IR 05000387/2021010
| ML21347A036 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/13/2021 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Berryman B Susquehanna |
| Gray M | |
| References | |
| IR 2021010 | |
| Download: ML21347A036 (8) | |
Text
December 13, 2021
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000387/2021010 AND 05000388/2021010
Dear Mr. Berryman:
On November 19, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2 and discussed the results of this inspection with Mr. Kevin Cimorelli, 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, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket Nos. 05000387 and 05000388 License Nos. NPF-14 and NPF-22
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000387 and 05000388
License Numbers:
Report Numbers:
05000387/2021010 and 05000388/2021010
Enterprise Identifier: I-2021-010-0027
Licensee:
Susquehanna Nuclear, LLC
Facility:
Susquehanna Steam Electric Station, Units 1 and 2
Location:
Berwick, PA
Inspection Dates:
November 1, 2021 to November 19, 2021
Inspectors:
P. Cataldo, Senior Reactor Inspector
M. Farnan, Mechanical Engineer
D. Kern, Senior Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating 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 Susquehanna Steam Electric Station, 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.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Power-Operated Valve 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. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) HV01222B, RHRSW - Ultimate Heat Sink Spray Bypass Isolation Valve
- (2) HV112F073A, RHRSW Loop A Crosstie Valve
- (3) HV151F028A, RHR Loop A Suppression Pool Spray Test Shutoff Valve
- (6) HV255F001, HPCI Turbine Steam Supply Valve
- (8) HV141F022A, A Inboard Main Steam Isolation Valve
- (9) HV25723, Containment Atmosphere Control - Drywell Air Purge Isolation Valve
- (10) SV12654A, Containment Instrument Gas - to Main Steam PSV1F013 GJM
- (11) XV247F010A/B, Control Rod Drive Scram Discharge Volume Vent Valves
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 19, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Kevin Cimorelli, 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
EC-006-0506
HV151F028A Thermal Overload Calculation
Revision 3
EC-049-1038
HV151F028A Weak Link Seismic Calculation
Revision 3
EC-088-0505
Unit 1 and Unit 2 Class 1E 250 VDC System Voltage Drop
Calculation EE5
Revision 8
EC-VALV-0569
V151F028A System Design Basis Calculation
Revision 22
EC-VALV-1073
HV151F028A Component Design Basis
Revision 49
EC-VALV-1109
Degradation Assessment Supporting Annual MOV
Performance Assessment Report
Revision 13
MDS-06
Verification of Motor-Operated Valve Functionality
Revision 18
MDS-08
Periodic Performance Assessment for SSES Motor-
Operated Valves
Revision 13
Corrective Action
Documents
CR 2021-02179
CR 2021-10413
Corrective Action
Documents
Resulting from
Inspection
CR 2021-15644
CR 2021-15645
CR 2021-15646
CR 2021-15702
CR 2021-15705
CR 2021-15706
CR 2021-15709
CR 2021-15711
CR 2021-15721
CR 2021-15821
CR 2021-16042
CR 2021-16387
CR 2021-16439
CR 2021-16461
Drawings
M-112
Unit 1 RHR Service Water System
Revision 55
M-2147
Unit 2 Control Rod Drive Part B
Revision 38
M-2150
Unit 2 RCIC Turbine Pump
Revision 32
Engineering
EQAR-084
Limitorque Actuator Environmental Qualification
Revision 23
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Evaluations
Assessment Report
Miscellaneous
Code-2006
2006 Addenda to ASME OM Code-2004 for Operation and
Maintenance of Nuclear Power Plants
08/31/2006
SUS-ISTPLN-
100.0
Unit 1 Inservice Testing Program Plan
Revision 8
SUS-ISTPLN-
200.0
Unit 2 Inservice Testing Program Plan
Revision 11
Procedures
NDAP-QA-0017
Motor Operated Valve Program
Revision 18
NDAP-QA-1170
Air Operated Valve Program
Revision 5
Work Orders
ERPM 1975504
PCWO 2419208
RTPM 2014246