IR 05000321/2021010
| ML21309A011 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/04/2021 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Gayheart C Southern Nuclear Company |
| References | |
| EPID I-2021-010-0006 IR 2021010 | |
| Download: ML21309A011 (15) | |
Text
November 4, 2021
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000321/2021010 AND 05000366/2021010
Dear Ms. Gayheart:
On October 1, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Edwin I. Hatch Nuclear Plant. On September 30, 2021, the NRC inspectors discussed the results of this inspection with Mr. Sonny Dean and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
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,
/RA/
Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000321 and 05000366 License Numbers: DPR-57 and NPF-5 Report Numbers: 05000321/2021010 and 05000366/2021010 Enterprise Identifier: I-2021-010-0006 Licensee: Southern Nuclear Company Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, GA Inspection Dates: September 13, 2021 to October 01, 2021 Inspectors: T. Beck, General Engineer NRAN D. Hardage, Senior Resident Inspector S. Mendez-Gonzalez, Allegations Specialist R. Smith, Senior Resident Inspector N. Staples, Senior Project Engineer Approved By: Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Edwin I. Hatch Nuclear 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment (SCWE).
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth Corrective Action Program (CAP) review of the 600V Switchgear, 4160VAC/250DC Switchgear, and Reactor Pressure Vessel Isolation system.
- Operating Experience: The inspectors assessed the effectiveness of the stations processes for use of operating experience.
- Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensee's self-assessments and audits.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B 1. Corrective Action Program Effectiveness Problem Identification: The team determined that the licensee was effective in identifying problems and entering them into the corrective action program and that there was a low threshold for entering issues into the corrective action program. This conclusion was based on a review of the requirements for initiating condition reports as described in licensee procedures NMP-GM-002, "Corrective Action Program," NMP-GM-002-001, "Corrective Action Program Instructions," NMP-GM-002-002, "Effectiveness Review Instructions," and managements expectation that employees were encouraged to initiate condition reports. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.
Problem Prioritization and Evaluation: Based on the review of condition reports, the team concluded that problems were prioritized and evaluated in accordance with the condition report significance determination guidance in procedure NMP-GM-002. The team determined that adequate consideration was given to system or component operability and associated plant risk. The team determined that plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and that cause determinations were appropriate, and considered the significance of the issues being evaluated.
Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the team determined that corrective actions were mostly timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. For significant conditions adverse to quality, the corrective actions directly addressed the cause and generally prevented recurrence. The team reviewed condition reports and effectiveness reviews to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to prevent recurrence were mostly sufficient to ensure corrective actions were properly implemented and were effective.
Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.
2. Operating Experience The team determined that the station's processes for the use of industry and NRC operating experience information and for the performance of audits and self-assessments were effective and complied with all regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented to address lessons learned as needed.
3. Self-Assessments and Audits The team determined that the licensee effectively performed self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance.
Self-assessments were generally detailed and critical. The team verified that condition reports (CRs) were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.
4. Safety Conscious Work Environment Based on interviews with plant staff and reviews of the latest safety culture survey results to assess the safety conscious work environment on site, the team found no evidence of challenges to the safety conscious work environment. Employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 30, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Sonny Dean and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or Date
Procedure
71152B Calculations BPCCALC-385,V-1,B-9 Station Battery Room Hydrogen Calculation Unit 1 11/27/1992
and 2
71152B Calibration 10640117
Records
71152B Corrective Action Condition Reports 10810374, 10814269, 10815991, 10665395,
Documents 10758146, 10773773, 10784790, 10806706,
10774904, 10675289, 10651020, 10585063,
10604899, 10610185, 10579200, 10610186,
10708251, 10752156, 10755002, 10767351,
10767819, 10772386, 10772719, 10774323,
10788352, 10788453, 10807557, 10814865,
10710583, 10712793, 10714056, 10715356,
10719817, 10120249, 10704520, 10577066,
10577173, 10727122, 10727016, 10725720,
10724743, 10718509, 10706650, 10706493,
10750150, 10748800, 10743790, 10743498,
10740766, 10736020, 10789579, 10823230,
10791253, 10822020, 10823556, 10824457,
10825262, 10825340, 10816320, 10819300,
10819907, 10820706, 10821025, 10821850,
10821902, 10822259, 10823561, 10823876,
10823892, 10823905, 10823950, 10824756,
10825313, 10825533, 10662187, 10662149,
10661604, 10650975, 10783840 10778355,
10776562, 10772704, 10772155, 10769827,
10766134, 10750052, 10745551, 10741526,
10735005, 10718778, 10718442, 10708040,
10690497, 10683741, 10678493, 10669275,
10644531, 10614864, 10699432, 10699998,
10678493, 10703997, 10708040, 10718778,
10735005, 10660835, 10592769, 10602071,
10609381, 10622405, 10626003, 10626004,
Inspection Type Designation Description or Title Revision or Date
Procedure
10660686, 10699432, 10722398, 10707710,
10731466, 10751877, 10781504, 10650975,
10661604, 10712920, 10762384, 10599312,
10606612, 10611235, 10615416, 10619875,
10627164, 10664027, 10664660, 10670443,
10670472, 10671911, 10673941, 10692481,
10692486, 10692644, 10694510, 10696523,
10694529, 10700491, 10702773, 10702784,
10708690, 10709123, 10711792, 10711926,
10715734, 10774818, 10815641, 10649708,
10705382, 10656334, 10660375, 10611579,
10664675, 10666810, 10683569, 10784272,
10800630, 10709279, 10766856, 10821874,
10827881, 10684253, 10738488, 10700491,
10712920, 10762384, 10610185, 10610186,
10650074, 10314651, 10327810, 103333178,
10731466, 10657734,10675186, 10675289,
2011105213
71152B Corrective Action Corrective Action Report 276803, 277887, 275939, 276390, 277167,
Documents 277141, 276935, 276662, 276592, 275824,
275682, 275830, 278964, 277846, 275622,
277352, 277272, 277071, 276673, 276512,
276237, 279006, 276984, 276764, 275924,
278645, 277272, 278323, 278800, 275924,
277004, 277097, 277887, 275824, 279170,
275824, 276828, 277277, 276237. 276512,
276803, 276475, 276564,
71152B Corrective Action Condition Reports 10827368, 10827438, 10827440, 10827441,
Documents 10827444, 10827456, 10827458, 10827459,
Resulting from 10829100, 10829169,10831467, 10831471,
Inspection 10831472
71152B Drawings H-10018 Edwin
File System Sheet 1
71152B Drawings H-10196 Edwin
Inspection Type Designation Description or Title Revision or Date
Procedure
File System Sheet 2
71152B Engineering Technical Evaluation 1050145, 1060113, 1060093, 1060092, 1044116,
Evaluations 1043387, 1044112, 1044113, 1044114, 1044115,
1044117, 1044118, 1062788, 1047506, 1064163,
1064164, 1064165, 1050457, 1042139, 1048493,
1037636, 1040410, 1064324, 1064331, 1064327,
1064324, 1064728, 1052900, 1044918, 1044830,
1044832, 1044909, 1064902, 1038548, 1063781,
1059476, 1059928, 1059927, 1051712, 278055,
1061968, 1083801,1083802, 1083803, 1088275,
1054714, 1057814, 1050305, 1042135, 1042136,
1042137, 1042138, 1042139, 1042140, 1042141,
1074890, 1086458, 1089215, 1098216, 1098217
71152B Miscellaneous Action Tracking Number: Assess Cognitive Trend Among System Operators 01/21/2020
1050145 Including Tagging Events and Determine if
Training is a Solution
71152B Miscellaneous Annunciator and Plant 2-13-028P, 1-21-049, 1-21-051 & 1-21-030
Component (APC) Sheet
71152B Miscellaneous BOS Training 19-06 Initial Lessons Learned from U2 SJAE Event 0.0
71152B Miscellaneous C & D Technologies VLA Cell Cover Crack Impact to Safety-Related 03/07/2016
Function; Hydrogen Out Gassing
71152B Miscellaneous Case Study: Dose Rate Alarm Received in Unposted High 09/04,08,16/2020
CR10685808/TE1063781 Radiation Area and Training Attendance Sheets
71152B Miscellaneous H-EC-PP-19104 Hatch 2R25 Lessons Learned 1.0
71152B Miscellaneous H-LOCT-19-105 HIT - Command and Control, Decision-Making, 06/25/2019
Anticipate ED
71152B Miscellaneous H-NL-PP-SOCT-DLA- Clearance and Tagging Tagout Review DLA 07/20/2020
2007B
71152B Miscellaneous LR-PG-00763 Plant Hatch Operating Philosophy 3.0
71152B Miscellaneous LR-PG-00763 Plant Hatch Operating Philosophy 05/20/2019
71152B Miscellaneous MR SSC Function H-1(2) - B21 - Nuclear Boiler - B21-01 Pressure 11/12/2019
Consolidation and Control and B21-03 Rod Worth Minimizer
Performance Criteria
Selection Form
Inspection Type Designation Description or Title Revision or Date
Procedure
71152B Miscellaneous MRFF Assessment Function: 2T23-01: Primary Containment
71152B Miscellaneous NMP-GM-024-F04 Nuclear Safety Culture Leadership Team Report 05/19/2021 &
Template 01/14/2021
71152B Miscellaneous Plant Hatch Long Range Unit 1 & 2, PSW & RHRSW 1.0
Buried Piping
Replacement Plan
71152B Miscellaneous Plant Health Report Unit 1 and 2 B21 Systems 08/01/2021
71152B Miscellaneous PMCR 95795, 95796
71152B Miscellaneous S-2019-04 Standing Order - Actions To Improve Operations 1.0
Performance (Interim Actions)
71152B Miscellaneous SOCT 20-2 Training Report for System Operator Continuing
Training
71152B Miscellaneous Standing Order S-2021-4 - Calculating SBLC Storage Tanks Level 06/25/2021
71152B Procedures 34AB-B21-003-1 Failure of Safety/Relief Valves 10.1
71152B Procedures 34AR-652-207-2 Diesel GEN B Loading Timer Failure 3.3
71152B Procedures 34AR-R43-218-1 Diesel GEN 1B Loading Timer Failure 2.2
71152B Procedures 34GO-OPS-003-1 Startup System Status Checklist 14.8
71152B Procedures 34GO-OPS-003-2 Startup System Status Checklist 15.4
71152B Procedures 34SO-G11-013-1 Drywell & Reactor Building Sumps System 15
71152B Procedures 34SO-G11-013-2 Drywell and Reactor Building Sumps Systems 2.1
71152B Procedures 34SO-T48-002-2 Containment Atmospheric Control and Dilution 02/12/2021
Systems
71152B Procedures 51GM-TOL-002-0 Control of I&C Measuring and Test Equipment 6.6
71152B Procedures 52GM-MME-015-1 Reactor Vessel Disassembly 22.5
71152B Procedures 64CI-OCB-001-0 Main Stack Radiation Monitoring 13.6
71152B Procedures NMP-AD-012 Operability Determination 14.0
71152B Procedures NMP-GM-002 Corrective Action Program 16.0
71152B Procedures NMP-GM-002-001 Corrective Action Program Instructions 41.0
71152B Procedures NMP-GM-002-002 Effectiveness Review Instructions 5.3
71152B Procedures NMP-GM-002-GL03 Cause Analysis and Corrective Actions Guideline 30.2
71152B Procedures NMP-GM-016-002 Non-Corrective Action Program (CAP) Business 6.0
Item Instructions
Inspection Type Designation Description or Title Revision or Date
Procedure
71152B Procedures NMP-GM-024 Nuclear Safety Culture Program 9.1
71152B Procedures NMP-GM-024-001 Nuclear Safety Culture Monitoring and Review 11.0
Process
71152B Procedures NMP-MA-053 SNC Maintenance Department Measuring and 2.3
Test Equipment Program (M&TE)
71152B Procedures NMP-OS-003-F01 Operational Decision-Making Worksheets - 1-20-
006, 1-21-002, 1-21-003, and 2-21-002
71152B Procedures NMP-OS-006-002 Aggregate Operator Impact Review Instruction 4.0
71152B Procedures NMP-OS-006-002 Attachment 1 Plant Hatch - Issue Challenging 09/29/2021
Operation of the Unit 1 and 2
71152B Procedures NMP-OS-007-001 Conduct of Operations Standards and 18.1
Expectations
71152B Procedures NMP-OS-026 License Administration 2.1
71152B Procedures NMP-OS-026 License Administration 2.1
71152B Procedures NMP-OS-026-F02 Senior Reactor Operator Reactivation for Core 1.0
Alterations
71152B Procedures NMP-OS-028 Adverse Condition Monitoring Plans - 2B CBP
Seal Leakage, 1A SJAE, and Unit 1 TB Chilled
water System 1P63 & Leakage Detection system
1U61
71152B Procedures NMP-OS-26-F02 Senior Reactor Operator Reactivation for Core 1.0
Alterations
71152B Procedures NMP-SE-021 Security Search Processes 9.0
71152B Procedures NMP-TR-210-F01 Performance Analysis Worksheet - 1043387 07/30/2019
71152B Procedures SCM-PSC-002 Control of Supply Chain Department Measuring 10.0
and Test Equipment
71152B Self- Fleet-MNT-2019 Nuclear Oversight Audit of Maintenance 01/11/2019
Assessments
71152B Self- NMP-GM-003-F19 Pre--NRC 71111.11 Inspection 07/02/2020
Assessments
71152B Work Orders SNC27631,
SNC1064135,
SNC1060123,
SNC1061680,
Inspection Type Designation Description or Title Revision or Date
Procedure
SNC1104277,
SNC1166158,
SNC1168821,
SNC1168823,
SNC1170060,
SNC1178535,
SNC1141325,
SNC865287,
SNC1119363,
SNC1094683,
SNC1104709,
SNC1125938,
SNC641095,
SNC624498,
SNC1145010,
SNC1144098,
SNC1141706,
SNC1141472,
SNC1071304,
SNC1064135,
SNC1060123,
SNC1099581,
SNC942938, SNC99646,
SNC1141706,
SNC1145010,
SNC534219,
SNC613456,
SNC1057178,
SNC1069622,
SNC1058876,
SNC1069175,
SNC632608,
SNC579408
2