IR 05000458/2022011

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Design Basis Assurance Inspection (Programs) Inspection Report 05000458/2022011
ML22131A364
Person / Time
Site: River Bend Entergy icon.png
Issue date: 06/02/2022
From: Vincent Gaddy
NRC/RGN-IV/DORS/EB1
To: Karenina Scott
Entergy Operations
References
IR 2022011
Download: ML22131A364 (13)


Text

June 02, 2022

SUBJECT:

RIVER BEND STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000458/2022011

Dear Mr. Scott:

On April 21, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at River Bend Station and discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at River Bend Station.

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 River Bend 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Vincent G. Gaddy, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket No. 05000458 License No. NPF-47

Enclosure:

As stated

Inspection Report

Docket Number:

05000458

License Number:

NPF-47

Report Number:

05000458/2022011

Enterprise Identifier:

I-2022-011-0008

Licensee:

Entergy Operations, Inc

Facility:

River Bend Station

Location:

St. Francisville, LA

Inspection Dates:

April 04, 2022 to April 22, 2022

Inspectors:

W. Cullum, Reactor Inspector

D. Reinert, Reactor Inspector

W. Sifre, Senior Reactor Inspector

Approved By:

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at River Bend Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Failure to follow the Corrective Action Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000458/2022011-01 Open

[H.11] -

Challenge the Unknown 71111.21N.

The inspectors identified a Green finding and associated Non-cited violation (NCV) of 10CFR50 Appendix B, Criterion V, Procedures, when the licensee failed to follow their Corrective Action Program procedure.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

Specific Guidance b. Determined whether the sampled POVs are capable of performing their design-basis functions.

c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).

(1) Reactor Building Equipment Drain Inboard Containment Isolation Valve - Air Operated Valve DER-AOV126
(2) Containment and Drywell Floor Drain Sump Pump Discharge Header Inboard Containment Isolation Valve - Air Operated Valve DFR-AOV101
(3) Residual Heat Removal Pump Shutdown Cooling Inboard Isolation Valve - Motor Operated Valve E12-MOVF009
(4) Residual Heat Removal Pump A Injection Line Shutoff Valve - Motor Operated Valve E12-MOVF027A
(5) Low Pressure Core Spray Pimp Low Pressure Core Spray Injection Shut Off Valve - Motor Operated Valve E21-MOVF005
(6) High Pressure Core Spray Pump Discharge Line Main Isolation Valve - Motor Operated Valve E22-MOVF004
(7) Reactor Core Isolation Cooling & Residual Heat Removal Systems Steam Supply Isolation Valve - Motor Operated Valve E51-MOVF063
(8) Reactor Core Isolation Cooling Steam Supply Line Outboard Containment Isolation Valve - Motor Operated Valve E51-MOVF064
(9) Suppression Pool Cleanup & Cooling System Suction Valve - Air Operated Valve RHS-AOV63
(10) Standby Service Water Pump A Discharge Isolation Valve - Motor Operated Valve SWP-MOV40A
(11) Drywell Unit Coolers Supply Header A Outboard Containment Isolation Valve - Motor Operated Valve SWP-MOV507A
(12) Standby Cooling Tower 1 Division 2 Return Line Isolation Valve - Motor Operated Valve SWP-MOV55B

INSPECTION RESULTS

Failure to follow the Corrective Action Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000458/2022011-01 Open

[H.11] -

Challenge the Unknown 71111.21N.0 The inspectors identified a Green finding and associated Non-cited violation (NCV) of 10CFR50 Appendix B, Criterion V, Procedures, when the licensee failed to follow their Corrective Action Program procedure.

Description:

The inspectors reviewed an as-found Motor-Operated Valve static test, dated March 8, 2021, of E22-MOVF004, HPCS Discharge Line Main Isolation Valve, and noted that the licensee documented negative margin in the test results. Since a negative margin falls outside of the acceptance criteria, the inspectors asked to review the condition report to assess the operability determination and corrective actions for the valve. The inspectors were informed that a condition report was not generated to document the negative margin. The site procedure EN-LI-102, Revision 47, titled, "Corrective Action Program," Section 5.2, Step 5, states, "Employees and contractors are required to initiate condition reports for adverse conditions." This procedure also defines adverse condition, in part, as "A general term which includes Conditions Adverse to Quality plus undesirable conditions related to... design basis."

Since the Motor-Operated Valve had negative margin, there was reasonable doubt as to whether the valve could perform its design basis function if called upon. Similarly, inspectors reviewed an as-left Motor-Operated valve static test, dated February 28, 2013, of E21-MOVF005, LPCS Injection Shut Off Valve, and noted that it also had negative margin. No condition report was written to document this occurrence of negative margin either. In both circumstances, the licensee used conservatisms within the calculations to determine that margin still existed and the valves were considered operable.

Corrective Actions: The licensee took action to restore margin to the affected valves. By using conservatisms in the calculations and revising assumptions, the valves were left with positive margin and, therefore, in an operable condition. The licensee entered the margin deficiencies and failure to write a condition report into their corrective action program.

Corrective Action References: CR-RBS-2022-02005, CR-RBS-2022-02241

Performance Assessment:

Performance Deficiency: The licensee failed to follow procedures for activities affecting quality as required by 10CFR50 Appendix B Criterion V, Procedures. Specifically, the licensee failed to follow Step 5 of Section 5.2 of procedure EN-LI-102, "Corrective Action Program," which states, "Employees and contractors are required to initiate a Condition Report for adverse conditions." The inspectors identified 2 examples of this performance deficiency.

First, on March 8, 2021, a Condition Report was not written to document an adverse condition when the As Found Motor-Operated Valve static test of E22-MOVF004, HPCS Discharge Line Main Isolation Valve, showed negative margin in the open direction.

Second, on February 28, 2013, a Condition Report was not written to document an adverse condition when the As Left Motor-Operated Valve static test of E21-MOVF005, LPCS Injection Shut Off Valve, showed negative margin in the open direction.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance 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. Specifically, regardless of the final operability or functionality, the as-found condition was such that there was a reasonable doubt whether E22-MOVF004 and E21-MOVF005 would have been capable of performing their functions had they been called upon since the safety-related Motor-Operated Valves had negative margin. When the licensee evaluated the as found condition, they determined that the remaining margin falls outside of the design process acceptance criteria and assumptions were revised solely to obtain favorable results.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors screened the issue using Inspection Manual Chapter 0609 Appendix A titled "The Significance Determination Process for Findings At-Power." The issue screened to Green using Exhibit 2, "Mitigating Systems Screening Questions," since the degraded condition did not represent a loss of the PRA function of a single train Technical Specification system for greater than its allowed outage time.

Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. The inspectors found the most recent example on March 8, 2021, is indicative of present performance. The inspectors selected this cross-cutting aspect because they found that the licensee did not stop when faced with uncertain conditions. The negative margin was resolved without entering the corrective action process. As a result, opportunities were missed to evaluate the cause and determine operability of components.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Procedures requires, in part, that the licensee prescribe and accomplish activities affecting quality by documented instructions, procedures, or drawings of a type appropriate to the circumstances. Procedure EN-LI-102, Corrective Action Program, Revision 20 Step 5.2[1](e) and Revision 42 Step 5.2.4, require, in part, that employees are required to initiate condition reports for adverse conditions.

Contrary to the above, on February 18, 2013, and March 8, 2021, the licensee failed to initiate a condition report for an adverse condition. Specifically, on February 28, 2013, a condition report was not generated to document negative margin found during an as-left static test of E21-MOVF005, LPCS Injection Shut Off Valve, and on March 8, 2021, a condition report was not generated to document negative margin found during an as-found static test of E22-MOVF004, HPCS Discharge Line Main Isolation Valve.

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

EXIT MEETINGS AND DEBRIEFS

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

On April 21, 2022, the inspectors presented the design basis assurance inspection (programs) inspection results to Kent Scott and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02

Calculations

21.412-000-

007C

Maximum Thrust Weak Link Seismic Calculation

B

71111.21N.02

Calculations

28.212-047-

019C

Design Report 10" 600lb Gate Valve Weak Link

71111.21N.02

Calculations

28.212-047-

24C

Seismic Analysis Report 10" 600lb Gate Valve

71111.21N.02

Calculations

28.212-047-

040C

Weak Link Analysis - Seismic Qualification of Motor

Operated Valves

B

71111.21N.02

Calculations

28.243-105-

007A

Weak Link and Seismic Analysis SWP-MOV40A

A

71111.21N.02

Calculations

G13.18.15.2*053

Maximum Thrust Force for Valves E12-MOVF042A,

2B, and 042C and E21-MOVF005

71111.21N.02

Calculations

G13.18.2.3*148

G.L. 89-10 Design Basis Review for E12-MOVF004A/B

71111.21N.02

Calculations

G13.18.2.3*157

G.L. 89-10 Design Basis Review for E12-MOVF027A/B

71111.21N.02

Calculations

G13.18.2.3*178

GL 89-10 Design Basis Review for E21-MOVF005

71111.21N.02

Calculations

G13.18.2.3*182

GL 89-10 Design Basis Review for E22-MOVF004

71111.21N.02

Calculations

G13.18.2.3*206

G.L. 89-10 Design Basis Review for E51-MOVF063 & 064

71111.21N.02

Calculations

G13.18.2.3*206

G. L. 89-10 DESIGN BASIS REVIEW FOR E51-

MOVF063 & F064

71111.21N.02

Calculations

G13.18.2.3*282

GL 89-10 Design Basis Review for SWP-MOV40A/B/C/D

71111.21N.02

Calculations

G13.18.2.3*290

G.L. 89-10 Design Basis Review for SWP-MOV81A/B &

507A/B

71111.21N.02

Calculations

G13.18.2.3*316

GL 96-05 MOV Periodic Static Test Frequency

71111.21N.02

Calculations

G13.18.2.3*325

River Bend Station NRC Generic Letter 96-05 AC MOV

Actuator Output Capability Calculation

71111.21N.02

Calculations

G13.18.2.3*339

Air Operated Valve Program System Level Calculation for

Reactor Building Equipment and Floor Drain System

(System 609)

71111.21N.02

Calculations

G13.18.2.3*345

Air Operated Valve Component Level Calculation for

Valve DFR-AOV101 and DFR-AOV102

71111.21N.02

Calculations

G13.18.2.6*183

High Pressure Core Spray System Hydraulic Performance

71111.21N.02

Corrective Action

CR-RBS-

2011-08093, 2014-03977, 2017-01907, 2019-02889,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

21-02048, 2021-02286, 2021-02626, 2021-07651,

1992-00673, 2017-02471, 2018-06872, 2019-04679,

21-01871, 2007-00351, 2017-00936, 2017-01811,

2018-02890, 2018-06782, 2020-04845, 2021-02049,

21-04891, 2021-07355, 2022-01833, 2014-00633,

2011-08093, 2014-03977, 2019-02373, 2021-01884

71111.21N.02

Corrective Action

Documents

Resulting from

Inspection

CR-HQN-

22-00732, 2022-00754

71111.21N.02

Corrective Action

Documents

Resulting from

Inspection

CR-RBS-

22-02013, 2022-01977, 2022-01978, 2022-01980,

22-02005, 2022-02061, 2022-02062, 2022-02063,

22-02065, 2022-02066, 2022-02067, 2022-02069,

22-02070, 2022-02088, 2022-02125, 2022-02241

71111.21N.02

Engineering

Changes

EC 0000039724

Adjust Limit Switch Settings for 2 MOVS, E22-MOVF004

and G33-MOVF054

71111.21N.02

Engineering

Changes

EC 60680

Provide HELB Scenario MOVs at Degraded Voltage in a

Design Basis Calculation for E51-MOVF063, E51-

MOVF064, G33-MOVF001, & G33-MOVF004

71111.21N.02

Engineering

Changes

EC 86640

Design/Seismic/Weak Link Analysis Report for 8" Gate

Valve

71111.21N.02

Engineering

Evaluations

MC-96-007

Motor Operated Valve Program Closure Report

71111.21N.02

Engineering

Evaluations

VA-7230.439-

000-009A

Weak Link Analysis for 30-IN. Tricentric Valves

71111.21N.02

Miscellaneous

AF E22-

MOVF004

As Found MOV Static Test Report

03/08/2021

71111.21N.02

Miscellaneous

AR 21006476

RBS Post R21 Static Test Frequency Changes for the

MOV Program

08/04/2021

71111.21N.02

Miscellaneous

E21-MOVF005-

ST-001

MOV Static Test Report

07/28/1992

71111.21N.02

Miscellaneous

E21-MOVF005-

ST-002

MOV Static Test Report

09/18/1997

71111.21N.02

Miscellaneous

E21-MOVF005-

MOV Static Test Report

2/20/2008

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ST-003

71111.21N.02

Miscellaneous

E21-MOVF005-

ST-004

MOV Static Test Report

2/28/2013

71111.21N.02

Miscellaneous

E21-MOVF005-

ST-005

MOV Static Test Report

03/13/2020

71111.21N.02

Miscellaneous

VTD-F130-0131

Instruction Manual for Type 667 Diaphragm Actuator

Sizes 30-76 and 87

71111.21N.02

Procedures

CEP-APJ-001

Primary Containment Leakage Rate Testing Program

Plan

71111.21N.02

Procedures

EN-DC-117

Post-Modification Testing and Special Instructions

71111.21N.02

Procedures

EN-DC-304

MOV Thrust Torque Setpoint Calculations

71111.21N.02

Procedures

EN-DC-311

MOV Periodic Verification

71111.21N.02

Procedures

EN-DC-312

Motor Operated Valve MOV Test Data Review

71111.21N.02

Procedures

EN-DC-331

MOV Program

71111.21N.02

Procedures

EN-DC-334

Primary Containment Leakage Rate Testing (Appendix J)

71111.21N.02

Procedures

EN-EP-S-003-

MULTI

ENS Magnesium Motor MOV Management Plan

71111.21N.02

Procedures

EN-LI-102

Corrective Action Program

71111.21N.02

Procedures

EN-MA-107

Post-Maintenance Testing

71111.21N.02

Procedures

OSP-0047

Local Leak Rate Testing Implementation

71111.21N.02

Procedures

SEP-APJ-004

Primary Containment Leakage Rate Testing Program

71111.21N.02

Procedures

SOP-0140

Suppression Pool Cleanup and Alternate Decay Heat

Removal

71111.21N.02

Procedures

STP-057-3800

Local Leak Rate Test - Outage Summation

71111.21N.02

Procedures

STP-204-6304

Div II RHR Quarterly Valve Operability Test

71111.21N.02

Procedures

STP-209-3818

RCIC Penetration KJB-Z15 Valve Leak Rate Test

71111.21N.02

Work Orders

WO-RBS-

00067202, 00111606, 00232968, 00361059, 00377354,

00419530, 52247989, 52763221, 52895690, 00408614,

00442627, 00523754, 00539666, 52670970, 52766967,

2800959, 52810875, 52896350, 52863845, 52863911,

00442627, 00222817, 00408614, 00178505, 00222817,

00469591, 00484868, 00494597, 00496171, 00513196,

00518871, 00518871, 00518871, 00525607, 00543336,

00553907, 00560225, 52441262, 52560099, 52560101,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2639670, 52639815, 52723206, 52767232, 52769527,

2771072, 52825271, 52830247, 52898905, 52902937,

2920964, 52887116,