ML111110841

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Initial Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000361-11-010 and 05000362-11-010
ML111110841
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/21/2011
From: Thomas Farnholtz
Region 4 Engineering Branch 1
To: Peter Dietrich
Southern California Edison Co
References
Download: ML111110841 (8)


See also: IR 05000361/2011010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSIO~J

REGION IV

612 E. LAMAR BLVD., SUITE 400

ARLiNGTON, TEXAS i6011~4005

April 21, 2011

Mr. Peter Dietrich

Senior Vice President and

Chief Nuclear Officer

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION -INITIAL

INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE

COMPONENT DESIGN BASES INSPECTiON NRC INSPECTION

REPORT 05000361/2011010 and 05000362/2011010

Dear Mr. Dietrich

On June 20, 2011, the NRC will begin a triennial baseline Component Design Bases

Inspection at San Onofre Nuclear Generating Station. An eight-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 uperating 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 three weeks of onsite inspection by the team. The inspection

will consist of four NRC inspectors, one NRC inspector in training, and three contractors.

Five inspectors wili focus on mechanical engineering activities, two inspectors wiii focus

on electrical engineering activities, and one inspector will focus on operations. The

current inspection schedule is as follows:

Onsite information gathering visit: Week of May 31, 2011

Preparation Week: June 13-17, 2011

Onsite weeks: June 20-24, 2011; July 4-8, 2011; July 18-23, 2011

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 of tirne will

be needed on the plant-referenced simulator in order to facilitate the development of

operator action-based scenarios. Additional information documentation needed to

support the inspection will be identified during the inspection, including interviews with

engineering managers, engineers, and probabilistic safety assessment staff.

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

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 May 25, 2011. 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 is those items that the team will need access

to during the preparation week in order to finalize the samples to be inspected. 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. Additional requests by

inspectors will be made throughout all three onsite weeks for specific documents needed

to complete the review of that component/selection. 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.

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. 'vVe understand that our

licensing engineer contact for this inspection is David Axline. If there are any questions

about the inspection or the requested materials, please contact the lead inspector at

(817) 860-8104 or via e-mail at ~=~=~=.:-.:~

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.

-2-

Edison

In accordance 10 2.390 of "a

will be made available electronically for public inspection in the NRC

Room or from the Publicly Available Records (PARS) component of NRC's document

system (ADAMS). ADAMS is accessible from the NRC Web site at

Public Reading Room).

sincerelCC

Thomas Farnholtz, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-361,50-362

License Nos. NPF-10, NPF-15

Enclosure:

Component Design Basis Inspection

Document Request

cc w/enclosure:

Distribution via List Serv for San Onofre Nuclear Generating Station

-3-

INFORMATION REQUEST FOR SAN ONOFRE NUCLEAR GENERATING STATION

COMPONENT DESIGN BASES (CDBI) INSPECTION

Inspection Report: 05000361/2011010 and 05000362/2011010

Information Gathering Dates: May 31 - June3, 2011

On-site Inspection Dates: June 20 - 24, 2011

July 4 - 8, 2011

July 18 - 22,2011

Inspection Procedure: IP 71111.21, "Component Design Bases

Inspection"

Lead InspectorlTeam Leader: Ronald A. Kopriva

817-860-8104

Ron.kopirva@nrc.gov

A. Information Requested Prior to the Information Gathering Visit (May 25, 2011)

The following information (Section I of this enclosure) should be sent to the

Region IV office in hard copy or electronic format (ims.certrec.com or compact

disc, preferred), in care of Ronald A. Kopriva, by May 25, 2011 to facilitate the

reduction in the items to be selected for a final list during the preparation week of

June 13, 20111. The inspection team will finalize the selected list during the prep

vJeek using the additional documents requested in Section !! 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(s), 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 (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. excel spreadsheet action basic events or risk ranking

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.

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

calculations with low design margins, (Le., 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. The San Onofre Nuclear Generating Station 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/switch yard supplies

Normal AC power systems

Emergency ACIDC power systems including

120VAC power, and

125VDC!24VDC safety class systems

-2- Enclosure

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.

21. System Description Manuals with simplified drawings of plant systems

22. List of system aCiOnyms.

B. Information Requested to be Available on First Day of Preparation Week (June

13,2011)

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 piOvide 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.

-3- Enclosure

1 Structure, """OTO'rY'I and nr",onT'" in (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.

C. Information Requested to be provided throughout the inspection.

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

team's 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 A. Kopriva

Senior Reactor Inspector

(817) 860-8104

Ron.kopriva@nrc.gov

Mailing Address:

US NRC, Region IV

Attn: Ron Kopriva

612 East Lamar Blvd, Ste 400

Arlington, TX 76011

- 4- Enclosure