ML19123A174

NRC Integrated Inspection Report 05000255/2019001

ML19123A174
Person / Time
Site:	Palisades
Issue date:	05/03/2019
From:	Dariusz Szwarc NRC/RGN-III/DRP/B2
To:	Arnone C Entergy Nuclear Operations
References
IR 2019001
Download: ML19123A174 (15)

See also: IR 05000255/2019001

Text

May 3, 2019

Mr. Charles Arnone

Vice President, Operations

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant

27780 Blue Star Memorial Highway

Covert, MI 49043-9530

SUBJECT: PALISADES NUCLEAR PLANT, UNIT 1NRC INTEGRATED INSPECTION

REPORT 05000255/2019001

Dear Mr. Arnone:

On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at your Palisades Nuclear Plant, Unit 1. On April 16, 2019, the NRC inspectors 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.

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/

Dariusz Szwarc, Acting Chief

Branch 2

Division of Reactor Projects

Docket No.: 05000255

License No.: DPR-20

Enclosure:

Inspection Report 05000255/2019001

cc: Distribution via LISTSERV

ML19123A174

SUNSI Review Complete ADAMS Publicly Non- Keyword:

By: Dariusz Szwarc Yes Available Sensitive NRC-002

No Non-Publicly Sensitive

Available

OFFICE RIII

NAME DSzwarc:bw

SIGNATURE /RA/

DATE 5/3/2019

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 05000255

License Number: DPR-20

Report Number: 05000255/2019001

Licensee: Entergy Nuclear Operations, Inc.

Facility: Palisades Nuclear Plant, Unit 1

Location: Covert, MI 49043

Inspection Dates: January 01, 2019 to March 31, 2019

Inspectors: J. Boettcher, Resident Inspector

J. Bozga, Senior Reactor Inspector

I. Hafeez, Reactor Inspector

P. Laflamme, Senior Resident Inspector

Approved By: Dariusz Szwarc, Acting Chief

Branch 2

Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees

performance by conducting a quarterly inspection at Palisades Nuclear Plant, Unit 1 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.

List of Findings and Violations

No findings or violations were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status

URI 05000255/2017007-02 Containment Dome Truss 71111.21M Closed

Analysis

LER 05000255/2019-001-00 LER 2019-001-00 for Palisades 71153 Closed

Nuclear Plant, Reactor

Protection System and Auxiliary

Feedwater System Actuation

due to Turbine Governor Valve

Failure.

LER 05000255/2019-002-00 LER 2019-002-00 for Palisades 71153 Closed

Nuclear Plant, Automatic Reactor Trip and AFW System

Actuation Due to the Loss of

Power to the RPS BD Matrix.

2

PLANT STATUS

The plant began the inspection period in power ascension from 80 percent after completing the

refueling outage on December 28, 2018. Full power operation was achieved on January 2,

2019, and the reactor remained at or near rated thermal power until January 3, 2019. On

January 3, 2019, operators reduced power to approximately 85 percent to complete repairs to

CV-0605, feedwater heater E-6B level control valve. The unit was manually tripped on the

same day due to oscillations on main turbine governor valve #4. After completing repairs on

governor valve #4, the reactor was taken critical on January 5, 2019, and reached full power

operation on January 7, 2019. On January 9, 2019, an automatic reactor trip occurred due to a

loss of power to the reactor protection system BD matrix. Following successful repairs to the

reactor protection system, the reactor was taken critical on January 11, 2019. The reactor

reached full power operation on January 12, 2019, and remained at our near rated thermal

power for the remainder of the inspection period.

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 performed plant status activities described in

IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem

Identification and Resolution. 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

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.03) (1 Sample)

The inspectors evaluated readiness for impending adverse weather conditions for a winter

storm with extreme cold temperatures, gale force winds, and heavy snow on

January 29, 2019.

71111.04 - Equipment Alignment

Partial Walkdown (IP Section 02.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1) Right train Auxiliary Feedwater (AFW) with P-8B AFW Pump out of service for

maintenance on February 7, 2019;

(2) Left train Safety Injection (SI) system during right train SI surveillance testing on

February 20, 2019; and

3

(3) Service Water (SW) pump P-7B during 1-2 Emergency Diesel Generator (EDG)

planned maintenance on March 18, 2019.

71111.04S - Equipment Alignment

Complete Walkdown (IP Section 02.02) (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the 1-1 and

1-2 EDG systems from March 21 through March 25, 2019.

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01) (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

(1) Fire Area 3: North Cableway and 1D Switchgear Room, and Fire Area 21: Electrical

Equipment Room, on January 16, 2019;

(2) Fire Area 26: Southwest Cable Penetration Room on February 6, 2019;

(3) Fire Area 13G: Spent Fuel Pool (SFP) Heat Exchanger Room on February 27, 2019;

(4) Fire Area 16: Component Cooling Pump Room on February 27, 2019; and

(5) Fire Area 17: Refueling and SFP area on March 12, 2019.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

Emergency Diesel Generator (EDG) rooms from March 11 through March 13, 2019.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(2 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the Control

Room during a downpower for emergent repairs to CV- 0605 and a start up from trip

between January 3 and January 5, 2019; and

(2) The post reactor trip actions and startup between January 9 and January 11, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

The inspectors observed and evaluated Licensed Operator Requalification Training Annual

Exam PL-N00320 on March 6, 2019.

4

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated with

the following equipment and/or safety significant functions:

(1) 480 VAC power system after failure of EX-12 transformer which occurred on October

15, 2018; and

(2) Main steam system after failure of #4 governor valve on January 3, 2019.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent work

activities:

(1) Emergent repairs to CV-0605, feedwater heater E-6B level control valve, on

January 3, 2019;

(2) Emergent troubleshooting of control rod drive (CRD) mechanism 24 after dropped rod

alarm on January 10, 2019;

(3) 6A feedwater heater temperature variations impacting heat balance calculations on

January 17, 2019;

(4) Emergent troubleshooting and repairs to Control Room HVAC system on

January 25, 2019; and

(5) Elevated risk for 1-2 EDG planned maintenance window during the week of

March 18, 2019.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determinations and Functionality Assessments (IP Section 02.01) (4 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) AFW Pump P-8B as documented in CR-PLP-2019-00180 on January 14, 2019;

(2) SV-3057A/B, air supply for CV-3057 Safety Injection and Refueling Water Tank

(SIRWT) outlet valve as documented in CR-PLP-2019-00715 during the week of

February 19, 2019;

(3) Low pressure SI pump P-67B suction valve open thrust evaluation as documented in

CR-PLP-2019-00944 on March 22, 2019; and

(4) Evaluation of scaffolding in contact with Bus 1C as documented in CR-PLP-2019-

01206 on March 25, 2019.

5

71111.19 - Post Maintenance Testing

Post Maintenance Test Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the following post maintenance tests:

(1) QO-3 after Reactor Protection System (RPS) power supply and fuse replacement on

January 10, 2019;

(2) Testing after V-95 Control Room ventilation main supply fan auxiliary motor starter

relay replacement on January 25, 2019;

(3) RO-145 after P-8B AFW pump maintenance on February 7, 2019;

(4) QO-16 after P-54B containment spray pump maintenance on February 13, 2019;

(5) QO-5 after MO-3062, high pressure SI train 2 to Loop 2B valve insulation resistance

and polarization index megger testing on February 25, 2019;

(6) MO-7A-1 after 1-1 EDG maintenance on March 4 and 5, 2019; and

(7) QO-14 after P-7A SW pump repack on March 15, 2019.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)

(1) The inspectors evaluated the 1F27 reactor trip outage activities from January 3 to

January 5, 2019; and

(2) 2F27 reactor trip outage activities from January 9 to January 11, 2019.

71111.21M - Design Bases Assurance Inspection (Teams)

Review of Operating Experience Issues (IP Section 02.06) (1 Partial)

The inspectors completed their review of Unresolved Item (URI) 05000255/2017007-03:

Containment Dome Truss Analysis. The inspectors review and closure of this URI did not

constitute an inspection sample.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

In Service Testing (IST) (IP Section 03.01) (1 Sample)

QO-19, P-66B High Pressure Safety Injection (HPSI) pump and engineered safeguards

system check valve operability test on January 14, 2019.

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) PO-1, Operations Pre-Startup tests on January 10, 2019; and

(2) QI-3, Reactor Protection Matrix logic tests on March 4, 2019.

6

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (1 Sample)

Unit 1 (January 1, 2018 - December 31, 2018)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

Unit 1 (January 1, 2018 - December 31, 2018)

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

Unit 1 (January 1, 2018 - December 31, 2018)

71152 - Problem Identification and Resolution

Annual Follow-Up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issues:

45-Year Containment Tendon Surveillance Summary Report Review

71153 - Follow-Up of Events and Notices of Enforcement Discretion

Event Follow-Up (IP Section 03.01) (3 Samples)

(1) The inspectors evaluated a manual reactor trip and AFW system actuation due to

turbine governor valve #4 failure and licensee's response on January 3, 2019; and

(2) An automatic reactor trip and AFW system actuation due to the loss of power to the

Reactor Protection System BD Matrix and licensees response on January 9, 2019.

(3) The inspectors evaluated [description of event] and licensees response on [date].

Event Report (IP Section 03.02) (2 Samples)

The inspectors evaluated the following licensee event reports which can be accessed at

https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) LER 2019-001-00, Reactor Protection System and AFW System Actuation due to

Turbine Governor Valve Failure, ADAMS accession number ML19059A082.

The inspectors determined that it was not reasonable to foresee or correct the cause

discussed in the LER therefore no performance deficiency was identified. The

inspectors also concluded that no violation of NRC requirements occurred.

7

(2) LER 2019-002-00, Automatic Reactor Trip and AFW System Actuation due to the

Loss of Power to the RPS BD Matrix, ADAMS accession number ML19059A136.

The circumstances surrounding this LER are documented in the Results section.

INSPECTION RESULTS

Unresolved Item Containment Dome Truss Analysis 71111.21M

(Closed)05000255/2017007-02

Description: The inspectors reviewed additional information provided by the licensee regarding

design and licensing basis and consulted with technical staff from the Office of Nuclear

Reactor Regulation (NRR) to ascertain licensing basis and technical adequacy. Based on this

review, the inspectors sufficiently resolved these concerns and consider URI

05000255/2017007-03 closed. Specifically, the inspectors did not identify any actions

inconsistent with the licensing basis or technically inadequate with respect to these concerns.

Corrective Action Reference: CR 2017-05016, Dome Trusses, dated November 1, 2017

Observation 71152

The licensee documented in condition report CR-PLP-2018-04976 that during the analysis of

the grease for containment tendon V-24, the water content in the corrosion medium was 16

percent. The ASME Section XI Article IWL 3221.4 acceptance criteria is 10 percent for water

content in the corrosion medium as delineated in ASME Section XI Table IWL-2525-1. The

licensee performed an evaluation in accordance with ASME Section XI Article IWL 3222. The

inspectors reviewed this evaluation and no performance deficiencies were identified.

LER LER 2019-002-00 for Palisades Nuclear Plant, Automatic 71153

(Closed) Reactor Trip and AFW System Actuation Due to the Loss

of Power to the RPS BD Matrix.

05000255/2019-002-00

Description: On January 9, 2019, the licensee experienced an automatic reactor trip and valid

actuation of the AFW system. All safety systems and shutdown equipment performed as

expected. The direct cause of the event was identified to be a loss of all power to the RPS BD

matrix due to shorted capacitors associated with the RPS B channel and a blown input fuse

associated with the RPS D channel BD matrix power supply. The loss of power to the RPS BD

matrix resulted in an automatic reactor trip per RPS design. The licensee replaced the RPS B

channel capacitors with insulated capacitors and the RPS D channel BD matrix power supply

and fuse were replaced as part of their corrective actions. Additionally, the licensee sent the

RPS D channel BD matrix power supply and fuse to the vendor for failure

evaluation. The licensee planned to review the results of this failure evaluation to determine if

any further corrective actions are required.

The inspectors reviewed the LER submittal for accuracy and completeness of

information. The completed and planned corrective actions were reviewed for appropriateness

by the inspectors. No performance deficiencies were identified.

8

EXIT MEETINGS AND DEBRIEFS

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

• On April 16, 2019, the inspector presented the quarterly integrated inspection results to

Mr. C. Arnone and other members of the licensee staff.

• On March 21, 2019, the inspector presented the URI 2017007-02, Containment Dome

Truss Analysis to Mr. K. O'Connor, Engineering Director and other members of the

licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- CR-PLP-2019-00382; Main Transformer Low Oil Flow Alarm; 01/25/2019

- CR-PLP-2019-00393; P-74 SIRW Tank Recirculation Pump Not Running; 01/25/2019

- CR-PLP-2019-00414; VUH Turbine Unit Heater Not Running; 1/27/2019

- SOP-14; Circulating Water and Chlorination Systems; Revision 89

- SOP-15; Service Water System; Revision 68

- SOP-23; Plant Heating System; Revision 61

71111.04Equipment Alignment

- CR-PLP-2019-00388; SIT T-82B Decreasing Trend; 01/25/2019

- CR-PLP-2019-00614; NRC Identified Light Housing Touching P-8D Piping; 02/08/2019

- CR-PLP-2019-00615; NRC Identified Current Positions of MV-FW60004 and MV-FW60005

are Throttled; 02/08/2019

- CR-PLP-2019-00629; Following the Condition Identified in CR-PLP-2019-00615; the

Remainder of Checklist 12/5, was Walked Down by Operations as an Extent of Condition;

02/09/2019

- CR-PLP-2019-01104; Vibration Analyzer did not Perform as Expected During Service Water

Testing; 03/15/2019

- DBD-5.01; Diesel Engine and Auxiliary Systems, Revision 7

- M-207; Piping & Instrument Diagram, Auxiliary Feedwater System; Sheet 2, Revision 44

- M-214; Lube Oil, Fuel Oil & Diesel Generator Systems; Sheet 1, Revision 81

- M-220; Piping & Instrument Diagram, Make-Up Domestic Water & Chemical Injection

Systems; Sheet 1, Revision 105

- SOP-12; Feedwater System; Revision 79

- SOP-22; Emergency Diesel Generators; Revision 75

71111.05AQFire Protection Annual/Quarterly

- DBD-7.10; NFPA 805 Fire Protection Program; Revision 3

- EA-FPP-03-001; Analysis of Combustible Loading at Palisades Nuclear Plant; Revision 4

- Pre-Fire Plan 13G; Spent Fuel Pool Heat Exchanger Room; Elevation 590

- Pre-Fire Plan 16; Component Cooling Water Room; Elevation 590

- Pre-Fire Plan 21; Electrical Equipment Room; Elevation 607-6

- Pre-Fire Plan 26; Southwest Cable Penetration Room; Elevation 590 & 607

- Pre-Fire Plan 3; North Penetration Room & North Cableway; Elevation 625

9

71111.06Flood Protection Measures

- AOP-39; Internal Plant Flooding; Revision 1

- CR-PLP-2019-01053; NRC Identified Door-170, Entrance to both Diesel Generator Rooms

from Outside, has its Dogs not in Contact with the Door; 03/13/2019

- DBD-7.08; Plant Protection Against flooding; Revision 6

- EC-82056; Watertight Door 170 - Middle Two Dogs on East Side not Fully Engaged;

Revision 0

- M-208; Piping & Instrument Diagram, Service Water System; Sheet 1A; Revision 67

- M-216; Piping & Instrument Diagram, Fire Protection System; Sheet 2; Revision 72

- WO 331182; CK-RW419, Diesel Generator Room Floor Drain Check Valve Post-Maintenance;

04/02/2014

- WO 331183; CK-RW420, Diesel Generator Room Floor Drain Check Valve Post-Maintenance;

08/30/2013

- WO 52457272; Test Operation of LS-5211, LS-5217, and LS-5218; 12/15/2016

- WO 52773249; Diesel Generators and D Bus Floor Drain Flow Verification; 07/27/2018

- WO 52775537; Annual Inspection of Watertight Barriers; 08/07/2018

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- CR-PLP-2019-00937; Licensed Operator Qualifications Removed; 03/06/2019

- SOP-8; Main Turbine and Generating Systems; Revision 107

- EOP-1.0; Standard Post-Trip Actions; Revision 21

71111.12Maintenance Effectiveness

- AR 18014838; PMCR for Approval of PMOS Dry Type Transformer Template Deviations;

02/28/2019

- CR-PLP-2003-01903; Trip of the A Charging Pump Breaker 52-1205; 03/19/2003

- CR-PLP-2014-00042; K-Line 480V Circuit Breakers Identified Subject ABB Part 21;

01/03/2014

- CR-PLP-2016-5341; Screen Wash Pump Breaker Spring Charging Motor Failure; 11/02/2016

- CR-PLP-2018-04747; Loss of Load Centers 12 and 20; 10/15/2018

- CR-PLP-2018-05108; Initiate Work Orders to Perform Testing of Dry Type Transformers

During 1R26; 10/26/2018

- PLP-RPT-12-00026; EGAD-EP-10 Palisades Maintenance Rule Scoping Document;

Revision 3

- PM Basis Template; EN-Transformer, Dry Type - Large; Revision 1 - 11/27/2018

- System Health Report; LAC - 480 VAC System; Q4-2018

- System Health Report; MSS-Main Steam System; Q3-2018

- System Health Report; MSS-Main Steam System; Q4-2018

- WO 156951; Replace EX-12 Nitrogen Relief Valve; 04/17/2012

- WO 511682; EX-11 Transformer Testing; 11/11/2018

- WO 511683; EX-14 Testing; 11/18/2018

- WO 511684; EX-16 Transformer Testing; 11/21/2018

- WO 51637109; EX-12, Nitrogen Level Low, Add Nitrogen; 03/17/2008

71111.13Maintenance Risk Assessments and Emergent Work Control

- Admin 4.02; Control of Equipment; Revision 81

- CR-PLP-2019-00145; CRD-24 did not Move with the Group; 01/10/2019

- DWO-1; Operators Daily/Weekly Items Modes 1, 2, 3, and 4; Revision 108

10

- CRD-E-16; Control Rod Drive Mechanism Troubleshooting; Revision 10

- EC 81199; E-6A Feedwater Heater Output Temperature Variations and Heat Balance Power;

Revision 0

- EN-WM-104; Online Risk Assessment; Revision 18

- M-206; Extractions, Heater Vents and Drain Systems; Sheet 1; Revision 53

- SOP-10; Extraction and Heater Drain System; Revision 39

- WO 516186; CRD-24; Control Rod Drive Mechanism Troubleshoot IAW EN-MA-125;

01/10/2019

71111.15Operability Determinations and Functionality Assessments

- CR-PLP-2019-00223; Stagnant Water on the Outboard Side of P-8A; 01/15/2019

- CR-PLP-2019-00715; Bill of Materials Determined to Call out EPDM Diaphragms; 02/15/2019

- CR-PLP-2019-00944; MO-3190 Found Back Seated; 03/06/2019

- CR-PLP-2019-01161; Issue with the Reported Number of Strokes of CV-3057 SIRW Tank T-

58 Outlet Isolation Valve; 03/13/2019

- EA-GL-8910-01; Generic Letter 89-10 MOV Thrust Window Calculations; 06/06/2015

- EC 56362; Evaluation of the Potential for Excessive Air Entrainment Caused by Vortexing in

the SIRWT During a LOCA; Revision 2

- EOP Supplement 42; Pre and Post RAS Actions; Revision 8

- M-204; Piping & Instrument Diagram; Safety Injection and Containment Spray; Sheet 1B,

Revision 41

- M-225; Piping & Instrument Diagram; High Pressure Air Operated Valves; Sheet 1A,

Revision 6

- QO-5 Attachment 16; Valve Stroke Testing Data Sheet for MO-3190; Revision 107

- QO-21; Inservice Test Procedure - Auxiliary Feedwater Pumps; Revision 50

- WO 513712; SV-3057A/B; Containment Sump O/L A/S, Replace SV and Solenoid Valves and

Clean Piping; 12/15/2018

- WO 514603; CV-3057; SIRW Take O/L Close Stroke Time too Slow; 12/15/2018

71111.19Post Maintenance Testing

- CR-PLP-2019-00601; In-Board Bearing Leakage Went from 1-2 Drops per Minute to 0 Drops

per Minute; 02/07/2019

- CR-PLP-2019-00671; NRC Identified a Missing Signature in Procedure; 02/12/2019

- CR-PLP-2019-00685; While Removing Breaker 152-112, Noted Pieces of a Broken Bumper

Stop; 02/13/2019

- CR-PLP-2019-00695; After Running P-67B, Low Pressure Safety Injection Pump; 02/13/2019

- CR-PLP-2019-00820; MO-3062 Polarization Index Lower than Acceptance Criteria; 2/25/2019

- CR-PLP-2019-00922; Discovered Air Leakage Under SV-1480; 03/06/2019

- CR-PLP-2019-00923; Found Air Leaks on 6th Elbow Downstream of Valve; 03/06/2019

- EC-79625; Alternate Packing Material for Service Water Pump P-7A, Selected for Longer

Packing Set Life When Increased Pump Wear/Shaft Motion is Present; Revision 0

- QO-14; Inservice Test Procedure - Service Water Pumps; Revision 43

- QO-16; Inservice Test Procedure - Containment Spray Pumps; Revision 40

- RO-145; Comprehensive Pump Test Procedure Auxiliary Feedwater Pumps P-8A, P-8B and

P-8C; Revision 20

- SPS-E-11; 480 Volt Breaker Inspection and Repair; 01/25/2019

- ST-0514; Inspection and Maintenance Post-Maintenance; 02/07/2019

- WO 434895; MV-DE113; Air Leak on Upper Elbow Downstream of Valve-VLC; 03/05/2019

- WO 451495; MV-ES3218; Grease Leak from Yoke Bushing - MDM; 02/13/2019

11

- WO 507957; EH-27A (K-6); Replace Heating Elements - Reduced Performance; 03/05/2019

- WO 507958; EH-27C (K-6A); Replace Heating Elements - Reduced Performance; 03/05/2019

- WO 510479; P-7A; Repack Pump with Alternate Packing per EC-79625; 03/08/2019

- WO 52744195; RO-145B -P-8B Auxiliary Feedwater Comprehensive Pump Test; 02/07/2019

- WO 52751954; MO-3062 Breaker PMT; 02/25/2019

- WO 52774211; PCV-1480, 1-1 DG Starting Air PCV PM; 03/05/2019

- WO 52775885; CK-MS402, (IST/CM Valve) Inspection Post-Maintenance per SEP-CV-PLP-

001; 02/07/2019

- WO 52782054; P-54B, EMA-1112; Coupling Inspection; 02/13/2019

- WO 52791870; EMA-1112; P-54B Motor/Pump Bearing Oil Change; 02/13/2019

- WO 52795726; EEQ-EMA-1112 Containment Spray P-54B Motor; 02/13/2019

- WO 52807845; K-8, Lubricate Governor Linkage; 02/07/2019

- WO 52807849; P-8B, K-8; B Auxiliary Feed Pump & Turbine Oil Change; 02/07/2019

- WO 52809920; E-22A: Eddy Current Testing of EDG Jacket Water Cooler; 03/05/2019

- WO 52849956; QO-6B - IST Procedure - Containment Spray Pump P-54B; 02/13/2019

- WO 52854057; MO-7A-1-Emergency Diesel Generator 1-1 (K-6A); 03/05/2019

71111.20Refueling and Other Outage Activities

- CR-PLP-2019-00126; Arc Observed in the Back Lower Corner of RI-62B Power Range

Drawer; 01/09/2019

- GOP-3; Mode 3 Greater Than or Equal to 525°F to Mode 2; Revision 33

- GOP-4; Mode 2 to Mode 1; Revision 24

- GOP-5; Power Escalation in Mode 1; Revision 45

- QI-3; Reactor Protection Matrix Logic Tests; 01/10/2019

- QI-9; Reactor Protective Trip Units; 01/10/2019

- WO 00515875-05; Troubleshoot Plant Trip- 28V Power Supply; 01/10/2019

71111.22Surveillance Testing

- M-201; Piping & Instrument Diagram; Primary Coolant System; Sheet 1, Revision 90

- M-203; Piping & Instrument Diagram; Safety Injection Containment Spray and Shutdown

Cooling System; Sheet 2, Revision 28

- M-204; Piping & Instrument Diagram; Safety Injection Containment Spray and Shutdown

Cooling System; Sheet 1, Revision 88

- M-204; Piping & Instrument Diagram; Safety Injection Containment Spray; Sheet 1B,

Revision 41

- M-204; Piping & Instrument Diagram; Safety Injection Containment Spray and Shutdown

Cooling System; Sheet 1A, Revision 44

- PO-1; Operations Pre-Startup Tests; Revision 17

- QI-3; Reactor Protection Matrix Logic Tests; Revision 7

- QO-19; Inservice Test Procedure - HPSI Pumps and ESS Check Valve Operability Test;

Revision 42

- SOP-6; Reactor Control System; Revision 36

- WO 52846581; QO-19B; High Pressure Safety Injection Pump and Engineered Safeguards

Check Valve Operation; 01/14/2019

71151Performance Indicator Verification

- NRC Performance Indicator Data Sheet, Mitigating Systems Performance Indicator, Auxiliary

Feedwater (MS08); First Quarter through Fourth Quarter 2018

- NRC Performance Indicator Data Sheet, Initiating Events - Unplanned Scrams per 7,000

12

Critical Hours (IE01) and Unplanned Scrams with Complications (IE04); First Quarter through

Fourth Quarter 2018

- Palisades Nuclear Plant Mitigating System Performance Index Basis Document; 07/12/2017

71152Problem Identification and Resolution

- Bechtel Report for Seismic Evaluation of Containment Dome Trusses for Consumers Power

Company, Palisades Nuclear Plant, South Haven, Michigan; 12/1981

- C-138; Containment Liner Support Trusses; Revision 9

- CR-PLP-2017-05016; Dome Trusses; 11/01/2017

- CR-PLP-2019-00234; During Research for Follow-on NRC Questions; 01/16/2019

- EA-SP-03369-01; Piping Evaluation for Containment Spray Piping; Revision 2

- EA-SP-03369-02; Piping Evaluation for Containment Spray Piping; Revision 0

- EA-SP-03370; Piping Analysis for Containment Spray Piping; Revision 2

- EDS Nuclear Report 02-0660-1087; Seismic Evaluation of Safety Injection Tank for Palisades

Nuclear Plant; Revision 1

- Letter from Consumers Power Energy to the Office of Nuclear Reactor Regulation; Palisades

Plant SEP Topic 1116, Seismic Design Considerations; 01/04/1982

- PNP 2018-057; 45-Year Containment Tendon Surveillance Summary Report; 11/27/2018

71153Follow-Up of Events and Notices of Enforcement Discretion

- CR-PLP-2019-00117; Plant Trip due to RPS BD Matrix Loss of Power; 01/09/2019

- EN-OP-126; Post-Transient Response and Review; Revision 1

- EOP-1.0; Standard Post-Trip Actions; Revision 21

- RI-62B; Technical Specification Surveillance Procedure; Power Range Safety Channel

Alignment - Channel B; Revision 18

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