 19, 2022, the inspectors performed an inoffice review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with IP
===71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 03.03, Requalification Examination Results, of IP 71111.11.
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating test administration, which the facility licensee completed on October 26, 2022.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04)===
The inspectors reviewed the facility operating history and associated documents in preparation for this inspection. During the week of October 17 - 20, 2022, the inspectors reviewed documentation, interviewed licensee personnel, and observed the administration of operating tests associated with the licensees operator requalification program. Each of the activities performed by the inspectors was done to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. The evaluations were also performed to determine if the licensee effectively implemented operator requalification guidelines established in NUREG1021, Operator Licensing Examination Standards for Power Reactors, and IP 71111.11, Licensed Operator Requalification Program. The inspectors also evaluated the licensees simulation facility for adequacy for use in operator licensing examinations using ANSI/ANS3.51985 and 2009, American National Standard for Nuclear Power Plant Simulators for use in Operator Training and Examination. The inspectors observed three crews during the performance of the operating tests. Documentation reviewed included written examinations, Job Performance Measures, simulator scenarios, licensee procedures, onshift records, simulator modification request records, simulator performance test records, operator feedback records, licensed operator qualification records, remediation plans, watch-standing records, and medical records. The records were inspected using the criteria listed in IP 71111.11.
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination approved on October 27, 2021.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Reexaminations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of reexaminations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) On October 9 and 10, 2022, the inspectors observed and evaluated licensed operator performance in the control room during Unit 2 plant shutdown in support of a maintenance outage. Specifically, the inspectors observed power decrease operations via reduction of reactor recirculation flow to minimum, insertion of control rods to 20 percent RTP, followed by a main turbine trip, and the insertion of a manual reactor trip to complete the shutdown. The inspectors then observed the operating crew establish a controlled cooldown rate within technical specification (TS) limits. On October 14 and 15, 2022, the inspectors observed and evaluated licensed operator performance in the control room during Unit 2 plant startup. Specifically, the inspectors observed the pulling of control rods to criticality, observed proper overlaps of nuclear instrumentation, and observed power increase above the point of adding heat. The inspectors then observed the operating crew establish a controlled heat up rate within TS limits.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated License Operator Requalification Program for the following Scenario HLTC-SE00162, "RCIC room cooler leak, Recirculation pump trip, loss of reactor feed pump turbine, high pressure coolant injection (HPCI) auto start fails, (HPCI) leak, and torus high level," for two teams during simulator training on October 11, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Unit 2 HPCI system for being greater than 75 percent of the allowed unavailability time during the system review period of two years, resulting in the system being near 10CFR50.65 (a)(1) status, on November 14, 2022.
- (2) Unit 2 RCIC system for being greater than 75 percent of the allowed unavailability time during the system review period of two years, resulting in the system being near 10CFR50.65 (a)(1) status, on November 16, 2022.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 1 elevated risk due to RCIC system outage from October 3 through 6, 2022.
- (2) Unit 2 elevated risk due to E SRV replacement during shutdown maintenance outage from October 11 through 14, 2022.
- (3) Unit 1 elevated risk due to HPCI system outage from October 18 through 21, 2022.
- (4) Unit 1 elevated risk due to the 'C' EDG outage from October 24 through 28, 2022.
- (5) Unit 1 and 2 elevated risk due to the '1B' EDG (site swing EDG) outage form November 7 through 10, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Condition Report (CR) 10915156, Unit 2 B recirculation pump discharge valve, 2B31F031B, dual light indication.
- (2) CR 10914542, Unit 2 RCIC steam supply inboard isolation valve, 2E51F007, exceeded the maximum allowable leakage.
- (3) CRs 10915924, 10916827, 10917138, 10918171, Unit 2 drywell pressure decreasing trend post maintenance outage.
- (4) CRs 10931906 and 10932866, Unit 2 RCIC pump, inboard bearing oil reservoir found with substantial percentage of water.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)34SV-E51002-1, "RCIC Pump Operability," Version 29.2, following RCIC system outage, on October 6, 2022.
(2)34SV-E41001-1,"HPCI Valve Operability, Version 20.1 and 34SV-E41002-1, HPCI Pump Operability," Version 33.2, following HPCI system outage on October 21, 2022.
(3)52SV-R43001-0, "Diesel, Alternator, and Accessories Inspection," Version 31.25 and 34SV-R43006-1, "Diesel Generator 1C Semi-Annual Test," Version 15.3, following 1C EDG outage, on October 28, 2022.
(4)52SV-R43001-0, "Diesel, Alternator and Accessories Inspection," Version 31.25 and 34SV-R43005-2, "Diesel Generator 2B Semi-Annual Test," Version 21.6, following 1B EDG outage, on November 10 and 11, 2022.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the unit 2 maintenance outage that replaced both A and B recirculation pump seals, replaced the E SRV due to seat leakage on the main seat, repacked the RCIC inboard steam isolation valve 2E52F007, and replaced reactor feed pump turbine seal water return line due to a steam leak, from October 9 through October 16, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
(1)34SV-R43011-2, Diesel Generator 2A 24-Month Operability Test, Version 7.2, on November 1 and 2, 2022.
(2)34SV-E41002-1, "HPCI Pump Operability," Version 33.2, on December 12, 2022.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.0102.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of December 12, 2022.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.0102.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of December 12, 2022.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.0102.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of December 12, 2022. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of December 12,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures Sample (IP Section 02.04)===
- (1) Unit 1 (October 1, 2021, to September 30, 2022)
- (2) Unit 2 (October 1, 2021, to September 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2021, to September 30, 2022)
- (2) Unit 2 (October 1, 2021, to September 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2021, to September 30, 2022)
- (2) Unit 2 (October 1, 2021, to September 30, 2022)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) July 1, 2021, through September 30, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2021, through September 30, 2022 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2021, through September 30, 2022
71152 A - Annual Follow up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CR 10907512 and corrective action report (CAR) 319701. Review of corrective actions for relay fire in main control room lighting panel, on October 27, 2022.
71152 S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends regarding actions associated with the implementation of NFPA 805 modifications to safety-related breakers for both units, that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow Up (IP Section 03.01)
- (1) The inspectors evaluated the licensees response to a fire main rupture on November 19,
INSPECTION RESULTS
Failure to Maintain an Emergency Plan Risk Significant Planning Standard Implementing Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness Green NCV 05000321,05000366/202200401 Open/Closed
[H.3] - Change Management 71114.04 On December 15, 2022, the inspectors identified a Green finding and associated NCV of Title 10 CFR Part 50, Appendix E, and the planning standards of Title 10 CFR 50.47(b)(9) when the licensee failed to maintain the effectiveness of the sites emergency plan. Specifically, the licensee failed to ensure adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency were in place for performing manual dose assessment.
Description:
While performing a detailed review of changes to the manual dose assessment procedure NMP-EP147F05, the inspectors identified that the licensee removed procedural guidance that instructs emergency response organization (ERO)/dose assessors to input the status of containment sprays into the dose assessment software. In the 50.54(q) change documentation the licensee concluded that removal of containment spray from the dose assessment implementing procedure was acceptable because Hatch is a boiling water reactor (BWR). The licensee stated that containment sprays do not apply to a BWR, and their removal was not considered a reduction in effectiveness of the Emergency Plan. The inspectors determined that containment sprays do apply to a BWR by use of drywell sprays and have the potential to impact dose projections generated by the dose assessment program. As a result, the potential exists for an ERO/dose assessor to incorrectly enter containment spray status into the dose assessment software, resulting in inaccurate dose assessment and potentially, inaccurate classifications and protective action recommendations (PARs). After further discussions with the licensee, the inspectors determined that mitigating factors could be taken into consideration for assessing the significance of the issue. Hatch dose assessment inputs, including containment spray status, is normally performed automatically from the plant computer system, so loss of the plant computer would have to occur for manual dose assessment to apply. Additionally, if dose assessment is performed manually, the Hatch dose assessment software requires the user to input status of containment sprays and dose assessors are trained to ensure containment spray status is entered into the dose assessment software.
Corrective Actions: The licensee entered the issue into the corrective action program on December 16, 2022.
Corrective Action References: Condition Report 10931814
Performance Assessment:
Performance Deficiency: The inspectors determined that removal of guidance from the dose assessment implementing procedure was a performance deficiency that was reasonably within the ability of the licensee to foresee and correct.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Emergency Preparedness cornerstone and adversely affected the cornerstone objective to ensure that the licensee is capable of implementing adequate measures to protect the health and safety of the public in the event of a radiological emergency. Specifically, the licensee made a procedure change that resulted in the potential for inaccurate estimates of offsite releases and could negatively impact classification and PAR development.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix B, Emergency Preparedness SDP. The performance deficiency was determined to have very low safety significance (Green) because the dose projection process is incapable of providing technically adequate estimates of radioactive material releases to the environment or projected offsite doses in some cases. The inspectors determined that mitigating factors, as described above, provide reasonable assurance that the planning standard function could be accomplished, albeit in a degraded manner, if an actual radiological emergency were to occur.
Cross-Cutting Aspect: H.3 - Change Management: Leaders use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority.
Specifically, the licensees 50.54(q) change process failed to identify that the removal of containment spray from the dose assessment procedure was inappropriate.
Enforcement:
Violation: Title 10 of the Code of Federal Regulations, Part 50.54(q)(2) requires, in part, that a holder of a nuclear power reactor operating license under this part, shall follow and maintain the effectiveness of an emergency plan that meets the requirements of Title 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b). 10 CFR 50.47(b)(9)requires methods, systems, and equipment for assessment of radioactive releases are in use.
Contrary to the above, on September 12, 2022, the licensee failed to maintain the effectiveness of its emergency plan. Specifically, the licensee did not adequately maintain methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency when they incorrectly removed guidance from a dose assessment implementing procedure for inputting the status of containment sprays into the dose assessment software.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 19, 2023, the inspectors presented the integrated inspection results to Johnny Weissinger, Site Vice President, and other members of the licensee staff.
On October 20, 2022, the inspectors presented the Licensed Operator Requalification Program inspection results to Andy Belcher, Training Director and other members of the licensee staff.
On December 15, 2022, the inspectors presented the Emergency Preparedness Program Inspection results to Mr. J. Weissinger and other members of the licensee staff.
On January 25, 2023, the inspectors presented the Emergency Preparedness Program Inspection ReExit inspection results to Mr. J. Weissinger and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
DIOPS360989
Cold Weather Checks
Revision 23.6
Condition Reports (CR)
10847703, 10847900, 10848137, 10855461,
10855499, 10855651, 10856598, 10857690,
10857760, 10852219, 10858261, 10858594,
10858625, 10860294, 10860825, 10864170,
10865105, 10867159, 10867171, 10872007,
10875521, 10878935, 10879072, 10879111,
10891070, 10892345, 10912951, 10918206
Corrective Action
Documents
Condition Reports (CR)
10911913, 10912206, 10912377, 10912458,
10912587, 10912803
Residual Heat Removal System
45.2
RCIC System
30.6
Procedures
Diesel Generator Standby AC System
29.4
NMP-
ES035019GL02F04
Control Building 164Foot Elevation
1.0
NMP-
ES035019GL02F08
U1 Turbine Building ELEV 112Foot Elevation
1.0
NMP-
ES035019GL02F16
U1 Reactor Building 203Foot Elevation
1.0
NMP-
ES035019GL02F32
U2 Reactor Building 185Foot Elevation
1.0
NMP-
ES035019GL02F36
Unit 2 Radwaste Building
1.0
Fire Plans
NMP-
ES035019GL02F53
Unit 2 Condensate Storage Tank
1.0
Miscellaneous
Scenario HLTC-
SE00162
"RCIC room cooler leak, Recirculation pump trip, loss
of reactor feed pump turbine, high pressure coolant
injection (HPCI) auto start fails, (HPCI) leak, and torus
high level
10/11/2022
Procedures
Plant Startup
51.11
Corrective Action
Documents
Condition Reports (CR)
10752262, 10752371, 10752519, 10762980,
10772157, 10772419, 10772431, 10773100,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10773182, 10773184, 10773973, 10774127,
10775453, 10776146, 10776824, 10776921,
10776967, 10777735, 10777750, 10777998,
10779485, 10780688, 10780774, 10780774,
10781771, 10782366, 10782719, 10783605,
10783705, 10783757, 10783847, 10785204,
10787291, 10787842, 10787845, 10787846,
10788499, 10792231, 10797623, 10797740,
10802238, 10825262, 10825300, 10825444,
10825452, 10826822, 10829013, 10829018,
10829367, 10831450, 10831473, 10831477,
10835757, 10835888, 10836780, 10838466,
10838655, 10838975, 10838990, 10839151,
10839226, 10839228, 10839346, 10839538,
10839678, 10844306, 10848189, 10848356,
10849215, 10849432, 10856438, 10856558,
10867413, 10874310, 10885572, 10890567,
10894012, 10906065, 10906745, 10908189,
10911277, 10913938, 10914183, 10914542,
10915223, 10915439, 10916820
Condition Reports (CR)
10849247, 10850131, 10855527, 10857809,
10857818, 10857887, 10859247, 10859614,
10861482, 10861626, 10861832, 10861842,
10861906, 10862530, 10862535, 10862642,
10862747, 10862846, 10862972, 10863108,
10863140, 10863631, 10865248, 10866317,
10866845, 10873546, 10886442, 10887033,
10892323, 10895796, 10896579, 10897221,
10909092, 10915818, 10916441, 10916500,
10916546, 10916550, 10916551, 10916569,
10916659, 10916742, 10916895, 10916918,
10916919, 10918179, 10918180, 10919328,
10919696, 10923542, 10924185, 10925034,
10926624, 10927391, 10927777, 10927889,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10928415, 10930945,10930947
Corrective Action
Reports (CAR)
278906, 278983, 278896, 279357
NEI 9902
Regulatory Assessment Performance Indicator
Guideline
Revision 7
NMP-ES027
Version 10.4
Procedures
Industry Guideline for Monitoring the Effectiveness of
Maintenance at Nuclear Power Plants
Revision 4 A
Work Orders
Work Orders (WO#
SNC)
1033618, 1141932, 12638891, 1293845, 1187166,
1157830, 1390751, 1160953, 1161216, 1395324,
1145828, 1181601, 1114460,
Corrective Action
Documents
Condition Reports (CR)
10917989
Corrective Action
Documents
Resulting from
Inspection
Condition Report (CR)
10922715
Hatch U1 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
10/24/2022
Hatch U1 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
11/10/2022
Hatch U2 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
11/10/2022
Hatch U2 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
10/1114/2022
Hatch U1 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
10/18/2022
Hatch U1 R8 OnLine Configuration Risk Monitor -
Current Risk Summary Report
10/36/2022
Miscellaneous
1ET221R4300005(1)
Tagout Coversheet for Protective Equipment (1C
EDG)
10/24/2022
NMP-GM031
OnLine Configuration Risk Management Program
9.2
NMP-OS010002
Hatch Protected Equipment Logs
11.1
Procedures
NMP-OS017
Severe Weather Checks (Tropical Storm Nicole)
11/09/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Reports (CR)
10915924, 10916827, 10917138, 10918171
Miscellaneous
Hatch Unit 2 Drywell and Torus Abnormal Pressure
Trend (Completed Fault Tree)
10/26/2022
Lubrication Analysis
4.1
NMP-AD002F04
Troubleshooting Log (Various PCIVs and DW
1.1
NMP-AD002F04
Troubleshooting Log - Installing a Recorder to Monitor
Containment for Flow Going Through DW Pneumatic
System
1.1
NMP-AD002F04
Various PCIVs and DW Penetrations
1.1
NMP-AD002F04
Troubleshooting for Containment Leakage from
Fission Product Monitor, H2O2 Analyzer and O2
Analyzer
1.1
NMP-AD012
15.0
NMP-AD012GL04
1.1
Procedures
NMP-ES074006
Fleet Lubrication Instruction
5.0
Work Orders
SNC847913
Take Oil Sample from Unit 2 RCIC Pump
11/05/21
HPCI Valve Operability
20.1
HPCI Pump Operability
33.2
Reactor Core Isolation Cooling Operability
29.2
Diesel Generator 2B Semi-Annual Test
21.6
Diesel Generator 1C Semi-Annual Test
15.3
Procedures
Diesel, Alternator, And Accessories Inspection
31.25
Work Orders (WO#
SNC)
1111522, 959067
Work Orders
Work Orders (WO)
SNC1133321, 957334
Plant Startup
51.11
Procedures
Normal Plant Shutdown
33.6
HPCI Operability
33.2
Procedures
Diesel Generator 2 A 24 Month Operability Test
7.2
Miscellaneous
FLT22010-01, 10 CFR 50.54(q)
Screening for NMP-EP147 Ver. 7.0, F04 Ver. 7.0,
F05 Ver. 5.0, F06 Ver. 3.0, F07 Ver. 5.0, F13 Ver. 3.0,
09/01/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
F14 Ver. 3.0, F15 Ver. 2.0, & F16 Ver. 2.0, dated
9/1/22
NMP-EP141
Event Classification, Ver. 3.0
NMP-EP144
Protective Actions, Ver. 8.0
Procedures
NMP-EP147
Offsite Dose Assessment Automated MIDAS, Ver. 7.0
Condition Reports (CR)
CRs 10907512, 10910270
Corrective Action
Documents
Corrective Action
Report (CAR)
Miscellaneous
NMP-OS007F01
4.0 Evaluation for Main Control Room Fire
11/27/2022
Fire Procedure
18.2
Procedures
NMP-ES035
7.0
SNC1061380
Control Room Emergency Lighting Quarterly Test
71152 A
Work Orders
SNC1377066
Control Room Fire
09/14/2022
SMNH19002
Plant Hatch NFPA 805 Monitoring Program - Scoping
2/05/2021
SMNH19003
Plant Hatch NFPA 805 Monitoring Program -
Qualitative Review
01/07/2021
SMNH19004
Hatch Units 1&2 NFPA 805 Monitoring Quantitative
Screening
2/05/2021
Calculations
SMNH19005
Hatch Units 1&2 NRPA 805 Monitoring Risk Target
Values
2/05/2021
Corrective Action
Documents
Condition Reports (CR)
10898080, 10633816, 10751486, 10766792,
10865147, 10869282, 10776921, 10777998,
10856781, 10857055, 10857108, 10678764,
10680332, 10768192, 10774901, 10776850,
10865470, 10874186, 10880527, 10888196,
10894678, 10778320, 10785119
Engineering
Evaluations
NMP-ES050F01
RER Response Form - Performance Based
Evaluation of Fire Damper Configurations
(SNC1244102)
10/17/2022
EOP Equipment Checks
18.3
Procedures
NMP-ES035018
NFPA 805 Monitoring Program
1.1
71152 S
Work Orders
Work Order (WO#
SNC)
1364935, 980070, 1010116, 1093155, 1098448,
1181658, 1305918, 937794, 937823, 980079,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
980080, 980081, 980798, 980800, 980801, 993157
Miscellaneous
NMP-ES005F01
Fire Protection Alternate Compensatory Measure
Evaluation for CR 10925361 Fire Main Rupture
11/21/2022