IR 05000528/2018008

NRC Biennial Problem Identification and Resolution Inspection Report 05000528/2018008, 05000529/2018008, and 05000530/2018008

ML18291A562
Person / Time
Site:	Palo Verde
Issue date:	10/16/2018
From:	Geoffrey Miller Division of Reactor Safety IV
To:	Bement R Arizona Public Service Co
Miller G
References
IR 2018008
Download: ML18291A562 (22)

Text

October 16, 2018

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION - NRC BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000528/2018008, 05000529/2018008, AND 05000530/2018008

Dear Mr. Bement:

On September 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The NRC inspection team discussed the results of this inspection with Ms. M. Lacal, Senior Vice President, Regulatory and Oversight, 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.

Palo Verde Nuclear Generating Station employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

The NRC inspectors documented one finding of very low safety significance (Green) in this report, which involved a violation of NRC requirements. Additionally, the team documented two licensee-identified violations that were determined to be of very low safety significance. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest these violations or their significance, 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 IV; the Director, Office of Enforcement; and the NRC resident inspector at the Palo Verde Nuclear Generating Station.

Likewise, 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 IV; and the NRC resident inspector at the Palo Verde Nuclear Generating Station.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA Gerond George Acting for/

Geoffrey B. Miller, Team Leader Inspection Program and Assessment Team Division of Reactor Safety

Docket Nos. 50-528, 50-529, and 50-530 License Nos. NPF-41, NPF-51, and NPF-74

Enclosure:

Inspection Report 05000528/2018008, 05000529/2018008, and 05000530/2018008 w/ attachment: Information Requests

Enclosure U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number(s):

05000528, 05000529, 05000530

License Number(s):

NPF-41, NPF-51, NPF-74

Report Number(s):

05000528/2018008, 05000529/2018008, and 05000530/2018008

Licensee:

Arizona Public Service Company

Facility:

Palo Verde Nuclear Generating Station

Location:

Tonopah, Arizona

Inspection Dates:

August 27, 2018, to September 14, 2018

Inspectors:

E. Ruesch, J.D., Sr. Reactor Inspector (Team Lead)

P. Jayroe, Reactor Inspector

G. Kolcum, Sr. Resident Inspector

D. Reinert, Resident Inspector

Approved By:

Geoffrey B. Miller, Team Leader

Inspection Program and Assessment Team

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Palo Verde Nuclear Generating Station, Units 1, 2, and 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. Findings and violations being considered in the NRCs assessment are summarized in the table below. A licensee-identified non-cited violation is discussed in report section 7115

List of Findings and Violations

Inadequate Corrective Actions For Missing Control Room Hand-Switch Operator Knobs Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green NCV 05000528, 05000529,05000530/2018008-01 Closed H.12 71152Problem Identification and Resolution The team reviewed a Green, NRC identified, non-cited violation of 10 CFR Part 50,

Appendix B, Criterion XVI, Corrective Action, for the licensees failure to promptly identify and correct the failures of multiple control room hand-switch operator knobs.

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 team 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 - BASELINE

71152Problem Identification and Resolution Biennial Team Inspection

The team performed a biennial assessment of the licensees corrective action program (CAP),use of operating experience, self-assessments and audits, and safety-conscious work environment. The assessment is documented below.

(1) Corrective Action Program Effectiveness: Problem Identification, Problem Prioritization and Evaluation, and Corrective Actions - The inspection team reviewed the stations CAP 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 CAPs. The sample included review of over 200 condition reports and associated records, and an in-depth 5-year review of condition reports associated with the safety injection and shutdown cooling systems.

(2) Operating Experience, Self-Assessments, and Audits - The team evaluated the stations processes for use of industry and NRC operating experience. The team also evaluated the effectiveness of the stations audits and self-assessments program by reviewing a sample of nine self-assessments (benchmark, simple, formal departmental) and seven audits.

(3) Safety-Conscious Work Environment - The team evaluated the stations safety-conscious work environment. The team interviewed 42 station personnel in 6 group interviews. These included personnel from operations, work management, maintenance, radiological protection, engineering, organizational effectiveness and performance improvement, and security. The team also interviewed employee concerns program personnel, reviewed employee concerns files, and reviewed the results of the most recent safety culture survey and the licensees actions to address priority groups identified through that survey.

71153Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports

The team evaluated licensee event report (LER) 05000528/2018-002: Condition Prohibited by Technical Specification for Inoperable Excore Instrument Channel (ADAMS Accession Number ML18130A986). The team reviewed two licensee-identified non-cited violations associated with the LER, described in the inspection results below.

INSPECTION RESULTS

- OBSERVATIONS/ASSESSMENT

Corrective Action Program Assessment 71152Problem Identification and Resolution Effectiveness of Problem Identification: Overall, the team found that the licensees identification and documentation of problems was adequate to support nuclear safety, though some challenges were noted. In particular, the team identified opportunities for improvement in the identification and screening of potential trends and other aggregate issues. These are described in observations, findings, and violations below.

Effectiveness of Prioritization and Evaluation of Issues: Overall, the team found that the licensees prioritization and evaluation of issues was adequate to support nuclear safety. The licensee continues to work to improve management oversight of the corrective action program, which has been consistently identified as an area for improvement by both third party and internal reviews. The team noted that the licensees actions appear to have improved management oversight, including improvements to quality and consistency of evaluation products through enhanced CARB oversight, and the addition of new tools for scoping the evaluation. However, these actions were too recently completed for the team to determine whether they have been fully successful. Additionally, the team noted that while individual problems were generally fixed, the licensee did not always expand evaluations to determine the cause or aggregate impact of multiple similar conditions. Examples are discussed below.

Effectiveness of Corrective Actions: Overall, the team found that the licensees corrective actions, when accomplished, generally supported nuclear safety. However, the team noted that the licensee failed to appropriately manage its backlog of conditions adverse to quality that were classified as nonconformances, this is discussed below as a minor violation.

Observations on the Corrective Action Program 71152Problem Identification and Resolution The team reviewed the engineering design change process and impact review process, and found it to be adequate and in line with industry standards. The team also screened a sample of condition reports that originated over the past 2 years and found several examples of misses tied to the design change process and impact reviews where the required updates to documentation were not completed or were incorrect. Personnel interviewed by the team indicated that these misses were sometimes identified by workers being unable to perform work activities as directed by work orders or unable to draft clearance orders due to incorrect drawings. In all examples reviewed by the team, the licensee revised or updated affected documentation after the condition report was written; however the team did not note any significant efforts to evaluate or improve the engineering design change impact review process. The team reviewed the stations use of trend codes to track these examples and identified several instances where expected trend codes were incorrectly applied or not applied at all. One particular trend code (CM 3.10) is applied to condition reports which are created in advance or just recently after a plant modification to create a tracking item for required updates to various documents; the team noted examples of documentation revisions tied to legacy modifications lumped in under this trend code. Liberal use of this particular trend code in coincidence with restricted use of more applicable trend codes may be masking potential trends in documentation revisions missed by the impact review process. The licensee documented this observation in Condition Report 18-14427.

The team observed that the licensees condition report classification committees (the Screening Committee and the Condition Review Group) did not always consistently apply the corrective action program (CAP) definitions of condition adverse to quality (CAQ) and non-condition adverse to quality. In particular, a lack of guidance or familiarity in what constituted an adverse trend in a quality process CAQ versus a potential adverse trend (non-condition adverse to quality until evaluated and confirmed) led to inconsistency in classification of condition reports documenting aggregate issues. The licensee documented this observation in Condition Reports 18-13648 and 18-14334.

Additionally, some identified deficiencies in quality programs were classified as non-condition adverse to quality. For example, on January 2, 2018, the licensees organizational effectiveness department issued a Corrective Action Program Elevation Letter, which identified, inconsistent identification of issues entered into the condition reporting process, CAP product quality decline, inappropriate closure of CAP actions, and rejection of CAP products including causal evaluation. The condition report associated with this letter, Condition Report 18-00055, was classified as non-condition adverse to quality. In procedure 01DP-0AP12, Condition Reporting Process the licensee defines CAQ to include, failures to comply with procedures that implement the current licensing basis (CLB), where CLB is defined to include both 10 CFR Part 50 and the licensees quality assurance program, both of which contain requirements implemented by CAP. In these examples and others reviewed by the team, the conditions adverse to quality were timely addressed, even when classified as non-condition adverse to quality. Therefore there was no violation of NRC regulations. The licensee documented this issue in Condition Report 18-13739.

Assessment of Use of Operating Experience 71152Problem Identification and Resolution Based on the samples reviewed, the team determined that the licensee appropriately evaluated industry operating experience for its relevance to the facility. Operating experience information was incorporated into plant procedures and processes as appropriate. The team further determined that the licensee appropriately evaluated industry operating experience when performing root cause analysis and apparent cause evaluations. The licensee appropriately incorporated both internal and external operating experience into lessons learned for training and pre-job briefs.

Self-Assessments and Audits Assessment 71152Problem Identification and Resolution Based on the samples reviewed, the team determined that station performance in these areas adequately supported nuclear safety. Generally, self-assessments and audits were effective at identifying deficiencies and enhancements. In all cases, deficiencies were documented in condition reports for both self-assessments and audits. Audits, in particular, were highly effective in identifying and documenting deficiencies. One self-assessment (16-10139) did not appear to have a tracking item (i.e. condition report) for an enhancement.

Safety-Conscious Work Environment Assessment 71152Problem Identification and Resolution The team found no evidence of challenges to the safety-conscious work environment of station work groups. Individuals appeared willing to raise nuclear safety concerns through at least one of the several means available.

INSPECTION RESULTS

- ISSUES/FINDINGS

Minor Violation 71152Problem Identification and Resolution Performance Deficiency: Failure to promptly identify and correct conditions adverse to quality as required by 10 CFR 50, Appendix B, Criterion XVI.

The team identified a backlog of conditions adverse to quality that the licensee had failed to timely correct. The oldest of these conditions was approximately 10 years old, with several hundred having been identified at least two operating cycles prior to the inspection. The team determined that the licensee was appropriately addressing degraded components that had an impact on safety or security, but was not always tracking or timely correcting nonconformances with its design bases in cases where these nonconformances had been assessed as not impacting safety-related functions. Further, the licensee was unable to initially determine the scope of its nonconformance backlog. The licensee documented this deficiency as Condition Reports 18-13549 and 18-14426.

Screening: The performance deficiency was minor because if left uncorrected it would not have led to a more significant safety concern and it did not adversely affect any cornerstone objectives.

Enforcement:

This failure to comply with 10 CFR 50, Appendix B, Criterion XVI constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Minor Violation 71152Problem Identification and Resolution Performance Deficiency: Failure to control the issuance of documents, such as instructions, procedures, and drawings, including changes thereto, which prescribe all activities affecting quality as required by 10 CFR 50, Appendix B, Criterion VI.

The team identified that the CAP procedure directed the use of the Cause Analysis Manual in performing some cause evaluations. This cause evaluation process is an activity affecting quality required by 10 CFR 50, Appendix B and the licensees Quality Assurance Program.

The licensee failed to control the Cause Analysis Manual in accordance with the Palo Verde Nuclear Generating Station Operations Quality Assurance Program Description, Revision 0, Section 2.6, Document Control. The licensee documented this violation in Condition Report 18-13996.

Screening: The performance deficiency is minor because if left uncorrected it would not have led to a more significant safety concern and it did not adversely affect any cornerstone objectives.

Enforcement:

This failure to comply with 10 CFR 50, Appendix B, Criterion VI constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Licensee-Identified Non-Cited Violation 71153 Follow-up of Events and Notices of Enforcement Discretion This violation of very low safety-significant was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR Part 50, Appendix B, Criterion V requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Contrary to the above, on May 24, 2007, the licensee failed to perform the installation of the Unit 1, channel C excore nuclear instrument preamplifier connection, an activity affecting quality, in accordance with these instructions, procedures, or drawings. The licensee determined that a human performance error occurred during the performance of the 2007 work order which explicitly stated that the o-rings were required for environmental qualification. As a result, the excore detector would not have performed its safety function during a design basis main steam line break.

Significance/Severity Level: The team determined this finding was of very low safety significance (Green) because a minimum of two excore detector channels always remained available to trip the reactor during a main steam line break. Redundant channels were not affected and were available to perform the required safety function to trip the reactor.

Corrective Action Reference(s): Condition Report 18-12217 Licensee-Identified Non-Cited Violation 71153 Follow-up of Events and Notices of Enforcement Discretion This violation of very low safety-significant was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR 50.73(a)(2)(i)(B) requires, in part, that the holder of an operating license shall submit an licensee event report within 60 days of discovery of the event, which includes any operation or condition which was prohibited by technical specifications.

Contrary to the above, the licensee failed to submit a licensee event report within 60 days of April 23, 2016, after discovering that the Unit 1 channel C excore was in a condition which was prohibited by technical specifications. The detector was found in a configuration without o-rings at two electrical connection interfaces. Condition Report 16-06735 documented the non-conforming condition, but was closed without performing a reportability review.

Significance/Severity Level: This violation was considered as traditional enforcement because the failure to notify the NRC had the potential for impacting the NRCs ability to perform its regulatory function. Consistent with the guidance in Section 6.9, Paragraph d.9, of the NRC Enforcement Policy, the failure to report the condition prohibited by technical specifications was determined to be a Severity Level IV violation.

Corrective Action Reference(s): Condition Report 18-02569

Non-Cited Violation (NCV): Inadequate Corrective Actions For Missing Control Room Hand-Switch Operator Knobs Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green NCV 05000528; 05000529;05000530/2018008-01 Closed None 71152Problem Identification and Resolution The team reviewed a Green, NRC identified, non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action for failure to promptly correct a condition adverse to quality. Specifically, since October 30, 2014, the licensee failed to implement prompt corrective actions to correct an adverse condition related to the failure of control room hand-switch operator knobs.

Description:

While performing control room observations on August 28, 2018, the team identified that various control room hand-switches were missing operator knobs. The control room switches are Coordinated Manual Controls 910 series currently manufactured and supported by Senasys. The switches are operated by turning the selector knob, which rotates a cam at the end of the knob shaft, pushing a set of plungers which will make or break electrical contact continuity within the contact block. The primary purpose of the knob is to allow operators to change the status of equipment in the plant.

The team identified a total of eighteen missing operator knobs among the three unit control rooms. Fourteen of these controlled safety-related, technical specification (TS)-related, or emergency operating procedure (EOP)-related components:1

Broken switches Number safety-related Number TS-related Number EOP-related Oldest Unit 1

2 October 30, 2014 Unit 2

2 October 18, 2015 Unit 3

2 April 27, 2018 Total

The licensee had provided one or two spare operator knobs in each control room that could be used to operate a hand-switch when necessary during routine, alarm, abnormal, or emergency events. However, the licensee had performed no formal evaluation of the use of these spare knobs as a compensatory action or of the aggregate impact to each control room during off-normal or emergency scenarios. The licensee did not control the spare knobs despite having dedicated them as basic components for use in safety-related applications. All equivalent knobs in the plant reference simulators were intact. The licensee did not model or brief this discrepancy between the simulator and the plant during training scenarios. Neither did the licensee list the missing knobs on the simulator differences list or evaluate the missing knobs in the overall simulator program of maintenance, testing, and correction of discrepancies with the actual plant.

Corrective Action(s): As an immediate corrective action, the licensee provided five additional knobs for each control room and provided a formal communication to control room staff regarding their use.

Corrective Action Reference(s): Condition Reports 18-13575 and 18-14201.

Performance Assessment:

Performance Deficiency: The failure to promptly identify and correct a condition adverse to quality related to the failure of control room hand-switch operator knobs as required by 10 CFR 50, Appendix B, Criterion XVI was a performance deficiency.

Screening: The performance deficiency was more than minor, and therefore a finding, because it affected the configuration control attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Since October 30, 2014, the licensee had failed to implement prompt corrective actions to correct an adverse condition of broken operator knobs in the control rooms of all three units.

Significance: The team performed the initial significance determination using NRC Inspection Manual Chapter 0609, Appendix A, Exhibit 2, Mitigating Systems Screening Questions. The team determined that the finding was of very low safety significance (Green) because it did not result in the loss of operability or functionality of any system or train.

1 Four of the eighteen switches met none of these criteria, though one of those four controlled a breaker that was included in the probabilistic risk model. The other fourteen switches variously met one or more of the criteria. Because of this overlap, the numbers in the table to not sum horizontally.

Cross Cutting Aspect: This finding had a cross-cutting aspect in the area of human performance, avoid complacency, in that the licensee failed to recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Specifically, the licensee did not implement prompt corrective actions to correct an adverse condition of broken operator knobs in the control room (H.12).

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to this requirement, the licensee failed to assure that conditions adverse to quality were promptly corrected. Specifically, since October 30, 2014, the licensee failed to correct a condition adverse to quality related to broken operator knobs in the control room, to which 10 CFR Part 50, Appendix B, applies. Consequently, the licensees failure to implement prompt corrective actions to correct an adverse condition related to the broken operator knobs in the control room resulted in not returning the switch to the vendor drawing configuration and specifications.

Disposition: This violation is being treated as a non-cited violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy.

Licensee Event Report (Closed)

Condition Prohibited by Technical Specifications for an Inoperable Excore Instrument Channel (LER 05000528/2018-002)71153 Follow-up of Events and Notices of Enforcement Discretion

EXIT MEETINGS AND DEBRIEFS

On September 14, 2018, the team presented the inspection results to Ms. M. Lacal, Senior Vice President, Regulatory & Oversight, and other members of the licensee staff. The team confirmed that any proprietary or sensitive information reviewed was controlled to protect from public disclosure.

DOCUMENTS REVIEWED

Condition Reports

10-00424

16-04624

17-12748

18-00837

18-06960

16-19560

2-00391

16-04625

17-13751

18-00869

18-07751

16-19864

13-00349

16-04628

17-13780

18-01277

16-13267

16-20048

13-00736

16-04646

17-14018

18-01512

16-13529

16-20333

14-01375

17-08432

17-14219

18-01657

16-13896

16-20383

14-01904

17-08633

17-14504

18-01685

16-14370

16-20395

14-02854

17-08634

17-15012

18-01702

16-14791

18-12743

15-02470

17-08636

17-15793

18-01737

16-14896

18-13345

15-02897

17-08672

17-16181

16-10666

16-15709

18-13446

15-06128

17-08818

17-16495

16-10742

16-16024

18-13575

15-07118

17-09022

17-16497

16-11578

16-16585

18-13996

16-03489

17-09222

17-16552

16-11605

16-16995

18-14126

16-03566

17-09257

17-16563

16-12160

18-07903

18-14201

16-03843

17-09326

17-17371

16-12430

18-07964

18-14212

16-03914

17-09336

16-07329

16-12465

18-08156

18-14215

16-04598

17-09524

16-07589

16-12783

18-08409

18-14218

17-16181

17-09656

16-07632

16-12797

18-08466

18-14222

17-16495

17-10518

16-08413

16-13128

18-08815

18-14223

17-16497

17-11997

16-09123

18-02462

18-09130

18-14224

17-16552

17-12205

16-09548

18-02960

18-09679

18-14226

17-16563

16-04677

16-09997

18-03038

18-10024

18-14372

17-17371

16-04977

16-10139

18-03154

18-10995

17-17791

16-04980

16-10173

18-03173

18-11453

17-17965

16-04982

16-10185

18-03177

18-12086

17-18155

16-04984

17-17791

18-03346

18-12157

18-00055

16-05436

17-17965

18-04528

18-12174

15-07118

16-05926

17-18155

18-04994

18-12217

16-03489

16-05966

18-00055

18-05015

18-12423

16-03566

16-06026

18-00055

18-05879

16-18951

16-03843

16-06578

18-00086

18-06317

16-19295

16-03914

17-12265

18-00194

18-06774

16-19296

16-04598

17-12466

18-00202

18-06912

16-19554

Plus approximately 100 anonymous condition reports initiated between January 1, 2018, and

August 7, 2018, and the text of most of the several hundred condition reports issued while the

team was on site.

Work Orders

24481

4340548

4616104

4699032

4842349

4316976

4412917

4699031

4699034

4857178

Audit Reports

2016-007

2016-010

2017-009

2018-003

2016-009

2017-003

2018-002

Procedures

Number

Title

Revision

01DP-0AP01

Procedure Process

01DP-0AP12

Condition Reporting Process

23, 24, 29, 30

01DP-0AP22

Procedure Writers Guide

01DP-0AP58-01

Trend Analysis and Coding Administrative Guideline

2DP-0AP01

Plant Review Board

2DP-0MC08,

Control of Purchasing Material and Equipment

5DP-0CC05

Simulator Instructors Guide and Reporting

15DP-0TR08

Systematic Approach to Training

30DP-0AC02

Station Rework Reduction

30DP-0WM15

Fix-It-Now Multi-Discipline Team

31MT-9SI02

High Pressure Safety Injection Pump Disassembly,

Examination, and Assembly

40AL-9RK6A

Panel B06A Alarm Responses

40AO-9ZZ21

Acts of Nature

40DP-9OP15

Operator Challenges and Discrepancy Tracking

40DP-9OP20

Watch Standing Practices

40DP-9OP26

Operations Condition Reporting Process and Operability

Determination / Functional Assessment

40DP-9OP33

Shift Turnover

40DP-9WP01

Operations Processing of Work Orders

40DP-9ZZ04

Time Critical Action (TCA) Program

40OP-9AF02

Non-Essential Auxiliary Feedwater Pump Operation

40OP-9CH03

RCP Seal Injection System

60DP-0QQ02

Trend Analysis and Coding

65DP-0QQ01

Industry Operating Experience Review

73TD-0ZZ03

System Engineering Handbook

75RP-9RP20

Use and Control of HEPA Filtration and Vacuum

Equipment

81DP-0EE10

Design Change Process

Procedures

Number

Title

Revision

93DP-0LC18

Part 21 Reporting Process

Miscellaneous

Documents

Number

Title

Revision

or Date

2018 PVNGS Condition Reports CRG Refuse Back to

SC Rate / Through Rate Performance

August 27, 2018

Active Night Orders

August 10, 2017

Active Standing Orders

August 10, 2017

Control Room Discrepancies

August 10, 2017

Open Operator Burdens

August 10, 2017

Operations Challenges List

August 10, 2017

Operator Work Arounds

August 10, 2017

Organizational Effectiveness Monthly Performance

Summary: 2018 1st Quarter

March 2018

Organizational Effectiveness Quarterly Performance

Summary

2nd Quarter

2018

PRB Meeting Minutes: Monthly PRB (October 2017)

and U1R20 Refueling Outage Restart

Oct 31, 2017

PRB Monthly and U2R20 Startup Meeting Minutes

April 28, 2017

PVNGS Operations Quality Assurance Program

Description (QAPD)

0, 0a

Simulator to Unit Differences

August 22, 2018

Training Slides: Introduction to Cause Analysis

November 16,

2016

13-NS-C088

Mission Time Study

Design Equivalent

Change 00462

Containment Construction Vent Concrete Cover Rework

and Design Drawing Detail Revision

Drawing 12-E-

2YU-009

Diesel Storage Tank Conduit Plan & Section

NLR17C030201

Licensed Operator Continuing Training

April 5, 2017

INFORMATION REQUESTS

ML18291A562

SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002

By: EAR Yes No

Publicly Available Sensitive

OFFICE

RI/IPAT

SRI/PBA

RI/PBD

C/PBD

SRI/IPAT

TL/IPAT

NAME

PJayroe

GKolcum

DReinert

NOKeefe

ERuesch

GMiller

SIGNATURE

/RA-e/

/RA-e/

/RA-e/

/RA/

/RA/

/RA GAG for/

DATE

9/21/2018

9/21/2018

9/21/2018

10/16/2018

10/16/2018

10/16/2018