IR 05000498/2022011
| ML22053A306 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/01/2022 |
| From: | Vincent Gaddy NRC Region 4 |
| To: | Gerry Powell South Texas |
| References | |
| IR 2022011 | |
| Download: ML22053A306 (10) | |
Text
March 01, 2022
SUBJECT:
SOUTH TEXAS PROJECT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000498/2022011 AND 05000499/2022011
Dear Mr. Powell:
On February 10, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at South Texas Project and discussed the results of this inspection with Ms. K.
Harshaw, Executive Vice President and CNO 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, Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos. 05000498 and 05000499 License Nos. NPF-76 and NPF-80
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000498 and 05000499
License Numbers:
Report Numbers:
05000498/2022011 and 05000499/2022011
Enterprise Identifier: I-2022-011-0007
Licensee:
STP Nuclear Operating Company
Facility:
South Texas Project
Location:
Wadsworth, TX
Inspection Dates:
January 24, 2022 to February 10, 2022
Inspectors:
J. Braisted, Reactor Inspector
D. Reinert, Reactor Inspector
W. Sifre, Senior Reactor Inspector
Approved By:
Vincent G. Gaddy, Chief
Engineering Branch 1
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 South Texas Project, 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, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves 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. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) Unit 1 Safety Injection Accumulator 1C Outlet Motor-Operated Valve 2N121XSI0039C
- (2) Unit 1 Main Steam to Terry Turbine Throttle Motor-Operated Valve 3S141XMS0514
- (3) Unit 2 Steam Generator 2D Blowdown Outside Reactor Containment Isolation Air-Operated Valve A2SBFV4150
- (4) Unit 1 Steam Generator 1A Main Steam Outlet Hydraulically Operated Power Operated Relief Valve A1MSPV7411
- (5) Unit 2 Essential Cooling Water Pump 2C Discharge Motor-Operated Valve
==3R28 2TEW0151
- (6) Unit 2 Steam Generator 2A Main Steam Outside Reactor Containment Air-Operated==
Isolation Valve A2MSFSV7414
- (7) Unit 1 RHR Pump 1C Suction Motor-Operated Valve 1R161XRH0061C
- (8) Unit 1 Reactor Containment Building Supplementary Purge Supply Isolation Air-Operated Valve A1HCFV9776
- (9) Unit 2 Safety Injection Pump 2B Discharge Motor-Operated Valve 2N122XSI0018B
- (10) Unit 2 Pressurizer Solenoid-Operated Power-Operated Relief Valve A2RCPCV0655A
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 10, 2022, the inspectors presented the design basis assurance inspection (programs) inspection results to Ms. K. Harshaw, Executive Vice President and CNO and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
2195C
KVAP Results Tag No. A1HCFV9776 18" Valtek Butterfly
E-4344_8344_2
Qualified Life for Paul Munroe Actuators & Components
MC-6441
Pressure Locking / Thermal Binding Evaluation
MC-6462
DVAC Calculation for DC Motor MOVs
MC-6472
DVAC Calculation AC Motor MOVs
ST400088-
00011WN
MOV Evaluation GNL 89-10 for 12GM88SEB
C
ST401865-
00001M2
Evaluation of South Texas Project MOVs using the EPRI
MOV Methodology
A
STI-94-009561-15 GL 89-10 Program Design Basis Review 2BSIMOV0018B
04/08/1994
Corrective Action
Documents
Condition Record
(CR)
19-6236, 06-16339, 21-7397, 09-9344, 14-5571, 20-3576,
21-10795, 03-6411, 07-6159, 20-8152, 13-13856, 13-
1770, 16-12727, 17-11550, 19-11601, 19-12655, 19-
2716, 20-8220, 21-8767, 19-12777, 21-1946, 21-2058,
18-6358
Station Problem
Report (SPR)
93-0603
Corrective Action
Documents
Resulting from
Inspection
Condition Record
(CR)
2-894,22-889, 22-897, 19-291-235, 22-1237, 22-1258,
2-1289, 12-27343, 16-13993, 22-1234
Drawings
00009E0S1144#1
ACCUMULATOR DISCHARGE ISOLATION MOV'S
0039A, 0039B & 0039C
5S201740203
STEAM GENERATOR BLOWDOWN CONTAINMENT
ISOLATION VALVES LOGIC DIAGRAM
A-34752-5
BODY SUBASSEMBLY MARK I, 4 INCH, CLASS 900,
CV 172, SCH 120 B/W
A-34752-75
ACTUATOR SUBASSEMBLY 200 SQUARE INCH W/
DUAL SPRINGS
Engineering
Changes
07-11727-4
Unit 2 Main Steam Isolation Valves (MSIVs) Stem to Pilot
Poppet Valve Replacement
03/19/2009
17-91-2
Main Steam Isolation Valve Drawing 0223-01(2)00015WN 05/02/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Update to Show Regulator & Filter Arrangement
18-12169-2
Alternate Material Replacement for Steam Generator
Main Steam Power Operated Relief Valve Bonnet
10/21/2018
19-217-10
Replacement Part for Pressure Reducing Regulator
09/03/2019
DCP 03-12393-10 Update QMDB for Pressurizer PORV Gaskets to reflect
Qualified Life
2/20/2005
DCP 06-16339-72 Update MEDP and Minimum Required Thrust for
RH0060, 0061 MOVs
10/11/2012
DCP 07-11515-3
MOV B2SIMOV0018B Maximum Expected Differential
Pressure (MEDP), Valve Weak Link, and Minimum
Required Thrust.
03/14/2011
EC-16-14959-17
Allowance for 3/8" Nominal Wall Thickness Pipe for Spool
EW-2301-B
MD-2655
GNL 89-10 MOV EVAL
10/19/1992
Engineering
Evaluations
CREE 19-10712-
STP Appendix J Program Type C Local Leak Rate
Testing (LLRT) Scope for a Reduction
10/03/2019
MC-6441
Pressure Locking / Thermal Binding Evaluation
ST400088-00053-
AWN
Motor Operated Valve (MOV) Evaluation 89-10
Miscellaneous
Air Operated Valve Component Health Report
09/20/2021
AOV Datasheet for A1HCFV9776
01/24/2022
2V149VB00114
Design Basis Document RCB HVAC System
5N129MB01045
Design Basis Document Safety Injection System
5R149MD01027
Design Basis Document Reactor Coolant System
5R169MB1021
Design Basis Document Residual Heat Removal System
PRA Rev 9 to
PRA Rev 10 Risk
Change Summary
Expert Panel Meeting 12/16/21 Attachment 3
PRA-22-003
TS 4.0.3 Risk Evaluation - Missed Surveillance for
Pressurizer Power Operated Relief Valve Close Stroke
Time Test
ST-W2-NOC-99-
0037
RSG Cold Overpressure Mitigation System Setpoints
06/29/1999
SwRI Project No.
Evaluation of Thermal Embrittlement of 17-4 PH MSIVs
November
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
18.24454
2019
VTD-L200-0009
SMB Instruction and Maintenance Manual
VTD-V037-0001
INSTALLATION, OPERATION, MAINTENANCE
INSTRUCTIONS FOR MARK ONE AND TWO CONTROL
VALVES
VTD-W120-0652
Motor Operated Gate Valves, Manually Operated Gate
Valves, Swing Check Valves Instruction Book
Procedures
MOV Diagnostic Testing Error Analysis and Acceptance
Criteria
LLRT Type B and Type C Failure/Troublshooting
Motor Operated Valve Program
Air Operated Valve Program
0PGP03-ZM-0002 Preventive Maintenance Program
MOV Performance and Degradation Trending
0POP01-ZO-0011 Operability, Functionality, and Reportability Guidance
0POP03-ZG-0001 Plant Heatup
Reactor Containment Building Supplementary Purge
System Valve Operability Test
0PSP03-MS-0001 Main Steam System Valve Operability Test
Pressurizer Power Operated Relief Valve Operability Test
RHR System Valve Leak Tests
ENG-0006
Component Health Reports
WCG-0005
Preventive Maintenance Administration Guide
Self-
Assessments
21-8612-1
21 Power Operated Valve (POV) Design Basis
Assurance Inspection (DBAI) Self-Assessment
11/16/2021
Work Orders
Preventive
Maintenance -
Work orders
01000776, 03001202, 04000249,
Work
Authorization
Number (WAN)
557588, 440177, 588903, 522670, 382379, 533069,
604821, 469133, 382379, 655533, 575278, 586167,
591420, 351427, 409328, 519907, 483049, 503614,
630986, 480263, 661027, 525909, 561613, 598596,
23701, 560477, 508975, 425931, 353014, 436093,
544976, 636949, 416247, 599598, 478331, 597819,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
586025, 607534, 639631, 580591, 100435, 615020,
587625, 609823, 534622, 597819