ML22013A751
| ML22013A751 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/13/2022 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Grabnar J Energy Harbor Nuclear Corp |
| Gray M | |
| References | |
| IR 2022010 | |
| Download: ML22013A751 (8) | |
See also: IR 05000334/2022010
Text
January 13, 2022
Mr. John Grabnar
Site Vice President
Energy Harbor Nuclear Corp.
Beaver Valley Power Station
Route 168
Shippingport, PA, 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION
REQUEST TO SUPPORT TRIENNIAL BASELINE DESIGN-BASIS CAPABILITY
OF POWER-OPERATED VALVES INSPECTION; INSPECTION REPORT
05000334/2022010 AND 05000412/2022010
Dear Mr. Grabnar:
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 Beaver Valley Power Station, Units 1 and 2.
Paul Cataldo, 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. ML20220A667).
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 January 13, 2022, with Ms. Julie Hartig, Regulatory
Compliance Supervisor, 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 performed onsite, remote, or a hybrid inspection. The schedule is as follows:
Information gathering visit: Week of February 14, 2022
Onsite weeks: Weeks of March 14 and March 28, 2022
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. Dave Werkheiser, a Region I Senior Risk Analyst, will
support Paul Cataldo during the information-gathering visit to review probabilistic risk
assessment data and identify the final POV samples to be examined during the inspection.
J. Grabnar
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 the information gathering week of February 14, 2022.
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 603-395-5536 or via e-mail at Paul.Cataldo@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,
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
Docket Nos. 05000334 and 05000412
License Nos. DPR-66 and NPF-73
Enclosure:
Document Request for Design Bases
Assurance Inspection
cc: Distribution via ListServ
Melvin K. Gray
Digitally signed by Melvin K.
Gray
Date: 2022.01.13 14:12:08
-05'00'
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
RI/DORS
RI/DORS
NAME
PCataldo
MGray
DATE
1/13/22
1/13/22
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
Enclosure
Inspection Report: 05000334/2022010 and 05000412/2022010
Onsite Inspection Dates:
March 14 through March 18, 2022; and
March 28 through April 1, 2022
Inspection Procedure:
Inspection Procedure 71111.21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a Requirements
Lead Inspector:
Paul Cataldo, Senior Reactor Inspector
603-395-5536
Paul.Cataldo@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), and solenoid-
operated valves (SOVs). 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, performed remotely through a series of Microsoft
Teams, or a hybrid inspection. 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 the week of February 14, 2022, 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, Word, Excel, or other searchable formats, preferably utilizing the typical file-sharing
applications, such as eDocs, Certrec or Box. 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 the AOV program.
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
2
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
January 1, 2017, (include document No., title/short description, date).
7. List of corrective action documents related to each of the 30 POVs listed below since
January 1, 2017 (include document No., title/short description, date).
8. List of significant modifications, repairs, or replacement of safety-related POVs
completed since January 1, 2017, including date completed (include document No., title,
date completed). If none are available, please provide a list of modifications on the
same population of valves, looking back an additional 5 years.
9. List of POVs removed from the In-Service Test program since January 1, 2012.
10. Any self-assessments or quality assurance type assessments of the MOV/AOV
programs (performed since January 1, 2017).
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.
Containment Depressurization - 1A
QUENCH SPRAY PP DISCH ISOL
MOV-1CH-115C
Chemical and Volume Control - VCT OUT
TO CHG PP SUCT HDR ISOL
MOV-1FW-151D
Feedwater & Auxiliary Feedwater - 1B SG
MOV-1MS-105
Main Steam - AFW TURB STEAM ISOL
MOV-1RC-535
Reactor Coolant - PRZR PORV ISOL
MOV-1RH-701
Residual Heat Removal - RESIDUAL
HEAT REMOVAL IN ISOL
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
3
MOV-1RW-102C2
Reactor Plant River Water - 1C RP RW
PUMP DISCH VLV TO A-HDR
MOV-1SI-860B
Safety Injection - 1B LHSI PP RX CNMT
SUMP SUCT ISOL
MOV-1SI-864B
Safety Injection - 1B LHSI PP TO RCL
COLD LEGS
ISOL
2CCP*MOV112A
Primary Component Cooling Water -
(2RHS*E21A,22A) SUPPLY ISOL
2CHS*MOV310
Chemical and Volume Control - REGEN
HX NORMAL CHARGING DISCHARGE
VALVE
2QSS*MOV101A
Containment Depressurization -
QUENCH PUMP 21A DISCHARGE
ISOLATION VALVE
2RCS*MOV536
Reactor Coolant - (2RCS*PCV456)
ISOLATION
2RHS*MOV701A
Residual Heat Removal - RHS TRAIN A
SUPPLY ISOLATION
2RHS*MOV720B
Residual Heat Removal - RHS TRAIN
RETURN TO C LOOP ISOLATION
2SIS*MOV865C
Safety Injection - SI ACCUMULATOR
TK21A DISCH STOP
2SWE*MOV116A
Service Water - STBY SW PUMPS
2SWS*MOV113D
Service Water - EMERG GEN HX 21 B
SERV WTR HDR B COOLING WTR
INLET VLV
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)
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
4
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)
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.
HYV-1FW-100C
Feedwater & Auxiliary Feedwater - 1C
STEAM GENERATOR MAIN
TV-1BD-100A
Steam Generator Blowdown - STM GEN
1A SLOWDOWN TRIP
TV-1CC-105D1
Reactor Plant Component Cooling Water
- RCP MOTORS 1B AND 1C CCR OUT
TV-1CC-111A2
Reactor Plant Component Cooling Water
- CRDM SHROUD CLG COILS CCR IN
CNMT ISOL
TV-1CH-200B
Chemical and Volume Control - 60 GPM
LTDN ORIFICE CNMT ISOL
TV-1MS-105B
Main Steam - AFW TURB STEAM SUP B
TRN TRIP VLV
2CCP*AOV107B
Primary Component Cooling Water - RCP
B THERMAL BARRIER COOLING
WATER DISCHARGE
2DAS*AOV100A
Reactor Plant Vents & Drains - CNMT
DISCHARGE ISOLATION
2FWE*HCV100A
Feedwater & Auxiliary Feedwater - 21C
2FWS*FCV488
Feedwater & Auxiliary Feedwater - 21B
SG MAIN FEED REG VALVE
2MSS*SOV105A
Main Steam - TURBINE DRIVEN AUX
FEEDWATER PMP STEAMLINE A ISOL
VALVE
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
5
2MSS*SOV105F
Main Steam - TURBINE DRIVEN AUX
FEEDWATER PUMP STEAMLINE C
ISOL VALVE
Item
Parameter/Information*
1
AOV/SOV/HOV 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)
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