ML20070J790
| ML20070J790 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/10/2020 |
| From: | Mel Gray Engineering Region 1 Branch 1 |
| To: | Vitale A Entergy Nuclear, Indian Point |
| Gray M | |
| References | |
| IR 2020012 | |
| Download: ML20070J790 (7) | |
See also: IR 05000286/2020012
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD., SUITE 100
KING OF PRUSSIA, PENNSLYVANIA 19406-2713
March 10, 2020
Mr. Anthony J. Vitale
Site Vice President
Entergy Nuclear Operations, Inc.
450 Broadway, Generation Support Building
P.O. Box 249
Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT, UNIT 3 - REQUEST FOR INFORMATION TO SUPPORT
TRIENNIAL BASELINE DESIGN-BASIS CAPABILITY OF POWER-OPERATED
VALVES INSPECTION; INSPECTION REPORT 05000286/2020012
Dear Mr. Vitale:
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 your Indian Point Energy Center Unit 3. Niklas
Floyd, 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 July 26, 2019 (ADAMS Accession No. ML19067A240).
The inspection will assess the reliability, functional capability, and design bases of risk-important
power-operated valves (POV) as required by 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 February 7, 2020, with Mahvash Mirzai, Manager of
Regulatory Assurance, we confirmed arrangements for an information gathering site visit and
the two-week onsite inspection. The schedule is as follows:
Information gathering visit: Week of May 4, 2020
Onsite inspection: Weeks of June 8 and June 22, 2020
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 Niklas Floyd during the information-gathering visit to review probabilistic risk
assessment data and help identify the final POV samples to be examined during the inspection.
Additionally, we will determine during this visit whether there are risk-important POVs that
should be considered for review in our sample selection based on Unit 3s planned transition to
decommissioning status (i.e. inventory control, spent fuel pool cooling, and fire protection).
A. Vitale
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.
Insofar as possible, this information should be provided electronically to the lead inspector at the
NRC Region I Office by April 27, 2020, about a week prior to the Information Gathering visit.
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 610-337-5282 or via e-mail at Niklas.Floyd@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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Thank you in advance for supporting this engineering inspection.
Sincerely,
/RA/
Mel Gray, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. [50-286]
License No. [DPR-64]
Enclosure:
DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION
cc: Distribution via ListServ
X
SUNSI Review
X
Non-Sensitive
Sensitive
X
Publicly Available
Non-Publicly Available
OFFICE
RI/DRS
RI/DRS
NAME
NFloyd/NPF
MGray/MG
DATE
03/09/2020
03/10/2020
DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION
Enclosure
Inspection Report: 05000286/2020012
Onsite Inspection Dates:
June 8 through June 12, 2020; and
June 22 through June 26, 2020
Inspection Procedure:
Inspection Procedure 71111.21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a Requirements
Lead Inspector:
Niklas Floyd, Senior Reactor Inspector
610-337-5282
Niklas.Floyd@nrc.gov
I.
Information Gathering Visit
During this visit, we plan to obtain sufficient insights to finalize 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 (MOV) and air-operated valves (AOV); and
additional valve types that may include hydraulic-operated valves (HOV), solenoid-operated
valves (SOV), 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. 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 April 27, 2020, about one week prior to the
Information Gathering visit, 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, online). 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 Update Final Safety Analysis Report. If not available in a single file,
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.
3. List of corrective action documents related to the MOV and AOV programs since June 1,
2015 (include document No., title/short description, date).
DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION
2
4. List of significant modifications, repairs, or replacement of safety related POVs
completed since June 1, 2015, including date completed (include document No., title,
date completed).
5. Any self-assessments or quality assurance type assessments of the MOV/AOV
programs (performed since June 1, 2015).
6. List and electronic copy of all Emergency Operating Procedures.
7. List of Abnormal Operating Procedures.
8. 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.
9. For each of the following MOVs, provide the information listed in the table below.
536, PORV Blocking Valve
746, #31 RHR HX Outlet Injection Stop Valve
797, RCP Seal & Bearing Coolers and Vessel Cooling Support Blocks
882, RHR Pump Suction
883, RHR Pump Discharge to SIS Isolation Valve
1810, RWST Outlet Isolation Valve
1802A, Recirculating Pump Discharge Isolation Valve
745B, RHR Pump Discharge to HX Inlet #32 Isolation Valve
822A, #31 RHR HX CCW Outlet Isolation Valve
850C, Pump #31 Discharge Isolation Valve
856B, High Head Safety Injection to Loop #3 Hot Let NonBit Header
866A, Containment Spray Pump #31 Discharge Valve
885A, Containment Sump RHR Suction Isolation Valve
888B, Low Head to High Head SI Recirculation Stop Valve
889A, #32 RHR HX Outlet to Spray Header Stop Valve
HCV-638, RHR HX #31 Outlet Throttle 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
DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION
3
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)
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
10. For each of the following AOVs, provide the information listed in the table below.
798, Excess Letdown HX CCW Supply Isolation
FCV-1176, Emergency Diesel Generators SWS Outlet Flow Control
FCV-405A, #32 Aux. Feed to #31 S/G Feed Control
HCV-1118, AFW Turbine Trip Throttle Valve
LCV-459, Letdown Line Isolation
MS-1-32, #32 Steam Generator Main Steam Isolation
PCV-1135, #32 Steam Generator Main Steam Atmospheric Relief
PCV-1139, #32 Aux. Feed Pump Steam Control
PCV-1310A, Main Steam Supply to #32 Aux. Feed Pump Room Isolation
PCV-455C, PORV
PCV-456, PORV
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
DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION
4
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
11. For each of the following miscellaneous POVs, provide the information listed in the table
below.
652, RX Vessel Head Vent Valve
Item Parameter/Information*
1
Safety Function
2
Fail safe position (open/close/as-is)
3
Valve manufacturer, type, and size
4
Actuator manufacturer, type, and size
5
Valve ASME Class
6
Risk significance
7
Design-basis differential pressure and flow (close/open)
8
Minimum required Voltage at the POV
9
Available voltage at the POV
10
Environmental Qualification harsh environment (Y/N)
11
Normally energized (Y/N)
12
Time in service
- Specify Not Applicable (NA) as appropriate