IR 05000282/2020010
| 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: |
|
| 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:
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
01110-C-004
Reactor Coolant System AOVs Functional and MEDP
Calculation
Revision 0
01110-C-008
Cooling Water System AOVs Functional and MEDP
Calculation
Revision 1
01110-C-015
AOV Component Level Calc. for Reactor Coolant Valves
Revision 1
27C
KVAP Analysis for Component Cooling Water Heat
Exchanger Outlet AOV's CV-31381, CV-31383, CV-
31384, & CV-31411
Revision 1
457444
31411-VZ VALVE POSITIONER REPLACEMENT
2/11/2016
89890-19
Prairie Island Weak Link Calculations for Valves MV-
2084, MV-32085, MV-32187, MV-32188
Revision 0
89890-2
PI Weak Link Calcs for Valves MV-32023, MV-32024,
MV-32028, MV-32029
Revision 1
89890-8
Prairie Island Weak Link Calculations for Valves MV-
2045, MV-32047, MV-32048, MV-32050, MV-32238,
MV-32239, MV-32246, MV-32247
Revision 0
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
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
Selected Appendix R MOVs
Revision 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Fully Stroke Pressurizer PORV
Revision 1
ENG-ME-675
Differential Pressure for Auxiliary Feedwater System
MOVs at Prairie Island
Revision 0
ENG-ME-679
Differential Pressure for the Feedwater System MOVs
Revision 00
ENG-ME-684
Differential Pressure for the Safety Injection System
Revision
000-A
ENG-ME-820
CL Hydraulic Analysis-LOOP, LOCA, And Seismic
Response
Revision 2
PI-996-127-M02
PORV Supplemental Air System Flow and Pressure Drop
Analysis During LTOP - Unit 1
Revision 1B
Corrective Action
Documents
01131641
Minor Leakage Noted on MV-32381 12 MDAFW to 11
S/G
03/19/2008
01132099
MV-32238 Leaks by Approximately 16 gpm
2/23/2008
202296
1R26, During SP 1100, MV-32382 had Leakage of 1.7
GPM
10/13/2009
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
Voltage
06/19/2015
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
2/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000035896
2019 POV FSA AFI: AOV OE Search
2/19/2019
501000035931
2019 POV FSA AFI: Calc. References
2/18/2019
501000035952
2019 POV FSA AFI: MOV Qualifying Bases
2/19/2019
Corrective Action
Documents
Resulting from
Inspection
501000040255
POV Insp: Valve Size Incorrect in H10.1
05/05/2020
501000040365
POV Insp: Typo in Question Resp. to NRC
05/07/2020
501000040440
POV Insp: Typo in EC26147 Conclusion
05/08/2020
501000040461
Clarify NIR 1084 for MV-32238 Cast Void
05/11/2020
501000040522
NF-39216-1 Shows SV-33133 as Normally Open valves.
The Logic Diagrams Show the Valves as Normally Closed
05/12/2020
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
Water
05/19/2020
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
21 Cooling Water Traveling Water Screen
Revision 77
NF-116752
UNIT 1 - UNIT 2 Safeguards Consolidated Circuit
Diagram
Revision 77
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
and 2
Revision 77
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 -
Unit 2
Revision
NF-40976-1
Wiring Diagrams Steam Exclusion Control Dampers Aux
Building A Train
Revision 78
NL-39776-258
Supply & Control Piping for Control Valve and Remote
Mounted Temperature Controller
Revision 78
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Differential Head Controls
Revision 76
Engineering
Changes
00501
Upgrade Unit 1 Pressurizer PORV Trim and Actuators
Revision 1
14003
(PRI 54) MV-32238, 11 AFW to 11 SG MV Internals
Replacement for 1R26 Results in Multiple Part Material
Changes. This Will Affect the Weak Link Analysis
Calculation. (1R26)
Revision 1
21303
2012 RE-VISIT OF GL 95-07 PRESSURE LOCKING
AND THERMAL BINDING
Revision 000
21303
2012 RE-VISIT OF GL 95-07 PRESSURE LOCKING
AND THERMAL BINDING
Revision 000
26147
Evaluation of Thermal Overloads for Safety MOVs With
Design Basis Throttle Function
Revision 0
6EQVENG22547
REPLACE 150 FT-LB MAGNESIUM MOTOR ROTORS
WITH ALUMINUM ROTORS
01/25/2019
6EQVENG27262
Replacement Material for Valve Wedge
04/10/2018
Engineering
Evaluations
NIR 1084
Evaluation of MV-32246 Actuator Mounting Flange due to
As-Found Condition
04/19/1994
NSP-09-100
Transmittal of LTR-RCPL-09-150 Rev. 1, "Auxiliary
Feedwater System - 8 GPM Analytical Allowable Leakage
of MV-32381"
Revision 1
SPCE ME-0202
TDAFW Pump Disch. MV Change from HB to NLM
(Hammerblow to No Lost Motion Drive)
03/22/2000
SPCE ME-0389
RCGVS SV Upgrade
08/21/2001
Miscellaneous
01108-TR-003
Nuclear Management Company Air Operated Valve
Program Calculation Guideline
Revision 1
Kalsi Letter, CV-
232 Valve
Factor
Justification
CV-31232, Pressurizer PORV Adjustment Factor
05/14/2020
Procedures
1ES-1.2
Transfer to Recirculation
Revision 26
B35
Cooling Water System
Revision 19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
2/08/2014
00433950
NDE MV-32024 UT Inspection of Valve Stem
2/21/2013
00477104
Remove Motor on MV-32024
09/07/2017
094827
U-1, CV-31232, Replace Trim and Actuator on PRZR
PORV A
05/23/2006
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
2/13/2020
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
Procedure
Type
Designation
Description or Title
Revision or
Date
700063586
SP1210 SFGDS Hold & Comp Status Verif
04/10/2020
700063586
SP 1210 SFGDS Hold & Comp Status Verification
04/11/2020
9509889
9803439
Rebuild Spare Actuator for Use on MV-32020
03/22/2000
9811018
P302020 Inspect and VOTES Test MV-32020
11/07/1998
Remove Motor on MV-32024
09/07/2017