ML24128A129
| ML24128A129 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  (NPF-057) |
| Issue date: | 05/07/2024 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| References | |
| IR 2024010 | |
| Download: ML24128A129 (1) | |
See also: IR 05000354/2024010
Text
May 7, 2024
Charles McFeaters
President and Chief Nuclear Officer
P.O. Box 236
Hancocks Bridge, NJ 08038
SUBJECT: HOPE CREEK GENERATING STATION - INFORMATION REQUEST FOR
QUADRENNIAL BASELINE COMPREHENSIVE ENGINEERING TEAM
INSPECTION; NOTIFICATION TO PERFORM INSPECTION 05000354/2024010
Dear Charles McFeaters:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a Comprehensive Engineering Team Inspection (CETI) at Hope
Creek Generating 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, Comprehensive Engineering Team Inspection (CETI), dated
January 1, 2023 (ADAMS Accession No. ML19084A030). This inspection combines elements of
the Design Basis Assurance Inspection (Teams), the Heat Exchanger/Sink Performance
inspection (71111.07T), and the Evaluations of Changes, Tests and Experiments inspection
(71111.17).
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 Teams meeting on November 28, 2023, with Harry Balian, PSEG Site Regulatory
Compliance, 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 5, 2024
Onsite weeks: Weeks of December 2, 2024 and December 9, 2024
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.
C. McFeaters
2
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. 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/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 5, 2024. By
August 12, 2024, the lead inspector will communicate the initial selected set of
components, modifications, 50.59 screenings, and operating experience samples.
The second group of documents requested is 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 November 18, 2024. 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 Harry Balian.
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 email 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.
C. McFeaters
3
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,
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
Docket No. 05000354
License No. NPF-57
Enclosure:
Document Request for Comprehensive
Engineering Team Inspection
cc w/encl: Distribution via ListServ
Melvin K.
Gray
Digitally signed by Melvin
K. Gray
Date: 2024.05.07
13:10:28 -04'00'
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE
RI/DORS
RI/DORS
RI/DORS
NAME
JSchoppy
FArner
MGray
DATE
5/2/2024
5/2/2024
5/7/2024
DOCUMENT REQUEST FOR COMPREHENSIVE ENGINEERING TEAM INSPECTION
Enclosure
Onsite Inspection Dates:
December 2, 2024 through December 6, 2024; and
December 9, 2024 through December 13, 2024
Inspection Procedure:
Inspection Procedure 71111.21M, Comprehensive Engineering
Team Inspection (CETI)
Lead Inspector:
Joe Schoppy, Senior Reactor Inspector
(610) 337-5286
jgs@nrc.gov
Inspection Report: 05000354/2024010
I.
Information Requested for Sample Selection Process
The following information is requested by August 5, 2024, 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, Word, Excel, or other searchable format. 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 Hope Creek.
2. Risk ranking of top 250 basic events sorted by Risk Achievement Worth (>/= 1.3). 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.
4. If you have an External Events PRA Model, provide the information requested in Item 2
for external events. Provide narrative description of each coded event, including flood
zone description.
5. List of time-critical and/or risk-significant operator actions.
6. List of emergency and abnormal operating procedures.
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).
8. If applicable, copy of any self-assessments and/or Quality Assurance assessments of
low-margin structures, systems, and components (SSCs), completed in the last 3 years.
2
9. List of available design margins in both the open and closed direction for valves in the
motor-operated valve (MOV) and air-operated valve (AOV) programs (related to GL 96-
05, looking for resultant output - matrix of risk vs margin for MOVs and AOVs, as
applicable).
10. The age and capacity of the safety-related (SR) DC batteries.
11. The In-Service Testing Program (IST) 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).
12. Listing of Maintenance Rule (a)(1) systems, date entered into (a)(1) status, and brief
description of why (a)(1).
13. List of maintenance rule functional failure (MRFF) evaluations completed since
September 1, 2021 (include those determined not to be a MRFF).
14. A copy of the most recent System Health and/or trending reports for the following
systems (as applicable): SR 4KV, High-Pressure Coolant Injection, Residual Heat
Removal, Standby Service Water, Safety Auxiliaries Cooling System, SR 125 Vdc,
Standby Liquid Control, and Emergency Diesel Generators.
15. 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.
16. List of open operability evaluations.
17. List of current operator work arounds and operator burdens.
18. List of Root Cause Evaluations associated with SSC failures or design issues
initiated/completed in the last three years.
19. List of permanent plant modifications to SSCs that are field work complete since
September 1, 2021. 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 September 1, 2021.
21. Copy of 50.59 program & corrective action program procedures.
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 notifications initiated since September 1, 2021, that address
permanent plant modifications and/or 50.59 issues, concerns, or processes.
3
24. A copy of any internal or external self-assessments performed in preparation for this
inspection.
25. Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications
Bases, and Technical Requirements Manual, as applicable.
26. Electrical simple one-line drawings for 4KV, 480 V, 500KV, & 13.8KV (11 X 17
preferred).
27. Copy of PSEGs internal response to the following NRC Information Notices: 2019-02,
2018-07, and 2006-31.
28. A list of NRC Part 21 Reports, determined to be applicable to Hope Creek, since
September 1, 2021.
29. An electronic copy of the following Design Basis Documents (if applicable & available):
SR 4KV, High-Pressure Coolant Injection, Residual Heat Removal, Service Water,
Safety Auxiliaries Cooling System, SR 125 Vdc, and Emergency Diesel Generators.
30. List of all 50.59 applicability reviews, screenings, and evaluations completed since
December 1, 2020. [Note: if six or less 50.59 safety evaluations, please include
electronic copy of all evaluations.]
31. Copy of PSEGs most recent Changes, Test, and Experiments summary report
[50.59(d)(2)].
II. Information Requested to Be Available by November 18, 2024
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 for the
last three years.
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 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.
5.
System Health Report (last completed) and Design Basis Documents associated with
each selected component.
6.
Access to or copy of vendor manual(s) for each selected component.
4
7.
List of open temporary modifications associated with each selected component, if
applicable.
8.
Trend data/graphs on the selected components performance for the last three years
(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 during
the last three years. 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.
13. A copy of the evaluation or screening document for each of the selected 50.59
evaluation/screens. A copy of the modification package if the evaluation/screen pertains
to a modification.