ML14027A279

Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000483-14-007

ML14027A279
Person / Time
Site:	Callaway
Issue date:	01/27/2014
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Heflin A Union Electric Co
References
IR-14-007
Download: ML14027A279 (7)

See also: IR 05000483/2014007

Text

UNITE D S TATE S

NUC LEAR RE GULATOR Y C OMMI S SI ON

R E G IO N I V

1600 EAST LAMAR BLVD

AR L I NGTON , TEXAS 7 601 1- 4511

January 27, 2014

Mr. Adam C. Heflin, Senior Vice

President and Chief Nuclear Officer

Union Electric Company

P.O. Box 620

Fulton, MO 65251

SUBJECT: CALLAWAY PLANT - INFORMATION REQUEST FOR NRC TRIENNIAL

BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION

REPORT 05000483/2014007

Dear Mr. Heflin:

On April 14, 2014, the NRC will begin a triennial baseline Component Design Bases Inspection

at the Callaway Plant. A seven-person team will perform this inspection using NRC Inspection

Procedure 71111.21, Component Design Bases Inspection.

The inspection focuses on components and operator actions that have high risk and low design

margins. 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 also be selected for review.

The inspection will include an information gathering site visit by the team leader and a senior

reactor analyst, and 3-weeks of onsite inspection by the team. The inspection will consist of

seven NRC inspectors, of which six will focus on engineering and one on operations. The

current inspection schedule is as follows:

Onsite information gathering visit: Week of March 24, 2014

Onsite weeks: First On-Site Week - April 14-18, 2014

Second On-Site Week - April 28 - May 2, 2014

Third On-Site Week - May 12-16, 2014

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. Additional information and documentation needed to support the inspection will be

identified, including interviews with engineering managers, engineers, and probabilistic safety

assessment staff.

A. Heflin -2-

Our experience with these inspections has shown 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 three 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 March 17, 2014. Insofar as

possible, this information should be provided electronically to the lead inspector. Since the

inspection will be concentrated on high risk/low margin components, calculations associated

with your list of high risk components 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 are those items that the team will need access to

when onsite and after the inspection samples are selected. The third group 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. It is important that all of these documents are up to date and

completed in order to minimize the number of additional documents requested during the

preparation and/or the 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 Mr. Ronald Kopriva. We understand that our licensing

engineer contact for this inspection is Mr. Steve Petzel. If there are any questions about the

inspection or the requested materials, please contact the lead inspector at (817) 200-1104 or via

e-mail at Ron.Kopriva@nrc.gov.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," 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 NRCs document system (ADAMS).

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: 50-483

License: NPF-30

Enclosure:

Component Design Basis Inspection

Document Request

cc w/ enclosure: Electronic Distribution for Callaway Plant

ML14027A279

SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials TRF

Publicly Avail Yes No Sensitive Yes No Sens. Type Initials TRF

RIV:SRI:DRS/EB1 BC/EB1

RKopriva TFarnholtz

/RA/ TRF for /RA/

01/23/2014 01/23/2014

INFORMATION REQUEST FOR CALLAWAY PLANT

COMPONENT DESIGN BASES (CDBI) INSPECTION

Inspection Report: 05000483/2014007

Information Gathering Dates: March 24-28, 2014

On-site Inspection Dates: First Week - April 14-18, 2014

Second Week - April 28 - May 2, 2014

Third Week - May 12-16, 2014

Inspection Procedure: IP 71111.21, Component Design Bases

Inspection

Lead Inspector/Team Leader: Ronald Kopriva

817-200-1104

Ron.Kopriva@nrc.gov

I. Information Requested Prior to the information Gathering Visit

The following information is requested by March 17, 2014, or sooner, to facilitate

inspection preparation. If you have any questions regarding this information,

pleased call the lead inspector as soon as possible. (Please provide the

information electronically in pdf files, Excel, or other searchable formats. 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 boiling water reactor

technology.)

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

including importance measures sorted by risk achievement worth (RAW)

and Fussell-Vesely (FV) from your internal events probabilistic risk

assessment (PRA). Include basic events with RAW value of 1.3 or

greater.

2. Provide a list of the top 500 cut-sets from your PRA.

3. Copies of PRA system notebooks, and the latest PRA summary

document.

4. An excel spreadsheet of PRA human action basic events or risk ranking

of operator actions from your site specific PSA sorted by RAW and FV.

Provide copies of your human reliability worksheets for these items.

5. If you have an external events or fire PSA model, provide the information

requested in items 1-4 for external events and fire.

-1- Enclosure

6. Any pre-existing evaluation or list of components and associated

calculations with low design margins, (i.e., 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, etc.).

7. List of high risk maintenance rule systems/components and functions;

based on engineering or expert panel judgment.

8. A list of operating experience evaluations for the last 2 years.

9. A list of all time-critical operator actions in procedures.

10. A list of permanent and temporary modifications sorted by component

identified in Item 1.

11. List of current operator work arounds/burdens.

12. A list of the design calculations, which provide the design margin

information for components included in Item 1. (Calculations should be

available during the information gathering visit.)

13. List of root cause evaluations associated with component failures or

design issues initiated/completed in the last 5 years.

14. Current management and engineering organizational charts.

15. Callaway Plant IPEEE, if available electronically.

16. Mechanical piping drawings for:

Engineered safety features

Emergency core cooling Systems

Emergency diesel generators

17 Electrical one-line drawings for:

Offsite power/switchyard supplies

Normal ac power systems

Emergency ac/dc power systems including

120Vac power, and

125Vdc/24Vdc safety class systems

18. List of any common-cause failures of components in the last 3 years.

19. An electronic copy of the Design Bases Documents.

20. An electronic copy of the System Health notebooks.

-2-

II. Information Requested to be Available on First Day of Inspection

(April 14, 2014)

1. List of condition reports (corrective action documents) associated with

each of the selected components for the last 5 years.

2. The corrective maintenance history associated with each of the selected

components for the last 2 years.

3. Copies of calculations associated with each of the selected components

(if not previously provided), excluding data files. Please review the

calculations and also provide copies of reference material (such as

drawings, engineering requests, and vendor letters).

4. Copies of operability evaluations associated with each of the selected

components and plans for restoring operability, if applicable.

5. Copies of selected operator work-around evaluations associated with

each of the selected components and plans for resolution, if applicable.

6. Copies of any open temporary modifications associated with each of the

selected components, if applicable.

7. Trend data on the selected electrical/mechanical components

performance for last 3 years (for example, pumps performance including

in-service testing, other vibration monitoring, oil sample results, etc., as

applicable).

8. A copy of any internal/external self-assessments and associated

corrective action documents generated in preparation for the inspection.

9. A copy of engineering/operations related audits completed in the last

2 years.

10. List of motor operated valves (MOVs) in the program, design margin and

risk ranking.

11. List of air operated valves (AOVs) in the valve program, design and risk

ranking.

12. Structure, system and components in the Maintenance Rule (a)(1)

category.

13. Site top 10 issues list.

14. Procedures used to accomplish operator actions associated with the

basic events in your PRA.

15. List of licensee contacts for the inspection team with pager or phone

numbers.

-3-

III. Information Requested to be provided throughout the inspection.

1. Copies of any corrective action documents generated as a result of the

teams questions or queries during this inspection.

2. 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).

3. Reference materials (available electronically and as needed during all

onsite weeks):

General set of plant drawings

IPE/PRA report

Procurement documents for components selected

Plant procedures (normal, abnormal, emergency, surveillance, etc.)

Technical Specifications

Updated Final Safety Analysis Report

Vendor manuals

Inspector Contact Information:

Ronald Kopriva

Senior Reactor Inspector

(817) 200-1104

Ron.Kopriva@nrc.gov

Mailing Address:

RONALD KOPRIVA

US NRC, REGION IV

1600 E LAMAR BLVD

ARLINGTON TX 76011

-4-