IR 05000282/2020010

Design Basis Assurance Inspection (Programs) Inspection Report 05000282/2020010 and 05000306/2020010

ML20178A546
Person / Time
Site:	Prairie Island
Issue date:	06/26/2020
From:	Karla Stoedter Division of Reactor Safety III
To:	Sharp S Nuclear Management Co
References
IR 2020010
Preceding documents:	ML20052F410 (21 February 2020)
Download: ML20178A546 (12)

Text

June 26, 2020

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000282/2020010 AND 05000306/2020010

Dear Mr. Sharp:

On May 22, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and 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.

No findings or violations of more than minor significance were identified during this inspection.

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 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000282 and 05000306 License Numbers: DPR-42 and DPR-60 Report Numbers: 05000282/2020010 and 05000306/2020010 Enterprise Identifier: I-2020-010-0051 Licensee: Northern States Power Company, Minnesota Facility: Prairie Island Nuclear Generating Plant Location: Welch, MN Inspection Dates: May 04, 2020 to May 22, 2020 Inspectors: I. Hafeez, Reactor Inspector M. Jones, Senior Reactor Inspector L. Rodriguez, Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Prairie Island Nuclear Generating Plant, in accordance with the Reactor Oversight Process.

The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

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

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), regional inspectors were directed to begin telework. For the inspection documented below, it was determined that the objectives and requirements stated in the IP could be performed remotely.

REACTOR SAFETY

71111.21N.02 - Design-Basis Capability of Power-Operated Valves (POVs) Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a.

Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b.

Determined whether the sampled POVs are capable of performing their design-basis functions.

c.

Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d.

Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

Selected Samples:

(1) MV-32187, Safety Injection - Refueling Water to 21 Residual Heat Removal Pump Isolation Motor Operated Valve

(2) MV-32020, Main Steam - Loop B Main Steam to 22 Turbine Driven Auxiliary Feedwater Pump Motor Operated Valve

(3) MV-32238, Auxiliary Feedwater - Auxiliary Feedwater to Steam Generator #11

(4) MV-32024, Main Feedwater - Feedwater to #12 Steam Generator

(5) CV 31084, Main Steam - 11 Steam Generator Main Steam Safety Relief to Atmosphere

(6) CV 31411, CC - 12 Component Cooling Heat Exchanger Cooling Water Return

(7) CV 31232, Reactor Coolant - Pressurizer Outlet to Pressurizer Relief Tank B

(8) SV 37036, Reactor Vessel - Pressurizer Vent Valve B

(9) SV 33133, Cooling Water to 121 Safeguards Travelling Screen

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On May 22, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. S. Sharp, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations 01110-C-004 Reactor Coolant System AOVs Functional and MEDP Revision 0

Calculation

01110-C-008 Cooling Water System AOVs Functional and MEDP Revision 1

Calculation

01110-C-015 AOV Component Level Calc. for Reactor Coolant Valves Revision 1

27C KVAP Analysis for Component Cooling Water Heat Revision 1

Exchanger Outlet AOV's CV-31381, CV-31383, CV-

31384, & CV-31411

457444 31411-VZ VALVE POSITIONER REPLACEMENT 12/11/2016

89890-19 Prairie Island Weak Link Calculations for Valves MV- Revision 0

2084, MV-32085, MV-32187, MV-32188

89890-2 PI Weak Link Calcs for Valves MV-32023, MV-32024, Revision 1

MV-32028, MV-32029

89890-8 Prairie Island Weak Link Calculations for Valves MV- Revision 0

2045, MV-32047, MV-32048, MV-32050, MV-32238,

MV-32239, MV-32246, MV-32247

ENG-EE-170 PINGP ETAP Electrical Analysis Revision 5

ENG-EE-171 Degraded Voltage Calculation Revision 1

ENG-EQ-0106 EEQ File: Limitorque Actuators and Motors Revision 2

ENG-EQ-0114 EEQ File: Rockbestos Cable Revision 1

ENG-EQ-0123 EEQ File: Target Rock Solenoid Valves Revision 1

ENG-EQ-0169 EEQ File: Oil and Greases Revision 2

ENG-ME-046 JOG MOV Evaluation Report MV-32024 Revision 7e

ENG-ME-046 MV-32187 Valve Setup Calc Att. B Revision 7A

ENG-ME-046 MV-32238 (PINGP-1) AC Motor Operated GL 96-05 Revision 6a

Globe Valve

ENG-ME-244 CC Heat Exchanger TCV Position Range Revision 0

ENG-ME-334 Sect XI Design Basis Valve Limiting Stroke Times Revision 6

ENG-ME-334 Sect. XI Design Basis Valve Limiting Stroke Times Revision 6

ENG-ME-353 Mechanical MOV Analysis to Support IN 92-18 Response Revision 2

ENG-ME-380 Thrust Capabilities of Body and Body/Bonnet Bolting for Revision 1

Selected Appendix R MOVs

Inspection Type Designation Description or Title Revision or

Procedure Date

ENG-ME-537 Analysis of PZR PORV Operations for LTOP Revision 0

ENG-ME-541 CC Hydraulic Model Proto-Power Calc 02-002 Revision 1

ENG-ME-592 Determination of Minimum Amount of Air Pressure to Revision 1

Fully Stroke Pressurizer PORV

ENG-ME-675 Differential Pressure for Auxiliary Feedwater System Revision 0

MOVs at Prairie Island

ENG-ME-679 Differential Pressure for the Feedwater System MOVs Revision 00

ENG-ME-684 Differential Pressure for the Safety Injection System Revision

MOVs at PINGP 000-A

ENG-ME-820 CL Hydraulic Analysis- LOOP, LOCA, And Seismic Revision 2

Response

PI-996-127-M02 PORV Supplemental Air System Flow and Pressure Drop Revision 1B

Analysis During LTOP - Unit 1

Corrective Action 01131641 Minor Leakage Noted on MV-32381 12 MDAFW to 11 03/19/2008

Documents S/G

01132099 MV-32238 Leaks by Approximately 16 gpm 02/23/2008

202296 1R26, During SP 1100, MV-32382 had Leakage of 1.7 10/13/2009

GPM

205983 MV-32381 12 MDAFWP to 11 S/G Leaks by 11/06/2009

220599 Extent of Condition for Unit 2 AFWP Discharge Valves 03/01/2010

01334819 Disk Nut Scored 04/20/2012

01483408 CDBI 2015- SR Motor Starts not Evaluated at Degraded 06/19/2015

Voltage

01508587 Defined Scope of MOVs Impacted by Hot Shorts 01/13/2016

500001483212 Potential Non Conservative MOV Calculations 06/17/2015

500001539369 A Przr PORV Reaches Rated Travel at 87.1 10/25/2016

500001541840 PZR PORVs Lifted and Reseated While Star 11/14/2016

500001561203 Possible Loss of RCGVS SOV Open Indication 06/15/2017

501000018719 U1 RCS Head Vent System 10/18/2018

501000018722 SV-37039 Outside Ref. Range Stroke Time 10/17/2018

501000018732 SV-37040 Failed to Clear Dual Light/Flow 10/17/2018

501000020407 Legacy: Stem Replacement PMT/Eval. 11/27/2018

501000035577 2019 POV FSA AFI: Calc. ENG-ME-592 Error 12/11/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

501000035896 2019 POV FSA AFI: AOV OE Search 12/19/2019

501000035931 2019 POV FSA AFI: Calc. References 12/18/2019

501000035952 2019 POV FSA AFI: MOV Qualifying Bases 12/19/2019

Corrective Action 501000040255 POV Insp: Valve Size Incorrect in H10.1 05/05/2020

Documents 501000040365 POV Insp: Typo in Question Resp. to NRC 05/07/2020

Resulting from 501000040440 POV Insp: Typo in EC26147 Conclusion 05/08/2020

Inspection 501000040461 Clarify NIR 1084 for MV-32238 Cast Void 05/11/2020

501000040522 NF-39216-1 Shows SV-33133 as Normally Open valves. 05/12/2020

The Logic Diagrams Show the Valves as Normally Closed

501000040579 NRC POV: SP 1298 Acceptance Criteria 05/15/2020

501000040739 POV Insp: Packing Load Discrepancy 05/18/2020

501000040813 CLG WTR TO 121 SFGRDS TRVLG SCRNS SV Cooling 05/19/2020

Water

501000040819 POV Inspec: PM has Incorrect Frequency 05/20/2020

501000040837 POV Insp: Surface Rust oMV-32020 Yoke 05/20/2020

Drawings NE-4000 Sheet 121 Cooling Water Traveling Water Screen Revision 77

NF-116752 UNIT 1 - UNIT 2 Safeguards Consolidated Circuit Revision 77

Diagram

NF-39216-3 Flow Diagram, Cooling Water - Aux Bldg Unit 1 Revision 81

NF-39222 Flow Diagram: Feedwater and Aux Feedwater Unit 1 Revision 89

NF-40022-2 Circuit Diagram 4KV and 480V Safeguard Busses Unit 2 Revision 80

NF-40310-2 Interlock Logic Diagram Feedwater System - Unit 1 Revision 76

NF-40315-6 Interlock Logic Diagram Cooling Water System - Units 1 Revision 77

and 2

NF-40322-1 Interlock Logic Diagram Main Steam System Unit 1 Revision 77

NF-40426 480V Circuit Diagram Motor Control Center 2K, 2KA Revision 77

NF-40782-3 Interlock Logic Diagram Residual Heat Removal System - Revision

Unit 2 77A-2

NF-40976-1 Wiring Diagrams Steam Exclusion Control Dampers Aux Revision 78

Building A Train

NL-39776-258 Supply & Control Piping for Control Valve and Remote Revision 78

Mounted Temperature Controller

Inspection Type Designation Description or Title Revision or

Procedure Date

XH-1-544 Instrument Block Diagram Reactor Protection System Revision 77

XH-1001-7 Flow Diagram Safety Injection Revision 82

XH-145-4 Model #45 Traveling Water Screens Arrangement of Revision 76

Differential Head Controls

Engineering 00501 Upgrade Unit 1 Pressurizer PORV Trim and Actuators Revision 1

Changes 14003 (PRI 54) MV-32238, 11 AFW to 11 SG MV Internals Revision 1

Replacement for 1R26 Results in Multiple Part Material

Changes. This Will Affect the Weak Link Analysis

Calculation. (1R26)

21303 2012 RE-VISIT OF GL 95-07 PRESSURE LOCKING Revision 000

AND THERMAL BINDING

21303 2012 RE-VISIT OF GL 95-07 PRESSURE LOCKING Revision 000

AND THERMAL BINDING

26147 Evaluation of Thermal Overloads for Safety MOVs With Revision 0

Design Basis Throttle Function

6EQVENG22547 REPLACE 150 FT-LB MAGNESIUM MOTOR ROTORS 01/25/2019

WITH ALUMINUM ROTORS

6EQVENG27262 Replacement Material for Valve Wedge 04/10/2018

Engineering NIR 1084 Evaluation of MV-32246 Actuator Mounting Flange due to 04/19/1994

Evaluations As-Found Condition

NSP-09-100 Transmittal of LTR-RCPL-09-150 Rev. 1, "Auxiliary Revision 1

Feedwater System - 8 GPM Analytical Allowable Leakage

of MV-32381"

SPCE ME-0202 TDAFW Pump Disch. MV Change from HB to NLM 03/22/2000

(Hammerblow to No Lost Motion Drive)

SPCE ME-0389 RCGVS SV Upgrade 08/21/2001

Miscellaneous 01108-TR-003 Nuclear Management Company Air Operated Valve Revision 1

Program Calculation Guideline

Kalsi Letter, CV- CV-31232, Pressurizer PORV Adjustment Factor 05/14/2020

232 Valve

Factor

Justification

Procedures 1ES-1.2 Transfer to Recirculation Revision 26

B35 Cooling Water System Revision 19

Inspection Type Designation Description or Title Revision or

Procedure Date

F5 APP B Control Room Evaluation (Fire) Revision 67

FP-PE-AOV-01 Air Operated Valve Program Revision 2

FP-PE-AOV-02 Air Operated Valve Program Design Standard Revision 0

H10.1 ASME Inservice Testing Program Revision 41

H5 Motor Operated Valve Program Revision 26

H8-A EEQ User's Manual Appendix A EEQ Master List Revision 28

H8-H Air Operated Valve Program Revision 2

Work Orders 00375286 MV 32187 U2 RWST TO 21 RHR PMP ISOL MOV D70.1 02/08/2014

PM

00433950 NDE MV-32024 UT Inspection of Valve Stem 12/21/2013

00477104 Remove Motor on MV-32024 09/07/2017

094827 U-1, CV-31232, Replace Trim and Actuator on PRZR 05/23/2006

PORV A

357450 U1, MV-32238, Leaks by Seat at 16 GPM 10/08/2009

21447 Overhaul CV-31411 Actuator 09/07/2017

543086 CV-31232-1 PRZR PORV A AOV D100 Test 05/09/2016

700011282 SP 1298 PRZR PORV Air Accum. CK VLV Leak 10/06/2018

700011314 SP 1083B INT SI W/SIM LOSS OFFSITE PWR 10/17/2018

700015042 SP 1168.1 - U1 RX Coolant Sys. Press. Test 10/22/2018

700015049 SP 1291 - PZR PORV CST Stroke Test 10/06/2018

700015133 SP 1248 RCGVS Test Each Cold Shutdown 10/18/2018

700018401 SP 1361 Exercise Fw Isol Ck Vlvs at Rfl 09/21/2018

700021441 Replace the EEQ Seal on SV-37036 10/19/2018

700024030 SP 1168.8 CL SYS Operating Press 07/19/2019

700024579 SP 1168.6 - 3YR AFW Sys. Oper. Press. Test 04/10/2019

700027147 PM 32238 11 AFW to 11 SG MOV D70.1 PM 06/12/2019

700041897 SP 1103A - Train A AFW Refuel Test 03/13/2019

700051083 SP 2082 - RHR System RFL Outage Leak TST 10/03/2019

700058224 SP 2089A-2A RHR Pmp & Suct Vlv From RWST 02/13/2020

700059752 SP 1155B - CC System Quarterly Test TRN B 03/19/2020

700059783 SP 1102-11 Turb-Driven AFWP Monthly Test 01/17/2020

700063586 SP 1210 SFGDS Hold & Comp. Status Verify 04/11/2020

700063586 SP 1210 SFGDS Hold& Comp Status Verif 04/10/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

700063586 SP1210 SFGDS Hold & Comp Status Verif 04/10/2020

700063586 SP 1210 SFGDS Hold & Comp Status Verification 04/11/2020

9509889 CC TCV Travel Stop CV Data

9803439 Rebuild Spare Actuator for Use on MV-32020 03/22/2000

9811018 P302020 Inspect and VOTES Test MV-32020 11/07/1998

WO 00477104 Remove Motor on MV-32024 09/07/2017

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