IR 05000382/2023040

Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter

ML23192A764
Person / Time
Site:	Waterford
Issue date:	07/12/2023
From:	Geoffrey Miller NRC Region 4
To:	Ferrick J Entergy Operations
Shared Package
ML23191A900	List: IR 05000382/2023040
References
EA-22-033, EA-22-119, EA-23-036 IR 2023040
Download: ML23192A764 (26)

Text

July 12, 2023

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REVISED 95001 SUPPLEMENTAL INSPECTION REPORT 05000382/2023040, EXERCISE OF ENFORCEMENT DISCRETION, AND FOLLOW-UP ASSESSMENT LETTER

Dear John Ferrick:

On May 16, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection using Inspection Procedure 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs at the Waterford Steam Electric Station, Unit 3 (Waterford). The results of this inspection were originally issued in a report, dated June 2, 2023 (Agencywide Document Access and Management System (ADAMS) Accession No.

ML23145A227.

The NRC staff subsequently determined that due to in-process revisions to Inspection Manual Chapter 0305 at the time of the report issuance and an administrative oversight, the associated cover letter incorrectly noted that the associated violation would be considered for agency actions through December 31, 2023. This statement is incorrect. As discussed in the original cover letter, the following paragraph remains correct, Overall, the NRC determined that Waterfords problem identification, causal analyses, and corrective actions sufficiently addressed the performance issues that led to the two White violations. All inspection objectives, as described in Inspection Procedure 95001, were met, and this inspection is, therefore, closed.

With the closure of the two White violations, and as a result of our continuous review of plant performance, the NRC has updated its assessment of Waterford. This assessment supplements, but does not supersede, the end of cycle letter issued on March 1, 2023. Based on successful completion of the supplemental inspection, and issuance of this inspection report, Waterford has transitioned to the licensee response column of the NRC Action Matrix (Column 1) as of the date of the exit meeting. Therefore, Waterford transitioned to Column 1 at the time of the exit meeting on May 16, 2023.

In addition, the subject of the cover letter should have also included follow-up assessment as discussed within the letter itself. These changes have no other impact on the findings documented in this report, but consistent with NRC process, this report is being reissued in whole. In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room and from the NRCs ADAMS, accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html.

Sincerely, Signed by Miller, Geoffrey on 07/12/23 Geoffrey B. Miller, Director (Acting)

Division of Radiological Safety & Security Docket No. 05000382 License No. NPF-38

Enclosure:

Supplemental Inspection Report 2023040

Inspection Report

Docket Number: 05000382 License Number: NPF-38 Report Number: 05000382/2023040 Enterprise Identifier: I-2023-040-0000 Licensee: Entergy Operations, Inc.

Facility: Waterford Steam Electric Station, Unit 3 Location: Killona, LA Inspection Dates: February 27, 2023 to May 16, 2023 Inspectors: S. Hedger, Senior Emergency Preparedness Inspector D. Antonangeli, Health Physics Inspector Approved By: Beth S. Alferink, Chief (Acting)

Response Coordination Branch Division of Radiological Safety & Security Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an inspection procedure 95001 supplemental inspection at the Waterford Steam Electric Station, Unit 3, 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

Type Issue Number Title Report Section Status NOV 05000382/2022091-01 Failure to Maintain Accurate 95001 Closed Dose Assessment Methods EA-22-119 NOV 05000382/2022501-01 Failure to Maintain Accurate 95001 Closed EAL Thresholds and Dose Assessment Methods EA-22-033 EDG EA-23-036 Main Steam Line B 95001 Closed Radiation Monitor (ARMIRE5500B) - Dose Assessment (Example 1)

EDG EA-23-036 Boron Waste Management 95001 Closed and Liquid Waste Management Radiation Monitors (PRMIRE0627,

PRMIRE0547) - Emergency Action Level Classification (Example 2)

EDG EA-23-036 Fuel Handling Building 95001 Closed WRGM Mid-Range Detector (PRMIRE3032) -

Emergency Action Level Classification and Dose Assessment (Example 3)

EDG EA-23-036 Containment High Range 95001 Closed Radiation Monitors A and B (ARMIRE5400AS,

ARMIRE5400BS) -

Emergency Action Level Classification (Example 4)

EDG EA-23-036 Main Steam Line A 95001 Closed Radiation Monitor (PRMIRE5500A) - Dose Assessment (Example 5)

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.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===95001 - Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs The inspectors reviewed and selectively challenged aspects of the licensees problem identification, causal analysis, and corrective actions in response to two White findings in the Emergency Preparedness cornerstone. The NRC communicated the licensees entry into Reactor Oversight Process Action Matrix Column 2, Regulatory Response Column, in the cover letter of NRC Inspection Report 05000382/2022090, dated September 12, 2022 (Agencywide Document and Management System (ADAMS) Accession Number ML22241A143). Further, the NRC indicated with the second White finding that licensee performance continued to be assessed in Action Matrix Column 2 in the cover letter of NRC Inspection Report 05000382/2023090, dated February 1, 2023 (ML23035A384). The findings are summarized below:

The licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2). Specifically, the licensee failed to maintain a standard emergency classification scheme as required by 10 CFR 50.47(b)(4) because PRM-IRE-0002 (condenser exhaust wide range gas monitor, mid and high range detectors) had errors in its output that could result in an over-classification up to a General Emergency, resulting in unnecessary public protective actions. Also, the licensee failed to use adequate methods, systems, and equipment for assessing and monitoring actual and potential offsite consequences of a radiological emergency as required by 10 CFR 50.47(b)(9), because those same errors would result in inaccurate dose assessments for a radiological release through the main condenser exhaust.

The licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2). Specifically, the licensee failed to use adequate methods, systems, and equipment for assessing and monitoring actual and potential offsite consequences of a radiological emergency as required by 10 CFR 50.47(b)(9),because the licensee had conversion factor errors that would result in inaccurate dose assessments for a radiological release through the plant vent stack exhaust path.

The correspondence communicating the changes in action matrix status documented the issuance of two White Notices of Violation (NOVs). For the first White NOV, the licensee responded in correspondence submitted on October 12, 2022 (ML22285A214). The licensees response to the second White NOV was documented on February 20, 2023 (ML23051A002).

The inspectors reviewed these responses as part of the inspection.

The licensee staff informed the NRC staff by letter, dated February 15, 2023, of their readiness for this supplemental inspection (ML23046A375). The licensee performed three root cause evaluations (RCEs) in preparation for the inspection to identify the process and organizational weaknesses that resulted in the two White findings. The key RCEs reviewed were:

RCE CR-WF3-2022-3999, Condenser Wide Range Gas Monitor RD72 Incorrect Calibration Methodology, Revisions 1 through 3 RCE CR-WF3-2022-6367, Incorrect Calibration of Wide Range Gas Monitors Used in Emergency Response Procedures, Revisions 1 through 3 RCE CR-WF3-2022-7836, Waterford 3 Steam Electric Station Collective Review of Radiation Monitors Issues, Revisions 1 through 3 As part of the evaluations, the licensee also assessed their safety culture to identify any contribution to the root or contributing causes. In addition, due to their having two White Action Matrix inputs, the licensee conducted a common-cause analysis to assess potential programmatic weaknesses in performance (RCE CR-WF3-2022-7836). The licensee provided the NRC inspectors a copy of their RCEs on February 16, 2023, along with other supporting evaluations and documentation by February 21, 2023. Subsequently, the NRC performed the onsite portion of this supplemental inspection during the week of February 27-March 3, 2023.

The objectives of this supplemental inspection included the following:

Provide assurance that the root causes and contributing causes of risk-significant performance issues were understood.

Provide assurance that the extent of condition and extent of cause of risk-significant performance issues were identified.

Provide assurance that the licensees corrective actions for risk-significant performance issues were sufficient to address the root and contributing causes and prevent recurrence.

Evaluate additional examples of failures to maintain the effectiveness of the Waterford Steam Electric Station, Unit 3 emergency plan occurring between 1987 and February 27, 2023, as identified by the licensee through their review of legacy radiation monitor calibration practices, supporting technical documentation maintenance, and equipment maintenance issues, as part of their overall corrective action review for the two White findings.

The inspectors reviewed the licensees RCEs and other corrective action program evaluations the licensee conducted in support of, or as a result of, the RCEs. The inspectors reviewed corrective actions that the licensee had taken to address the identified causes. The inspectors also held discussions, conducted field walkdowns reviewing subject radiation monitoring equipment, and conducted interviews with licensee personnel to determine if the root and contributing causes, and the contribution of safety culture components, were understood, as well as whether completed or planned corrective actions were adequate to address the causes and prevent recurrence.

Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs

=

(1) This supplemental inspection is being conducted in response to the licensee being placed in the Regulatory Response column due to two White findings in the Emergency Preparedness Cornerstone.

INSPECTION RESULTS

Assessment 95001 1) Problem Identification a) Identification The issues resulting in the two White findings were identified by the licensee. The situations leading to their identification are described in detail within the Event Narrative of RCE CR-WF3-2022-3999 and CR-WF3-2022-6367.

RCE CR-WF3-2022-3999 - Reviews of questions involving the licensees maintenance of calibration source information led to a review of calibration documentation and performance starting in late 2021. On January 18, 2022, the licensee identified that the main condenser wide range gas monitor (WRGM) mid- and high-range detectors post replacement calibrations did not correctly account for source decay correction.

RCE CR-WF3-2022-6367 - Engineering reviews of post-corrective maintenance documentation on September 8, 2022, revealed engineering conversion factors for the plant stack WRGM had been updated with incorrect values on June 6, 2022.

b) Exposure Time The issues had the following exposure times:

RCE CR-WF3-2022-3999 - The main condenser WRGM detectors had been in this condition since January 18, 2011, until February 4, 2022 (approximately 11 years).

RCE CR-WF3-2022-6367 - The plant stack WRGM high-range detectors had incorrect factors in use from June 6, 2022, until September 11, 2022 (approximately 97 days).

c) Identification Opportunities The licensee had multiple prior opportunities to identify the conditions leading to the two White findings, including operating experience, previous detector failures, response to previous regulatory issues with calibration and maintenance practices, and system reviews. The licensees RCEs sufficiently addressed these prior opportunities to identify these conditions, as discussed below.

d) Risk and Compliance With emergency preparedness issues being evaluated from a deterministic perspective, no formal risk analysis was performed for the two White findings.

However, using the existing criteria, the two issues had violations of White significance issued in their respective inspection reports. The licensee did evaluate the risk and consequences as part of the Analysis of Risk and Safety Consequences sub-section of Section 3.0, Analysis of the Event, in each RCE. The described consequences and risk insights were consistent with the NRC assessments.

NRC Assessment:

The inspectors determined that the licensee had multiple opportunities to identify and address the conditions that led to the White findings, prior to their recent licensee identification.

However, the root and common cause evaluations adequately addressed prior opportunities to identify. The licensee appropriately understands the risk and compliance aspects of the White findings.

2) Causal Analysis a) Methodology The RCE for the first White finding (CR-WF3-2022-3999) employed multiple causal analysis methods to identify root and contributing causes. Methods included a comparative timeline, event, and causal factor charting; barrier analysis, organization and programmatic screening; and performance gap analyses.

For the second White finding RCE (CR-WF3-2022-6367), the licensee used similar causal analysis methods to the first, with additional ones added in the effort to identify root and contributing causes. Methods included event and causal factor charting; barrier analysis, task analysis, performance gap analyses, organizational and programmatic screening; and human performance evaluation.

To identify additional broader root or contributing causes related to both White findings, the common-cause analysis RCE (CR-WF3-2022-7836) utilized similar analysis tools.

Common methods included event and causal factor charting (including Why Trees);barrier analysis, and organization and programmatic screening. In addition, the licensee employed a common cause analysis. The scope for using these tools included not only the events associated with the two White findings, but also other radiation monitoring system (RMS) events captured in the corrective action program over the previous two years.

The inspectors determined that the different methods provided a reliable and scrutable evaluation. Also, the inspectors determined these analyses were performed with sufficient rigor to identify root and contributing causes.

b) Level of Detail The inspectors determined that each of the three RCEs was of sufficient detail commensurate with the significance and complexity of the issues and regulatory requirements.

c) Operating Experience For each of the three evaluations, the licensee conducted reviews of internal and external operating experience. The reviews looked for occurrences of same or similar performance issues where knowledge gained could be used to improve the evaluation.

RCE CR-WF3-2022-3999: Review of internal operating experience found one issue previously identified that had applicability to this evaluation: a 2009 issue where questions regarding the appropriate actions and calibration procedure accuracy with respect to a RD-72 detector replacement in the plant stack WRGM mid-range detector (CR-WF3-2009-1101). Additional text addressing calibration practice review after detector replacement was added to an existing RMS desk guide (MI-005-906), but no requirements to review and revise calibration procedures were implemented. This was a missed opportunity to identify the lack of direction to correctly replace and calibrate WRGM RD-72 detectors. Regarding external operating experience the licensee found that there were missed opportunities to detect the White finding based on review of NRC Information Notice 2013-13 and RMS users group feedback on engineering conversion factor replacement requirements with detector replacements (CR-WF3-2022-0284). The inspectors concluded the operating experience review was appropriate.

RCE CR-WF3-2022-6367: Internal operating experience review considered whether reviews of the RMS database update process were appropriate while evaluating and correcting the first White finding (CR-WF3-2022-0284, -3999). However, since the first White finding involved historical technical errors in WRGM calibration methods, and dealt with RMS factor database configuration control processes, the issues appeared to be separate. Regarding external operating experience, the licensee concluded there were no specific opportunities where instrument database configuration control events could have resulted in this issue being avoided. The inspectors concluded that the operating experience review was appropriate.

RCE CR-WF3-2022-7836: Internal operating experience review included events with all types of RMS equipment over the last two years. These provided input in the common cause analysis conducted within the evaluation. Regarding external operating experience the licensee found that there were missed opportunities to detect the White findings based on review of NRC Information Notice 2013-13 and other industry information. The inspectors concluded that the operating experience review was appropriate.

d) Extent of Condition and Cause RCE CR-WF3-2022-3999: The extent of condition started with the review of methodology used to calibrate WRGM detectors needing calibration after replacement.

The same condition was confirmed to exist in other WRGM detectors. Based on this, the licensee extended the review to include all other radiation detectors that need calibration after replacement. There was the potential that inadequate calibration practices mentioned as part of the root cause statement affected other radiation monitors at the plant. Therefore, an additional expansion in review scope took place, including site radiation monitors with questions about their calibrations with same or similar conditions to those originally being evaluated. In some cases, the licensee identified radiation monitor issues that constituted failures to maintain the effectiveness of the emergency plan. This resulted in identification of the following:

Conflicts between directions in Procedure MI-005-906, Radiation Monitor System Desk Guide, and specific radiation monitor calibration procedures, led to incorrect calibration practices.

Additional radiation monitors were found to be out of calibration with similar conditions. This included WRGMs and area radiation monitors which support emergency preparedness, Technical Specifications, and other licensing basis assumptions. Some examples are detailed in the enforcement discretion descriptions (examples 2, 3, and 4).

Detectors calibrated without calibration certificates being maintained.

Detectors with incorrect supporting equipment installed. An example is detailed in the enforcement discretion descriptions (example 4).

Detectors not calibrated on required intervals.

Area radiation monitor calibrations that did not account for needed calibration practice changes based on changes in equipment configuration and design basis changes. An example is detailed in the enforcement discretion descriptions (example 5).

The extent of cause scope included a review of all radiation detector calibration procedures and instrument calibrations to see if changes made over the years had resulted in calibration methodologies that were invalid in some respect. This was because the licensee recognized the practice of making procedural changes without adequate technical reviews, a key part of the root cause, most likely caused issues elsewhere. For the procedure change review process, it was identified that past efforts to ensure cross discipline reviews of technical procedure changes with supporting documentation, using document W2.109, Procedure Development, Review &

Approval, were incomplete. Therefore, changes were needed in the process (CR-WF3-2022-3999, CA-04) (associated with enforcement discretion example 1). This lack of adequate procedure change reviews contributed to an example in the enforcement discretion descriptions (example 2). This resulted in identification of the following:

Calibration procedures lacked transfer calibration datasheets, as well as steps for correct detector replacement.

Area radiation detectors did not have their specific reference values and dates of calibration.

Area radiation detectors did not have their own isotope half-life calculation worksheets.

The inspectors concluded that the licensees root cause evaluation adequately addressed the extent of condition and extent of cause.

RCE CR-WF3-2022-6367: The extent of condition review included an assessment of computer database constant values for the WRGMs in the plant, as well as other radiation monitors that have computer database constant values maintained. The values were compared with the controlled printed copy of the database values located in the control room. Further, the controlled database values were verified versus vendor information to ensure that the controlled copy had the correct values. This resulted in identifying needed corrections in another electronic reference set of the controlled values, separate from those used for controlling the radiation instrumentation, as well as actions to check engineering changes and work orders over the last two years to see if they had any effects on the computer database constant values being maintained.

The extent of cause included review of equipment important to emergency response with digital parameters that could be negatively affected if configuration control is not completed correctly for parameter changes. Control mechanisms of other documentation that can affect RMS equipment function, both licensee-developed and vendor supplied, were part of this review as well. The inspectors concluded that the licensees root cause evaluation adequately addressed the extent of condition and extent of cause.

RCE CR-WF3-2022-7836: The extent of condition review was largely an assessment to see if extent of condition items identified in the other two RCE addressed the appropriate scope. The licensee added an additional review to CR-WF3-2022-6367 to perform a comprehensive evaluation for other potential conditions affecting radiation monitors that could create vulnerabilities for operability or functionality. The extent of cause reviewed the root and contributing causes from the other two RCEs to identify any gaps in scope for corrective action that may have existed. Of note, this review identified that earlier efforts with RCE CR-WF3-2022-3999 ensuring technically defensible reviews of procedure changes using Procedure W2.109 were not fully effective (CR-WF3-2022-7836, CA-08). Therefore, actions addressing the procedure change review process were re-opened and addressed as a root cause in this evaluation (focus of enforcement example 1). The inspectors concluded that the licensees root cause evaluation adequately addressed the extent of condition and extent of cause.

e) Safety Culture The licensee addressed the safety culture aspects of the events within each of the three evaluations. In each, there was a provided matrix discussing each of the performance issues resulting in the subject White finding(s) with respect to each of the safety culture traits noted in NUREG-2165, Safety Culture Common Language. The licensee provided appropriate corrective actions for any of the performance deficiencies that aligned with safety culture aspects. The inspectors concluded that the licensees root cause evaluation appropriately considered safety culture traits.

NRC Assessment:

The licensee identified the following root causes and contributing causes for each of the problem identification statements associated with the three RCEs:

RCE CR-WF3-2022-3999 Root

Cause:

Technical reviews of procedure revisions to MI-003-387, Condenser Vacuum Pump Discharge Wide Range Noble Gas Radiation Monitor Channel Calibration PRMIR0002, were inadequate to account for validation methodology changes to ensure proper setup and calibration to within requirements for dose assessment for the RD-72 detectors (detector type in WRGMs).

Contributing Cause 1: The instrumentation and control (I&C) maintenance group had not established requirements for calibrating the RD-72 detector to account for infrequent performance and unique requirements for calibration when the detector is replaced.

Contributing Cause 2: The I&C maintenance group had not obtained equipment to validate specific count rates for replaced equipment or utilized vendor support with available equipment (for example, a Multi-level Channel Analyzer) to verify detector replacement setup is adequate.

Contributing Cause 3: Standards had not been reinforced for the I&C maintenance group to incorporate lessons learned from post maintenance activities when additional information was required to complete task.

Contributing Cause 4: Condition Reports related to calibration and replacement of the RD-72 detectors had not been screened appropriately to require thorough evaluation (level of evaluation and extent of condition) and effective corrective actions assigned.

This would have identified proper calibration actions after detector replacement and would have provided assessments of equipment post-calibration ensuring the tasks were completed correctly.

RCE CR-WF3-2022-6367 Root

Cause:

The configuration control process for radiation monitoring system (RMS)monitors (Procedure UNT-007-029, Control of the Radiation Monitoring System Database) had not been consistently implemented for the affected equipment.

Verification that the RMS data and documentation was complete, accurate, and up-to-date was not consistently occurring when returning equipment to service.

Contributing Cause 1: Engineering and I&C Maintenance supervision had not reinforced standards with their personnel requiring documentation to be maintained complete, accurate, and up-to-date for radiation monitoring equipment.

Contributing Cause 2: WRGM calibration and functional test instructions were not explicit as to what actions were needed to verify accuracy of RMS databases, what information should be maintained for documentation, and what documentation is required to be up-to-date and accurate prior to return to service.

Contributing Cause 3: Previous corrective actions had focused specifically on correctly updating the equipment data points and the technical procedure for replacing RD-72 detectors. Corrective actions did not fully evaluate the administrative process for updating the RMS database, leading to unforeseen issues after return to service.

RCE CR-WF3-2022-7836 Root Cause 1: Historic technical issues with RMS maintenance instructions were not identified and addressed during the procedure revision process.

Root Cause 2: Maintenance instructions and change processes did not have clear guidance that would ensure documentation for radiation monitoring systems was maintained up-to-date and accurate.

Contributing Cause 1: I&C maintenance and engineering management had not been enforcing corporate standards for procedural use and adherence. This includes processes for updating procedures and performance of maintenance activities on RMS equipment.

Contributing Cause 2: I&C maintenance and engineering management had not ensured internal and external operating experiences, including industry best practices, had been integrated into the RMS program and processes.

Contributing Cause 3: Plant management had not ensured that risks were identified, evaluated, and mitigated for radiation monitoring maintenance activities through systematic methods to ensure acceptable outcomes.

Contributing Cause 4: Historic corrective action process reviews associated with prior RMS deficiencies have not resulted in aggregate reviews to identify larger issues.

Contributing Cause 5: Program governance had not been adequately established, ensuring that periodic assessments and benchmarking activities resulted in system improvements.

The inspectors determined that each of the three RCEs appropriately identified and documented the root and contributing causes for the associated problem statements and identified the appropriate extent of cause and condition.

3) Corrective Actions RCE CR-WF3-2022-3999 a) Corrective Actions to Preclude Repetition

(1) Completed

(a) Revised the Fuel Handling Building WRGM calibration procedure (MI-003-371) to include calibration instructions when replacement of a RD-72 detector replacement is required. Revisions address use of a multi-channel analyzer for replacement activities.

(b) Revised the Plant Stack WRGM calibration procedure (MI-003-383) to include calibration instructions when replacement of a RD-72 detector replacement is required. Revisions address use of a multi-channel analyzer for replacement activities.

(c) Revised the Main Condenser WRGM calibration procedure (MI-003-387) to include calibration instructions when replacement of a RD-72 detector replacement is required. Revisions address use of a multi-channel analyzer for replacement activities.

The effectiveness reviews for the Corrective Action to Preclude Repetition (CAPR)involved an independent technical review of actions taken and produced documentation following the next calibration following a RD-72 detector replacement in one of the three subject WRGMs. The inspectors concluded that the licensee has identified an appropriate effectiveness review for RCE CR-WF3-2022-3999.

b) Other Corrective Actions

(1) Completed

(a) Completed calibration verifications of multiple site radiation monitors due to questions raised about past calibration practices, calibration equipment usage, and maintenance or correct supporting documentation. Initiated and completed corrective maintenance as identified (extent of condition and cause).

(b) Revised WRGM calibration procedures to include transfer calibration datasheets.

(c) Revised Procedure W2.109, Procedure Development and Approval, to include independent technical review (engineering cross-discipline reviews at minimum) for proposed revisions changing the methodology for completing tasks, as well as changing the equipment used to address a task.

(d) Updated radiation monitor engineering basis documentation to ensure it is based on the most accurate source information.

(e) Revised other radiation detector calibration procedures (non WRGM) to ensure that correct calibration methodology following detector replacement was documented. In addition, revised these procedures to ensure that correct calculations and reference documentation will be maintained with subsequent calibrations.

(f) Updated I&C maintenance group training to better address infrequent activities such as detector replacement practices.

(g) Revised arrangements and plans for RD-72 detector replacements to ensure that appropriate equipment and expertise are involved replacement activities.

(h) Documented risk mitigation expectations for site management, providing training on site-wide expectations.

(i) Revised both corrective action and performance improvement process documentation to better address the level of rigor desired in condition report reviews.

RCE CR-WF3-2022-6367 a) Corrective Actions to Preclude Repetition

(1) Completed

(a) Revised RMS calibration procedures with instruction ensuring database values are maintained complete, accurate, and up to date prior to returning affected equipment to service.

(b) Define reviewer and supervisor roles ensuring database values are addressed during maintenance correctly. Individuals in these roles ensure any database value change is implemented correctly as required.

(c) Define engineering reviews for database value changes to ensure impacts are reviewed and addressed prior to returning affected equipment to service.

The effectiveness reviews for the CAPR involve a sample review of work activity documentation associated with replacement and calibration of radiation monitors.

This review activity will verify that correct vendor information is being documented, actions to ensure accurate database values are in place and are being completed appropriately, supervisory reviews are correctly being performed, and that engineering reviews of proposed changes are taking place correctly. The inspectors concluded that the licensee has identified an appropriate effectiveness review for RCE CR-WF3-2022-6367.

b) Other Corrective Actions

(1) Completed

(a) Performed a review of RMS database values in place to ensure that correct ones are being used for all associated radiation monitors.

(b) Reviewed work orders over the last two years affecting radiation monitors to see if anything affecting database values was being documented correctly and updated in the respective database.

(c) Reviewed radiation monitor database values and supporting basis documentation to ensure that traceability of correct values can be established to support their design functions.

(d) Established and communicated standards for RMS database value maintenance to engineering and I&C maintenance supervision. Standards were documented in observation tools used by supervision to ensure that activities affecting the RMS database values are addressed appropriately.

(e) Revised radiation monitor calibration and functional test procedures (not just those affecting WRGMs) to include database value verification activities before and after doing work affecting the associated monitor. This included line-by-line independent verification of actions steps, and revisions to technician training on completing these tasks.

(f) Provided training on the RMS database change process to ensure staff understand standards to improve audit quality and issue identification. Also included was an action to audit the database change process semiannually.

RCE CR-WF3-2022-7836 a) Corrective Actions to Preclude Repetition

(1) Completed

(a) Root Cause 1: Revised Procedure W2.109, Procedure Development and Approval, with direction in the editorial review process ensuring that proposed changes get categorized as editorial or non-editorial changes properly. This procedure revision ensures that technical issues are reviewed by the appropriate licensee personnel. This was an additional action beyond what was taken as part of corrective actions associated with RCE CR-WF3-2022-3999 addressing a gap in previous efforts ensuring calibration procedure changes get appropriate cross discipline reviews and have technical background documentation supporting the changes adequacy.

(b) Root Cause 2: No additional corrective actions were identified following review of RCE CR-WF3-2022-7836. CAPR RCE CR-WF3-2022-6367 (a)(1)remains sufficient to address maintenance instructions and change processes.

The effectiveness review for the CAPR involves sampling calibration procedure changes to see if the changes to Procedure W2.109 are being implemented as designed. This will involve reviewing the procedure change documentation, as well as radiation monitor work orders and condition reports to see if the RMS database values are being maintained up to date, and if there are any other needed corrections to see if any issues with radiation monitor procedures and equipment are being identified that were previously missed. The inspectors concluded that the licensee has identified an appropriate effectiveness review for RCE CR-WF3-2022-7836.

b) Other Corrective Actions

(1) Completed - None

(2) Planned

(a) Perform an independent technical review of site maintenance instructions for radiation monitors using vendor technical guidance. Identify any discrepancies and address them using the corrective action program.

(b) Complete a health assessment of the RMS in the next year. Document any identified common deficiencies, repetitive issues, and outstanding maintenance activities which could negatively affect the systems health.

(c) Perform a review of procedure revisions categorized as editorial changes over the last 24 months to see if the process described in Procedure W2.109 was followed correctly. This involves radiation protection procedures, as well as other types of procedures onsite (extent of cause).

(d) Complete training on lessons-learned and desired behaviors in procedural adherence for leadership, managers, and supervisors. Leaderships observation tools for work will be reviewed and documentation from required observations will be evaluated to verify training effectiveness.

(e) Incorporate lessons learned from response to the two White findings into the model work orders used for radiation monitor work activities.

(f) Perform a radiation monitor program self-assessment on a 12-month periodicity. This is to ensure RMS equipment parameters are being maintained accurately, and calibrations are being performed error-free.

NRC Assessment:

The inspectors determined that the licensee implemented or planned appropriate and timely corrective actions to preclude repetition. The licensee also identified appropriate effectiveness reviews for these actions. With respect to evaluating the licensees response to the two White NOVs, the licensee demonstrated actions addressing the reasons for the violations, have taken or planned for corrective actions with achievable results, and have addressed restoration of full compliance. The inspectors identified the following weaknesses/performance deficiencies (no significant weaknesses identified) in this inspection:

Weaknesses:

The inspectors identified that one of the actions for the first White findings root cause (RCE CR-WF3-2022-3999, RC-CA4) was appropriately identified, but was not appropriately implemented. Corrective action to revise document W2.109, Procedure Development, Review & Approval, included revising parts of the process to include independent technical reviews (cross-discipline, at a minimum including engineering)for revisions changing methodology or equipment requirements to carry out tasks.

While procedure changes were implemented to address this as part of the normal procedure revision process, no changes were made in the Editorial Correction (EC)

Review Process to ensure that proposed changes, which were not editorial by nature, were identified, and assigned the necessary independent technical reviews. As a result, this contributed to the issue with Main Steam Line B Radiation Monitor ARMIRE5500B not reading correctly in October-November 2022 (CR-WF3-2022-6367) (see enforcement discretion example 1). However, the inspectors noted the licensee reevaluated this process issue in RCE CR-WF3-2022-7836; elevating actions from a contributing cause to a CAPR; and completing the new actions in a prompt manner, which fully addressed process vulnerabilities.

The inspectors identified that appropriate measures of success for the CAPR with RCE CR-WF3-2022-3999 had not been developed such that the corrective actions effectiveness would be evaluated. This involved an effectiveness review assessing calibration effectiveness of RD-72 detectors after replacement. As was stated in Section 8.0 of the RCE, the time standard for conducting this effectiveness review would be completed at the next detector calibration after CAPR completion. Since the next RD-72 detector calibration may occur for various situations, one of which is if there is a detector replacement, the scope of when the effectiveness review could be completed may be implemented for a calibration activity that does not include the appropriate circumstances to measure corrective action effectiveness. In addition, the reviews success criteria did not include qualitative measures for evaluation. The licensee initiated actions to revise the effectiveness reviews scope addressing this issue in CR-WF3-2023-01052.

4) Conclusion Overall, the inspectors determined that the licensees problem identification, causal analyses, and corrective actions sufficiently addressed the performance issues that led to the two White findings. All inspection objectives, as described in the Inspection Procedure 95001, were met.

Scheduled corrective action items will be inspected as part of the ongoing NRC baseline inspection program. Therefore, this inspection is closed.

Enforcement Discretion Enforcement Action EA-23-036: Main Steam Line B 95001 Radiation Monitor (ARMIRE5500B) - Dose Assessment (Example 1)

Description:

During the licensees extent of cause reviews associated with RCEs CR-WF3-2022-3999 and CR-WF3-2022-6367, they broadened the scope of their corrective actions to look at all radiation monitor detector replacements and the associated procedures.

The licensee added steps into their procedure change process to include independent technical reviews of procedure changes associated with calibration methodology. However, a subject matter expert evaluation of the detector replacement of Main Steam Line B Radiation Monitor on October 20, 2022, resulted in the monitor being declared inoperable since it was replaced (CR-WF3-2022-07376). Based on a causal analysis review, a calibration after the monitor was replaced did not take place and was required to restore operability. In 2022, the procedure MI-003-389 was revised to include steps for detector replacement. However, no independent technical review of this procedure change occurred, which could have recognized the error of no calibration required after install being in the revised procedure. As a result, there was no radiation monitor calibration after detector replacement in October 2022. For ARMIRE5500B, during the affected time, the monitor would read 40 percent lower than it was supposed to. The normal calibration range is plus or minus 10 percent. Similar to RCE CR-WF3-2022-3999 and RCE CR-WF3-2022-7836, technical reviews of the change to Procedure MI-003-389 were inadequate in order to ensure proper setup and calibration of the Main Steam Line B Radiation Monitor after replacement to within requirements for dose assessment.

The inoperable radiation monitor resulted in a failure to comply with a risk significant planning standard (RSPS), with a degraded RSPS function. This is due to there being some cases in which the dose projection process would be incapable of providing technically adequate estimates of radioactive material releases to the environment or projected offsite doses.

Corrective Action(s): The licensee corrected the condition and completed the necessary calibration activities. The radiation monitor was returned to operable status on November 10, 2022. To prevent future issues with technical procedure changes being inappropriately categorized as editorial changes, and thus receiving inadequate reviews, additional revisions to Procedure W2.109, Procedure Development and Approval, were completed, addressing the CAPR for RCE CR-WF3-2022-7836. Actions are documented in the licensees corrective action program.

Corrective Action Reference(s): Condition Reports CR-WF3-2022-07376, CR-WF3-2022-07836

Enforcement:

Severity/Significance: The staff determined the significance of the violation is not greater than White as determined by a bounding evaluation with Manual Chapter 0609, Appendix B,

2. Violation: Title 10 CFR 50.54(q)(2) requires, in part, that a holder of a license under

10 CFR Part 50 shall follow and maintain the effectiveness of an emergency plan that meets the requirements in 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b).

Title 10 CFR 50.47(b)(9) requires, in part, that adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Contrary to the above, from October 20 to November 10, 2022, the licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2),which meets the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to have adequate methods for assessing and monitoring offsite consequences for a radiological release through the steam generator B release path as required by 10 CFR 50.47(b)(9).

Discretion Basis: The NRC exercised enforcement discretion in accordance with Section 3.3 of the Enforcement Policy, because the violation was identified by Waterford Steam Electric Station, Unit 3 staff as part of the extent of condition for a previous enforcement action, the violation has the same or similar root causes as the violation for which enforcement action was previously taken, the violation does not substantially change the safety significance or character of the initial violation, and the violation was corrected.

Enforcement Discretion Enforcement Action EA-23-036: Boron Waste 95001 Management and Liquid Waste Management Radiation Monitors (PRMIRE0627, PRMIRE0547) -

Emergency Action Level Classification (Example 2)

Description:

During licensee extent of cause reviews associated with RCEs CR-WF3-2022-3999 and CR-WF3-2022-6367, it was identified that the calibration of the Boron Waste Management and Liquid Waste Management Radiation Monitors had not been done correctly for some time. Errors in engineering conversion factors used, as well as an incorrect background radiation assumption used in calibration caused the issues, similar to the root and contributing causes associated with RCE CR-WF3-2022-3999. Site calibration procedures allowed for using a background radiation level of 800 counts per minute (cpm), whereas the primary calibration documents associated with the radiation monitors allow for a maximum of 100 cpm. Background radiation at the time was roughly 700 cpm. For the two monitors, during the affected time, they read 16.4 percent lower than they were supposed to. The normal calibration range is plus or minus 15 percent.

The non-functional radiation monitor resulted in a failure to comply with a risk significant planning standard (RSPS), with no loss of PS function or a degraded RSPS function. This is due to an emergency action level being rendered ineffective such that an Unusual Event (AU1.1) would be declared in a degraded manner.

Corrective Action(s): The licensee initiated compensatory measures for their emergency preparedness function while the calibration issues were being resolved. The licensee entered these issues into the corrective action program.

Corrective Action Reference(s): Condition Reports CR-WF3-2022-07572, CR-WF3-2023-00243

Enforcement:

Severity/Significance: The staff determined the significance of the violation is not greater than Green as determined by a bounding evaluation with Manual Chapter 0609, Appendix B,

2. Violation: Title 10 CFR 50.54(q)(2) requires, in part, that a holder of a license under

10 CFR Part 50 shall follow and maintain the effectiveness of an emergency plan that meets the requirements in 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b).

Title 10 CFR 50.47(b)(4) requires, in part, that a standard emergency classification and action level scheme is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.

Contrary to the above, from January 1, 1989, to May 16, 2023, the licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2),which meets the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to have a standard emergency classification and action level scheme in use by the nuclear facility licensee as required by 10 CFR 50.47(b)(4).

Discretion Basis: The NRC exercised enforcement discretion in accordance with Section 3.3 of the Enforcement Policy, because the violation was identified by Waterford Steam Electric Station, Unit 3 staff as part of the extent of condition for a previous enforcement action, the violation has the same or similar root causes as the violation for which enforcement action was previously taken, the violation does not substantially change the safety significance or character of the initial violation, and the violation was corrected.

Enforcement Discretion Enforcement Action EA-23-036: Fuel Handling 95001 Building WRGM Mid-Range Detector (PRMIRE3032) - Emergency Action Level Classification and Dose Assessment (Example 3)

Description:

During licensee extent of cause reviews associated with RCEs CR-WF3-2022-3999 and CR-WF3-2022-6367, the licensee identified that the Fuel Handling Building WRGM mid-range detector was out of calibration. Past operability review established that it had been inoperable since November 11, 1987. The cause was found to be the removal of the requirement to use a multi-channel analyzer during the calibration from the controlling procedure, similar to the cause identified in RCE CR-WF3-2022-3999. A calibration of the Fuel Handling Building WRGM mid-range detector was conducted using appropriate equipment (multi-channel analyzer and a Barium-133 alignment source).

The as-found condition was that the detector was reading 18 percent higher than it was supposed to (LER 2022-01-02, CR-WF3-2022-08104). The normal calibration range is plus or minus 10 percent.

The inoperable radiation monitor resulted in a failure to comply with a risk significant planning standard (RSPS), with a degraded RSPS function. This is due to there being some (but not all)cases in which the dose projection process would be incapable of providing technically adequate estimates of radioactive material releases to the environment or projected offsite doses. Also, an emergency action level was rendered ineffective because it could have resulted in an overclassification of a General Emergency (AG1.1), leading to unnecessary protective actions being issued to the public.

Corrective Action(s): Adjustments and calibration were completed, returning it to operable service on December 15, 2022. The licensee entered these issues into the corrective action program.

Corrective Action Reference(s): Condition Reports CR-WF3-2022-03999, CR-WF3-2022-08104

Enforcement:

Severity/Significance: The staff determined the significance of the violation is not greater than White as determined by a bounding evaluation with Manual Chapter 0609, Appendix B,

2. Violation: Title 10 CFR 50.54(q)(2) requires, in part, that a holder of a license under

10 CFR Part 50 shall follow and maintain the effectiveness of an emergency plan that meets the requirements in 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b).

Title 10 CFR 50.47(b)(4) requires, in part, that a standard emergency classification and action level scheme is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.

Title 10 CFR 50.47(b)(9) requires, in part, that adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Contrary to the above, from November 11, 1987, to December 15, 2022, the licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2), which meets the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to have adequate methods for assessing and monitoring offsite consequences for a radiological release through the steam generator B release path as required by 10 CFR 50.47(b)(9). In addition, the licensee failed to have a standard emergency classification and action level scheme in use by the nuclear facility licensee as required by 10 CFR 50.47(b)(4).

Discretion Basis: The NRC exercised enforcement discretion in accordance with Section 3.3 of the Enforcement Policy, because the violation was identified by Waterford Steam Electric Station, Unit 3 staff as part of the extent of condition for a previous enforcement action, the violation has the same or similar root causes as the violation for which enforcement action was previously taken, the violation does not substantially change the safety significance or character of the initial violation, and the violation was corrected.

Enforcement Discretion Enforcement Action EA-23-036: Containment High 95001 Range Radiation Monitors A and B (ARMIRE5400AS, ARMIRE5400BS) - Emergency Action Level Classification (Example 4)

Description:

During licensee extent of cause reviews associated with RCE CR-WF3-2022-3999, it was identified that Containment High Range Radiation Monitors A and B had both been inoperable for varying time periods. For Containment High Range Monitor A, the cause was due to a installed pico-ammeter board and a detector signal cable that were incapable of providing for its design performance functions. The engineering conversion factors for Containment High Range Monitor B were incorrect, negatively affecting the monitors calibration. Further, for Containment High Range Monitors A and B, there was a failure to account for the keep-alive source during half-life calculations, which is necessary for correct calibration. The calibration practice issues were caused by inadequate legacy instructions in their calibration Procedure MI-003-360, similar to the causes identified in RCE CR-WF3-2022-3999.

The as-found condition was that Containment High Range Radiation Monitor A indication during that affected time could not be used for reliable indication. Containment High Range Radiation Monitor B was reading 29.8 percent lower than it was supposed to, with a normal calibration range of plus or minus 15 percent.

The inoperable radiation monitors resulted in a failure to comply with a risk significant planning standard (RSPS), with a degraded RSPS function. This is due to an emergency action level rendered ineffective such that a General Emergency (FG1.1) would not be declared for a particular off-normal event but an appropriate declaration would have been made in a degraded manner.

Corrective Action(s): Containment High Range Radiation Monitor A was returned to operable service on May 14, 2022. On May 11, 2022, Containment High Range Radiation Monitor B was returned to operable service. The licensee entered these issues into the corrective action program.

Corrective Action Reference(s): Condition Report CR-WF3-2022-03097

Enforcement:

Severity/Significance: The staff determined the significance of the violation is not greater than White as determined by a bounding evaluation with Manual Chapter 0609, Appendix B,

2. Violation: Title 10 CFR 50.54(q)(2) requires, in part, that a holder of a license under

10 CFR Part 50 shall follow and maintain the effectiveness of an emergency plan that meets the requirements in 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b).

Title 10 CFR 50.47(b)(4) requires, in part, that a standard emergency classification and action level scheme is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.

Contrary to the above, from July 11, 2012, to May 11, 2022, the licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2),which meets the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to have a standard emergency classification and action level scheme in use by the nuclear facility licensee as required by 10 CFR 50.47(b)(4).

Discretion Basis: The NRC exercised enforcement discretion in accordance with Section 3.3 of the Enforcement Policy, because the violation was identified by Waterford Steam Electric Station, Unit 3 staff as part of the extent of condition for a previous enforcement action, the violation has the same or similar root causes as the violation for which enforcement action was previously taken, the violation does not substantially change the safety significance or character of the initial violation, and the violation was corrected.

Enforcement Discretion Enforcement Action EA-23-036: Main Steam Line A 95001 Radiation Monitor (PRMIRE5500A) - Dose Assessment (Example 5)

Description:

During licensee extent of condition reviews associated with RCE CR-WF3-2022-3999, the licensee identified that Main Steam Line A Radiation Monitor failed numerous calibrations since detector replacement. Previous calibrations did not correctly track new reference ion chamber output dose-rate values, which would be needed to correctly calibrate the monitor on subsequent occasions. The cause was that calibration Procedure MI-003-389 did not have steps directing recording these values for later use, similar to the causes identified in RCE CR-WF3-2022-3999. Based on past reviews, the monitor had not been operating with a satisfactory calibration, and therefore inoperable, since March 17, 2004.

The as-found condition was that the detector was reading 17 to 24 percent higher than it was supposed to (CR-WF3-2022-03392). The normal calibration range is plus or minus 15 percent.

The non-functional radiation monitor resulted in a failure to comply with a risk significant planning standard (RSPS), with a degraded RSPS function. This is due to there being some (but not all) cases in which the dose projection process would be incapable of providing technically adequate estimates of radioactive material releases to the environment or projected offsite doses.

Corrective Action(s): The licensee determined the correct values and revised the calibration procedure. With the corrected procedure, the radiation monitor was calibrated correctly and returned to service on May 5, 2022. The licensee entered these issues into the corrective action program.

Corrective Action Reference(s): Condition Reports CR-WF3-2022-02539, CR-WF3-2022-03392, CR-WF3-2022-03097

Enforcement:

Severity/Significance: The staff determined the significance of the violation is not greater than White as determined by a bounding evaluation with Manual Chapter 0609, Appendix B,

2. Violation: Title 10 CFR 50.54(q)(2) requires, in part, that a holder of a license under

10 CFR Part 50 shall follow and maintain the effectiveness of an emergency plan that meets the requirements in 10 CFR Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b).

Title 10 CFR 50.47(b)(9) requires, in part, that adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Contrary to the above, from March 17, 2004, to May 5, 2022, the licensee failed to follow and maintain the effectiveness of an emergency plan in accordance with 10 CFR 50.54(q)(2),which meets the planning standards of 10 CFR 50.47(b). Specifically, the licensee failed to have adequate methods for assessing and monitoring offsite consequences for a radiological release through the steam generator B release path as required by 10 CFR 50.47(b)(9).

Discretion Basis: The NRC exercised enforcement discretion in accordance with Section 3.3 of the Enforcement Policy, because the violation was identified by Waterford Steam Electric Station, Unit 3 staff as part of the extent of condition for a previous enforcement action, the violation has the same or similar root causes as the violation for which enforcement action was previously taken, the violation does not substantially change the safety significance or character of the initial violation, and the violation was corrected.

EXIT MEETINGS AND DEBRIEFS

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

On May 16, 2023, the inspectors presented the 95001 supplemental inspection results to John Ferrick, Site Vice President, and other members of the licensee staff.

On March 3, 2023, the inspectors presented the 95001 supplemental inspection preliminary inspection results to Mandy Halter, General Manager of Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

95001 Corrective Action Condition Reports 2020-04019, 2022-0284, 2022-02010, 2022-02221, 2022-

Documents (CR-WF3-) 03999, 2022-06367, 2022-06378, 2022-06467, 2022-06477,

22-06663, 2022-07326, 2022-07376, 2022-07572, 2022-

07593, 2022-07836, 2022-08104, 2023-00764, 2023-00765,

23-00810

95001 Corrective Action Condition Reports 2023-0550, 2023-00978, 2023-00994, 2023-01001, 2023-

Documents (CR-WF3-) 01002, 2023-01003, 2023-01014, 2023-01016, 2023-01020,

Resulting from 2023-01052, 2023-01053, 2023-01055

Inspection

95001 Engineering EC 86890 Radiological Effluent EAL Values 0, 1

Changes

95001 Engineering EC 93677 Evaluate Impact of Detector Sensitivity Change For 0

Changes PRMIRE0110 & PRMIRE3032 Per CR-WF3-2022-02010 CA-

and Update Related Documents

95001 Miscellaneous CR-WF3-2022- Root Cause Evaluation, Condenser Wide Range Gas Monitor 1, 2, 3

03999 RD72 Incorrect Calibration Methodology

95001 Miscellaneous CR-WF3-2022- Root Cause Evaluation, Incorrect Calibration of Wide Range 1, 2, 3

6367 Gas Monitors Used in Emergency Response Procedures

95001 Miscellaneous CR-WF3-2022- Root Cause Evaluation, Waterford 3 Steam Electric Station 2, 3

7836 Collective Review of Radiation Monitor Issues

95001 Miscellaneous Work Task 2022-00095, 2023-0023, 2023-0024

Tracking

Documents (LO-

WLO-)

95001 Procedures EN-AD-106 Site Procedure Writer's Manual 2

95001 Procedures EN-HU-106 Procedure and Work Instruction Use and Adherence 9

95001 Procedures EN-LI-100 Process Applicability Determination 33

95001 Procedures EN-LI-101 10 CFR 50.59 Evaluations 21

95001 Procedures EN-LI-102 Corrective Action Program 47, 48

95001 Procedures EN-LI-118 Causal Analysis Process 35

95001 Procedures MI-003-350 Containment Purge Isolation Area Radiation Monitor Channel 302, 305

A or B Functional Test, ARMIR5024, ARMIR5025,

Inspection Type Designation Description or Title Revision or

Procedure Date

ARMIR5026, or ARMIR5027

95001 Procedures MI-003-360 Containment High Range Safety Channel A or B Area 309, 316

Radiation Monitor Calibration, ARMIR5400 A or ARMIR5400

B

95001 Procedures MI-003-370 Fuel Handling Building Ventilation Noble Gas Radiation 302, 304

Monitor Channel Functional Test PRMIR3032

95001 Procedures MI-003-371 Fuel Handling Building Ventilation System Emergency 311, 318

Exhaust High Range Noble Gas Radiation Monitor Channel

Calibration PRMIR3032

95001 Procedures MI-003-382 Plant Vent Stack High Range Noble Gas Radiation Monitor 6, 10

Channel Functional Test PRMIR0110

95001 Procedures MI-003-383 Plant Vent Stack High Range Noble Gas Radiation Monitor 21, 29

Channel Calibration PRMIR0110

95001 Procedures MI-003-386 Condenser Vacuum Pump Discharge High Range Noble Gas 301, 303

Radiation Monitor Channel Functional Test PRMIR0002

95001 Procedures MI-003-387 Condenser Vacuum Pump Discharge Wide Range Noble 19, 26

Gas Radiation Monitor Channel Calibration PRMIR0002

95001 Procedures MI-003-389 Main Steam Line Radiation Monitor Channel Calibration 312

ARMIR5500A or ARMIR5500B

95001 Procedures MI-005-906 Radiation Monitoring System Desk Guide 6

95001 Procedures MI-005-910 Mobile Airborne Radiation Monitor Calibration, ARMIR5132, 7, 9

ARMIR5144

95001 Procedures MI-005-919 Containment Post LOCA Area Radiation Monitor Safety 303, 309

Channel A or B Calibration, ARMIR5028, 5029, 5030, 5031

95001 Procedures UNT-007-029 Control of the Radiation Monitor System Database 4, 5, 7

95001 Procedures W2.109 Procedure Development, Review, and Approval 31, 32, 33,

95001 Work Orders Work Order 573242, 573245, 582053, 585706, 585710, 587031, 587955,

Number 588201, 588499

23