ML24136A062

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Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010
ML24136A062
Person / Time
Site: Beaver Valley
Issue date: 05/15/2024
From: Mel Gray
Division of Operating Reactors
To: Blair B
Vistra Operations Company
References
IR 2024010
Download: ML24136A062 (1)


See also: IR 05000334/2024010

Text

May 15, 2024

Barry Blair

Site Vice President

Vistra Operations Company, LLC

Beaver Valley Power Station

P.O. Box 4 - Route 168

Shippingport, PA 15077-0004

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION

REQUEST FOR QUADRENNIAL BASELINE COMPREHENSIVE

ENGINEERING TEAM INSPECTION; NOTIFICATION TO PERFORM

INSPECTION 05000334/2024010 AND 05000412/2024010

Dear Barry Blair:

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 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 71111.21M, 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.

In a telephone call between Paul Cataldo and Hope Gilliam, Beaver Valley Regulatory

Compliance, on May 8, 2024, we confirmed arrangements for an information-gathering and the

two-week onsite inspection. The schedule is as follows:

Information-gathering week: Week of June 17, 2024

Onsite weeks: Weeks of July 15, 2024, and July 29, 2024

The purpose of the information-gathering week is to have discussions 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. Carey Bickett, a Region I Senior Risk Analyst, will support Paul Cataldo during the

information-gathering week to review probabilistic risk assessment data and identify

B. Blair

2

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. 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 June 7, 2024. By

June 24, 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 and on-site activities. This set of documents, specific to the selected

components and modifications, should be provided to the lead inspector no later than

July 8, 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 Hope Gilliam, and selected points-of-contact identified by Hope, to facilitate

the requests.

If there are any questions about the inspection or the material requested in the enclosure,

please contact the lead inspector at (610) 337-5365 or via email at pcc1@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.

B. Blair

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 (10 CFR), Part 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 Comprehensive

Engineering Team Inspection

cc w/encl: Distribution via ListServ

Melvin K.

Gray

Digitally signed by Melvin

K. Gray

Date: 2024.05.15

12:14:44 -04'00'

ML24136A062

SUNSI Review

Non-Sensitive

Sensitive

Publicly Available

Non-Publicly Available

OFFICE

RI/DORS

RI/DORS

NAME

PCataldo

MGray

DATE

5/15/2024

5/15/2024

DOCUMENT REQUEST FOR COMPREHENSIVE ENGINEERING TEAM INSPECTION

Enclosure

Onsite Inspection Dates:

July 15, 2024 through July 19, 2024; and

July 29, 2024 through August 2, 2024

Inspection Procedure:

Inspection Procedure 71111.21M, Comprehensive Engineering

Team Inspection (CETI)

Lead Inspector:

Paul Cataldo, Senior Reactor Inspector

PCC1@nrc.gov

(610) 337-5365

Inspection Report: 05000334/2024010 and 05000412/2024010

I.

Information Requested for Sample Selection Process

The following information is requested by June 7, 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 to facilitate ease of use; and, if possible, identifiable using the query function

in eDocs. 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 suitable 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.

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.

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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) for both units.

10. The age and capacity of the safety-related batteries for both units.

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) for both units.

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)/maintenance preventable functional

failure (MPFF) evaluations completed since November 2020 (include those determined

not to be a MRFF/MPFF).

14. A copy of the most recent System Health and/or trending reports for the following

systems (as applicable):

Unit 1

Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution, River

Water/Service Water, Class 1E 125 VDC System, Auxiliary Feedwater

System, Safety Injection (High and Low Pressure) Systems, Chemical and

Volume Control Systems, Containment/Quench Spray System, Recirculation

Spray System, Component Cooling Water System, Alternate AC Source and

Emergency Diesel Generators.

Unit 2

Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution,

Service Water System, Class 1E 125 VDC, Auxiliary Feedwater

System, Safety Injection (High and Low Pressure) Systems,

Chemical and Volume Control System, Containment/Quench

Spray System, Residual Heat Removal System, Component

Cooling Water System, Alternate AC Source and Emergency

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 for both units.

17. List of Root Cause Evaluations associated with SSC failures or design issues

initiated/completed since November 2020.

18. List of permanent plant modifications to SSCs that are field work complete since

November 2020. For 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

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each document, title (sufficient to understand the purpose of the modification),

revision/date, and the affected system.

19. List of calculation changes (including new calculations) that have been issued for use

since November 2020.

20. List of corrective action documents initiated since November 2020, that address

permanent plant modifications and/or 50.59 issues, concerns, or processes.

21. A copy of any internal or external self-assessments performed in preparation for this

inspection.

22. Updated Final Safety Analysis Report, Technical Specifications, and Technical/Licensing

Requirements Manual for both units.

23. Electrical simple one-line drawings for Units 1 and 2 - from offsite power to 4.16KV and

125 VDC.

24. A list of NRC Part 21 Reports, determined to be applicable to the Beaver Valley Units 1

and 2 since November 2020.

25. List of all 50.59 applicability reviews, screenings, and evaluations completed since

November 2020. [Note: if six or less 50.59 safety evaluations, please include electronic

copies of all evaluations.]

26. Copy of Beaver Valleys most recent Changes, Test, and Experiments summary report

[50.59(d)(2)] for both units.

27. Copies of Fleet/Plant Program documents and procedures for the following: In-Service

Testing, Maintenance Rule, Operating Experience, Corrective Action Program, Material

Degradation, Self-Assessments, River Water and Service Water Reliability (GL-89-13),

Surveillance Frequency Control Program, Time-Critical and Time-Sensitive Operation

Actions, and Engineering Changes or applicable Design Control (10 CFR 50, Appendix

B, Criterion III) including post-modification testing, setpoint changes, associated 10 CFR

50.59 applicability/screening/evaluation procedures, and commercial grade dedications.

II. Information Requested to Be Available by July 8, 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, Item 12 is for the selected

modifications, and Item 13 is associated with screens/evaluations.

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.

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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.

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.