ML21102A070
| ML21102A070 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/12/2021 |
| From: | Vincent Gaddy NRC Region 4 |
| To: | Welsch J Pacific Gas & Electric Co |
| References | |
| IR 2021011 | |
| Download: ML21102A070 (9) | |
See also: IR 05000275/2021011
Text
April 12, 2021
Mr. James M. Welsch
Senior Vice President, Generation
and Chief Nuclear Officer
Pacific Gas and Electric Company
P.O. Box 56
Mail Code 104/6
Avila Beach, CA 93424
SUBJECT: DIABLO CANYON POWER PLANT, UNITS 1 AND 2 -NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)
(05000275/2021011 AND 05000323/2021011) AND INITIAL REQUEST FOR
INFORMATION
Dear Mr. Welsch:
On July 26, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Diablo Canyon Power Plant Units 1 and 2. A three-person team will perform
this inspection using NRC Inspection Procedure 71111, Attachment 21N.02, Design Bases
Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.
This inspection will evaluate the reliability, functional capability, and design basis of risk-
important power-operated valves as required by Title 10 of the Code of Federal Regulations (10
CFR) 50.55a and applicable 10 CFR Part 50, Appendix A and Appendix B, requirements, and
as required by the Diablo Canyon Power Plant Units 1 and 2 Operating Licenses. Additionally,
the team will perform an inspection of the documentation files to verify that the plant activities
associated with safety-related motor-operated valves meet your commitments to Generic Letter (GL) 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance, and GL 96-05,
"Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." In
conducting this inspection, the team will select power-operated valves used to prevent and
mitigate the consequences of a design basis accident.
The inspection will include an information gathering site visit by the team leader and two weeks
of onsite inspection by the team. The inspection will consist of three NRC inspectors. The
current inspection schedule is as follows:
Onsite Information Gathering Visit: June 28-July 2, 2021
Preparation Weeks: July 19-23, 2021, and August 2-6, 2021
Onsite Weeks: July 26-30, 2021 and August 9-13, 2021
J. Welsch 2
The purpose of the information gathering visit is to meet with members of your staff to become
familiar with the power-operated valve activities at the Diablo Canyon Power Plant. The lead
inspector will request a meeting with your personnel to discuss the site power-operated valve
procedures. Additionally, the lead inspector will request a discussion with your staff to become
familiar with the regulations and standards applicable to power-operated valves at the site.
Additional information and documentation needed to support the inspection will be identified
during the inspection, including interviews with engineering managers and engineers.
In order to minimize the inspection impact on the site and to ensure a productive inspection, we
have enclosed a request for information needed for the inspection. This information should be
made available to the lead inspector during the week of June 14-18, 2021. Since the inspection
will be concentrated on safety-related and risk significant power-operated valves, a list of such
power-operated valves should be available to review during and following the information
gathering visit to assist in our selection of appropriate power-operated valves to review.
Additional requests by inspectors will be made during the onsite weeks for specific documents
needed to complete the review of specific power-operated valves and associated activities. It is
important that all these documents are up-to-date and complete in order to minimize the number
of additional documents requested during the preparation and/or the onsite portions of the
inspection. To facilitate the inspection, we request that a contact individual be assigned to each
inspector to ensure information requests, questions, and concerns are addressed in a timely
manner.
The lead inspector for this inspection is Mr. Ronald A. Kopriva. We understand that our
licensing engineer contact for this inspection is Ms. Amanda Sorensen. If there are any
questions about the inspection or the requested materials, please contact the lead inspector by
telephone at 817-200-1104 or by e-mail at Ron.Kopriva@nrc.gov.
This letter contains mandatory information collections that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget
(OMB) approved these information collections (approval number 31500011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington, DC
205550001, or by email to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of
Information and Regulatory Affairs, NEOB-10202, (31500011) Office of Management and
Budget, Washington, DC 20503.
The NRC may not conduct nor 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 OMB control number.
J. Welsch 3
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
Vincent G. Digitally signed by Vincent G.
Gaddy
Gaddy Date: 2021.04.12 09:32:35
-05'00'
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 05000275 and 05000323
License Nos. DPR-80 and DPR-82
Enclosures:
1. Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Request for Information
2. Valves of Interest List
cc w/ encl: Distribution via LISTSERV
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: RAK Yes No Publicly Available Sensitive NRC-002
OFFICE SRI:EB1 C:PBD C:EB1
NAME RKopriva JJosey VGaddy
SIGNATURE RKopriva JJosey VGaddy
DATE 4/12/2021 4/12/2021 04/12/2021
Initial Request for Information
Design Bases Capability of Power-Operated Valves
Diablo Canyon Power Plant Units 1 and 2
Inspection Reports: 05000275/2021011 AND 05000323/2021011
Information Gathering Dates: June 28-July 2, 2021
Inspection Dates: July 26-30, 2021, and August 9-13, 2021
Inspection Procedure: IP 71111, Attachment 21N.02, Design Bases Capability of
Power-Operated Valves Under 10 CFR 50.55a
Requirements
Lead Inspector: Ronald A. Kopriva, Senior Reactor Inspector
I. Information Requested for Information Gathering Visit (June 28, 2021)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of Ronald A. Kopriva, by June 14, 2021, to facilitate the
reduction in the items to be selected for a final list of components. The inspection team
will finalize the selected list during the prep week using the documents requested in this
enclosure. The specific items selected from the lists shall be available and ready for
review on the day indicated in this request. *Please provide requested documentation
electronically in PDF files, Excel, or other searchable formats, if possible. The
information 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 pressurized water reactor technology. If
requested documents are large and only hard copy formats are available, please inform
the inspectors, and provide subject documentation during the first day of the onsite
inspection.
1. Provide the valve characteristics for the valves listed in the attached list as described
in Appendix C of Nuclear Regulatory Commission (NRC) Inspection Procedure
71111, Attachment 21N.02, Design Bases Capability of Power-Operated Valves
Under 10 CFR 50.55a Requirements.
2. List of power-operated valves (POVs) important to safety for the Diablo Canyon
Power Plant. The list should include (a) component identification number; (b)
applicable plant system; (c) ASME Boiler and Pressure Vessel Code (BPV Code)
Class; (d) safety-related or nonsafety-related classification; (e) valve type, size and
manufacturer; and (f) actuator type, size, and manufacturer. If the NRC has granted
a license amendment to categorize structures, systems, and component in
accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.69, please
provide the risk-informed safety category of the component.
3. Listing of POVs sorted by risk importance, including external risk considerations.
4. Word searchable updated final safety analysis report (UFSAR), license conditions,
Enclosure 1
technical specifications, and most recent inservice testing (IST) program plan (and
bases document), including any standards that have been committed to with respect
to POV capability and testing. Also, identify which UFSAR sections address
environmental, seismic, and functional qualification of POVs.
5. Provide copies of the latest POV program level procedures or manuals.
6. NRC Safety Evaluation Report(s) associated with the Diablo Canyon Power Plant
IST program and relief and alternative requests submitted in accordance with 10
CFR 50.55a for POVs.
7. Provide the most recently completed audit, self-assessment, or benchmark of POV
programs at Diablo Canyon Power Plant.
8. List of systems, system numbers/designators and corresponding names.
9. List of site contacts that will be associated with the inspection.
II. Discussions Requested
1. Interview with a Diablo Canyon Power Plant representative to discuss site POV
capability analyses, including plant drawings and assumptions. This includes
analysis for accident conditions.
2. Interview with a Diablo Canyon Power Plant representative to discuss POV
maintenance elements as integrated into plant programs and procedures.
3. Interview with a Diablo Canyon Power Plant representative to discuss maintaining
the design-basis capability of POVs if they have entered a period of extended
operation, if applicable.
III. Information Requested for Inspection Preparation (July 19, 2021)
1. Calculations and/or evaluations associated with the selected POVs, as applicable.
For example, these may include those related to motor-operated valve (MOV) torque
switch setpoint, MOV terminal (degraded) voltage, maximum expected differential
and pressure, torque switch bypass settings, rate of loading, environmental and
process conditions during normal/accident operation, seismic and weak-link analysis,
and pressure locking and thermal binding, etc. (Eight to Twelve specific valves will
be identified and communicated to you prior to July 6, 2021.)
2. Vendor manuals and technical sheets associated with the selected POVs.
3. Provide results (i.e., completed work orders) from the last three performances of
diagnostic (static and/or dynamic) testing and inservice testing (stroke time, leak
rate, etc.) of the selected POVs.
4. Provide performance (or failure) trending data for the selected POVs.
5. List of modifications related to the selected POVs.
2
6. List of corrective action program documents, with a brief description, related to the
selected POVs over the past five years.
7. List of preventive maintenance activities for the selected POVs (valve and actuator).
Include the identification number, title and/or description, and frequency.
8. System training manuals and/or design basis documents associated with the
selected POVs.
9. Piping and instrument diagrams for systems related to the selected POVs.
10. Tours of the rooms in which the selected POVs are installed. If the inspection will be
performed remotely, multiple pictures of selected valve and valve location can be
provided. The pictures must have an orientation reference, a size reference, pictures
of the surrounding environment, and pictures of the nameplates of both valve and
valve operator.
IV. Discussions Requested During the First Inspection Week (July 26, 2021)
1. Brief presentation of POV programs at Diablo Canyon Power Plant.
2. Interviews with representatives to discuss the design basis capability of POVs based
upon the teams review of gathered information.
Inspector Contact Information:
Ronald Kopriva Dustin Reinert Fabian Thomas
Senior Reactor Inspector Reactor Inspector Reactor Inspector
817-200-1104 817-200-1534 817-200-1126
Ron.Kopriva@nrc.gov Dustin.Reinert@nrc.gov Fabian.Thomas@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Ronald Kopriva
1600 East Lamar Blvd.
Arlington, TX 76011-45
3
Valves of Interest List
PLANT DKT SYS ID POV SAFETY VLV Type Size
Diablo 275 Reactor Coolant System - PZR PORV ISOL 1-8000B MOV Gate 3
Canyon 1
Diablo 275 Reactor Coolant System - REACTOR VESSEL 1-8078B SOV Globe 1
Canyon 1 HEAD VENT
Diablo 275 Chemical and Volume Control System - RCP 1-8100 MOV Gate 4
Canyon 1 SEAL WTR RETRN ISOL OC
Diablo 275 Chemical and Volume Control System - CHG 1-8108 MOV Gate 3
Canyon 1 LINE ISOL
Diablo 275 Safety Injection System - CHG INJ TO RCS 1-8801B MOV Gate 4
Canyon 1
Diablo 275 Safety Injection System - SIPP-1 SUCT 1-8923A MOV Gate 6
Canyon 1
Diablo 275 Containment Spray System - RHR HX-1 TO CS- 1-9003A MOV Gate 8
Canyon 1 A HDR
Diablo 275 Component Cooling Water System - RHR HX-2 1-FCV-364 AOV Butterfly 12
Canyon 1 CCW RETURN
Diablo 275 Feedwater System - SG-2 FW ISO 1-FCV-439 MOV Gate 16
Canyon 1
Diablo 275 Fire Protection System - CONT FIREWATER 1-FCV-633 AOV Globe 3
Canyon 1 ISOL OC
Diablo 275 Component Cooling Water System - RCP THM 1-FCV-750 MOV Globe 6
Diablo 275 Residual Heat Removal System - RHR HX-1 1-HCV-638 AOV Ball 8
Canyon 1 OUTLET
Diablo 275 Feedwater System - AUX FP-1 TO SG-3 REG 1-LCV-108 MOV Globe 3
Canyon 1
Diablo 275 Feedwater System - AUX FP-3 TO SG-3 REG 1-LCV-115 HOV Globe 2
Canyon 1
Diablo 275 Reactor Coolant System - PZR PORV 1-PCV-455C AOV Globe 2
Canyon 1
Enclosure 2
PLANT DKT SYS ID POV SAFETY VLV Type Size
Diablo 323 Chemical and Volume Control System - LTDN 2-8152 AOV Globe 2
Canyon 2 LINE ISOL OC
Diablo 323 Residual Heat Removal System - RCS LOOP-4 2-8702 MOV Gate 14
Canyon 2 TO RHR
Diablo 323 Residual Heat Removal System - RHR TO HOT 2-8703 MOV Gate 12
Canyon 2 LEGS- 1, 2 IC
Diablo 323 Residual Heat Removal System - RHR TRAIN 2-8716B MOV Gate 8
Canyon 2 XTIE OC
Diablo 323 Safety Injection System - RWST TO CHG PP 2-8805 MOV Gate 8
Canyon 2 SUCT
Diablo 323 Containment Spray System - CS PP-2 ISOL 2-9001B MOV Gate 8
Canyon 2
Diablo 323 Component Cooling Water System - RCP THM 2-FCV-357 MOV Globe 6
Diablo 323 Component Cooling Water System - CCW HX-2 2-FCV-431 MOV Butterfly 30
Canyon 2 OUT ISOL
Diablo 323 Saltwater System - CCW HX-1 SW INLET 2-FCV-602 AOV Butterfly 24
Canyon 2
Diablo 323 Residual Heat Removal System - RHR PP-1 2-FCV-641A MOV Globe 2
Canyon 2 RECIRC
Diablo 323 Turbine Steam System - AUX FP-1 STM SUP 2-FCV-95 MOV Gate 4
Canyon 2
Diablo 323 Feedwater System - AUX FP-2 TO SG-1 REG 2-LCV-110 HOV Globe 2
Canyon 2
Diablo 323 Turbine Steam System - SG-2 10% ATM DUMP 2-PCV-20 AOV Globe 8
Canyon 2
Diablo 323 Turbine Steam System - SG-3 10% ATM DUMP 2-PCV-21 AOV Globe 8
Canyon 2
Diablo 323 Reactor Coolant System - PZR PORV 2-PCV-456 AOV Globe 2
Canyon 2
2