ML20149K412
| ML20149K412 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/29/2020 |
| From: | Mel Gray NRC Region 1 |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2020010 | |
| Download: ML20149K412 (8) | |
See also: IR 05000220/2020010
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD., SUITE 100
KING OF PRUSSIA, PENNSLYVANIA 19406-2713
May 29, 2020
Mr. Bryan C. Hanson
Senior Vice President, Exelon Generation Company, LLC
President and Chief Nuclear Officer, Exelon Nuclear
Exelon Generation Company, LLC
4300 Winfield Road
Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION - REQUEST FOR INFORMATION FOR
A TRIENNIAL BASELINE DESIGN BASES ASSURANCE INSPECTION (TEAM);
INSPECTION REPORT 05000220/2020010 AND 05000410/2020010
Dear Mr. Hanson:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a Design Bases Assurance Inspection (DBAI) at Nine Mile Point
Nuclear Station. Joe Schoppy, 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 71111.21M, Design Bases Assurance Inspection (Team), dated December 8, 2016
(ADAMS Accession No. ML16340B000).
The inspection will evaluate the capability of risk-significant/low-margin components to function
as designed to support proper system operation. The inspection will also include a review of
selected modifications, operating experience, and as applicable, operator actions.
During a phone conversation on May 21, with Denise Wolniak, Principal Regulatory Engineer,
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 August 31
Onsite weeks: Weeks of October 19 and November 2
The purpose of the information-gathering visit is to meet with members of your staff to identify
risk-significant components, modifications, operator actions, and operating experience items.
Information and documentation needed to support the inspection will also be identified.
Frank Arner, a Region I Senior Risk Analyst, will support Joe Schoppy during the information-
gathering visit to review probabilistic risk assessment data and identify components to be
examined during the inspection.
Experience with previous baseline design/modification inspections of similar depth and length
has shown this type of inspection is resource intensive, both for the NRC inspectors and the
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.
B. Hanson
2
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/or the onsite portions of
the inspection. Insofar as possible, this information should be provided electronically to the lead
inspector. The information request has been divided into two groups:
The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector by August 31. By
September 8, the lead inspector will communicate the initial selected set of components
and modifications.
The second group of documents requested are those items needed to support our in-
office preparation activities. This set of documents, specific to the selected components
and modifications, should be provided to the lead inspector at the Regional Office no
later than October 12. During the in-office preparation activities, the team may identify
additional information needed to support the inspection, and those items will be
communicated directly to Denise Wolniak.
If there are any questions about the inspection or the material requested in the enclosure,
please contact the lead inspector at 610-337-5286 or via e-mail at jgs@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.
Sincerely,
X /RA/
Signed by: Melvin K. Gray
Mel Gray, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 05000220 and 05000410
License Nos. DPR-63 and NPF-69
B. Hanson
3
Enclosure:
Document Request for Design Bases
Assurance Inspection
cc: Distribution via ListServ
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE
RI/DRS
RI/DRS
RI/DRS
NAME
JSchoppy
FArner per email
MGray
DATE
5/21/20
5/26/20
5/29/20
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
Inspection Report: 05000220/2020010 and 05000410/2020010
Onsite Inspection Dates:
October 19 through October 23; and
November 2 through November 6
Inspection Procedure:
Inspection Procedure 71111.21M, Design Bases Assurance
Inspection (Team)
Lead Inspector:
Joe Schoppy, Senior Reactor Inspector
610-337-5286
jgs@nrc.gov
I.
Information Requested for Selection of Components and Modifications
The following information is requested by April 20 to facilitate inspection preparation. Feel
free to contact the lead inspector as soon as possible 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.
1.
The site probabilistic risk analysis (PRA) System Notebook and latest PRA Summary
Document for both units.
2.
Risk ranking of top 250 basic events sorted by Risk Achievement Worth (>/= 1.3) for
both units. Include values for Risk Reduction Worth, Birnbaum Importance, and
Fussell-Vesely (as applicable). Please provide in an excel spreadsheet or other
sortable format and include an understandable definition of the coded basic events.
3.
Risk-ranking of top 100 components from site specific PRA sorted by Large Early
Release Frequency for both units.
4.
If you have an External Events PRA Model, provide the information requested in Item 2
for external events for both units. Provide narrative description of each coded event,
including flood zone description.
5.
List of time-critical and/or risk significant operator actions for both units.
6.
List of emergency and abnormal operating procedures for both units.
7.
If available, any pre-existing evaluation or list of components and associated
calculations with low design margins (e.g., pumps closest to the design limit for flow or
pressure, diesel generator close to design required output, heat exchangers close to
rated design heat removal) for both units.
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
8.
If applicable, copy of any self-assessments and/or Quality Assurance assessments of
low margin structures, systems and components (SSCs) completed since October 5,
2017.
9.
List of available design margins in both the open and closed direction for valves in the
motor-operated valve and air-operated valve programs (related to GL 96-05, looking for
resultant output - matrix of risk vs margin for MOVs and AOVs, as applicable) for both
units.
10. The age and capacity of the safety-related DC batteries for both units.
11. The In-Service Testing (IST) Program Basis document identifying the in-scope valves
and pumps, and the associated IST Program requirements for each component
(e.g., IST valve table identifying category, active/passive function) for both units.
12. Access to IST trend data for the following pumps: U1 core spray, U1 containment spray,
U1 CSS raw water, U1 DG raw water, U1 SLC, U2 HPCS, U2 LPCS, U2 LPCI, U2
RCIC, U2 SLC, and U2 SW pumps. [Note: needed for each discrete component
(e.g. for each SW pump)]
13. Listing of MR (a)(1) systems, date entered into (a)(1) status, and brief description of
why (a)(1).
14. List of MRFFs evaluations completed since October 5, 2017 (include those determined
not to be a MRFF).
15. A copy of the most recent System Health and/or trending reports for the following
systems (as applicable): SR 4KV for both units, SR 600 Vac for both units, U2 HPCS,
U2 RCIC, U2 LPCS, U2 LPCI, U2 SW, U1 emergency cooling system, U1 core spray,
U1 containment spray, U1 CSS raw water, U1 DG raw water, SR 125 Vdc for both
units, SLC for both units, and EDGs for both units.
16. A copy of the most recent Program Health and/or trending reports for the following
programs, as applicable: GL 89-10 (MOVs), GL 89-13, IST, AOVs, breakers, relays.
17. List of open operability evaluations.
18. List of current operator work arounds/burdens.
19. List of permanent plant modifications to SSCs that are field work complete since
October 5, 2017. For the purpose of this inspection, permanent plant modifications
include permanent: plant changes, design changes, set point changes, equivalency
evaluations, suitability analyses, and commercial grade dedications. The list should
contain the number of each document, title (sufficient to understand the purpose of the
modification), revision/date, and the affected system.
20. List of calculation changes (including new calculations) that have been issued for use
since October 5, 2017.
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
21. Corrective Action Program procedure.
22. Procedures addressing the following: modifications, design changes, set point changes,
equivalency evaluations or suitability analyses, commercial grade dedications, and
post-modification testing.
23. List of corrective action documents (open and closed) since October 5, 2017, that
address permanent plant modifications issues, concerns, or processes.
24. Any internal/external self-assessments and associated corrective action documents
generated in preparation for this inspection.
25. Updated Final Safety Analysis Report, Technical Specifications, Technical
Specifications Bases, and Technical Requirements Manual for both units.
26. Electrical simple one-line drawings for U1 & U2 4KV, 600V, 345KV, and 115KV; and U2
13.8KV (11 X 17 preferred).
27. Copy of Exelons internal response to the following NRC Information Notices: 2017-03,
2018-07, and 2019-02.
28. A list of NRC Part 21 Reports, determined to be applicable to NMP, since October 5,
2017.
29. An electronic copy of the following DBDs (if applicable & available): SR 4KV for both
units, SR 600 Vac for both units, U2 HPCS, U2 RCIC, U2 LPCS, U2 LPCI, U2 SW, U1
emergency cooling system, U1 core spray, U1 containment spray, U1 CSS raw water,
U1 DG raw water, SR 125 Vdc for both units, SLC for both units, and EDGs for both
units.
II. Information Requested to Be Available by October 12
This information should be separated for each selected component and modification,
especially if provided electronically (e.g., a folder for each component and modification
named after the component or modification that includes the information requested below).
Items 1 through 11 are associated with the selected components and Item 12 is for the
selected modifications.
1.
List of corrective action documents associated with each selected component since
October 5, 2017
2.
Maintenance history (e.g., corrective, preventive, and elective) associated with each
selected component for the last five years. Identify frequency of preventive
maintenance activities.
3.
Aging Management Program documents and/or License Renewal committed inspection
results applicable to each selected component.
4.
List of calculations associated with each selected component, excluding data files. Pipe
stress calculations are excluded from this request.
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
5.
System Health Report (last completed) and Design Basis Document associated with
each selected component, as applicable.
6.
Access to or copy of vendor manual(s) for each selected component.
7.
List of open temporary modifications associated with each selected component, if
applicable.
8.
Trend data/graphs on the selected components performance since October 5, 2017
(e.g., pump performance including IST, other vibration monitoring, oil sample results).
9.
List of normal operating and alarm response procedures associated with each selected
component.
10. Last completed tests and surveillances for each selected component performed since
October 5, 2017. For those tests and surveillances performed at a periodicity of greater
than three years, provide the latest test performed.
11. Schedule of surveillance testing of selected components that occur during the onsite
inspection weeks.
12. For each selected modification, copies of associated documents such as modification
package, engineering changes, 50.59 screening or evaluation, relevant calculations,
post-modification test packages, associated corrective action documents, design
drawings, and new/revised preventive maintenance requirements.