ML081130702

IR 05000361-08-010, IR 05000362-08-010, 06/09/2008, San Onofre Generating Station - Information Request for NRC Triennial Baseline Component Design Bases Inspection

ML081130702
Person / Time
Site:	San Onofre
Issue date:	04/22/2008
From:	Russ Bywater Division of Reactor Safety IV
To:	Rosenblum R Southern California Edison Co
References
IR-08-010
Download: ML081130702 (9)

See also: IR 05000361/2008010

Text

UNITED STATES

NU CLE AR RE GU LATOR Y C O M M I S S I O N

R EGI ON I V

611 R YAN PLAZA D R IV E, SU ITE 400

AR LI N GTON , TEXAS 76011-4005

April 22, 2008

Richard M. Rosenblum

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: SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION -

INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT

DESIGN BASES INSPECTION (NRC INSPECTION REPORT

05000361/2008010;050000362/2008010)

Dear Mr. Rosenblum:

On June 9, 2008, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial baseline

Component Design Bases Inspection at the San Onofre Nuclear Generating Station. A team of

six inspectors plus a team leader will perform this 3-week inspection. This inspection will be

performed in accordance with revised NRC Baseline Inspection Procedure 71111.21 and

replaces the biennial Safety System Design and Performance Capability inspection.

The component design bases inspection focuses on components that have high risk and low

design margins. The components to be reviewed during this baseline inspection will mainly be

identified during an information gathering visit and during the subsequent in-office preparation

week. In addition, a number of risk significant operator actions and operating experience

issues, associated with the component samples, will also be selected for review.

The inspection will be 4-weeks onsite, including the information gathering site visit and 3-weeks

of onsite inspection. The inspection will consist of six NRC inspectors, of which five will focus

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

Onsite information gathering visit: Week of June 9, 2008

Onsite weeks: June 23, July 7 and July 14, 2008

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 a member of your probabilistic risk analyst staff. Additional information

and documentation needed to support the inspection will be identified. A Region IV senior

reactor analyst was requested and may accompany the inspection team during the information

gathering visit to review probabilistic risk assessment data and assist in identifying risk

significant components, which will be reviewed during the inspection.

Experience with previous baseline design inspections of similar depth and length has shown

that these inspections 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 12, 2008. Insofar as possible, this information should be

provided electronically to the lead inspector. Since the inspection will be concentrated on high

risk/low margin component, calculations associated with your list of high risk components

should be available for the inspectors 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 components 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. Kelly Clayton. We understand that our licensing

engineer contact for this inspection is Mr. Mike McBrearty. If there are any questions about the

inspection or the requested materials, please contact the lead inspector at (817) 860-8216 or via

e-mail at kelly.clayton@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/

Russ Bywater, Chief

Engineering Branch One

Division of Reactor Safety

Dockets: 50-361; 50-362

Licenses: NPF-10; NPF-15

Enclosure:

Component Design Basis Inspection

Document Request

cc w/enclosure:

Mr. Ross T. Ridenoure

Vice President and Site Manager

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

Chairman, Board of Supervisors

County of San Diego

1600 Pacific Highway, Room 335

San Diego, CA 92101

Gary L. Nolff

Assistant Director-Resources

City of Riverside

3900 Main Street

Riverside, CA 92522

Mark L. Parsons

Deputy City Attorney

City of Riverside

3900 Main Street

Riverside, CA 92522

Dr. David Spath, Chief

Division of Drinking Water and

Environmental Management

California Department of Health Services

850 Marina Parkway, Bldg P, 2nd Floor

Richmond, CA 94804

Michael J. DeMarco

San Onofre Liaison

San Diego Gas & Electric Company

8315 Century Park Ct. CP21G

San Diego, CA 92123-1548

Director, Radiological Health Branch

State Department of Health Services

P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414

Mayor

City of San Clemente

100 Avenida Presidio

San Clemente, CA 92672

James D. Boyd, Commissioner

California Energy Commission

1516 Ninth Street (MS 34)

Sacramento, CA 95814

Douglas K. Porter, Esq.

Southern California Edison Company

2244 Walnut Grove Avenue

Rosemead, CA 91770

A. Edward Scherer

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

Mr. Steve Hsu

Department of Health Services

Radiologic Health Branch

MS 7610, P.O. Box 997414

Sacramento, CA 95899-7414

Mr. James T. Reilly

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

Chief, Radiological Emergency Preparedness Section

National Preparedness Directorate

Technological Hazards Division

Department of Homeland Security

1111 Broadway, Suite 1200

Oakland, CA 94607-4052

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

DRP Director (Dwight.Chamberlain@nrc.gov)

DRS Director (Roy.Caniano@nrc.gov)

DRS Deputy Director (Troy.Pruett@nrc.gov)

Senior Resident Inspector (Clyde.Osterholtz@nrc.gov)

Branch Chief, DRP/D (Michael.Hay@nrc.gov)

Senior Project Engineer, DRP/D (Greg.Werner@nrc.gov)

Senior Project Engineer, DRP/D (Geoff.Miller@nrc.gov)

Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

NRR CDBI Coordinator, (Donald.Norkin@nrc.gov)

Only inspection reports to the following:

DRS STA (Dale.Powers@nrc.gov)

J. Adams, OEDO RIV Coordinator (John.Adams@nrc.gov)

ROPreports

SO Site Secretary (Heather.Hutchinson@nrc.gov))

SUNSI Review Completed: _Yes_ ADAMS: Yes No Initials: _KDC _____

Publicly Available Non-Publicly Available Sensitive Non-Sensitive

S:DRS\REPORTS\SO CDBI FRI ltr-KDC ML

RIV:RI:DRS/EB1 BC/EB1

KDClayton RBywater

/RA/ /RA/

04/22/08 04/22/08

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

INFORMATION REQUEST FOR SAN ONOFRE NUCLEAR GENERATING STATION

COMPONENT DESIGN BASES INSPECTION (CDBI)

Inspection Report: 05000361/2008010; 05000362/2008010

Information Gathering Dates: June 9 - 11, 2008

On-site Inspection Dates: June 23 - 27 2008, July 7 through July 18, 2008

Inspection Procedure: IP 71111.21, Component Design Bases

Inspection

Lead Inspector/Team Leader: Kelly Clayton

817-860-8216

kelly.clayton@nrc.gov

I. Information Requested Prior to the information Gathering Visit

The following information is requested by May 12, 2008, 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 pressurized water reactor technology).

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

including importance measures risk achievement worth, Fusselly-Veseley

(RAW, FV) from your internal events probabilistic risk assessment (PRA),

including risk ranking of top 50 components from your site-specific PRA

sorted by (RAW). Include values for Birnbaum Importance, risk reduction

worth (RRW), and Fussell-Veseley FV (as applicable).

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

3. Copies of PRA system notebooks.

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 1-3 for external events and fire.

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. Any pre-existing evaluation or list of components and calculations with

low design margins (i.e., pumps closest to the design limit for flow or

pressure, diesel generators close to design required output, heat

exchangers close to rated design heat removal, etc.).

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. 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/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.

II. Information Requested to be Available on First Day of Inspection (June 23,

2008)

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 he 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. Provide list of PRA assumptions regarding operator actions and the

associated procedures.

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

numbers.

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:

Kelly Clayton

Senior Reactor Inspector

(817) 860-8216

kelly.clayton@nrc.gov

Mailing Address:

US NRC, Region IV

Attn: Kelly Clayton

611 Ryan Plaza Dr, Ste 400

Arlington, TX 76011