IR 05000317/2020011
| ML20275A201 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/01/2020 |
| From: | Mel Gray Engineering Region 1 Branch 1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Gray M | |
| References | |
| IR 2020011 | |
| Download: ML20275A201 (10) | |
Text
October 1, 2020
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000317/2020011 AND 05000318/2020011
Dear Mr. Hanson:
On August 27, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 and discussed the results of this inspection with Mr. Tom Haaf, Site Vice President, 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, X /RA/
Signed by: Melvin K. Gray
Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos. 05000317 and 05000318 License Nos. DPR-53 and DPR-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000317 and 05000318
License Numbers:
Report Numbers:
05000317/2020011 and 05000318/2020011
Enterprise Identifier: I-2020-011-0009
Licensee:
Exelon Generation Company, LLC
Facility:
Calvert Cliffs Nuclear Power Plant, Units 1 and 2
Location:
Lusby, MD
Inspection Dates:
August 10, 2020 to August 27, 2020
Inspectors:
E. Dipaolo, Senior Reactor Inspector
D. Kern, Senior Reactor Inspector
A. Turilin, Reactor Inspector
Approved By:
Mel Gray, 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 Calvert Cliffs Nuclear Power 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.
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.
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. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely as well as on site and all the objectives and requirements for completion of the IP were met.
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 power-operated valves (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)1-FW-4517-MOV Feedwater - Steam Generator Feedwater Isolation Valve (2)2-SI-399-MOV, Safety Injection/Containment Spray - Shutdown Cooling HX (3)2-RC-405-MOV, Reactor Coolant - PORV (Power Operated Relief Valve) Blocking Valve (4)2-FW-4516-MOV, Feedwater - Steam Generator Feedwater Isolation Valve (5)2-EAD-5463-MOV, Plant Drains - Normal Containment Sump Discharge to Auxiliary Building (6)1-MS-4071-CV, Main Steam - Steam Generator Auxiliary Feedwater (AFW) Pump Turbine Steam Supply Valve (7)1-SW-5153-CV, Saltwater - 12A & 12B SRW HX Saltwater Back-up Outlet Valve (8)2-SRW-1638-CV, Service Water - Turbine Building SRW Isolation Valve (9)2-MS-3939-CV, Main Steam - Atmospheric Dump Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 27, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Tom Haaf, 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
011-C TURB
ISOL
Turbine Building Service Water Isolation Valves,
1(2)CV1600, 2CV1637, 1(2)CV1638, and 2CV1639
Service Water Heat Exchangers Saltwater Inlet and Back-
up Outlet Valves, 1CV5150, 1CV5152, and 1CV5153
083-C ATMOS
DUMP VLV
Atmospheric Dump Calves: 1(2) CV3928 and 1(2)
CV3939
2MOV0405
(CAL-2)
2MOV-405 AC Motor Operated GL96-05 Gate Valve
MidaCalc Results
Revision 3
C-91-227
Support of Valve Actuator 2-MOV-399
8/28/1991
CA 01749
Thermal Aging for NAMCO EA-740 Limit Switches
Revision 3
CA 05972
Design, Seismic, and Weak Link Analysis for PORV Block
Valves - 2.5" Class 1703 SS Double Disc Gate Valve with
SMB-00-15 Limitorque Actuator
Revision 0
CA 06165
Environmental Qualification, Normal and Accident
Radiation Doses
Revision 1
CA00740
Modification to Valve Actuator Support
0000
CA07358
Atmospheric Dump Valve Weak Link Analysis, 1(2)
CV3938 and 1(2) CV3939
08/24/2010
DE 04278
Maximum Line and Differential Pressure Calculation for
1(2)MOV4516-4517
DE 12320
AOV Program Calculation Update Project Support
Documentation
07/17/2017
E-90-038
MOV Minimum Voltages Lasting Longer than 5 Seconds
M-91-44
Velan Motor Operated Valve Maximum Thrust Calculation
MIDACALC
Results
1MOV4517
(CAL-1)
AC Motor Operated GL 96-05 Gate Valve
MIDACALC
RESULTS
2MOV0399
AC MOTOR OPERATED GL96-05 GLOBE VALVE
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(CAL-2)
MIDACALC
Results
2MOV4516
(CAL-2)
AC Motor Operated GL 96-05 Gate Valve
TR02.018
Flowserve Comparative Analysis with Actuator Sizing for
Calvert Cliffs Nuclear Power Plant, 2.5 inch Class 1703
Stainless Steel Double Disc Gate Valve with SMB-00-15
Limitorque Motor Actuator
Revision A
Corrective Action
Documents
2453685
2467839
03973598
03979432
04022139
242546
Corrective Action
Documents
Resulting from
Inspection
04362683
04362690
04362979
04363171
04363179
04365333
04365433
04365735
04365737
Drawings
Drawing No.
2312-0002
Model D-100-100 Operator 5 - 600 Pound Standard
Valve Assembly,
Engineering
Changes
ECP-14-000377
FLEX Mod-Replacement of ADV Gear Assemblies and
Chainwheel for NRC Order EA-12-049
ECP-14-000714
Atmospheric Dump Valve Positioner Replacement
Equivalent Change Evaluation
Engineering
Evaluations
Summary of Ambient Environmental Service Conditions
Revision 4
Miscellaneous
Inservice Testing Program Plan, Fifth Ten-Year Interval
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Seimens Industries Inc. ValvePAC Series 760 Pneumatic
and Electro-Pneumatic Valve Positioners Vendor Manual
09/01/2012
Generic Communications Learning Analysis Report for
OE-2013-002093 (NRC Information Notice 13-14
10/11/2013
6750-M-292
Specification for Atmospheric Dump and Turbine Bypass
Control Valves
ASME OM-2012
Operation and Maintenance of Nuclear Power Plants
Revision 0
IST-CCNP-
BDOC-V-015
Calvert Cliffs-Inservice Testing Basis Document
08/17/2020
STP 0-2-2
ADV Manual Stroke Test
03/01/2019
STP-O-66C-1
Feedwater Isolation Valves Operability Test
2/17/2020
STP-O-66C-2
Feedwater Isolation Valves Operability Test
2/18/2019
Procedures
Preventive Maintenance Program
Motor-Operated Valve Program Engineering Procedure
Motor Operated Valve Performance Trending
MOV Limitorque Actuator Capability Determination
Methodology
Revision 11
Inservice Testing Program Plan Format and Content
Air Operated Valve Design Basis Review and Setpoint
Control
MOV-009Q
Operating the Quicklook 3 Diagnostic System
MOV-13
Limitorque Motor Operated Valve Limit Switch
Compartment Inspection and Preventive Maintenance
Forced/Maintenance Outage Management
Unit 1 Abnormal
Operating
Procedure (AOP)
3G
Malfunction of Main Feedwater System
1400
Unit 2
Emergency
Operating
Procedure (EOP)
EOP 6
Steam Generator Tube Rupture
Work Orders
2199302533
3/3/1999
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2199605572
1/10/1997
C01791135
C220093721
C22090962
C91185565
C91897585
C91952809
C92672330
C92978932
C93002287
C93078897
C93346935
C93464272
C93600823
C93610195
C93611599
C93689627
C93700455
C93711623
C93741734