IR 05000266/2019001
ML19113A114 | |
Person / Time | |
---|---|
Site: | Point Beach |
Issue date: | 04/23/2019 |
From: | Eric Duncan Reactor Projects Region 3 Branch 4 |
To: | Craven R Point Beach |
References | |
IR 2019001 | |
Download: ML19113A114 (13) | |
Text
ril 23, 2019
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC INTEGRATED INSPECTION REPORT 05000266/2019001 AND 05000301/2019001
Dear Mr. Craven:
On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2. On April 3, 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/
Eric Duncan, Chief Branch 4 Division of Reactor Projects Docket Nos.: 05000266; 05000301 License Nos.: DPR-24; DPR-27
Enclosure:
IR 05000266/2019001; 05000301/2019001
Inspection Report
Docket Numbers: 05000266 and 05000301 License Numbers: DPR-24 and DPR-27 Report Numbers: 05000266/2019001 and 05000301/2019001 Enterprise Identifier: I-2019-001-0051 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Inspection Dates: January 01, 2019 to March 31, 2019 Inspectors: K. Barclay, Resident Inspector T. Hartman, Senior Resident Inspector T. McGowan, Reactor Engineer Approved By: Eric Duncan, Chief Branch 4 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a quarterly inspection at 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. 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 LER 05000301/2018001-00 LER 2018-001-00 for Point 71153 Closed Beach Nuclear Plant, Unit 2,
Operation or Condition Prohibited by Technical Specifications, Less than Minimum Refueling Cavity Water Level.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On March 10, 2019, the unit began coastdown for the upcoming refueling outage. On March 23, 2019, the unit was taken offline for planned refueling outage U1R38. The unit remained offline for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power and remained at or near full power throughout 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 External Flooding Sample (IP Section 03.04)
The inspectors evaluated the licensees readiness to cope with external flooding in the Primary Auxiliary Building and the Turbine Building.
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for high winds, extreme cold, and heavy snowfall on January 24, 2019.
71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Diesel-driven fire pump on January 25, 2019;
- (2) G-03 emergency diesel generator on January 28, 2019; and
- (3) Unit 1 motor-driven auxiliary feedwater train on March 6, 2019.
71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire Zones 184 and 185 on January 19, 2019;
- (2) Fire Zone 183 on January 19, 2019;
- (3) Fire Zone 187 on January 19, 2019;
- (4) Fire Zone 215 on January 19, 2019; and
- (5) Fire Zone 217 on January 19, 2019.
71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)
The inspectors evaluated the readiness and performance of the following equipment:
Primary Auxiliary Building (PAB) Battery Room Vent Cooler HX-105A.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during Control Rod F6 recovery on February 6, 2019.
- (2) The inspectors observed and evaluated licensed operator performance in the Control Room during a Unit 1 reactor shutdown on March 22, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated a licensed operator simulator scenario on January 14, 2019.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Refueling Water Storage Tank (RWST) level transmitter failure on November 2, 2018; and
- (2) Unit 2 source range detector 2N-31 failure on October 6, 2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) 2P-10A Unit 2 residual heat removal pump maintenance on January 17, 2019;
- (2) G-01 emergency diesel generator (EDG) maintenance on January 22, 2019;
- (3) 2P-11A component cooling water pump maintenance on February 19-20, 2019; and
- (4) 1P-10A Unit 1 residual heat removal pump maintenance on March 18, 2019.
71111.15 - Operability Determinations and Functionality Assessments Operability Determinations and Functionality Assessments (IP Section 02.01)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) White flakes present in snubber fluid;
- (2) High as-found airlock leakage;
- (3) 1CS-256B leaking air to atmosphere;
- (4) Service air pipe ultrasonic testing (UT) does not meet minimum wall thickness; and
- (5) B Train EDGs frequency response not bounded by calculation 2005-007.
71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
The inspectors evaluated the following modification:
EC 290355 - Rod Control Stationary and Moveable Gripper Fuse Upgrade.
71111.19 - Post Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)
The inspectors evaluated the following post maintenance tests:
- (1) G-01 EDG after governor replacement on January 21, 2019;
- (2) G-02 EDG air system testing after maintenance on February 13, 2019;
- (3) 2P-11A component cooling water pump after maintenance on February 19, 2019;
- (4) P-32C service water pump discharge check valve testing after maintenance on March 5, 2019; and
- (5) 1P-10A residual heat removal pump testing after maintenance on March 18, 2019.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: In Service Testing (IST) (IP Section 03.01)
IT-06, Train B Containment Spray Pump and Valve Test, on March 6, 2019.
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) ORT 4, Unit 1 Main Turbine Mechanical Overspeed Trip Device, on March 23, 2019; and
- (2) ORT 3B, Unit 1 Safety Injection Actuation with Loss of Engineered Safeguards AC
[Alternating Current] (Train B), on March 25, 2019.
71114.06 - Drill Evaluation Drill and/or Simulator-Based Licensed Operator Requalification Training (IP Section 02.01)
The inspectors evaluated:
A crew simulator evaluation with Drill Exercise Performance (DEP) on January 14,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified the licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===
- (1) Unit 1 (January 1-December 31, 2018); and
- (2) Unit 2 (January 1-December 31, 2018).
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(2 Samples)
- (1) Unit 1 (January 1-December 31, 2018); and
- (2) Unit 2 (January 1-December 31, 2018).
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03)
(2 Samples)
- (1) Unit 1 (January 1-December 31, 2018); and
- (2) Unit 2 (January 1-December 31, 2018).
71152 - Problem Identification and Resolution Annual Follow-Up of Selected Issues (IP Section 02.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:
NFPA [National Fire Protection Association] 805 Fire Protection Corrective Action Review.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following Licensee Event Report (LER) which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
LER 05000301/2018-001-00, Operation or Condition Prohibited by Technical Specifications, Less than Minimum Refueling Cavity Water Level (ADAMS Accession: ML18347B033). The circumstances surrounding this LER are documented in Inspection Report 05000266/2018004; 05000301/2018004, Results Section 1R20, Outage Activities, (ADAMS No. ML19022A242). This LER is closed.
INSPECTION RESULTS
Observation 71152 The inspectors reviewed condition reports associated with the licensees transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants. Specifically, the inspectors reviewed the licensees identification and resolution of various problems that had been identified after the licensee implemented NFPA 805 in February 2017. Examples of documented problems included required procedure changes that were not implemented prior to NFPA 805 transition, incorrect fire barrier categorization, and control cables incorrectly categorized as instrument cables.
Generally, the inspectors found that the licensees corrective actions were appropriate to correct the issues once they were identified; however, the inspectors determined gaps existed in the licensees NFPA 805 transition process and many of the issue could have been identified prior to NFPA 805 implementation.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 3, 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 47
- AR 2300774; Previous AR Contains Erroneous Information; 02/06/2019
- AR 2305225; Water Leaking From Ceiling In EDG Building; 03/12/2019
- AR 2305436; PAB Truck Bay Flood Barrier Installation Questions; 03/12/2019
- Calculation FPL-076-CALC-015; Maximum Precipitation Flood Effects; Revision 0
- Calculation FPL-076-CALC-019; Precipitation Effects Sensitivity Analysis; Revision 1
- NP 8.4.17; PBNP Flooding Program; Revision 32
- RMP 9422; Circulating Water Pumphouse and Turbine Hall Barrier Placement; Revision 2
- WO 40614753; PC 6 Part 9 Operations Flood Equipment Inventory; 02/19/2019
71111.04Equipment Alignment
- CL 11A G-03; G-03 Diesel Generator Checklist; Revision 9
- CL 13E Part 2; Auxiliary Feedwater Valve Lineup Motor Driven; Revision 56
- CL 19; Fire Protection System Valves; Revision 54
- Drawing M-208, Sheet 1; P&ID Fire Water; Revision 51
- Drawing M-208, Sheet 2; P&ID Fire Protection Water; Revision 42
- Drawing M-209, Sheet 14; P&ID Starting & Service Air System Diesel Generator Building;
Revision 13
- Drawing M-217, Sheet 1; P&ID Auxiliary Feedwater System; Revision 104
- Drawing M-217, Sheet 3; P&ID Auxiliary Feedwater System; Revision 08
- Drawing M-219, Sheet 3; P&ID Fuel Oil System Diesel Generator Building; Revision 17
71111.05AQFire Protection Annual/Quarterly
- AR 2296034; NRC Identified Issue With Door-3 G-01 To TH1 Door; 12/29/2018
- AR 2296425; NFPA 805 Fire Dampers Missing From Inspection Procedure; 01/03/2019
- AR 2301676; Door 8 Does Not Freely Close; 02/12/2019
- AR 2302811; OM 3.27 Comp Action Tracking Concern Not Addressed; 02/21/2019
- AR 2304468; NRC Identified Concern For Sprinkler Interference; 03/05/2019
- PFP-0-PAB 26; Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 26 FT; Revision 0
- PFP-SOG-001; Pre-Fire Plan Standard Operating Guidelines; Revision 0
- R2014-03-001; NFPA 805 Radioactive Release Review; Revision 0
71111.07Heat Sink Performance
- AR 2306947; NRC Identified Question on Process for Repeating Steps; 03/22/2019
- WO 40601350-01; HX-105A GL 89-13 Remove End Bells and Hydrolance; 03/06/2019
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
- AR 2306966; Procedural Enhancement Identified during Shutdown; 03/23/2019
- EPIP 2.1 Attachment B; Nuclear Accident Reporting Form (NARS) - ALERT (Drill); 01/14/2019
- OP 3A Unit 1; Power Operation to Hot Standby Unit 1; Revision 17
- OP 3B; Reactor Shutdown; Revision 46
- OP-AA-100-1000; Conduct of Operations; Revision 26
- PBN LOC 19A 001E; As-Found/DEP; Revision 0
71111.12Maintenance Effectiveness
- AR 1937578; Cognitive Trend: RWST Low Level Alarms; 1/31/2014
- AR 2094169; U1 Reactor Startup Aborted; 11/30/2015
- AR 2131582; L-972 RWST Level PPCS Indication; 6/12/2016
- AR 2228928; N-32 Failed To Energize; 10/07/2018
- AR 2284111; 2N-31 Source Range Not Responding As Expected; 10/06/2018
- AR 2289262; RWST Level Channel Failure; 11/2/2018
- AR 2292061; Establish MR Evaluation Assignment For Previous (MRR) CR; 11/26/2018
- EVT-SI-2018-33415; Maintenance Rule Event Report; L-972 Failure; 11/15/2018
- PBN-1-SI-SYS01; Maintenance Rule Function Scoping/Function Criteria; Unit 1 Safety
Injection System; 03/2019
- PBN-2-NI-SYS01; Maintenance Rule Function Scoping/Function Criteria; Unit 2 Nuclear
Instrumentation System; 03/2019
- WO 40433003; 1N-31 Indicates Lower Than Expected; 11/30/2015
- WO 40564164; N-32 Failed to Energize; 10/27/2017
- WO 40625698; 2N-31 Source Range Not Responding As Expected; 10/09/2018
71111.13Maintenance Risk Assessments and Emergent Work Control
- Current Risk Summary Report; PBN Unit 1 and 2; 0/17/2019
- Current Risk Summary Report; PBN Unit 1 and 2; 01/22/2019
- Current Risk Summary Report; PBN Unit 1 and 2; 03/18/2019
- Current Risk Summary Report; PBN Unit 1 and 2; 02/19-02/20/2019
71111.15Operability Determinations and Functionality Assessments
- AR 2296502; Found White Flakes in Snubber Fluid; 01/03/2019
- AR 2297046; Contingency WO to Replace 2HS-26; 01/08/2019
- AR 2298453; As-Found Leakage High on Air Lock; 01/18/2019
- AR 2294643; U2 Containment Outer Door Trend; 12/14/2018
- AR 2299832; 1CS-256B Leaking Air to Atmosphere; 01/30/2019
- AR 2303713; Service Air Pipe UT Does Not Meet Minimum Thickness; 2/27/2019
- AR 2307523; B Train EDGs Frequency Response Not Bounded by Calculation 2005-0007;
03/27/2019
71111.18Plant Modifications
- AR 2300663; Documentation Weakness Identified In EC290355; 02/05/2019
- AR 2307399; Fuses Installed For Unit 2 Rod F-06 Without Proper Justification; 03/26/2019
- Drawing WEST 1051E005, Sheet 4C; Schematic Diagram Moving Gripper Power Circuitry
Rack NO. 1C40/2C40 Power Cab. 1BD; Revision 2
- EC 290355; Rod Control Stationary and Moveable Gripper Fuse Upgrade; Revisions 0 and 1
- EC 292546; Temporarily Isolate Unit 2 Control Rod F-6 Moveable Coil Internal; Revision 0
- WO 40641721-01; Control Rod F6 Experienced Uncontrolled Motion; 02/06/2019
71111.19Post Maintenance Testing
- AR 2298907; G-01 Governor Tuning Engine Response Criteria; 01/23/2019
- AR 2301266; PMT Failed On 2C-2D1 U2 Upper Outer Hatch; 02/08/2019
- AR 2306539; Work Planning/Manage: PMT Guidance Inadequate; 03/20/2019
- WO 40450455; G-01; Replace G-01 2301A Governor & DRU; 01/25/2019
- WO 40563625; SW-00032 Disassemble/Visually Inspect Check Valve; 03/06/2019
- WO 40575847; T-60D / Replace Tank Due To Wall Thinning; 01/17/2019
- WO 40594548; TS-81, G-01 Emergency Diesel Generator Operability Test; 01/23/2019
- WO 40598236; IT-100, Seat Lkg Test of DA Compressor Disch Checks; 02/13/2019
- WO 40598258; TS-82, G-02 Emergency Diesel Generator Operability Test; 02/14/2019
- WO 40604014-01; 1P-10A Lubricate Coupling As Required; 03/18/2019
- WO 40604871-01; IT 03 Train A, 1P-10A Low Head SI Pumps/Vlvs; 03/18/2019
- WO 40607974-01; IT-07B, P-32B Service Water Pump Test; 03/06/2019
- WO 40610316-01; IT-07C, P-32C Service Water Pump Comprehensive Test; 03/06/2019
- WO 40627704; 2P-11A / CCW Pump Inboard Seal Housing Leak; 2/21/2019
- WO 40627720; DA-230/G-02 DA System Valve DA-230 Very Difficult To Operate; 02/13/2019
71111.20Refueling and Other Outage Activities
- AOP-8F; Loss of Spent Fuel Pool Cooling; Revision 24
- Drawing 541F091, Sheet 1; P&ID Reactor Coolant System; Revision 56
- Drawing 541F091, Sheet 2; P&ID Reactor Coolant System; Revision 41
- OP 3A Unit 1; Power Operation to Hot Standby Unit 1; Revision 17
- OP 3B; Reactor Shutdown; Revision 46
- OP 3C Unit 1; Hot Standby to Cold Shutdown Unit 1; Revision 17
- PBNP Shutdown Safety Assessment and Fire Inspection Checklist; 03/28/2019
- RP 2A; Receipt of New Fuel Assemblies; Revision 58
- RP 2C; New Fuel and Fuel Insert Inspection; Revision 27
- U1R38 Outage Safety Review Supporting Documentation; 03/06/2019
71111.22Surveillance Testing
- AR 2306963; U1R38 ORT 4 Turbine Overspeed Results; 03/23/2019
- IT 06 Train B; Train B Containment Spray Pump and Valves Unit 2; Revision 5
- ORT 3B; Safety Injection Actuation with Loss of Engineered Safeguards AC (Train B) Unit 1;
Revision 47
- ORT 4; Main Turbine Mechanical Overspeed Trip Device Unit 1; Revision 35
71114.06Drill Evaluation
- EPIP 2.1 Attachment B; Nuclear Accident Reporting Form (NARS) - ALERT (Drill); 01/14/2019
- PBN LOC 19A 001E; As-Found/DEP; Revision 0
71151Performance Indicator Verification
- Performance Indicators; Units 1 and 2; Unplanned Power Changes Per 7000 Critical Hours;
01/01/2018-12/31/2018
- Performance Indicators; Units 1 and 2; Unplanned Scrams Per 7000 Critical Hours;
01/01/2018-12/31/2018
- Performance Indicators; Units 1 and 2; Unplanned Scrams with Complications (USwC);
01/01/2018-12/31/2018
- Point Beach PI Reporting Data; Units 1 and 2; 01/01/2018-12/31/2018 For Unplanned Power
Changes Per 7,000 Critical Hours
- Point Beach PI Reporting Data; Units 1 and 2; 01/01/2018-12/31/2018 For Unplanned Scrams
Per 7,000 Critical Hours
- Point Beach PI Reporting Data; Units 1 and 2; 01/01/2018-12/31/2018 For Unplanned Scrams
with Complications Per 7,000 Critical Hours
71152Problem Identification and Resolution
- 0-SOP-DC-003; 125 VDC System, Bus D-03 & Components; Revision 20
- AR 2195016; OM 3.27 High Safety Significant Fire Barriers Questionable; 03/30/2017
- AR 2251410; Restoration of D-109 in AOP-40 Series Procedures; 02/26/2018
- AR 2259195; Mods Do Not Completely Resolve MOD-26-3 For NFPA 805; 04/11/2018
- AR 2282513; Fire Protection Evaluation Report Incorrect Statement; 09/27/2018
- AR 2289102; Additional Cables Need Evaluation Regarding NFPA 805; 11/01/2018
- AR 2300038; Door Did Not Close Freely Due to Wind; 01/31/2019
- AR 2302041; OM 3.27 Not Updated Timely With New HSS Barriers; 02/14/2019
- AR 2302823; HSS FP Sys Components Not Conservative in OM 3.27; 02/21/2019
- AR 2303103: NRC Identified Error In FPTE 2016-005; 02/22/2019
- Drawing E-7; Sheet 25; Connection Diagram 120V AC Instrument Bus Distribution
Panel 1Y-104; Revision 5
- Drawing E-98; Sheet 47; Connection Diagram Local Devices Instrumentation; Revision 1
- FPTE-2015-003; Evaluation of Selective Coordination and Cable Protection For NFPA 805;
Revision 0
- Point Beach Cable Schedule; Cables WN1I965E, WN1I965N, WN1I967 E, and WN1I967N;
10/05/2018
- R2542-001; NFPA 805 Transition Project - Common Power Supply Evaluation; Revision 0
71153Follow-Up of Events and Notices of Enforcement Discretion
- AR 2286011; Lowering Refuel Cavity Level; 10/15/2018
- AR 2286439; Incorporate OE from CR02286011; 10/17/2018
- RP 1C; Refueling; Revisions 80 and 81
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