IR 05000348/2022010
| ML22080A168 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/22/2022 |
| From: | James Baptist NRC/RGN-IV/DORS/EB1 |
| To: | Kharrl C Southern Nuclear Operating Co |
| References | |
| IR 2022010 | |
| Download: ML22080A168 (12) | |
Text
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000348/2022010 AND 05000364/2022010
Dear Mr. Kharrl:
On February 10, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant and discussed the results of this inspection with Mr. Delson Erb, Plant Manager, 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, James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000348 and 05000364 License Nos. NPF-2 and NPF-8
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000348 and 05000364
License Numbers:
Report Numbers:
05000348/2022010 and 05000364/2022010
Enterprise Identifier:
I-2022-010-0021
Licensee:
Southern Nuclear Operating Co., Inc.
Facility:
Joseph M. Farley Nuclear Plant
Location:
Columbia, AL
Inspection Dates:
February 07-February 10, 2022
Inspectors:
R. Kopriva, Senior Reactor Inspector
P. Meier, Senior Resident Inspector
P. Braxton, Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests, and experiments baseline inspection at Joseph M. Farley Nuclear 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, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors evaluated the following samples for compliance with Title 10, Code of Federal Regulations (CFR) 50.59, Changes, Tests, and Experiments, from February 7-February 10, 2022:
- (1) Screen: SNC1000660, Unit 1, Design Equivalent Change Package (DECP)- Unit 1 Anchor Head Replacement
- (2) Screen: SNC1012404, Unit 2, 2C Service Water Minimum Flow Line Sleeve
- (3) Screen: SNC920821, Unit S, 2C Emergency Diesel Generator Jacket Water Heat Exchanger Tube Bundle Replacement
- (4) Screen: SNC997278, Unit 1, Design Change Package (DCP)- Unit 1 MSIP (Mechanical Stress Improvement Process)
- (5) Screen: SNC1096073, Unit 2, Service Water Header Drain and Vent Line Addition
- (6) Screen: SNC935408, Unit S, DECP to Replace Auxiliary Building Roofing
- (7) Screen: SNC1086636, Unit 1, Loss of Coolant Accident Motor Operated Valve Thermal Overload Sizing Degraded
- (8) Screen: SNC1125459, Unit 2, 2C Service Water Minimum Flow Line Reinforcement Sleeve Removal
- (9) Screen: SNC1127095, Unit 2, Turbine Driven Auxiliary Feedwater Pump Steam Admission Valve Thrust Washer Shim
- (10) Screen: SNC508548, Unit 2, Minor Design Change (MDC) to Replace the 2B Emergency Diesel Generator Intercooler Heat Exchanger Tube Bundle
- (11) Screen: SNC980617, Unit 1, Design for C-7 Setpoint Change.
- (12) Screen: SNC990743, Unit 2, 2A Charging Pump Minimum Flow Line Motor Operated Valve Hand Switch Replacement
- (13) Screen: SNC1014130, Unit 2, DECP to Provide a Test Connection for Performance of FNP-2-STP-212.21 for Q2P16V577, Q2P
- (14) Screen: SNC1047870, Unit 1, 1R29 Hand Switch Replacements
- (15) Screen: SNC706480, Unit 1, Radiation Monitor Replacement Group 9A (R24A, R24B, R25A, R25B, R35A and R35A)
- (16) Screen: SNC706481, Unit 2, Radiation Monitor Replacement Group 9B (R24A, R24B, R25A, and R25B)
- (17) Screen: SNC730101, Unit 1, DCP-U1 Main and Bypass Feed Regulating Valve Digital Positioner Upgrade.
- (18) Screen: SNC952158, Unit 2, Replace Remote Hand Switch Q2R16HS2017HA with Krauss and Nalmer (K&N) Hand Switch
- (19) Evaluation: NCORP TE 1064469 - - Evaluations Performed to Address Long Term Cooling with Containment Sump Debris (GSI-191)
- (20) Evaluation: TE 1066707 - - Revise Final Safety Analysis Report (FSAR) Polar Crane Main Hoist Load Block Safe Path Restrictions
- (21) Evaluation: TE 1040425 - - Incorporate Auxiliary Feedwater Analysis Contained in Westinghouse Letter ALA-14-12 into Final Safety Analysis Report
- (22) Evaluation: LDCR20-008 - - Revise the Farley Nuclear Plant (FNP) License Basis for Tornado Missile Protection
- (23) Evaluation: SNC108663650 - - Bypass Thermal Overloads for Unit 1 Loss of Coolant Accident (LOCA) Motor Operated Valves
- (24) Evaluation: SNC1097052 - - Revision to Farley Containment Pressure/Temperature (P/T) Analysis to Incorporate Outstanding NSALs
- (25) Evaluation: SNC873765 - - Unit 1 Main Generator Exciter Switchgear Replacement
- (26) Evaluation: SNC892053 - - Unit 2 Main Generator Exciter Switchgear Replacement
- (27) Evaluation: SNC1030354 - - Unit 2 Radiation Monitoring System (RMS) - U2 Group 8B (RE15s)
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 triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Delson Erb, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
Farley TMRE Model Development and Quantification -
Tornado Missile Risk
Corrective Action
Documents
Condition Reports
10600935, 10749757, 10837988, 10837992, 10841665
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10850100, 10857908, 10857914, 10858741
170 WIB
170 Wire Nuclear Field Anchor Head
11/02/1971
SNC1012404M001
J.M. Farley Nuclear Plant - Unit 2 Piping - River Water &
Service Water at Intake Structure - Sections
SNC1012404M002
Service Water Pump Minimum Flow from Discharge to Wet
Pit
SNC1012404M003
Reinforcement Sleeve
SNC1012404M004
- J.M. Farley Nuclear Plant - Unit No. 2, ISI Boundary
Diagram Service Water System
SNC1096073M001
P&ID - River Water, Service Water and Circulation Water
System
SNC1096073M002
J. M Farley Nuclear Plant - Unit No. 2 Service Water Header
Vent and Drain Line Details
SNC1096073M003 J.M. Farley Nuclear Plant - Unit No. 2 ISI Boundary Diagram
Service Water System
SNC1096073M005
J.M. Farley Nuclear Plant Unit No. 2 - Manifold - Service
Water System (P16)
SNC920821M003
Diesel Generator Heat Exchanger No. 13096CPK - Bundle
Assembly
SNC920861M001:
U184804, Page
1079
Heat Exchanger Assembly
Drawings
SNC920861M002:
U184804 Page
13096 "CPK" Exchanger Assembly
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1084
SNC935408C00
J.M. Farley Nuclear Plant Unit No.2 - Architectural -
Containment and Auxiliary Bldg. - Rood Details
SNC935408C001
J.M. Farley Nuclear Plant - Unit No. 1 Architectural -
Containment and Auxiliary Building Roof Plan
SNC935408C002
J.M. Farley Nuclear Plant - Unit No.1 Architectural -
Containment and Auxiliary Building - Roof Details
SNC935408C003
J.M. Farley Nuclear Plant - Unit No.1 Architectural -
Containment and Auxiliary Bldg. - Roof Details
SNC935408C004
J.M. Farley Nuclear Plant - Unit No.1 - Architectural -
Containment and Auxiliary Building - Roof Details
SNC935408C005
J.M. Farley Nuclear Plant - Unit No.1 - Architectural - CTMT
and Auxiliary Bldg. Roof Plan - Fire Barrier Delineation
SNC935408C007
J.M. Farley Nuclear Plant - Unit No.2 - Architectural -
Containment and Auxiliary Building Roof Plan
SNC935408C009
J.M. Farley Nuclear Plant - Unit No.2 - Architectural -
Containment and Auxiliary Bldg. - Roof Details
SNC935408C010
J.M. Farley Nuclear Plant - Unit No.2 Architectural -
Containment and Auxiliary Building - Roof Details
SNC935408C011
J.M. Farley Nuclear Plant - Unit No.2-Architectural - Ctmt.
and Auxiliary Bldg. Roof Plan - Fire Barrier Delineation
SNC935408C012
J. M. Farley Nuclear Plant - Unit No.2 - Architectural - Aux.
Bldg. Sealed Watertight and Airtight Penetration Delineation
Dwg. Roof Plan
SNC997278C001
J.M. Farley Nuclear Plant - Unit No.1 Refueling Cavity Liner
Plate - Plan at El. 155'-0", Sects. & Dets. - Containment
SNC997278C002
J.M. Farley Nuclear Plant - Unit No.1 Refueling Cavity Liner
Plate Wall Elevations & Sections - Containment
SNC997278C003
J.M. Farley Nuclear Plant - Unit No.1 Refueling Cavity Liner
Plan -Wall Elevations - Containment
SNC997278C004
J. M. Farley Nuclear Plant Unit No.1 - Refueling Cavity Liner
Plate Misc. Details - Containment
SNC997278E001
Joseph M. Farley Nuclear Plant Unit No.1 Lighting Layout -
Containment - El. 155'0" - Areas 5 & 6
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC997278E002
Joseph M. Farley Nuclear Plant Unit No.1 - Underwater
Lighting Fixtures - Aux Bldg. & Ctmt. - El 155'0"
SNC997278E003
J.M. Farley Nuclear Plant Unit No.1 - Underwater Lighting
Fixtures Aux. Bldg. and Containment - El. 155'0"
SNC997278E004
Bill of Material for Drawings - D-177536 - Underwater
Lighting Fixtures Aux. Bldg. and Containment - El. 155'0"
SNC997278M001
Farley Nuclear Plant - Unit No. 1 - Reactor Coolant System
- B13 - Containment Building - El. 105'9" - Loop 1
SNC997278M002
Farley Nuclear Plant - Unit No.1 - Reactor Coolant System -
B13 - Containment Bldg. - El.105'9" - Loop 2
SNC997278M003
Farley Nuclear Plant - Unit No. 1 - Reactor Coolant System
- B13 - Containment Building - El. 105'9"
SNC997278M004
Farley Nuclear Plant - Unit No. 1 - Reactor Coolant System
- B13 - Hanger Isometric - Ctmt. Bldg. El. 124'3"
SNC997278M005
Farley Nuclear Plant - Unit No.1 - Reactor Coolant System -
B13 - Piping Isometric - Ctmt. El. 124'3"
DCP/SNC997278:
LDCR 2020-001
Farley Unit 1 Reactor Vessel Nozzles Mechanical Stress
Improvement Process (MSIP)
SNC1000660
DECP-U1 Anchor Head Replacement
SNC1012404
Design Equivalent Chang Package - Unit 2, 2C Service
Water Mini Flow Line Sleeve
SNC1096073
Unit 2 Service Water Header Drain and Vent Line Addition
SNC920821
2C Emergency Diesel Generator Jacket Water Tube Bundle
Replacement
SNC935408
AUX Building Roof Replacement
Engineering
Changes
SNC997278
Farley Unit 1 Reactor Vessel Nozzles Mechanical Stress
Improvement Process (MSIP)
DECP
SNC1096073 -
Applicability
Determination
Service Water Header Drain and Vent Addition
Engineering
Evaluations
DOEJ-
FDSNC935408-
C001
Evaluation of the Farley Unit 1 and 2 Auxiliary Buildings for
Roof Replacement and Temporary Equipment Live Loads
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DOEJ-
FDSNC935408-
M001
Effects on Control Room Habitability from Auxiliary Building
Roof Resurfacing Chemicals
DOEJ-
FDSNC935408-
M002
CREFS Charcoal Adsorber Impact from Application of
Roofing Products Containing Volatile Organic Compounds
on the Auxiliary Building Roof
DOEJ-
FDSNC935408-
M003
X/Q Evaluation for Chemical Releases While Reroofing the
Auxiliary Building at Farley
NCORP TE
1064469:
CFR 50.59
Evaluation
Evaluations Performed to Address Long-Term Cooling with
Containment Sump Debris (GSI-191)
03/08/2021
SNC1012404 -
Applicability
Determination
Unit 2 Service Water (SW) Mini Flow Line Leak
SNC1012404 -
Screening
Unit 2 Service Water (SW) Mini Flow Line Leak
SNC997278 -
Applicability
Determination
DCP Farley Unit 1 Reactor Vessel Nozzles Mechanical
Stress Improvement Process (MSIP)
SNC997278:
CFR 50.59
Screening
Application of the Mechanical Stress Improvement Process
(MSIP) to Unit 1 Reactor Vessel Nozzles
TE 1040425:
CFR 50.59
Screening
Incorporate AFW Analysis Contained in Westinghouse letter
ALA-14-12
11/14/2019
TE 1040425:
CFR 50.59
Evaluation
Incorporate AFW Analysis Contained in Westinghouse
Letter ALA-14-12 into FSAR
11/13/2019
TE 1066707:
CFR 50.59
Evaluation
Revise FSAR Polar Crane Main Hoist Load Block Safe Path
Restrictions.
06/19/2020
Miscellaneous
FE-S-18-001
Specification for Generator Exciter Switchgear Replacement Rev. 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
for Joseph M. Farley Nuclear Plant-Units 1 & 2
NCORP TE
106469, LDCR
No.: 2021-002
Licensing Document Change Request: Evaluations
Performed to Address Long-Term Cooling with Containment
Sump Debris (GSI-191)
2/22/2021
NMP-ES-084-007-
F01
Configuration Control Activity Worksheet: Roof
Replacement & Appurtenances (Insulated Fluid-Applied
Roofing System and Smoke/ Heat Ventilator Replacement)
for Turbine, Service abuilding, & Auxiliary Building (El 175'-
0")
NMP-ES-084-007-
F01
Configuration Control Activity Worksheet: Specification for
Membrane Roofing, Lightweight Concrete Fill and Flashing
for Farley Nuclear Plant - Auxiliary Buildings - Units 1 and 2
NMP-ES-084-007-
F01
Configuration Control Activity Worksheet: Sikalastic -641
LO-VOC Roofing System Product Data Sheets 47 Pages
(Including this Sheet) Liquid Applied Single Component
Fully Reinforced LO-VOC, Low-Odor System with
Fiberglass or Polyester Reinforcement
TE 1066707:
LDCR No.: 2020-
20
Licensing Document Change Request: Revise FSAR Polar
Crane Main Hoist Load Block Safe Path Restrictions.
06/02/2020
ABB Reliability and Availability Report-Farley Unit 2
ABB Reliability and Availability Report-Farley Unit 1
Rev. 1
ABB Unitrol 6000 Failure Mode and Effects Analysis
Rev. 1
Letter: ALA-14-12
Sothern Nuclear Operating Company Joseph M. Farley
Nuclear Plant, Transmittal of LTR-TA-13-159, "Farley Units
and 2 Feedline Break Analysis Results and FSAR
Markups for a Reduced AFW Flow Rate (105 gpm)"
03/24/2014
IP-ENG-001
Standard Design Process (EB-17-06)
Revision 2
IP-ENG-001-DAR
Design Attribute Review - Engineering Disciplines
11/12/2018
NMP-AD-008
Applicability Determinations
Version 22.1
NMP-AD-009
Licensing Document Change Requests
NMP-AD-010
CFR 50.59 Screenings and Evaluations
Version 17.1
Procedures
NMP-AD-025
Quality Assurance and Non-Quality Assurance Records
Administration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NMP-ES-035-006
Fire Protection Program Impact Screen and Detailed
Reviews
Rev. 13
NMP-ES-095
Interface Procedure for IP-ENG-001, "Standard Design
Process"
Version 9.1