IR 05000387/2021010

Design Basis Assurance Inspection (Programs) Inspection Report 05000387/2021010 and 05000388/2021010

ML21347A036
Person / Time
Site:	Susquehanna
Issue date:	12/13/2021
From:	Mel Gray NRC/RGN-I/DORS
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, Digitally signed by Melvin K.

Melvin K. Gray GrayDate: 2021.12.13 12:51:49-05'00'

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: NPF-14 and NPF-22 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 Enclosure

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

(4) HV155F003, HPCS - HPCI Steam Supply Outboard Isolation Valve

(5) HV250F046, RCIC Lube Oil Cooler Water Supply Valve

(6) HV255F001, HPCI Turbine Steam Supply Valve

(7) HV255F006, HPCS - HPCI Injection 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 Type Designation Description or Title Revision or

Procedure 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 Revision 8

Calculation EE5

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 Revision 13

Performance Assessment Report

MDS-06 Verification of Motor-Operated Valve Functionality Revision 18

MDS-08 Periodic Performance Assessment for SSES Motor- Revision 13

Operated Valves

Corrective Action CR 2021-02179

Documents CR 2021-10413

Corrective Action CR 2021-15644

Documents CR 2021-15645

Resulting from CR 2021-15646

Inspection 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 Type Designation Description or Title Revision or

Procedure Date

Evaluations Assessment Report

Miscellaneous ASME OMB 2006 Addenda to ASME OM Code-2004 for Operation and 08/31/2006

Code-2006 Maintenance of Nuclear Power Plants

SUS-ISTPLN- Unit 1 Inservice Testing Program Plan Revision 8

100.0

SUS-ISTPLN- Unit 2 Inservice Testing Program Plan Revision 11

200.0

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

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