IR 05000266/2018004

NRC Integrated Inspection Report 05000266/2018004 and 05000301/2018004

ML19022A242
Person / Time
Site:	Point Beach
Issue date:	01/18/2019
From:	Eric Duncan Reactor Projects Region 3 Branch 4
To:	Craven R Point Beach
References
IR 2018004
Download: ML19022A242 (26)

Text

First initial UNITED STATES January 18, 2019

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC INTEGRATED INSPECTION REPORT 05000266/2018004 AND 05000301/2018004

Dear Mr. Craven:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Point Beach Nuclear Power Station. On January 11, 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 findings or violations of more than minor significance.

However, the inspectors documented a licensee-identified violation, which was determined to be of very low safety significance, in this report. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the NCV, 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 III; the Director, Office of Enforcement; and the NRC Resident Inspectors at the Point Beach Nuclear Plant. 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/

Eric R. Duncan, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. DPR-24 and DPR-27 Enclosure:

IR 05000266/2018004; 05000301/2018004 cc: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensee performance by conducting an integrated quarterly inspection at the Point Beach Nuclear Plant, Units 1 and 2, 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. A licensee-identified non-cited violation is documented in report section: 71111.20 List of Findings and Violations No findings or violations were identified.

PLANT STATUS

Unit 1 began the inspection period at full power. On December 5, 2018, the unit was taken offline due to lowering condenser vacuum. The unit was restarted on December 6, 2018, and achieved full power on December 9, 2018. On December 30, 2018, reactor power was reduced to 45 percent to support condenser waterbox cleaning. The unit returned to full power on December 31, 2018, and remained at or near rated thermal power for the remainder of the inspection period.

Unit 2 began the inspection period at 91 percent power and in coastdown for an upcoming refueling outage. On October 6, 2018, the unit was taken offline for planned refueling outage U2R36. The unit was restarted on October 26, 2018, achieved full power on October 30, 2018, and remained at or near full 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

71111.01Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures.

71111.04Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2 chemical and volume control system while the reactor was lower in inventory, in Mode 5, on October 20, 2018;

(2) G-01 emergency diesel generator (EDG) on November 24, 2018; and

(3) 1P-29 turbine driven auxiliary feedwater (AFW) pump on December 29, 2018.

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the Unit 1 safety injection system on October 1, 2018.

71111.05AQFire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Fire Zone 304N, AFW Pump Room North, on November 7, 2018;

(2) Fire Zone 304S, AFW Pump Room South, on November 7, 2018;

(3) Fire Zone 305, 4160 Volt Vital Switchgear Room, on November 7, 2018;

(4) Fire Zones 308 and 309, G-01/G-02 EDG Rooms on December 1, 2018; and

(5) Fire Zones 770, 771, 772, and 773, EDG Support Equipment Rooms on December 20, 2018.

71111.06Flood Protection Measures Internal Flooding

The inspectors evaluated internal flooding mitigation protections for the residual heat removal pump cubicles on October 3, 2018.

71111.08Inservice Inspection Activities

The inspectors assessed the effectiveness of the licensees programs for monitoring degradation of the reactor coolant system (RCS) boundary, risk-significant piping system boundaries, and the containment boundary by reviewing the following activities from October 9 - October 18, 2018.

(1) Ultrasonic examination (UT) of reactor coolant system pipe-to-elbow weld, RC-06-SI-2002-25 (Work Order 40535682-01);

(2) UT of reactor coolant system elbow-to-pipe weld, RC-10-AC-2001-04 (Work Order 40535690-01);

(3) Dye penetrant examination (PT) of reactor coolant system pump B seal injection piping socket welds CVC-02-PSI-2002-25, CVC-02-PSI-2002-26 and CVC-02-PSI-2002-27 (Work Order 40535673-01);

(4) Magnetic particle examination (MT) of AFW system pipe hanger integral attachment weld, EB-10-HYY-IWA and visual examination (VT-3) of auxiliary feedwater system pipe hanger, EB-10-HYY (Work Order 40535667-01);

(5) VT-1, VT-3 & general visual examination of IWE boundary components: containment electrical penetrations Q13, Q14, Q15, Q16, Q17, Q18, Q19, Q20, Q21 and Q22; and containment piping penetration CPP-03 (Work Order 40543936-02);

(6) Reactor coolant pump (2P-001A), seal bypass line 3/4"-CH-2501R-1, piping welds W-1, W-2, W-3, W-4 and W-7 (Work Order 40430777-08);

(7) Safety injection valve (2SI-876B) replacement, welds W-1, W-2 and W-3 (Work Order 40526403-01 and Work Order 40526403-05);

(8) Bare metal visual examination (VT-2) of reactor vessel upper head penetrations (Work Order 40544093-01); and

(9) Boric acid evaluations (BAEs) and corrective action records (ARs): BAE 18-066-E, 2RH-701 Packing Leak; BAE 18-068-E, Boric Acid Leak Found on 2SC-955; BAE 18-070-E, 2SI-1408 Has Boric Acid Leak; AR 2192921, Boric Acid Leak on 2FT-413 Manifold; AR 2220105, Boric Acid Leak on Stem of Valve 2CV-253; and AR 2220617, Inactive Boric Acid Leak at Fitting Near 2CV-231A.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated just-in-time training for the Unit 1 reactor startup on December 6, 2018; and licensed operator simulator training on December 11 and 13, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated the Unit 2 plant shutdown and cooldown on October 6, 2018, and Unit 2 startup on October 26, 2018.

71111.12Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) DA-100, G-01 EDG air compressor discharge check valve repeatedly leaking;

(2) Reactor protection system after unavailability hours exceeded criteria; and

(3) P-38B AFW pump exceeded unavailability hours.

71111.13Maintenance Risk Assessments and Emergent Work Control

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

(1) Planned maintenance on 1P-53 AFW pump;

(2) Planned maintenance on 2P-53 AFW pump; and

(3) Planned maintenance on 1P-10A residual heat removal (RHR) pump.

71111.15Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Tubing lost in service water pump bay;

(2) High energy line break barrier breached for demineralized water hose;

(3) Reduced recirculation flow on 1P-53 AFW pump;

(4) Diesel-driven fire pump did not meet design pump curve;

(5) Multiple rod stop and runback settings incorrect; and

(6) Control rod F6 moving coil grounded.

71111.18Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change 291226; Fire Protection Pipe Support.

71111.19Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) Testing after 1P-10A RHR pump maintenance on December 18, 2018; and

(2) Testing after 2P-11A component cooling water pump replacement on October 17, 2018.

71111.20Refueling and Other Outage Activities

The inspectors evaluated refueling outage U2R36 activities from October 6 - 30, 2018.

===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:

Routine ===

(1) TS 4A, Turbine Trip Test, on October 26, 2018;

(2) ORT 3A, Safety Injection Actuation with Loss of Engineered Safeguards AC [Alternating Current] (Train A) Unit 2, on October 7, 2018; and

(3) IT 535D, Leakage Reduction and Preventive Maintenance Program Train B HHSI [high head safety injection] and RHR Piggyback Test Mode 1, 5, 6, (Refueling) Unit 2, on

===October 4, 2018.

Containment Isolation Valve (1 Sample)===

(1) ORT-59, Train A Spray System CIV [containment isolation valve] Leakage Test Unit 2, on October 15, 2018.

71114.02Alert and Notification System Testing

The inspectors evaluated the maintenance and testing of the alert and notification system on November 13 - 16, 2018.

71114.03Emergency Response Organization Staffing and Augmentation System

The inspectors evaluated the readiness of the Emergency Response Organization on November 13 - 16, 2018.

71114.04Emergency Action Level and Emergency Plan Changes

The inspectors completed the evaluation of submitted Emergency Action Level and Emergency Plan changes on December 12, 2018. This evaluation does not constitute NRC approval.

71114.05Maintenance of Emergency Preparedness

The inspectors evaluated the maintenance of the emergency preparedness program on November 13 - 16,

RADIATION SAFETY

71124.01Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment

The inspectors evaluated radiological hazards assessments and controls.

Instructions to Workers (1 Sample)

The inspectors evaluated worker instructions.

Contamination and Radioactive Material Control (1 Sample)

The inspectors evaluated contamination and radioactive material controls.

Radiological Hazards Control and Work Coverage (1 Sample)

The inspectors evaluated radiological hazards control and work coverage.

High Radiation Area and Very High Radiation Area Controls (1 Sample)

The inspectors evaluated risk-significant high radiation area and very high radiation area controls.

Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)

The inspectors evaluated radiation worker performance and radiation protection technician proficiency.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

The inspectors verified the licensee performance indicators submittals listed below:

(1) BI01: RCS Specific Activity - 2 Samples (September 1, 2017 - August 30, 2018);

(2) OR01: Occupational Exposure Control Effectiveness - 1 Sample (September 1, 2017 -

August 30, 2018);

(3) PR01: RETS/ODCM Radiological Effluent Occurrences - 1 Sample (September 1, 2017

- August 30, 2018);

(4) MS09: Residual Heat Removal Systems - 2 Samples (October 1, 2017 -

September 30, 2018);

(5) MS10: Cooling Water Support Systems - 2 Samples (October 1, 2017-September 30, 2018);

(6) EP01: Drill/Exercise Performance - 1 Sample (July 1, 2017 - April 30, 2018);

(7) EP02: Emergency Response Organization Drill Participation - 1 Sample (July 1, 2017 -

April 30, 2018); and

(8) EP03: Alert And Notification System Reliability - 1 Sample (July 1, 2017 -

April 30, 2018).

71152Problem Identification and Resolution Semiannual Trend Review

The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue.

Annual Follow-Up of Selected Issues (2 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Inservice inspection of baffle former bolts; and

(2) G-01 EDG and G-02 EDG control relay failures from contact resistance.

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

The inspectors evaluated Event Notification 53779: Manual Reactor Trip on Loss of Main Condenser Vacuum, and the licensees response from December 5 - 9,

INSPECTION RESULTS

71111.20Refueling and Other Outage Activities Licensee Identified Non-Cited Violation 71111.20Refueling and Other Outage Activities This violation of very low safety significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a Non-Cited Violation (NCV), consistent with Section 2.3.2.a of the Enforcement Policy.

Enforcement:

Violation: 1) Technical Specification 3.9.6 requires that refueling cavity water level shall be maintained greater than or equal to () 23 feet above the top of the reactor vessel flange during movement of irradiated fuel assemblies within containment.

Contrary to the above, on October 15, 2018, the licensee failed to maintain refueling cavity water level 23 feet above the top of reactor vessel flange during movement of irradiated fuel Licensee Identified Non-Cited Violation 71111.20Refueling and Other Outage Activities assemblies within containment. Specifically, the licensee moved approximately 14 fuel assemblies while allowing reactor cavity level to lower to 22 feet, 8 inches.

2) Technical Specification 3.9.5 requires two RHR loops shall be operable, and one RHR loop shall be in operation in Mode 6 with the reactor cavity water level < 23 feet above the top of the reactor vessel flange.

Contrary to the above, on October 15, 2018, the licensee failed to have two RHR loops operable and one RHR loop in operation in Mode 6 with reactor cavity water level < 23 feet above the top of the reactor vessel flange. Specifically, the licensee only had one RHR loop operable and in operation while reactor cavity water level had lowered to 22 feet, 8 inches.

Significance/Severity Level: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). The inspectors assessed the significance of the finding using SDP Appendix G and concluded the issue was of very low safety significance (i.e., Green) because all the Mitigating Systems screening questions were answered No.

Corrective Action Reference: AR 2286011 71152Semi-Annual Trend Review Observations 71152Problem Identification and Resolution The inspectors review was focused on procedure use and adherence, and procedure quality issues, but also considered the results of daily inspector corrective action program item screening and licensee trending efforts. The inspectors review nominally considered the 6-month period of June 1 - November 30, 2018, although some examples expanded beyond those dates when warranted by the scope of the trend.

The inspectors reviewed condition reports, trend reports, and procedure change requests to evaluate procedure compliance gaps at the site. During the inspection period, the NRC inspectors noted instances where low-level procedure compliance errors occurred in multiple departments, including Operations, Maintenance, and Chemistry. Examples include operators who performed steps out of sequence within a safety-related surveillance procedure, maintenance personnel who performed steps out of sequence within a safety-related surveillance procedure, and chemistry personnel who failed to store quality records in accordance with station procedures. Additionally, there were several instances where station procedures affecting quality lacked clarity or critical information to ensure desired results.

These issues illustrated a decline in the use of human performance tools to prevent errors while performing procedures; all of which could potentially impact nuclear safety.

The licensee appropriately entered these issues into their corrective action program and completed timely evaluations of these issues to determine the causes of the performance decline. Corrective actions included training and a re-emphasis on following human performance tools such as pre-job briefs, procedure use and adherence, and verification and validation activities. At the end of this inspection period, some corrective actions were still open and the effectiveness of the actions taken was still being assessed. The inspectors determined that the corrective actions taken to date appeared to be effective at addressing the identified gaps. The inspectors planned to continue to evaluate these actions during routine observations and inspections.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect it from public disclosure. No proprietary information was documented in this report.

• On October 18, 2018, the inspector presented the inservice inspection activities results to Mr. R. Craven, Site Director, and other members of the licensee staff.

• On October 25, 2018, the inspector presented the radiation protection program inspection results to Mr. R. Craven, and other members of the licensee staff.

• On November 16, 2018, the inspector presented the emergency preparedness program inspection results to Mr. D. Smith, Emergency Preparedness Manager, and other members of the licensee staff.

• On December 13, 2018, the inspector presented the emergency preparedness inspection results to Mr. D. Smith, and other members of the licensee staff.

• On January 11, 2019, the inspector presented the quarterly integrated inspection results to Mr. R. Craven, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- AOP-13C; Severe Weather Conditions; Revision 45

- List of Open WOs and WRs Coded Seasonal Readiness; 10/29/2018

- OP-AA-102-1002; Seasonal Readiness; Revision 26

- WO 40544767: OPS Swing Shift Weekly Routine; April 9, 2018

71111.04Equipment Alignment

- AR 2191803; 2P-15B, Inboard Pump Bearing Sightglass has a Small Oil Leak

- AR 2193978; 2SI-829C Has Excessive Seat Leakage; 03/26/2017

- AR 2213861; 1HX-179B, Active BA Fitting Leak

- AR 2231267; 1SI-825A-O MOV Found with No Grease in Motor Cavity; 10/19/2017

- AR 2231924; PPCS Point for LI-972 RWST Level is Diverging

- AR 2232334; 1SI-829C, SI Test Line Flow Control Seat Leakage Identified; 10/24/2017

- AR 2233196; Leakage Too High for 1SI-845E During TS-30 1SI-845E, P-15B SI Pump to RC

Loop a Cold Leg SI Check; 10/27/2017

- AR 2249233; Contingency Work/Replace 1SI-845E Pending U1R38 TS-30 Result; 02/13/2018

- AR 2254126; 2-PT-SI-6 Train B / Work Order 40548369; 03/14/2018

- AR Search Report; MISPO-MISPOSITIONING, MISPOS1 - MISPOSITION LEVEL 1,

MISPOS2 - MISPOSITION LEVEL 2, MISPOS3 - MISPOSITION LEVEL 3, MISPOS4 -

MISPOSITION LEVEL 4, MISPOS5 - MISPOSITION LEVEL 5; 04/30/2018-10/31/2018

- AR Search Report; SI - Safety Injection; 10/26/2016-10/26/2018

- CL 11A G-01; G-01 Diesel Generator Checklist; Revision 28

- CL 13E Part 1; Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1; Revision 52

- CL 7A; Safety Injection System Checklist Mode 1, 2, 3 Unit 1; Revision 38

- Drawing 110E17, Sheet 1; P&ID Safety Injection System, Unit 1; Revision 60

- Drawing 110E17, Sheet 2; P&ID Safety Injection System, Unit 1; Revision 66

- Drawing 685J175; Sheet 1; P&ID Chemical & Volume Control; Revision 52

- Drawing 685J175; Sheet 2; P&ID Chemical & Volume Control; Revision 66

- Drawing 685J175; Sheet 3; P&ID Chemical & Volume Control; Revision 20

- Drawing E-94, Sheet 12F; Diesel Generator G-01 Cabinet C-34 Inside; Revision 5

- Drawing E-94, Sheet 12L; Diesel Generator G-01 C-34 Cabinet Right Door; Revision 2

- Drawing E-94, Sheet 12N; Diesel Generator G-01 Cabinet C-34 Right Side Panel; Revision 7

- Drawing E-94, Sheet 13A; Local Control Boards & Racks Power Transfer Panels C78 & C79;

Revision 8

- Drawing M-201; Sheet 1; P&ID Main & Reheat Steam System; Revision 62

- Drawing M-209; Sheet 12; Emergency Diesel Air Starting System; Revision 23

- Drawing M-217; Sheet 1; P&ID Auxiliary Feedwater System; Revision E

- Drawing M-219; Sheet 1; P&ID Fuel Oil System; Revision 50

- Drawing M-219; Sheet 2; P&ID Fuel Oil System Diesel Generator Building; Revision 16

- Drawing PBM-231; Sheet 1; F/D De-Ionized & Reactor De-Ionized and Reactor Makeup

Water; Revision 41

- PBF-1562; PBNP Shutdown Safety Assessment and Fire Inspection Checklist; Revision 25

Completed for Unit 2 on October 18, 2018

- PBNP Inservice Testing Background Valve Data Sheet; SI Pump P-15B to RCS Loop A Cold

Leg Injection Check Valve

- System Health Report; Q2-2018; SI - Safety Injection; 10/31/2018

- WO 40551819 01; SI Pump Seal Cooler Alternate Tubing Connection; 10/15/2017

71111.05AQFire Protection Annual/Quarterly

- AR 2273209; XS-5199 Unit 1 Containment Smoke Detector Non-Functional; 07/23/2018

- AR 2284648; XS-5784 and FS-7312 Trouble Alarms; 10/09/2018

- AR 2293521; FNOT Assignment not Scheduled for Next Outage; 12/06/2018

- AR 2293780; Received Maintenance Alert on Smoke Detector; 12/08/20108

- Door Transaction History Log; Door 3 and 9; December 14, 2018 to December 16, 2018

- Drawing M-211, Sheet 3; Diesel Generator Building Air Flow Diagram HVAC Systems;

Revision 6

- Drawing M5-3-30, Sheet 1; Fire Barrier Cond. Tank/Fan Room 320 Floor El 26 -0; Revision 6

- Fire Rounds Log; October 19, 2018 - December 17, 2018

- FPTE 2016-019; Point Beach Nuclear Plant Detailed Fire Modeling Report - Fire

Compartment 304N, Auxiliary Fwater Pump Room North Section, El. 8-0; Revision 0

- FPTE 2016-020; Point Beach Nuclear Plant Detailed Fire Modeling Report - Fire

Compartment 304S, Auxiliary Fwater Pump Room South Section, El. 8-0; Revision 0

- FPTE 2016-021; Point Beach Nuclear Plant Detailed Fire Modeling Report - Fire

Compartment 305, 4160V Vital Switchgear Room, El. 8-0; Revision 0

- PBF-2058A; Fire Round Performance Sheet - Turbine Hall and Miscellaneous Areas;

Revision 17; Completed 12/14-12/16/2018

- PFP-0-CB; Pre-Fire Plan Control Building Elev 8 Ft, 26 Ft, 44 Ft and 66 Ft; Revision 1

- PFP-0-CB; Pre-Fire Plan, Control Building Elev 8ft, 26ft, 44ft, and 66ft; Revision 1

- PFP-0-PAN; Pre-Fire Plan Protected Area North (Inside the Fence); Revision 0

- RMP 9057; Fire Barrier Penetration Fire Seal Surveillance; Revision 33

- WO 40530609-01; G-02 Fire Barrier Inspection Per RMP 9057; 09/14/2017

71111.06Flood Protection Measures

- AOP-1A Unit 1; Reactor Coolant Leak; Revision 18

- AOP-SA Unit 1; Secondary Coolant Leak; Revision 16

- AR 2053608; Perform Annual Flooding Walkdown; 06/11/2015

- AR 2230963; Flood Path to Unit 1 RHR Pump Cubicle Created

- AR 2255839; WR IN Support of the Flooding Recovery Effort (EC 28248); 03/23/2018

- AR 2269521; Error in NP 8.4.17 Update

- AR 2290039; Flooding Documentation Corrections Required; 11/08/2018

- ARP 1C20 A 1-4; Auxiliary Building - 19Ft Sump/Area Level High; Revision 1

- ARP C01 A 2-8; Waste Disposal System; Revision 1

- ARP C180A BDE A 2-2; Unit 2 Fan Room Level HI; Revision 1

- ARP C180A BDE A 2-5; ECCS Piping Trench Level HI; Revision 0ARP C180A BDE A 1-2;

Unit 1 Fan Room Level HI; Revision 1

- Calculation 2014-0007; Allowable Flood Levels; Revision 3

- Drawing M-202, Sheet 2; Feedwater System; Revision 56

- EN-AA-100-1004-F01; Calculation Cover Sheet; Revision 0; Allowable Flood Levels;

Completed 05/18/2018

- NP 7.7.9; Facilities Monitoring Program; Revision 20

- NP 8.4.17; PBNP Flooding Program; Revision 31

- OM 4.3.8; Control of Time Critical and Time Sensitive Operator Actions; Revision 15

- OP-AA-19; Control of Time Critical Operator Actions and Time Sensitive Actions; Revision 4

- WO 40580025-01Test PAB and TB Sump Alarms; 10/08/2018

71111.08Inservice Inspection Activities

- AR 2192921; Boric Acid Leak on 2FT-413 Manifold; 03/22/2017

- AR 2196150; Recordable Indications in New Valve 2SI-876B; 04/04/2017

- AR 2196375; Inspection Tools Have Missing Pieces Upon Return to Vendor; 04/04/2017

- AR 2197395; Recordable Indications on Containment Moisture Barrier; 04/08/2107

- AR 2220105; Boric Acid Leak on Stem of Valve 2CV-253; 08/14/2017

- AR 2220617; Inactive Boric Acid Leak at Fitting Near 2CV-231A; 08/16/2017

- AR 2223429; Sodium Spike Seen in Unit 2 Generators; 09/03/2017

- AR 2231212; Recordable Indications on PORV Mod Weld M5-61-PWE; 10/18/2017

- AR 2254126; 2-PT-SI-6 Train B / Work Order 40548369; 03/14/2018

- AR 2258145; Spare Check Valves Fail Shop Testing/Inspection PWE; 04/05/2018

- AR 2262247; Piping HB-19 - UT Thickness Upstream FP-03741; 05/01/2018

- AR 2284207; 2RH-701 Packing Leak; 10/06/2018

- AR 2284241; Boric Acid Leak Found on 2SC-955; 10/07/2018

- AR 2284266; 2SI-1408 Has Boric Acid Leak; 10/07/2018

- AR 2285521; Recordable PT Indication Found in Weld CVC-02-PSI-2002-26; 10/12/2018

- AR 2285546; Recordable PT Indication Found in Weld CVC-02-PSI-2002-26; 10/12/2018

- AR 2285618; Debris Found on Reactor Pressure Vessel Closure Head; 10/13/2018

- BALCM Program; Boric Acid Leakage and Corrosion Monitoring Program; Revision 8

- BALCM Appendix C; Boric Acid Indication Evaluation; Revision 13

- Boric Acid Evaluation 18-066-E; 2RH-701 Packing Leak; 10/06/2018

- Boric Acid Evaluation 18-068-E; Boric Acid Leak Found on 2SC-955; 10/06/2018

- Boric Acid Evaluation 18-070-E; 2SI-1408 Has Boric Acid Leak; 10/14/2018

- Boric Acid Screening 17-245; Boric Acid Leak on Stem of Valve 2CV-253; 08/15/2017

- Boric Acid Screening 17-248; Inactive Boric Acid Leak at Fitting Near 2CV-231A; 08/17/2018

- Boric Acid Screening 18-066; 2RH-701 Packing Leak; 10/06/2018

- Boric Acid Screening 18-068; Boric Acid Leak Found on 2SC-955; 10/06/2018

- Boric Acid Screening 18-070; 2SI-1408 Has Boric Acid Leak; 10/07/2018

- ISI-2103; ISI Isometric, Reactor Pressure Vessel Bolting and Control Rod Drive Housing,

PBNP Unit 2; Revision 4

- ISI-2279; ISI Isometric, Auxiliary Feedwater to Steam Generator A, PBNP Unit 2; Revision 2

- Procedure NDE-178; Ultrasonic Examination of Piping for Thermal Fatigue Cracking in

Accordance with MRP-146 or MRP-192; Revision 4

- Procedure NDE-350; Magnetic Particle Examination Alternating Current (AC) Yoke;

Revision 34

- Procedure NDE-451; Visible Dye Penetrant Examination, Temperature Applications 45ºF to

25 ºF; Revision 30

- Procedure NDE-750; Visual Examination (VT-1) of Nuclear Power Plant Components;

Revision 27

- Procedure NDE-753; Visual Examination (VT-2) Leakage Detection of Nuclear Power Plant

Components; Revision 18

- Procedure NDE-754; Visual Examination (VT-3) of Nuclear Power Plant Components;

Revision 21

- Procedure NDE-757; Visual Examination for Leakage of Pressure Vessel Penetrations;

Revision 10

- Procedure NDE-760; VT-1, VT-3 & General Visual Examination of IWE Boundary

Components; Revision 10

- Procedure PDI-UT-2; General Procedure for the Examination of Austenitic Pipe Welds;

Revision H

- NPS-PQR-1270/1271; Welding Procedure Qualification Record: P8 Stainless Steel to P8

Stainless Steel; Revision 0

- Repair/Replacement Activity 2017-0019; Replacement and Rerouting of 2P-001A, RCP, Seal

Bypass Piping 3/4"-CH-2501R-1; Revision 2

- Repair/Replacement Activity 2017-0024; Replacement of 2SI-00876B Valve; Revision 0

- Report 2018U2CA-002; UT Calibration Report; 10/16/2018

- Report 2018U2CA-003; UT Calibration Report; 10/18/2018

- Report 2018U2CA-008; UT Calibration Report; 10/16/2018

- Report 2018U2CA-009; UT Calibration Report; 10/18/2018

- Report 2018U2CA-012; UT Calibration Report; 10/18/2018

- Report 2018U2MT-001; Magnetic Particle Examination (MT) of Pipe Hanger Welded

Attachment, Component EB-10-HYY-IWA; 10/13/2018

- Report 2018U2PT-001; Liquid Penetrant Examination (PT) of Pipe-to-Elbow Weld, Component

CVC-02-PSI-2002-25; 10/13/2018

- Report 2018U2PT-002; Liquid Penetrant Examination (PT) of Elbow-to-Pipe Weld, Component

CVC-02-PSI-2002-26; 10/13/2018

- Report 2018U2PT-003; Liquid Penetrant Examination (PT) of Pipe-to-Tee Weld, Component

CVC-02-PSI-2002-27; 10/13/2018

- Report 2018U2PT-004; Liquid Penetrant Examination (PT) of Elbow-to-Pipe Weld, Component

CVC-02-PSI-2002-26; 10/17/2018

- Report 2018U2UT-001; UT Pipe Weld Examination, Component RC-10-AC-2001-04;

10/16/2018

- Report 2018U2UT-002; UT Pipe Weld Examination, Component RC-06-SI- 2002-25;

10/18/2018

- Report 2018U2VT-001; Visual Examination (VT-3) of Pipe Hanger, Component EB-10-HYY;

10/14/2018

- Report 2018U2VT-011; Visual Examination (VT-3) of IWE Surfaces for Containment Piping

Penetration CPP-03; 10/17/2018

- Report 2018U2VT-091; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-13; 10/13/2018

- Report 2018U2VT-092; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-14; 10/13/2018

- Report 2018U2VT-093; Visual Examination (VT-3 ) of IWE Surfaces for Containment Electrical

Penetration Q-15; 10/13/2018

- Report 2018U2VT-094; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-16; 10/13/2018

- Report 2018U2VT-095; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-17; 10/13/2018

- Report 2018U2VT-096; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-18; 10/13/2018

- Report 2018U2VT-097; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-19; 10/13/2018

- Report 2018U2VT-098; Visual Examination (VT-3) IWE Surfaces for of Containment Electrical

Penetration Q-20; 10/14/2018

- Report 2018U2VT-099; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-21; 10/14/2018

- Report 2018U2VT-100; Visual Examination (VT-3) of IWE Surfaces for Containment Electrical

Penetration Q-22; 10/14/2018

- Report 2018U2VT-171; Visual Examination (VT-1) of IWE Surfaces for Containment Piping

Penetration CPP-03; 10/17/2018

- Report 2018U2VT-235; Visual Examination System Leakage (VT-2) of Reactor Pressure

Vessel Closure Head Upper Surface; 10/16/2018

- WO 40430777-08; 2P-001A / Correct Flange Misalignment EC288721; 04/02/2017

- WO 40430777-14; Visible Liquid Penetration Examination Record, 2P-001A, Seal Housing

Piping Welds: W-1, W-2, W-3, W-4, W-5, W-6, and W-7; 05/10/2017

- WO 40430777-15; Visual Weld Examination Record (Root Pass and Final Pass), 2P-001A,

Seal Housing Piping Welds: W-1, W-2, W-3, W-4, and W-7; 05/10/2017

- WO 40526403-01; 2SI-00876B / Replace Valve (Welding) EC288765; 04/04/2017

- WO 40526403-05; 2SI-00876B / Prefab Welding; 04/03/2017

- WO 40526403-08; Weld Records, Visual Examination (Root and Final Passes) and Visible

Liquid Penetrant Examination, 2SI-00876B Valve Replacement Welds: W-1, W-2 and W-3;

05/23/2017

- WO 40535667-01; Perform Visual Examination (VT-3) on Piping Hanger EB-10-HYY and

Magnetic Particle Examination (MT) on Welded Attachment EB-10-HYY-IWA; 10/11/2018

- WO 40535673-01; Perform Liquid Penetrant (PT) Examinations on Pipe Welds, Components

CVC-02-PSI-2002-25, CVC-02-PSI-2002-26 and CVC-02-PSI-2002-27; 10/16/2018

- WO 40535682-01; Perform Ultrasonic Examination (UT) on RC-06-SI- 2002-25 Pipe-to-Elbow

Weld; 10/17/2018

- WO 40535690-01; Perform Ultrasonic Examination (UT) on RC-10-AC-2001-04 Elbow-to-Pipe

Weld; 10/13/2018

- WO 40543936-02; Containment Penetration IWE Exams, General Area IWE Exams;

10/20/2018

- WO 40544093-01; 2R-1 / RPV Closure Head Visual Examination; 10/16/2018

- WPS FP-PE-B31-P8P8-GTSM-037; Welding Procedure Specification: P8 Stainless Steel to

P8 Stainless Steel; Revision 5

71111.11Licensed Operator Requalification Program and Licensed Operator Performance

- AR 2284101; U2 Turbine Overspeed Trip Immediately After 19KV Bkr Opened; 10/06/2018

- AR 2284100; 2TG-01 Overspeed Trip Prior to ORT-4 - Data Gathered; 10/06/2018

- OP 1B; Reactor Startup; Revision 76

- OP 1C Unit 2; Startup to Power Operation Unit 2; Revision 43

- OP 3A Unit 2; Power Operation to Hot Standby Unit 2; Revision 17

- OP 3B; Reactor Shutdown; Revision 46

- OP 3C Unit 2; Hot Standby to Cold Shutdown Unit 2; Revision 16

- OP-AA-100-1000; Conduct of Operations; Revision 25

71111.12Maintenance Effectiveness

- AR 2228976; Ground on P-38B SSG Pump; 10/07/2017

- AR 2232305; Quarterly MR Review: AF Exceeding 80 Percent Unavailable; 10/24/2017

- AR 2242586; DA-100 Check Valve Leaking; 01/01/2018

- AR 2243719; DA-100, K-5A Discharge Check Valve is Still Leaking By; 01/09/2018

- AR 2248961; DA-100, K-5A EDG Air Comp. Check Valve Leaking By PWE; 02/11/2018

- AR 2254105; Replace DA-100; 03/14/2018

- AR 2257940; DA-100 Minor Seat Leakage; 04/04/2018

- AR 2258225; Replace DA-100 with Alternate Design per EC 290610; 04/06/2018

- AR 2265633; P-38B SSG MR Unavailability Criteria Exceeded; 05/23/2018

- AR 2270335; 1-276/A06 Relay Was OOT High (Conservative); 06/28/2018

- AR 2292061; Establish MR Evaluation Assignment for Previous (MRR) CR; 11/26/2018

- AR Search Report; Subject: Maintenance Rule; 04/20/2018-11/20/2018

- AR Search Report; System: RP; 09/09/2016-11/09/2018

- EE-AA-100-2002-F01; Revision 2; Unit 2 Failure of TE-406BD ()/OTDT Turbine Runback

(White); Completed 10/21/2016

- ER-AA-100-2002-F01; Revision 2; 1TC-404R, QL>QU Delta Flux Controller; Completed

09/28/2016

- ER-AA-100-2002-F01; Revision 2; Unexpected Failure of 2PC-431G and TSAC Entry PWE;

Completed 02/01/2017

- ER-AA-100-2002-F01; Revision 3; 1LC-463E Bistable Tripped and Cleared Without Low Level;

Completed 05/11/2017

- ER-AA-100-2002-F01; Revision 3; 2-276/A06 As Found Pickup and Dropout Settings OOT

Low (and 2-274/A06 As Found Pickup and Dropout Settings OOT Low); Completed

08/31/2017

- ER-AA-100-2002-F01; Revision 4; 1-274/A05 Relay as Found OOT High on Dropout and

Pickup; Completed 11/13/2018

- ER-AA-100-2002-F01; Revision 4; 1-276/A06 As Found Pickup and Dropout Setting OOT Low;

Completed 02/21/2018

- ER-AA-100-2002-F01; Revision 4; 2FC-00475A/B; Completed 08/08/2018

- ER-AA-100-2002-F01; Revision 4; U1 PPCS Alarm for TSM6131B Delta T Deviation @ -3

DEGF; Completed 09/26/2018

- ER-AA-100-2002-F01; Revision 4; Unexpected Unit 2 STM Line B Isol Channel Alert Alarm;

Completed 05/02/2018

- EVAL-PB-AF-01342; P-38B Exceeded UA; Draft

- EVT-RP-2016-25188; PBN-1-RP-1C; 09/28/2016

- EVT-RP-2017-25947; PBN-1-RP-1C; 12/12/2016

- EVT-RP-2017-28415; PBN-2-RP-2C; 04/15/2017

- EVT-RP-2017-28416; PBN-2-RP-2C; 04/16/2017

- EVT-RP-2017-28433; PBN-1-RP-1C; 04/27/2017

- EVT-RP-2017-28435; PBN-1-RP-1C; 05/02/2017

- EVT-RP-2017-28436; PBN-1-RP-1C; 05/04/2017

- EVT-RP-2017-28438; PBN-1-RP-1C; 05/11/2017

- EVT-RP-2017-28439; PBN-1-RP-1C; 05/15/2017

- EVT-RP-2017-28440; PBN-1-RP-1C; 05/17/2017

- EVT-RP-2017-28451; PBN-1-RP-1C; 06/21/2017

- EVT-RP-2017-28452; PBN-1-RP-1C; 07/11/2017

- EVT-RP-2017-28532; New Event; 07/27/2017

- EVT-RP-2017-29065; PBN-2-RP-2C; 08/09/2017

- EVT-RP-2017-29068; PBN-2-RP-2C; 08/17/2017

- EVT-RP-2017-29098; PBN-1-RP-1C; 07/27/2017

- EVT-RP-2017-29099; PBN-1-RP-1C; 07/31/2017

- EVT-RP-2017-29100; PBN-1-RP-1C; 08/02/2017

- EVT-RP-2017-29102; PBN-1-RP-1C; 08/08/2017

- EVT-RP-2017-29103; PBN-1-RP-1C; 08/10/2017

- EVT-RP-2017-29103; PBN-1-RP-1C; 08/10/2017

- EVT-RP-2017-29104; PBN-1-RP-1C; 08/15/2017

- EVT-RP-2018-30213; PBN-1-RP-1C; 11/06/2017

- EVT-RP-2018-30214; PBN-1-RP-1C; 11/07/2017

- EVT-RP-2018-30216; PBN-1-RP-1C; 11/09/2017

- EVT-RP-2018-30310; PBN-1-RP-1C; 10/07/2017

- EVT-RP-2018-30311; PBN-1-RP-1C; 10/08/2017

- EVT-RP-2018-32360; PBN-1-RP-1C; 06/04/2018

- EVT-RP-2018-32361; PBN-1-RP-1C; 06/06/2018

- EVT-RP-2018-32367; PBN-2-RP-2C; 04/18/2018

- EVT-RP-2018-32369; PBN-2-RP-2C; 04/19/2018

- EVT-RP-2018-32375; PBN-2-RP-2C; 07/16/2018

- EVT-RP-2018-33270; PBN-1-RP-1C; 09/08/2018

- EVT-RP-2018-33280; PBN-2-RP-2C; 07/25/2018

- EVT-RP-2018-33281; PBN-2-RP-2C; 07/25/2018

- IT-100 G-01; Seat Leakage Test of Diesel Air Compressor Discharge Check Valves G-01;

Revisions 2 & 3

- PBF-7029; Documentation of Maintenance Rule Performance Criteria; System: MRR;

2/18/2017

- PBF-7029; System: Reactor Protection (RP); Completed 04/162018

- PBF-7029; System: Reactor Protection; Completed 12/13/2016

- PBN-1-RP-SYS01; Reactor Protection System; 11/08/2018; 11/14/2018

- PBN-2-RP-SYS01; Reactor Protection; 11/08/2018; 11/14/2018

- PBNP Inservice Testing Background Valve Data Sheet - EDG Starting Air, 0DA-00100

- PI-AA-100-1007-F01; Revision 10; 2-276/A06 As Found Pickup and Dropout Settings OOT

Low (and 2-276/A06 As Found Pickup and Dropout Settings OOT Low); Completed

09/13/2017

- PI-AA-100-1007-F03; Revision 3; Unexpected Failure of 2PC-431G and TSAC Entry (PWE);

Completed 02/02/2017

- QF-0437; AR 2160866; Completed 10/21/2016

- Station Logs; 01/08/2018-11/07/2018

- System Health Report; Q2-2018; PB Unit 1 RP; 11/14/2018

- WO 40511091; IT-100, Seat LKG Test of DA Compressor Disch Checks; 10/20/2017

- WO 40527545; IT-100, Seat LKG Test of DA Compressor Disch Checks; 01/24/2018

- WO 4056418901; P-038B-M: Troubleshoot RMP 9201, Perform McE W/O RIC; 10/08/2017

71111.13Maintenance Risk Assessments and Emergent Work Control

- AR 2288026; Update to PRA Risk Due to 2P-28A SGFP Out of Service; 10/25/2018

- AR 2270997; PRA Test Factor; 07/05/2018

- AR 2292647; CR Screened As NCAQ VS. CAQ; 11/29/2018

- Drawing M-209, Sheet 14; Starting & Service Air System Diesel Generator Building;

Revision 13

- PBN Unit 1 and 2 (V.12) Current Risk Summary Reports; 11/28/2018; 12/11/2018; 12/17/2018

- Station Logs; 12/18-12/19/2018

- NP 10.3.7; On-Line Safety Assessment; Revision 42

71111.15Operability Determinations and Functionality Assessments

- 0-PT-FP-004; Annual Fire Pump Capacity Test; Revision 16; Completed 08/17/2017

- 0-PT-FP-004; Annual Fire Pump Capacity Test; Revision 18; Completed 08/15/2018

- 2RESP 6.1; Core Power Distribution and Nuclear Power Range Detector Calibration Unit 2;

Revision 6; Completed 12/14/2018

- AOP-6A Unit 2; Dropped Rod; Revision 23

- AOP-6B Unit 2; Stuck or Misaligned Control Rod; Revision 26

- AOP-6C Unit 2; Uncontrolled Motion of RCCA(S); Revision 19

- AR 2276051; P-35B Diesel Fire Pump Did Not Meet Required Hydraulic Perfo; 08/14/2018

- AR 2277437; OTDT and OPDT Rod Stop / Runback Settings; 08/24/2018

- AR 2280448; Hose Through HELB Barrier; 09/14/2018

- AR 2282310; Z-1011A Leak in CWPH; 09/26/2018

- AR 2288809; 1P-53 Run at Reduced Flow Rate; 10/30/2018

- AR 2292172; Reduced Flow in Mini Recirc Line; 11/27/2018

- AR 2294755; Control Rod F-06 Experienced Uncontrol Motion; 12/14/2018

- AR 2294859; Request Engineering Review for 50.59 Applicability for F06; 12/16/2018

- Drawing 1051E005, Sheet 2C; Stationary Gripper Power Circuitry Rack No. 1C40/2C40 Power

Cab 1BD; Revision 1

- Drawing 1051E005, Sheet 3C; Lift Power Circuitry Rack No 1C40/2C40 Power Cab 1BD;

Revision 2

- Drawing 1051E005, Sheet 4C; Moving Gripper Power Circuitry Rack No 1C40/2C04 Power

Cab. 1BD; Revision 2

- Drawing M-208, Sheet 2; Fire Protection Water; Revision 41

- EN-AA-203-1001-F02; Functionality Assessment (FA) Form; Revision 12; AR 2276051;

Completed 08/17/2018

- EN-AA-203-1001-F02; Functionality Assessment (FA) Form; Revision 12; OTDT and OPDT

Rod Stop / Runback Settings

- ICP 06.093; Rod Control System Troubleshooting; Revision 1

- LER 301/2010-003-00; Technical Specification Required Shutdown; 12/13/2010

- PBF-1515c; 10 CFR 50.59/72.48 Screening; Revision 8; Completed 06/16/2011

- Station Log Entries; 12/10-12/12/2018; 12/14-12/17/2018

- TS 6; Rod Exercise Test Unit 2; Revision 35

- Vendor Technical Manual; VTM 01975; Installation, Operation, and Maintenance Instructions

1P-053 and 2P-053; Revision 1

- WO 4057345; GL 89-13 Inspect and Clean Pumphouse Forebay

- WR 94183211; South SW Pump Bay / Retrieve 3/8 OD Tubing

- Calculation 027094-CALC-02; Water Based Fire Suppression System Supply Calculations;

Revision 3

- FPEE-2017-001; Water Supply Evaluation for NFPA Required Fire Suppression; Revision 3

71111.18Plant Modifications

- Adendum: K to Piping System Qualification Report; Piping Analysis of Service Water Pump

Discharge Piping; Revision 00; 05/14/2018

- AR 2255306; Error in Seismic Analysis for FP Piping PWE; 03/21/2018

- AR 2255306; Error in Seismic Analysis for FP Piping; 03/21/2018

- AR 2282423; TMOD EC 276172 Closed in 2012 but Never Converted or Removed;

09/27/2018

- AR Search Report; Subject: Modification; 06/26/2018-11/26/2018

- DG-C01; Summary of Design Requirements for Concrete Expansion Anchors; Revision 2

- DG-M10; Pipe Support Guidelines; Revision 3

- Drawing 3688 M-16; Circ Water Pumphouse Piping Section G-G & H-H; Revision 15

- Drawing PBA-6055, Sheet 13; Piper Hanger Support Detail KB-01-H46 Fire Protection

System; Revision 00

- Drawing PBA-6055, Sheet 14; Piper Hanger/Support Detail KB-01-H47 Fire Protection

System; Revision 00

- Drawing SK-EC 291226-S1; New 3-Way Supports for FP Header at North & South Ends of

Circ Water Pump House; Revision 0

- Drawing SK-EC 291226-S2; New 3-Way Supports for FP Header at North & South Ends of

Circ Water Pump House; Revision 0

- Drawing SK-EC 291226-S3; New 3-Way Supports for FP Header at North & South Ends of

Circ Water Pump House; Revision 0

- Drawing SK-EC 291226-S4; New 3-Way Supports for FP Header at North & South Ends of

Circ Water Pump House; Revision 0

- EC 29166; Add (2) new 3-Way FP Pipe Supports in Pump House Overhead; Revision 0

- Eval. No. SL-014431; Revision 0; Resolution of AR 2255306

- IMC 0609, Appendix O; 10/07/2016

- NDE 700.1; Revision 8; Piping; Completed 05/17/2018

71111.19Post Maintenance Testing

- AR 2285843; Determine Necessity of PMT Leak Test and Track Performance; 10/15/2018

- ER-AA-100-2002-F01; Maintenance Rule Functional Failure Determination; Revision 4;

Unusual Operation During C Charging Pump PMT; 09/27/2018

- IT 13A; CC Pumps and Valves While Aligned for RHR Operation (Cold Shutdown) Unit 2;

Revision 31; Completed 10/17/2018

- OI 163; SI, RHR, and CS Pump Runs and Venting SI Pump Casings; Revision 18; Completed

2/18/2018

- WO 40588342-01; Sample and Change Oil as Required, General Housekeeping

Requirements; 12/18/2018

- AR 2282516; Unusual Operation During C Charging Pump PMT; 09/27/2018

- Station Log Entries; 10/04-10/24/2018

- WO 40104738-26; 2P-011A - Replace Pump Per EC 273506; 12/03/2018

- WO 40104738-28; Hydrostatic Test of New CCW Pump and Pipe; 10/17/2018

- WO 40104738-40; 2P-011A - Seven Day Grout Cube Crush Test; 10/23/2018

71111.20Refueling and Other Outage Activities

- 0-SOP-FH-001; Fuel/Insert/Component Movement in the Spent Fuel Pool or New Fuel Vault;

Revision 31

- 2ICP 05.064; Reactor Vessel Level Outage Calibration; Revision 9; Completed 10/07/2018

- 2ICP 06.015; Auxiliary Coolant System (Non-Outage); Revision 3

- 2R36 ORTS Schedule; October 9, 2018

- AR 2284100; 2TG-01 Overspeed Trip Prior to ORT-4 - Data Gathered; 10/06/2018

- AR 2284101; U2 Turbine Overspeed Trip Immediately After 19KV Bkr Opened; 10/06/2018

- AR 2284180; Items Identified During NRC Walkdown of U2 CTMT (PWE); 10/06/2018

- AR 2284834; FME Dress Requirements Not Met; October 9, 2018

- AR 2286744; Fatigue Rule Waiver Request Needed for 2 I&C Techs; 10/19/2018

- AR 2287517; Incomplete Fatigue Assessment Forms; 10/23/2018

- AR 2287594; NRC Walkdown of Containment Identified Items for Resolution; 10/23/2018

- AR 2287684; Containment Closure Walkdown Effectiveness; 10/24/2018

- ARB 2C04 2C 2-4; BA Flow Deviation or Potential Dilution in Progress; Revision 9

- CL 1E; Containment Closure Checklist Unit 2; Revision 25

- CLE 1E; Containment Closure Checklist Unit 2; Revision 25

- Drawing 110E029, Sheet 1; Auxiliary Coolant System; Revision 57

- Drawing 541F445, Sheet 1; Reactor Coolant System; Revision 51

- Drawing 541F445, Sheet 2; Reactor Coolant System; Revision 33

- Drawing 541F445, Sheet 3; Reactor Coolant System; Revision 19

- Drawing M-82; Sheet 1; Piping and Mechanical Detail of Containment Piping Penetration

Closure; Revision 13

- Drawing M-82; Sheet 2; Cont Piping Penetration Closure; Revision 6

- EC 291255; Point Beach Unit 2 Cycle 37 Core Reload Modifications; Revision 1

- ESOMS Clearance Package; 2 CC P-11A Replace MM 03A

- ESOMS Clearance Package; 2 CC P-11A X-Connect Isol 01

- MA-AA-101-1000; Foreign Material Exclusion Procedure; Revision 21

- OP 1B; Reactor Startup; Revision 73; Completed 04/13/2017

- OP 1B; Reactor Startup; Revision 74; Completed 10/31/2017

- OP 1B; Reactor Startup; Revision 76

- OP 1C; Startup to Power Operation Unit 2; Revision 43

- OP 3A Unit 2; Power Operation to Hot Standby Unit 2; Revision 17

- OP 3B; Reactor Shutdown; Revision 46

- OP 3C Unit 2; Hot Standby to Cold Shutdown Unit 2; Revision 16

- OP 4D Part 3; Draining the Reactor Cavity and Reactor Coolant System; Revision 38

- OP 5A; Reactor Coolant Volume Control; Revision 49

- Outage Progress Summary Sheets; October 9-18, 2018

- PBF-5101; Revision 19; U2R36 HEUFC; Completed October 13, 2018

- PBF-5101; Revision 19; U2R36 Insert Moves; Completed October 14, 2018

- PBF-5101; Revision 19; U2R36 Offload; Completed October 12, 2018

- PBF-5101; Revision 19; U2R36 Reload; Completed October 16, 2018

- PBF-5105; Revision 1; SNM and Other Device Physical Inventory Unit 2 Reactor Core Map;

Cycle 37; Completed October 16, 2018

- Point Beach 2R36 Schedule Pictorial View; 09/13/2018

- Point Beach Turnover Report P2R36 Day Shift; October 7, 2018

- REI 26.0; Fuel/Insert/Component Movement Planning; Revision 22

- RESP 4.1; BOL Physics Tests; Revision 29

- RM-AA-100-1000-F02; Record Supplement Form; Revision 4; WO 4048806801; Completed

07/06/2017

- RP 1C; Refueling; Revision 80

- Spent Fuel Pool Maps w/ Legend; October 29, 2018

- Station Logs Search; 2X-03 October 8-13, 2018

- U2R36 Shutdown Safety Assessments; October 6-23, 2018

- WO 40430879-01; 2ICP 14.005 - RHR MOVS 700 and 720 Interlock Test; 03/28/2017

- WO 40431271-01; 2ICP 10.3 - Fill and Vent PZR Press and Level; 04/10/2017

- WO 40431274-01; 2ICP 4.4-6 - LTOP Transmitters Outage Cal; 03/31/2017

- WO 40431276-01; 2ICP 5.56 - RCS Instruments Outage Call; 04/01/2017

- WO 40431278-01; 2ICP 5.61 - Pressurizer Cold Level Transmitter; 04/01/2017

- WO 40543997-01; 2ICP 4.4-6 - LTOP Transmitters Outage Cal; 10/14/2018

71111.22Surveillance Testing

- AR 2228265; Insulation Removed from U-1 B RHR HX

- AR 2233196; Leakage Too High for 1SI-845E During TS-30

- AR 2278976; Unit 1 Flux Map Detector C Drift Unacceptable; 09/05/2018

- AR 2284385; *P* IT 305D Train A - Main Feedwater Isolation Valve Test; 10/07/2018

- AR 2284777; As Found Leak Rate Limit at 143% of Administative Limit; 10/09/2018

- AR 2284859; As Found Leak Rate is 43% of Admin Limit - Increasing Trend; 10/09/2018

- AR 2286589; ORT 59 Spray System Required Pen/Ink Change; 10/18/2018

- AR 2286855; Mini-Recirc Operation for 2P-53, MDAFW During ORT 3; 10/19/2018

- AR 2292333; Valve 2CS-3136 Failed 1st Surveillance Basis for Acceptance; 11/28/2018

- CLRT Testing Program; Basis Document; Revision 17

- Drawing 10668 BD-10; Reactor Protection System Pressurizer Pressure Control; Revision 4

- Drawing 541F091, Sheet 1; Reactor Coolant System; Revision 56

- Drawing 883D195, Sheet 7; Safeguards Actuation Signals; Revision 25

- ISI CL 1,2,3 Program; PBNP Class 1,2, and 3 Inservice Inspection Program; Revision 15

- IT 305D Train A; Main Feedwater Isolation Valve Test Train A Unit 2; Revision 3; Completed

10/08/2018

- IT 535D; Leakage Reduction and Preventive Maintenance Program Train B HHSI and RHR

Piggyback Test Mode 1, 5, 6, (Refueling) Unit 2; Revision 18; Completed 10/04/2018

- ORT 3A; Safety Injection Actuation with Loss of Engineered Safeguards AC (Train A) Unit 2;

Revision 48

- ORT 59; Train A Spray System CIV Leakage Test Unit 2; Revision 35

- STPT 14.2; Condensate and Feedwater; Revision 36

- TS 4A; Turbine trip Test Unit 2; Revision 32

71114.02Alert and Notification System Testing

- AR 2161382; EP Sirens Temporary Loss of AC Power to 2 Sirens (01 & 18); 10/10/2016

- AR 2162431; Bad Batteries in Siren 18 Noted During Annual Maintenance; 10/13/2016

- AR 2176032; Momentary Door Open Alarm on Siren 18; 12/20/2016

- AR 2177917; Door Open Alarm on EP Siren 18; 01/04/2017

- AR 2178334; PWE - Door Open Alarm Siren 18 (rework); 01/06/2017

- AR 2185697; Temporary AC Power Loss to Siren 18; 02/15/2017

- AR 2205859; Improper Use of Procedure for Siren Activation; 05/18/2017

- AR 2236435; Improper Use of Siren Procedure by County; 11/15/2017

- AR 2239317; Improper Use of Siren Procedure by County; 12/06/2017

- AR 2248452; Improper Use of Siren Procedure by County; 02/07/2018

- AR 2270618; Siren 13 Out of Service Due to Low Comm Battery; 06/30/2018

- AR 2271567; Siren 13 Low Comm Battery UNSAT; 07/10/2018

- AR 2274970; EPZ Siren 13 Communications Battery Low Voltage; 08/06/2018

- EPMP 6.0; Alert and Notification System (ANS); Revision 19

- REP-10 Design Report; NextEra Energy Point Beach, LLC; Revision 1

71114.03Emergency Response Organization Staffing and Augmentation System

- AR 2198664; 1Q17 EP Call-In Augmentation Drill SAT With Comments; 04/13/2017

- AR 2212514; 2Q17 ERO Call-In Augmentation Drill Results; 06/27/2017

- AR 2234564; ERO Team Coverage - Not Verified; 11/03/2017

- AR 2249828; EAL Monitor Alternate Facility Not Clear; 02/15/2018

- AR 2257199; Below Minimum EP Staffing for 52 Minutes; 03/31/2018

- AR 2257415; 1Q18 Call-In Drill SAT with Comments; 04/02/2018

- AR 2285205; Site Grading of EP Drills Not IAW Fleet Procedure; 10/11/2018

- EPIP 4.1; Technical Support Center (TSC) Activation and Evacuation; Revision 54

- EPIP 4.3; Emergency Operations Facility (EOF) Activation and Evacuation; Revision 47

- Q04-01; ERO Pager Staff Augmentation Drills - 4th Quarter 2016-3rd quarter 2018

- 71114.04Emergency Action Level and Emergency Plan Changes

- Current Revisions of the Point Beach Emergency Plan and Associated Sections

- EPIP 1.2; Emergency Classification; Revision 22

- Evaluation 2017-PB-014; 10 CFR 50.54(q) Screening Form; 06/06/2017

- Evaluation 2017-PB-020; 10 CFR 50.54(q) Screening Form; 07/05/2017

- Evaluation 2017-PB-021; 10 CFR 50.54(q) Screening Form; 07/05/2017

- Evaluation 2018-PB-001; 10 CFR 50.54(q) Screening Form; 01/13/2018

- Evaluation 2018-PB-012; 10 CFR 50.54(q) Screening Form; 04/18/2018

- Evaluation 2018-PB-021; 10 CFR 50.54(q) Screening Form; 04/26/2018

- Evaluation 2018-PB-022; 10 CFR 50.54(q) Screening Form; 04/26/2018

71114.05Maintenance of Emergency Preparedness

- AR 2214815; Update EAL Thresholds for Pumpbay Level in HU1 and HA1; 07/12/2017

- AR 2251085; First Level Escalation to PBN EP SFAM; 02/23/2018

- AR 2080131; Pre-NRC Inspection Assessment of PBNP EP Program; 08/31/2017

- Current Revisions of the Point Beach Emergency Plan and Associated Sections

- ERO Drill Reports for Drills Conducted from the 4th quarter 2016-2nd quarter 2018

- NPM 2017-0036; Point Beach Unusual Event 03/20/2017; 03/23/2017

- NPM 2017-0115; Point Beach Unusual Event 10/09/2017; 10/10/2017

- PBN 17-006; Point Beach Nuclear Assurance Report on Emergency Preparedness;

08/11/2017

- PBN 18-006; Point Beach Nuclear Assurance Report on Emergency Preparedness;

08/11/2018

71124.01Radiological Hazard Assessment and Exposure Controls

- AR 2261316; Actual Site Daily Dose >50% Below the Estimate; 04/25/2018

- AR 2265424; PAB Roof - Radiological Boundary Found Sagging; 05/22/2018

- AR 2266370; Areas for Improvement in Radiological Practices; 05/30/2018

- AR 2270567; Annual RCA Yard Survey Identified Contamination Inside RCA; 06/29/2018

- AR 2274917-04; NRC Inspection Assessment; 09/24/2018

- AR 2282199; U2R36 Potential Dose Increase; 09/26/2018

- AR 2284303; Cavity Shield Rack Not Stable in U2 Cavity; 10/07/2018

- AR 2285252; Radworker Observed in PCs Crossing Contaminated Boundary; 10/11/2018

- HP 1.1; Personnel Dose Determination and Reporting; Revision 12

- HP 1.15; Area Monitoring Program; Revision 2

- HP 2.1.2; Personnel Contamination Monitoring, Decontamination and Documentation;

Revision 25

- HP 2.14; Containment Keyway Personnel Access; Revision 19

- HP 3.1; Radiological Surveys and Records; Revision 17

- HP 3.2; Radiological Labeling, Posting and Barricading Requirements; Revision 64

- Radiation Work Permit 18-2004; Outage Shielding Activities; Revision 00

- Radiation Work Permit 18-2016; Remove/Reinstall RV Head; Revision 01

- Radiation Work Permit 18-2017; Remove - Reinstall RV Internals; Revision 00

- Radiation Work Permit 18-2020; Keyway Entries; Revision 00

- Radiation Work Permit 18-2041; Containment Close Out Walk-Downs; Revision 00

- Sentinel SEN0258; Source Leak Check Inventory (Exempt); 07/24/2018

- Sentinel SEN0258; Source Leak Check Inventory (None Exempt); 01/31/2018

71151Performance Indicator Verification

- NP 5.2.16; NRC Performance Indicators, Attachment B PI Data Calculation, Review and

Approval, Occupational Exposure Control Effectiveness; September 2017-August 2018

- NP 5.2.16; NRC Performance Indicators, Attachment B PI Data Calculation, Review and

Approval, ODCM Radiological Effluent Occurrences; September 2017-August 2018

- NP 5.2.16; NRC Performance Indicators, Attachment B PI Data Calculation, Review and

Approval, RCS Activity - Fuel Performance; September 2017-August 2018

- NRC Performance Indicator Data, Emergency Preparedness - Alert and Notification System

Reliability; 3rd Quarter 2017-2nd Quarter 2018

- NRC Performance Indicator Data, Emergency Preparedness - Drill/Exercise Performance;

3rd Quarter 2017-2nd Quarter 2018

- NRC Performance Indicator Data, Emergency Preparedness - ERO Readiness;

3rd Quarter 2017-2nd Quarter 2018

- AR Searches; Systems: Component Cooling Water, Service Water; 10/1/2017 - 9/30/2018

- AR Searches; Systems: Residual Heat Removal; 10/1/2017 - 9/30/2018

- MSPI Derivation Reports; Residual Heat Removal, Cooling Water; Unavailability Index; Units 1

and 2; October 2017 - September 2018

- MSPI Derivation Reports; Residual Heat Removal, Cooling Water; Unreliability Index; Units 1

and 2; October 2017 - September 2018

- Point Beach Maintenance Rule Data Tracking Logs; Reliability, Availability; 10/1/2017 -

9/30/2018

71152Problem Identification and Resolution

- Application Note 13C3236; Tyco Electronics Corporation; Relay Contact Life

- AR 1862935; MRP-227-A Baffle-Former Bolt Inspection Results; 04/04/2013

- AR 1954827; MRP-227-A Baffle-Former Bolt Examination Results; 04/04/2013

- AR 2152252; G-01 ESTR Relay Found Unsat, Replaced, Is PMID Adequate?; 08/25/2016

- AR 2154733; Replace 15 Relays on G-01; 09/08/2016

- AR 2154734; Replace 16 Relays on G-02; 09/08/2016

- AR 2193700; Fleet Review of MRP 2017-009, RVI Program, BFB FREQ.; 03/24/2017

- AR 2226448; Evaluate the Prairie Island Green Non-Cited Violation; 09/11/2017

- AR 2245034-01; Fleet Review of MRP-2018-002, RVI Program, BFB Expansion Inspection;

03/14/2018

- AR 2258514; G-02 South Air Bank Motors Failed to Engage during TS 82; 04/09/2018

- AR 2258738; G-02/C-35, ESR2 Relay Parts Traceability Discrepancies PWE; 04/10/2018

- AR 2271902; EDG Relay Replacement Moved Without Written Documentation; 07/12/2018

- AR 2274213; G-01 Instantaneous Relays Contacts Cleaned by Use of DLRO; 07/31/2018

- Drawing 4998466, Sheet 263A; 4160V Switchgear Cubicle 60 Emergency Generator Breaker

1A52-60; Revision 14

- Drawing 499B466, Sheet 293A; 4160V SWGR. - 2A05 EDG. - G01 Cubicle 73; Revision 15

- Drawing 8413730, Sheet 2; Diesel Generator G01 DC Control; Revision 9

- EVT-DG-2018-31346; G-02 South Air Bank Motors Failed to Engage; 04/09/2018

- MA-AA-203-1000; Maintenance Testing; Revision 10

- OE 02142699-01; Operating Experience Review for MRP 2016-021; 09/01/2016

- Point Beach; 2014 PM Sub-Component Optimization Project Document; Pages 10-19

- QF-0437; Condition Evaluation; Revision 5; Completed 09/08/2016

- RMP 9043-18; Emergency Diesel Generator G-01 2 Year Relay Maintenance; Revision 4

- Station Logs; 04/09/2018

- STPT 19.2; Emergency Diesel: Generator G-02 General Instrumentation; Revision 8

- Trend Report for Jun 1 - Nov 30; 12/04/2018

- WDI-PJF-1309122-FSR-001; Point Beach 1R34 Baffle Bolt Ultrasonic Inspection Final Report;

Revision 1

- WDI-PJF-1311923-FSR-001; Point Beach Nuclear Plant 2R33 Baffle Bolt Ultrasonic

Inspection Final Report; March 2014

- AR 2249084; Procedure Issue for SI Pump Cap Installation; 2/1218

- AR 2277741; HU Issues Need to be Reviewed in Aggregate; 8/28/18

- AR 2278154; Procedure Step Performed Out of Sequence; 8/30/18

- AR 2279020; NRC Identified Issues during Performance of IT-13 Train B; 9/5/18

- AR 2285504; U2R36 Trend in HU Performance with Increasing Significance; 10/12/18

- AR 2285545; Chemistry Records Improperly Stored; 10/12/18

71153Follow-Up of Events and Notices of Enforcement Discretion

- OP 1B; Reactor Startup; Revision 76

- OP 1C; Startup to Power Operation Unit 1; Revision 40

- OP 3B Appendix A; Shutdown Margin Calculation; Revision 18

- OP 3B; Reactor Shutdown; Revision 46

- OP 3D; Post Reactor Trip Stabilization to Hot Standby; Revision 1

- OP-AA-100-1000; Conduct of Operations; Revision 25

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