IR 05000255/2019011

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000255/2019011

ML19336C651
Person / Time
Site:	Palisades
Issue date:	11/27/2019
From:	Robert Daley Engineering Branch 3
To:	Corbin D Entergy Nuclear Operations
References
IR 2019011
Download: ML19336C651 (8)

Text

November 27, 2019

SUBJECT:

PALISADES NUCLEAR PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000255/2019011

Dear Mr. Corbin:

On November 1, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant and discussed the results of this inspection with Mr. Dale Lucy and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety

Docket No. 05000255 License No. DPR-20

Enclosure:

As stated

Inspection Report

Docket Number:

05000255

License Number:

DPR-20

Report Number:

05000255/2019011

Licensee:

Entergy Nuclear Operations, Inc.

Facility:

Palisades Nuclear Plant

Location:

Covert, MI

Inspection Dates:

October 28, 2019 to November 01, 2019

Inspectors:

J. Neurauter, Senior Reactor Inspector

G. O'Dwyer, Reactor Engineer

D. Szwarc, Senior Reactor Inspector

Approved By:

Robert C. Daley, Branch Chief

Engineering Branch 3

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Palisades Nuclear Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

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

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for Title 10 of the Code of Federal Regulations (10 CFR) 50.59 from 2016 to 2019.

(1)17-0122, Changes to Technical Specification Bases 3.8.3 Concerning the Fuel Oil Transfer System, Revision 0 (2)19-021, EC 76687 / V24A/B/C/D Emergency Diesel Generator Room Ventilation Fans Modify Control Circuit to Resolve CR-PLP-2016-03456, Revision 0 (3)19-022, EC 76688 / V-27A/B/C/D Engineering Safeguards Room Ventilation Fans Modify Circuit to Resolve CR-PLP_2016-03456, Revision 0 (4)17-0030, EC 44749 - Calculation Spent Fuel Pool Dilation Analysis (Calculation EA-WJB-00-01 Revision 2), Revision 0 (5)16-0230, MSM-M-29, Lifting Equipment, Rigging and Tackle Inspection, Revision 0 (6)17-0060, EN-QV-137, Supplier Commercial Grade Survey Procedure, Revision 0 (7)17-0193, EN-DC-214, Freeze Seal Evaluations, Revision 0 (8)18-0191, EN-MA-159, Concrete Anchor Bolt Installation, Revision 0 (9)19-0093, EC 82734 - Temporary Modification to Block CV-3223, Shutdown Cooling Heat Exchanger Inlet Valve, Open during VOP-3223 Removal for Overhaul, Revision 1 (10)16-0201, Licensing Basis Document Change Request (LBDCR 16-048) for Final Safety Analysis Report Section 5.5, Revision 0 (11)18-0090, Technical Specifications Bases Limiting Condition for Operation 3.7.6, Revision 0 (12)17-0094, EC [Engineering Change] 72434: TSR [Temporary Shielding Request]

2017-095 "P-55B Charging Pump Discharge Line (Elbow on South End and Support Bracket Above FE-0212):, Revision 0 (13)19-028, EC 81574 Evaluate Station Battery Remaining Life Capacity Relative to Ambient Temperature, Revision 0 (14)16-0248, Revise RT-35, Inservice Inspection of Safety Related Components, Revision 0 (15)17-0081, EC 1743, 1R25 Flow Accelerated Corrosion Evaluations, Revision 0 (16)17-0089, Long Term Scaffold 17-026 in 607 Component Cooling Water, Revision 0 (17)17-0139, ACADIA 4 Software Application, Revision 0 (18)18-0135, EC 78263, Revise Calculation EA-GL-8910-02 Torque Loss Calculation for Motor Operated Valves at Elevated Temperatures, Revision 0 (19)18-0143, EC 78472, Temporary Leak Repair of Two 2 Elbow Fittings on Steam Trap Drain Line Upstream of MV-CD190, Isolation Valve for Condensate Return from Main Steam Lines Steam Traps, Revision 0 (20)19-0018, EN-CS-S-008-MULTI, Pipe Wall Thinning Structural Evaluation, Revision 0 (21)19-0046, EC 82059, MO-3010 Spring Hanger, Reconcile Setting, Revision 0 (22)16-0110, EAR [Engineering Assistance Request] 199-0081, "Chemical and Volume Control Declassification", Revision 0 (23)19-0010, Revision of EN-DC-315, Rev 15, Flow Accelerated Corrosion Program; Revision 0 (24)19-0034, change to FSAR Section 9.4.2.1, System Description, to add floating filter used to clear spent fuel pool water; Revision 0 (25)19-0056, COP-2, Chemical and Volume Control System Chemistry, Revision 67; Revision 0 (26)19-0113; Procedure Change SOP-24, Ventilation and Air Conditioning System; Revision

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On November 1, 2019, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Dale Lucy and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

EA-EC171743-01

Flow Accelerated Corrosion, 1R25 Non-Safety Related Wall

Thinning Evaluations

EA-EC171743-02

Flow Accelerated Corrosion, 1R25 Safety Related Wall

Thinning Evaluations

EA-EC171743-03

Engineering Analysis of Component ES-GB-2-E023

EA-WJB-00-01

Spent Fuel Pool Dilution Analysis

Corrective Action

Documents

CR-PLP-2016-

01143

Licensing Review of the NRC 4th Quarter 2015 Integrated

Inspection Report

03/07/2016

CR-PLP-2016-

05054

Temporary Shield Requests for the Charging Pump Cubicles

Beyond Allowed Installation Time

10/21/2016

CR-PLP-2017-

00364

Documentation Deficiencies in Process Applicability

Determination Forms

01/30/2017

CR-PLP-2017-

225

Legacy Shielding Installed in Evaporator Concentrate Tank

and Pump Rooms

09/14/2017

CR-PLP-2019-

00387

Remove Temporary Measuring and Test Equipment within

Days of Installation Or Perform 50.59 Screening for

Measuring and Test Equipment to Remain Installed Beyond

Days

01/24/2019

CR-PLP-2019-

01872

ADMIN 7.14 Does Not Address Extending Temporary

Shielding Request Beyond Approved Duration

05/07/2019

CR-PLP-2019-

03552

Pre-NRC Inspect Audit Identified, Identified Improperly

Completed Process Applicability Determination

09/10/2019

WT-WTPLP-

2017-00011

Evaluate Addressing Maintaining the Seismic Adequacy of

the Chemical and Volume Control System

01/31/2017

Corrective Action

Documents

Resulting from

Inspection

CR-PLP-2019-

04362

PAD Log Number 17-0139 had Incorrect Boxes Checked

10/30/2019

CR-PLP-2019-

04379

Calculation Incorrectly Set to Historical in Electronic

Database

10/31/2019

CR-PLP-2019-

04381

Configuration Enhancements were Identified Related to

Seismic Requirements in the Equipment Database

10/31/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Changes

76687

V-24A/B/C/D Emergency Diesel Generator Rooms

Ventilation Fans Modify Control Circuit to Resolve CR-PLP-

2016-03456

76688

V-27A/B/C/D Engineered Safeguards Rooms Cooler Fans

Modify Control Circuit to Resolve CR-PLP-2016-03456

2059

MO-3010 Spring Hanger, Reconcile Setting Basis

Miscellaneous

Licensing Basis

Document

Change Request

16-048

Revise Final Safety Analysis Report Section 5.5.1 to Delete

Site Specific Tornado Missiles

10/06/2016

Licensing Basis

Document

Change Request

17-0010

Clarify Section 5.5.1 of Final Safety Aanalysis Report

(Tornado Missiles) to Accurately Reflect Licensing and

Design Bases of Plant

04/24/2017

Procedures

EN-CS-S-008-

MULTI

Pipe Wall Thinning Structural Evaaluation

EN-DC-214

Freeze Seal Evaluations

EN-LI-100

Process Applicability Determination

EN-MA-119-01

Control, Storage, and Inspection of Lifting Equipment

EN-MA-159

Anchor Bolt Installation

EN-QV-137

Supplier Commercial Grade Survey Procedure

Work Orders

2705342-01

Spent Fuel Pool Level and Temperature Instrument

Checkout

01/02/2018

2750453-01

LE/LI-2141 Pre-Refuel Outage Functional Check

09/21/2018

2750454-01

LE/LI-2142 Pre-Refuel Outage Functional Check

09/21/2018

2837472-01

LE/LI-2141 Channel Functional Check

08/20/2019

2837473-01

LE/LI-2142 Channel Functional Check

09/16/2019