ML18344A577

Notification of NRC Design Bases Assurance Inspection (05000498/2019010 and 05000499/2019010) and Initial Request for Information

ML18344A577
Person / Time
Site:	South Texas
Issue date:	12/10/2018
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Gerry Powell South Texas
References
IR 2019010
Download: ML18344A577 (7)

See also: IR 05000498/2019010

Text

December 10, 2018 Mr. G. T. Powell

President and Chief Executive Officer

STP Nuclear Operating Company

P.O. Box 330

Wadsworth, TX 77483

SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION

- NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION

(TEAMS) (05000 498/201 9 0 10 and 05000 499/201 9 0 10) AND INITIAL REQUEST FOR INFORMATION

Dear Mr. Powell: On March 25, 201 9, the Nuclear Regulatory Commission (NRC) will begin a

triennial baseline Design Bases Assurance Inspection at the

South Texas Project Electric Generating Station

. A six-person team will perform this inspection using NRC Inspection Procedure

71111 , Attachment 21M

"Design Bases Assurance Inspection

(Teams)." The inspection focuses on the maintenance of component design bases

and modifications made to structures, systems, and components. The samples reviewed during this inspection will be identified during an information gathering visit and during the subsequent in

-office preparation week. In addition, a number of operating experience issues will be selected for review. The inspection will include an information gathering site visit by the team leader

and a risk analyst, and two weeks of onsite inspection by the team. The inspection will consist of three NRC inspectors and two contractors, of which four will focus on engineering and

one on operations. The current inspection schedule is as follows:

Onsite Information Gathering Visit:

March 4-8, 201 9 Preparation Week:

March 18-22, 201 9 Onsite W eek (s): March 25-29, 201 9 and April 8-12, 201 9 The purpose of the information gathering visit is to meet with members of your staff to identify potential risk

-significant components and operator actions. The lead inspector will also request a tour of the plant with members of your operations staff and

probabilistic safety assessment staff. During the onsite weeks, several days and administration

will be needed on the plant

-referenced simulator in order to facilitate the development of operator action

-based scenarios. Additional information and documentation needed to support the inspection will be identified during the inspection, including interviews with engineering managers, engineers, and probabilistic safety assessment staff.

G. T. Powell

2 Our experience with these inspections has shown that they are extremely 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, we have enclosed a request for information needed for the inspection. The request has been divided into two groups. The first group lists information necessary for the information gathering visit and for general preparation. This information should be available to the regional office no later than February 25, 2019, unless otherwise stated. If possible, this information should be provided electronically to the lead inspector. Since the inspection will be concentrated on high risk/low margin components and modifications, calculations associated with your list of high risk components and

modifications should be available to review during the information gathering visit to assist in our selection of components based on available design margin.

The second group of documents requested lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. An additional request will be made by the team during the preparation week once the specific components and modifications have been selected. Additional requests by inspectors will also be made throughout the onsite weeks for specific documents needed to complete the review. 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 onsite portions of the inspection. In order 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

Ronald A. Kopriva. We understand that our licensing engineer contact for this inspection is

Mr. Rafael Gonzale

s. If there are any questions about the inspection or the requested materials, please contact the lead inspector by telephone at 817-200-11 04 or by e-mail at Ron.Kopriva@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.

In accordance with Title 10 of the Code of Federal Regulations

(CFR) 2.390 of the NRC's

"Agency Rules of Practice

and Procedure," a copy of this letter will be made

available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).

G. T. Powell

3 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html

(the Public Electronic Reading Room).

Sincerely, /RA/ Thomas R. Farnholtz, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-498; 50-499 License Nos

.: NPF-76 and NP F-80 Enclosure:

Design Bases Assurance

Inspection (Teams) Request for Information

ML18344A577

SUNSI Review:

ADAMS: Non-Publicly Available

Non-Sensitive Keyword: By: RAK Yes No Publicly Available

Sensitive

NRC-002 OFFICE SRI:EB1 C:PB B C:EB1 NAME RKopriva NTaylor TFarnholtz

SIGNATURE /RA/ /RA/ /RA/ DATE 12/10/18 12/10/18 12/10/2018

Enclosure Initial Request

for Information

Design Bases Assurance Inspection

(Teams) South Texas Project Electric Generating Station

Inspection Report:

05000 498/201 9 01 0 , 05000 499/201 9 01 0 Information Gathering Dates:

March 4-8, 2019 Inspection Dates:

March 25-29, 2019 , and April 8-12, 201 9 Inspection Procedure:

IP 71111 , Attachment 21 M, "Design Bases Assurance Inspection

(Teams)" Lead Inspector:

Ronald A. Kopriva, Senior Reactor Inspector

I. Information Requested Prior to

Information Gathering Visit

(February 25, 201 9) The following information (Section I of this enclosure) should be sent to the Region IV office in hard copy or electronic format to the attention

of Ron Kopriva

by February 25, 201 9 , to facilitate the reduction in the items to be selected for a final list during the preparation week , March 18-22, 201 9. The inspection team will finalize the selected list during the prep week using the additional documents requested in Section I of 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 inspector

and provide subject documentation during the first day of the onsite inspection.

1. An Excel spreadsheet of equipment basic events (with definitions)

, including importance measures sorted

by risk achievement worth

and Fussell-Vesely from your internal events probabilistic risk assessment.

Include basic events with risk achievement worth value of 1.3 or greater.

2. A list of the top 50 cut

-sets from your PRA.

3. Copies of probabilistic risk assessment "system notebooks" and the latest probabilistic risk assessment summary document.

4. An Excel spreadsheet of probabilistic risk assessment human action basic events or risk ranking of operator actions from your site

-specific P

RA sorted by risk achievement worth and Fussell

-Vesely. Provide copies of your human reliability worksheets for these items.

5. If you have an external events or fire P RA model, provide the information requested in items 1

-4 for external events and fire.

2 6. A list of high large early release frequency

impact events and associated components.

7. Structure s, system s, and components in the Maintenance Rule (a)(1) category.

8. A list of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.

9. Site top 10 issues list, if available

. 10. Any pre-existing list of components and associated calculations with low design margins. 11. A list of operating experience evaluations for the last 3 years.

12. A list of all time

-critical operator actions in procedures.

13. A list of current "operator work arounds/burdens."

14. Procedures, including emergency and abnormal, used to accomplish operator actions associated with the basic events credited in

your PRA. 15. List s of permanent and temporary modifications performed in the past 5

years to structures, systems, and components sorted by component identified in Item 1.

16. List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years.

17. A list of any common

-cause failures of components in the last 3 years.

18. A copy of any internal/external self

-assessments and associated corrective action documents generated in preparation for this

inspection.

19. A copy of engineering/operations

-related audits completed in the last 2 years.

20. Electronic copies of the Technical Specifications, Technical Specifications Bases, and the Final Safety Analysis Report, as updated

. 21. A copy of the Individual Plant Examination of External Events, if available electronically.

22. One-line drawings of emergency core cooling system, ultimate heat sink, emergency feedwater, and safety-related electrical systems.

23. A copy of condition reports associated with inspection findings from the previous NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).

24. A list of system designators.

25. A list of licensee contacts for the inspection team with phone numbers.

26. A copy of the current management and engineering organizational charts.

3 II. Information Requested to be provided throughout the inspection.

1. Electronic copies of the design bases documents for selected components and modifications

. 2. Electronic copies of the system health notebooks

for selected components and modifications

. 3. A list of the design calculations that

provide the design margin information for

selected components.

(Calculations for selected components should be available during the information gathering visit

.) 4. Calculations and drawings associated with selected components.

5. Modification d

ocumentation

associated with modifications selected from Item I.15, this includes:

a. Post-modification testing, including performance characteristics affected, assumptions, and acceptance criteria associated with modifications selected. b. Updated maintenance and surveillance procedures associated with modifications.

c. Updated operation procedures and training plans associated with the

modifications.

6. Copies of any corrective action documents generated as a result of the team's questions or queries during this inspection.

7. Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the inspection to each team member).

Inspector Contact Information:

Ronald A. Kopriva

Wes Cullum

Shiattin Makor

Senior Reactor Inspector

Reactor Inspector

Reactor Inspector

817-200-11 04 817-200-1 563 817-200-1 507 Ron.Kopriva@nrc.gov Wes.Cullum@nrc.gov Shiattin.Makor@nrc.gov Richard Smith

Mailing Address:

Nuclear Systems Engineer

U.S. NRC, Region IV

817-200-1472 Attn: Ronald A. Kopriva

Rich.Smith@nrc.gov

1600 East Lamar Blvd.

Arlington, TX 76011

-4511