ML21210A223
| ML21210A223 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/29/2021 |
| From: | Mel Gray NRC/RGN-I/DORS |
| To: | Berryman B Susquehanna |
| Gray M | |
| References | |
| IR 2021010 | |
| Download: ML21210A223 (8) | |
See also: IR 05000387/2021010
Text
July 29, 2021
Mr. Brad Berryman
President and Chief Nuclear Officer
Susquehanna Nuclear, LLC
769 Salem Blvd., NUCSB3
Berwick, PA 18603
SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
INFORMATION REQUEST TO SUPPORT TRIENNIAL BASELINE DESIGN-
BASIS CAPABILITY OF POWER-OPERATED VALVES INSPECTION;
INSPECTION REPORT 05000387/2021010 AND 05000388/2021010
Dear Mr. Berryman:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a team inspection at Susquehanna Steam Electric Station, Units 1
and 2. David Kern, a Senior Reactor Inspector from the NRCs Region I Office, will lead the
inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21N.02, Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a
Requirements, dated October 9, 2020 (ADAMS Accession No. ML 20220A667).
The inspection will assess the reliability, functional capability, and design bases of risk-important
power-operated valves (POVs) as required by Title 10 of the Code of Federal Regulations
(10 CFR) 50.55a, and Appendix A and B requirements. The inspectors will select a sample of
POVs based on risk insights, safety significance, and operating margin.
During a telephone conversation on July 30, 2020, with Mr. Shane Jurek, Senior Licensing
Engineer, we confirmed arrangements for an information gathering visit and the two-week onsite
inspection. Depending on site access conditions, the information gathering visit may be onsite
or may be performed remotely. The schedule is as follows:
- Information gathering visit: Week of August 16
- Onsite weeks: Weeks of November 1 and November 15
The purpose of the information gathering visit is to meet with members of your staff and to
become familiar with your programs and procedures intended to ensure compliance with 10 CFR 50.55a for POVs. The lead inspector will discuss aspects of the programs including any
specific applicable regulatory commitments made by your facility and your use of NRC
Regulatory Guides or industry standards. Frank Arner, a Region I Senior Risk Analyst, will
support David Kern during the information-gathering visit to review probabilistic risk assessment
data and identify the final POV samples to be examined during the inspection.
B. Berryman 2
Experience with previous design basis team inspections of similar depth and length has shown
this type of inspection is resource intensive, both for NRC inspectors and licensee staff. In
order to minimize the inspection impact on the site and to ensure a productive inspection for
both parties, we have enclosed a request for information needed for the inspection.
It is important that all of these documents are up-to-date and complete in order to minimize the
number of additional documents requested during the preparation and onsite portions of the
inspection. Insofar as possible, this information should be provided electronically to the lead
inspector at the NRC Region I Office by August 16, 2021. Recognizing the timeframe, my staff
will work with your staff to prioritize our document requests so these activities can be
accomplished, as much as possible, in the normal course of your activities. Additional
documents may be requested during the information gathering visit and/or during team
preparation week (the week prior to the first onsite inspection week). The inspectors will
minimize your administrative burden by specifically identifying only those documents required
for the inspection.
If there are any questions about the inspection or the material requested in the enclosure,
please contact the lead inspector at 610-337-6931 or via e-mail at David.Kern@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, Control Number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget Control Number.
This letter and its enclosure 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
Digitally signed by
Melvin K. Melvin K. Gray
Date: 2021.07.29
Gray 13:03:23 -04'00'
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
Docket Nos. 05000387 and 05000388
License Nos. NPF-14 and NPF-22
Enclosure:
Document Request for Design Bases
Assurance Inspection
cc: Distribution via ListServ
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DORS RI/DORS
NAME DKern MGray
DATE 7/28/21 7/29/21
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
Inspection Report: 05000387/2021010 and 05000388/2021010
Onsite Inspection Dates: November 1 through November 5, 2021; and
November 15 through November 19, 2021
Inspection Procedure: Inspection Procedure 71111.21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a Requirements
Lead Inspector: David Kern, Senior Reactor Inspector
610-337-6931
David.Kern@nrc.gov
I. Information Gathering Visit
During this visit, we plan to obtain sufficient insights to finalize power-operated valve (POV)
samples for this inspection. We would like to meet with POV specialists to discuss the
upcoming inspection and our sample selection process. The primary valve types to be
reviewed for this inspection include motor-operated valves (MOVs) and air-operated valves
(AOVs); and additional valve types include hydraulic-operated valves (HOVs), solenoid-
operated valves (SOVs), and pyrotechnic-actuated (squib) valves. During this visit, the lead
inspector will: (a) discuss the scope of the planned inspection; (b) identify additional
information needed to review in preparation for the inspection; (c) ensure that the
information to be reviewed is available at the beginning of the inspection; and (d) verify that
logistical issues will be identified and addressed prior to the teams arrival. Depending on
the local COVID environment and potential travel restrictions, this visit may be either onsite
or performed remotely through a series of skype video calls. If performed onsite, please
reserve a room during the site visit with a telephone, wireless internet access, and a
licensee computer with access to procedures, corrective action program documents, and a
printer.
II. Information Requested for Selection of Power-Operated Valves
The following information is requested by August 16, 2021, to facilitate inspection
preparation. Feel free to contact the lead inspector if you have any questions regarding this
information request. Please provide the information electronically in pdf files, Excel, or
other searchable formats, preferably on some portable electronic media (e.g., CD-ROM,
DVD). The files should contain descriptive names, and be indexed and hyperlinked to
facilitate ease of use. Information in lists should contain enough information to be easily
understood by someone who has knowledge of light water reactor technology and POVs.
1. A word-searchable Updated Final Safety Analysis Report. If not available in a single file
for each unit, please ensure a collective table of contents is provided.
2. Site (and corporate if applicable) procedures associated with implementation of the MOV
program required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory
Appendix III; and site (corporate) procedure for AOV program.
Enclosure
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
3. Site response(s) to NRC Generic Letter (GL) 95-07, Pressure Locking and Thermal
Binding of Safety-Related Power-Operated Gate Valves.
4. Site response(s) to NRC GL 96-05, Periodic Verification of Design-Basis Capability of
Safety-Related Motor-Operated Valves.
5. Site evaluation of NRC Information Notice 2012-14, MOV Inoperable due to Stem-Disc
Separation.
6. List of corrective action documents related to the MOV and AOV programs since
November 1, 2016 (include document No., title/short description, date).
7. List of corrective action documents related to each of the 30 POVs listed below since
November 1, 2016 (include document No., title/short description, date).
8. List of significant modifications, repairs, or replacement of safety-related POVs
completed since November 1, 2016, including date completed (include document No.,
title, date completed).
9. List of POVs removed from the In-Service Test program since January 1, 1990.
10. Any self-assessments or quality assurance type assessments of the MOV/AOV
programs (performed since November 1, 2016).
11. Most recent POV (e.g., MOV, AOV, SOV) program health report(s).
12. List and electronic copy of all Emergency Operating Procedures.
13. List of Abnormal Operating Procedures.
14. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
(OM Code) that is the Code of Record for the current 10-year Inservice Test Program
interval, as well as any standards to which the station has committed with respect to
POV capability and testing.
15. For each of the following MOVs, provide the information listed in the table below.
HV01222B Residual Heat Removal Service Water - UHS Spray Bypass Isolation
Valve
HV112F073A Residual Heat Removal Service Water - RHR/RHRSW Loop A
Crosstie Valve
HV149F007 RCIC Turbine Pump - RCIS Turbine Steam Supply Inboard Isolation
Valve
HV151F004A Residual Heat Removal - RHR Pump A Suppression Pool Suction
Valve
HV151F016B Residual Heat Removal - RHR Loop B Drywell Spray Outboard
Isolation Valve
HV151F028A Residual Heat Removal - RHR Loop A Suppression Pool Spray Test
Shutoff Valve
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
HV155F003 High Pressure Core Spray - HPCI Turb Steam Supply Outboard
Isolation Valve
HV155F003 High Pressure Core Spray - HPCI Turb Steam Supply Outboard
Isolation Valve
HV155F079 High Pressure Core Spray - HPCI Turb Exhaust Inboard Vac Breaker
Valve
HV21210A Residual Heat Removal Service Water - RHR HX A SW Supply
Isolation Valve
HV249F013 RCIC Turbine Pump - RCIC Injection Valve
HV250F045 RCIC Turbine Pump - RCIC Turbine Steam Supply Valve
HV250F046 RCIC Turbine Pump - RCIC Lube Oil Cooler Water Supply Valve
HV251F015B Residual Heat Removal - RHR Loop B Injection Outboard Isolation
Valve
HV251F021A Residual Heat Removal - RHR Loop A Drywell Spray Inboard
Isolation Valve
HV251F024B Residual Heat Removal - RHR Loop B Supp Pool Cooling/Test
Control Valve
HV251F048B Residual Heat Removal - RHR HX B Shell Side Bypass Valve
HV255F001 Residual Heat Removal - HPCI Turb Steam Supply Valve
HV255F006 High Pressure Core Spray - HPCI Injection Valve
HV255F042 High Pressure Core Spray - HPCI Pump Suction Suppression Pool
Supply Valve
Item Parameter/Information*
1 MOV Identification
2 Safety Function
3 Valve manufacturer, type, and size
4 Actuator manufacturer, type, and size
5 Motor manufacturer, type (AC/DC), and size
6 Valve ASME Class
7 Risk Significance
8 Control Switch Trip (CST) Application (Close/Open)
9 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)
10 Rising-Stem Valve: Assumed Valve Factor (VF)
11 Quarter-Turn Valve: Assumed bearing torque coefficient
12 Assumed Stem Friction Coefficient (SFC)
13 Assumed Load Sensitive Behavior (LSB) (%)
14 % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)
15 Calculated Required Thrust/Torque (Close/Open)
16 Least Available Output (e.g., actuator, CST, rating, spring pack, weak link)
17 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,
and temperature; ambient temperature; and motor voltage) (Close/Open)
18 Thrust and torque required to overcome dynamic conditions (Close/Open)
19 Rising-Stem Valve: Measured VF (Close/Open)
20 Rising-Stem Valve: Available VF (Close/Open)
21 Measured SFC (Close/Open)
22 Measured LSB (%)
23 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)
24 Determined % Margin (Close/Open)
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
25 Basis for Design-Basis Capability:
25.a Dynamic test performed at design-basis DP/flow conditions
25.b Extrapolation of dynamic test data
25.c Justification from normal operation at or above design-basis conditions
25.d Industry dynamic test methodology (such as EPRI MOV PPM)
25.e Grouped with similar valves dynamically tested at plant
25.f Grouped with similar valves dynamically tested at other plants
25.g Valve qualification testing (such as ASME QME-1-2007)
25.h Other (such as large calculated margin)
- Specify Not Applicable (NA) as appropriate
16. For each of the following AOVs/SOVs/HOVs, provide the information listed in the table
below.
HV141F022A Main Steam - "A" Main Steam Line Inboard Isolation Valve
HV141F028D Main Steam - "D" Main Steam Line Outboard Isolation Valve
HV16108A1 Liquid Rad Waste - Drywell Floor Drain Sump Pump Discharge
Isolation Valve
HV16116A2 Liquid Rad Waste - Drywell Equipment Drain Tank Discharge Isolation
Valve
HV18792B2 Reactor Building Chill Water - RRP A Cooling Water Inboard Isolation
Reactor Building Chilled Water Return
HV25703 Liquid Rad Waste - Suppression Chamber Purge Exhaust Upstream
Isolation Valve
HV25723 Containment Atmosphere Control - Drywell Air Purge Isolation Valve
SV12654A Containment Instrument Gas - I-G to Main Steam PSV1F013 GJM
TV01124E Emergency Service Water - DG E ESW Loop B Return Temperature
Control Valve
XV247F010A Control Rod Drive Hydraulic - CRD SDV Vent Valve
XV247F010B Control Rod Drive Hydraulic - CRD SDV Vent Valve
Item Parameter/Information*
1 AOV Identification
2 Safety Function
3 Fail safe position (open/close)
4 Valve manufacturer, type, and size
5 Actuator manufacturer, type, and size
6 Valve ASME Class
7 Risk Significance
8 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)
9 Rising-Stem Valve: Assumed Valve Factor (VF)
10 Quarter-Turn Valve: Assumed bearing torque coefficient
11 % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)
12 Calculated Required Thrust/Torque (Close/Open)
13 Minimum allowable air pressure (Beginning/End Stroke)
14 Maximum allowable air pressure (Beginning/End Stroke)
15 Minimum allowable spring preload (Beginning/End Stroke)
16 Maximum allowable spring preload (Beginning/End Stroke)
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
17 Least Available Actuator Output (e.g., actuator capability, actuator limit, valve
weak link limitation)
18 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,
and temperature; and ambient temperature) (Close/Open)
19 Thrust and torque required to overcome dynamic conditions (Close/Open)
20 Rising-Stem Valve: Measured VF (Close/Open)
21 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)
22 Determined Margin (%) (Least margin for air stroke operation, spring stroke
operation, maximum spring load, and structural capability)
23 Basis for Design-Basis Capability:
24.a Dynamic test performed at design-basis DP/flow conditions
24.b Extrapolation of dynamic test data
24.c Justification from normal operation at or above design-basis conditions
24.d Industry dynamic test methodology
24.e Grouped with similar valves dynamically tested at plant
24.f Grouped with similar valves dynamically tested at other plants
24.g Valve qualification testing (such as ASME QME-1-2007)
24.h Other (such as large calculated margin)
- Specify Not Applicable (NA) as appropriate