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

ber 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 Enterprise Identifier: I-2019-011-0048 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations EA-EC171743-01 Flow Accelerated Corrosion, 1R25 Non-Safety Related Wall 0

Thinning Evaluations

EA-EC171743-02 Flow Accelerated Corrosion, 1R25 Safety Related Wall 0

Thinning Evaluations

EA-EC171743-03 Engineering Analysis of Component ES-GB-2-E023 0

EA-WJB-00-01 Spent Fuel Pool Dilution Analysis 2

Corrective Action CR-PLP-2016- Licensing Review of the NRC 4th Quarter 2015 Integrated 03/07/2016

Documents 01143 Inspection Report

CR-PLP-2016- Temporary Shield Requests for the Charging Pump Cubicles 10/21/2016

05054 Beyond Allowed Installation Time

CR-PLP-2017- Documentation Deficiencies in Process Applicability 01/30/2017

00364 Determination Forms

CR-PLP-2017- Legacy Shielding Installed in Evaporator Concentrate Tank 09/14/2017

225 and Pump Rooms

CR-PLP-2019- Remove Temporary Measuring and Test Equipment within 01/24/2019

00387 90 Days of Installation Or Perform 50.59 Screening for

Measuring and Test Equipment to Remain Installed Beyond

Days

CR-PLP-2019- ADMIN 7.14 Does Not Address Extending Temporary 05/07/2019

01872 Shielding Request Beyond Approved Duration

CR-PLP-2019- Pre-NRC Inspect Audit Identified, Identified Improperly 09/10/2019

03552 Completed Process Applicability Determination

WT-WTPLP- Evaluate Addressing Maintaining the Seismic Adequacy of 01/31/2017

2017-00011 the Chemical and Volume Control System

Corrective Action CR-PLP-2019- PAD Log Number 17-0139 had Incorrect Boxes Checked 10/30/2019

Documents 04362

Resulting from CR-PLP-2019- Calculation Incorrectly Set to Historical in Electronic 10/31/2019

Inspection 04379 Database

CR-PLP-2019- Configuration Enhancements were Identified Related to 10/31/2019

04381 Seismic Requirements in the Equipment Database

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering 76687 V-24A/B/C/D Emergency Diesel Generator Rooms 0

Changes Ventilation Fans Modify Control Circuit to Resolve CR-PLP-

2016-03456

76688 V-27A/B/C/D Engineered Safeguards Rooms Cooler Fans 0

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

2059 MO-3010 Spring Hanger, Reconcile Setting Basis 0

Miscellaneous Licensing Basis Revise Final Safety Analysis Report Section 5.5.1 to Delete 10/06/2016

Document Site Specific Tornado Missiles

Change Request

16-048

Licensing Basis Clarify Section 5.5.1 of Final Safety Aanalysis Report 04/24/2017

Document (Tornado Missiles) to Accurately Reflect Licensing and

Change Request Design Bases of Plant

17-0010

Procedures EN-CS-S-008- Pipe Wall Thinning Structural Evaaluation 2

MULTI

EN-DC-214 Freeze Seal Evaluations 3

EN-LI-100 Process Applicability Determination 26

EN-MA-119-01 Control, Storage, and Inspection of Lifting Equipment 9

EN-MA-159 Anchor Bolt Installation 1

EN-QV-137 Supplier Commercial Grade Survey Procedure 2

Work Orders 52705342-01 Spent Fuel Pool Level and Temperature Instrument 01/02/2018

Checkout

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

6