IR 05000266/2018011

NRC Triennial Inspection Changes, Tests and Experiments; Inspection Report 05000266/2018011 and 05000301/2018011 (DRS-G.Hausman)

ML18275A206
Person / Time
Site:	Point Beach
Issue date:	10/01/2018
From:	Robert Daley Division of Reactor Safety III
To:	Craven R Point Beach
References
IR 2018011
Download: ML18275A206 (8)

Text

ber 1, 2018

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC TRIENIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS; INSPECTION REPORT 05000266/2018011 AND 05000301/2018011

Dear Mr. Craven:

On September 14, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluation of Changes, Tests and Experiments Inspection at your Point Beach Nuclear Plant.

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.

Based on the results of this inspection, the NRC inspectors did not identify any findings or violations 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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-266, 50-301 License Nos. DPR-24; DPR-27

Enclosure:

IR 05000266/2018011; 05000301/2018011

REGION III==

Docket Numbers: 50-266, 50-301 License Numbers: DPR-24; DPR-27 Report Numbers: 05000266/2018011; 05000301/2018011 Enterprise Identifier: I-2018-011-0003 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: September 10, 2018, to September 14, 2018 Inspectors: G. Hausman, Senior Engineering Inspector (Lead)

M. Domke, Engineering Inspector D. Szwarc, Senior Engineering Inspector Approved by: R. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an Evaluations of Changes, Tests and Experiments 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. The NRC and self-revealed findings, violations, and additional items are summarized in the table below. Licensee-identified non-cited violations are documented in report sections.

List of Findings and Violations No findings or violations were identified.

Additional Tracking Items None

INSPECTION SCOPES

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

REACTOR SAFETY

===71111.17TEvaluations of Changes, Tests and Experiments The inspectors evaluated the following from September 10, 2018, to September 14, 2018:

10 CFR 50.59 Evaluations71111.17T ===

(1) Evaluations (EVAL) 2014-004; Engineering Change (EC) 277545 Reactor Coolant Pump Seal Replacement; Revision 0

(2) EVAL 2014-005; External Wave Run-Up Flood Mitigation Strategy; Revision 0

(3) EVAL 2015-001; National Fire Protection Association-805 License Amendment Request MOD-14 IA Isolation Capabilities for the Condenser Steam Dump & Moisture Separator Reheater Valves, Unit 1 & 2 (EC 282784); Revision 0

(4) EVAL 2016-001; Updated Final Safety Analysis Report Chapter 11 Changes Are Needed to be Consistent with License Amendment Request 279 Submittal; Revision 0

(5) EVAL 2018-001; EC 289216Branch River Project Switchyard Change Package; Revision 0 10 CFR 50.59 Screening/Applicability Determinations71111.17T (13 Samples)

(1) Screening/Applicability Determinations (SCR) 2015-0118; Procedure Changes Due To Increase In Allowable Train B Emergency Diesel Generator Room Normal Temperature; Revision 2

(2) SCR 2016-0032; Revise Emergency Contingency Action (ECA) -1.3, Unit 1 and Unit 2 Reactor Vessel Level Setpoint; Revision 0

(3) SCR 2016-0060; Changes to 1WG-1787 In-Service Testing (IST) Acceptance Criteria in In-Service Tests (IT) 60; 04/28/2016

(4) SCR 2016-0139; Screening for Clearance Order 1PI-2326 Isolated (Galled Fitting) 01A, Repairs to Piping and Valve, 1 Main Steam-115D, Due to Leak from Galled Fitting; 09/09/2016

(5) SCR 2016-0164; Remove Door #150 as a Credited High Energy Line Break Barrier; Revision 0

(6) SCR 2016-0176; Revision 4 of Calculation 96-0229 Requires Updates to Residual Heat Removal IST Surveillances; 12/14/2016

(7) SCR 2017-0001; Narrow Range Resistance Temperature Detector Resistance/Voltage Conversion Electronics Replacement (Dana Amplifier Replacement); Revision 0

(8) SCR 2017-0050; Revise AOP [Abnormal Operating Procedure]-25 to Provide Better Operator Control; Revision 0

(9) SCR 2017-0061; Unit 1 Narrow Range Resistance Temperature Detector Resistance/

Voltage Conversion Electronics Replacement (Dana Amplifier Replacement); Revision 0

(10) SCR 2018-0004; IT-08A Cold Start of Turbine Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 1; IT-09A Cold Start of Turbine Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 2; 01/17/2018

(11) SCR 2018-0016; Temporarily Change the Unit 1 Reactor Coolant Pump 1B No. 1 Seal Controlled Leakage Low Flow Alarm Setpoint; 01/31/2018

(12) SCR 2018-0052; Revise AOP-13C for NRC DSS-ISG-2016-01 for Tornado Missile Protection; Revision 1

(13) SCR 2018-0061; EC 289256, STPT [Setpoint Document] 14.4 Revision of 2HX-I9A/B and 2HX-21A/B Level Control Range and 2HX-21A/B Dump And High Level Alarm Setpoints; Revision

INSPECTION RESULTS

No findings or violations were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure. The inspectors verified no proprietary information was retained or documented in this report.

On September 14, 2018, the inspectors presented the Evaluation of Charges, Tests and Experiments inspection results to Mr. Robert Craven, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.17TEvaluations of Changes, Tests and Experiments

- AR 02031290; 2015 NRC CDBI [Component Design Basis Inspection] - Error Found in

Calculation 96-0229; 03/10/2015

- AR 02121169; UFSAR Chapter 11 Analyses Assume Operation of the PAB [Primary Auxiliary

Building] Vent System; 03/29/2016

- AR 02135689; Revise 50.59 Documentation; 06/02/2016

- AR 02153409; HELB Door-150 Found Propped Open; 08/31/2016

- AR 02183993; Conflict Between Two Controller Docs and RHR Operability; 02/06/2017

- AR 02242125; IT 08A - (EC 289661); 12/27/2017

- AR 02258119; Incorrect Values in STPT 14.4 Feedwater Heater Drain; 04/05/2018

- AR 02271734; NRC Self-Assessment: SCRs 2016-0060 and 2016-0062; 07/11/2018

- AR 02272406; NRC 50.59 Self-Assessment: EVAL 2016-001; 07/17/2018

- AR 02272407; NRC 50.59 Self-Assessment: EVAL 2014-005; 07/17/2018

- AR 02272417; NRC 50.59 Self-Assessment: SCR 2017-0061; 07/17/2018

- AR 02273687; Not All 50.59s are in Records; 07/26/2018

- AR 02278906; Record Copy of SQ-003293; 09/05/2018

- AR 02279342; 2018 NRC 5059 Inspection Enhancement to EN-AA-203-1202; 09/07/2018

- AR 02280235; 2018 NRC 5059 Inspection-Formality and Rigger with Documents; 09/13/2018

- AR 02280240; 2018 NRC 5059 Inspection -Typos Identified in Documents; 09/13/2018

- ASME PTC 12.1-2000; Closed Feedwater Heaters Section 3; 2000

- Calculation 96-0244; Minimum Allowable IST Acceptance Criteria for Turbine Driven and

Motor Driven AFW [Auxiliary Feedwater] Pump Performance; Revision 4

- Calculation 2005-0055; DGB [Diesel Generator Building] GOTHIC [Generation of Thermal

Hydraulic Information in Containments] Model and Temperature Calculation; Revision 3

- Calculation 2010-0018; Reactor Vessel Level EOP [Emergency Operating Procedure]

Setpoints; Revision 2

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

- Calculation FPL-076-CALC-002; Antecedent Lake Level Evaluation; Revision 0

- Calculation FPL-076-CALC-004; Calculated External Average Water Levels at Turbine

Building; Revision 1

- Design Guideline Manual DG-I01; Instrument Setpoint Methodology; Revision 7

- DIT[Design Information Transmittal]-286111-01; Tavg Control Initial Condition Uncertainty

Assumptions; 03-03-2017

- Drawing C-60; Architectural Schedules Doors & Hardware, Sheet 2; Revision 26

- Drawing E-1 JOB 6118 (EC 289216); Single Line Diagram Station Connections; Revision 34

- Drawing PB07322; Simplified Electrical Power Distribution Diagram; Revision 11

- Drawing POB-27-01;Switch Designation Diagram 345kV Point Beach Switchyard ;Revision 6

- [Emergency Contingency Action] ECA-1.1 Background; Step Description Table for ECA-1.1;

03/31/2014

- [Emergency Response Guideline] ERG Footnote Basis Document; K.01, K.02; 03/31/2014

- Engineering Change 281811; External Wave Run-Up Flood Mitigation Strategy; Revision 0

- Engineering Change 289216; Branch River Project Switchyard Change Package; Revision 2

- Evaluation 2016-003; Increase Maximum Allowable Service Water Temperature; Revision 0

- Operating Instruction 168; Emergency Diesel Generator Operability; Revision 23

- Procedure 1-PT-FD-002, Unit 1 Feedwater Heater 1HX-21A/B Knee Test; Attachment D, Drain

Approach Temperature Test Discussion; Revision 2

- Procedure 1-SOP-4kV-001; 4kV System Operations Unit 1; Revision 6

- Procedure 1-SOP-4kV-A06; Unit 1 Vital Train B 4160V Bus; Revision 12

- Procedure 2-SOP-4kV-001; 4kV System Operations Unit 2; Revision 6

- Procedure 2-SOP-4kV-A06; Unit 2 Vital Train B 4160V Bus; Revision 15

- Procedure AOP-13C; Severe Weather Conditions; Revision 36

- Procedure AOP-13C; Severe Weather Conditions; Revision 46

- Procedure AOP-25 Unit 1; Turbine Trip Without Reactor Trip; Revision 13

- Procedure AOP-25 Unit 1; Turbine Trip Without Reactor Trip; Revision 14

- Procedure AOP-25 Unit 1; Turbine Trip Without Reactor Trip; Revision 15

- Procedure ECA-1.1; Loss of Emergency Coolant Recirculation; 04/30/2005

- Procedure ECA-1.1; Loss of Emergency Coolant Recirculation; 03/31/2014

- Procedure IT 08A; Cold Start of Turbine Driven Auxiliary Feed Pump and Valve Test

(Quarterly) Unit 1; Revision 79

- Procedure IT 08A; Cold Start of Turbine Driven Auxiliary Feed Pump and Valve Test

(Quarterly) Unit 1; Revision 80

- Procedure NP 8.5.1; Equipment Identification and Labeling Procedure; Revision 17

- Procedure NP 7.4.4; ASME [American Society of Mechanical Engineers] OM [Operation and

Maintenance of Nuclear Power Plants] Code Pump and Valve In-Service Testing; Revision 9

- Procedure RMP [Routine Maintenance Procedure] 9422; Circulating Water Pumphouse and

Turbine Hall Barrier Placement; Revision 2

- Regulatory Guide 1.105; Setpoints for Safety-Related Instrumentation; Revision 3

- Screening 2016-0128; EC 286487 - Control Room Recorder Replacement; Revision 0

- Screening 2016-0142; Revise AOP-31 for Additional Maintenance Actions; Revision 0

- Screening 2016-0162; Increase Maximum Allowable Service Water Temperature; Revision 0

- Screening 2018-0002; Branch River Project Switchyard Change Package; Revision 2

- Setpoint Document STPT 14.4; Secondary Systems, Feedwater Heater Drain; Revision 15

- [Topical Report] TR-FSE-14-1-P; Use of Westinghouse SHIELD Passive Shutdown Seal for

FLEX [Diverse and Flexible Coping Strategies] Strategies; Revision 1

- WCAP [Westinghouse Commercial Atomic Power report]-7306; Reactor Protection System

Diversity in Westinghouse Pressurized Water Reactors; April 1969

- WCAP-16983-P; Point Beach Units 1 and 2 Extended Power Uprate (EPU) Engineering

Report; Revision 0

- WCAP-16983-P; Point Beach Units 1 and 2 Extended Power Uprate (EPU) Engineering

Report; Revision 1

- WE [We Energy] Internal Correspondence NPM 97-0329; Stroke Time Performance

Requirements for Valves in the IST Program; 05/22/1997

- Westinghouse Letter LTR-RES-14-78; Reactor Coolant Pump Seal Response in the Event of

Inadvertent Actuation of the SHIELD Shutdown Seal; Revision 0

- Westinghouse Transmittal NEXT-17-53; Transmittal of Evaluation of Changes to the Tavg Initial

Condition Uncertainty; 03-23-2017

- Work Order 40384045 01; 1MS-00115D / Replace Threaded Fitting; 10/29/2017

- Work Order 40439510 01; PBTP [Point Beach Test Procedure] 265 (IT 08A) 1P-29

AFP [Auxiliary Feedwater Pump] Cold Start Test/VLVS [Valves]; 10/20/2016

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