ML051570033

Notification of Safety System Design & Performance Capability Inspection, IR 05000424/05-006 & IR 05000425/05-006

ML051570033
Person / Time
Site:	Vogtle
Issue date:	06/03/2005
From:	Ogle C NRC/RGN-II/DRS/EB
To:	Gasser J Southern Nuclear Operating Co
References
IR-05-006
Download: ML051570033 (6)

See also: IR 05000424/2005006

Text

June 3, 2005

Southern Nuclear Operating Company, Inc.

ATTN: Mr. J. T. Gasser, Vice President

P. O. Box 1295

Birmingham, AL 35201-1295

SUBJECT: NOTIFICATION OF VOGTLE NUCLEAR PLANT - SAFETY SYSTEM DESIGN

AND PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION

REPORT 50-424,425/2005006

Dear Mr. Gasser:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a safety system design and performance capability inspection at

your Vogtle Nuclear Plant during the weeks of August 15-19, 2005 and August 29-September

2, 2005. A team of five inspectors will perform this inspection. The inspection team will be led

by Mr. Caswell Smith, a Senior Reactor Inspector from the NRC Region II Office. This biennial

inspection will be conducted in accordance with baseline inspection program Attachment

71111.21, Safety System Design and Performance Capability.

The inspection will evaluate the capability of installed plant equipment to detect and respond to

a loss of coolant accident. Procedures which direct the mitigating actions for this event will also

be evaluated.

During a telephone conversation on May 26, 2005, Mr. Smith of my staff, and

Mr. Ken Lowery of your staff, confirmed arrangements for an information gathering site visit and

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

• Information gathering visit: Week of July 18, 2005

• Onsite inspection weeks: August 15 and August 29, 2005.

The purpose of the information gathering visit is to obtain information and documentation

outlined in the enclosure needed to support the inspection. Mr. Walter Rogers, a Region II

Senior Reactor Analyst, may accompany Mr. Smith during the information gathering visit to

review probabilistic risk assessment data and identify risk significant components which will be

examined during the inspection. Please contact Mr. Smith prior to preparing copies of the

materials listed in the enclosure. The inspectors will try to minimize your administrative burden

by specifically identifying only those documents required for inspection preparation.

During the information gathering visit, the team leader will also discuss the following inspection

support administrative details: office space; specific documents requested to be made

available to the team in their office space; arrangements for site access; and the availability of

knowledgeable plant engineering and licensing personnel to serve as points of contact during

the inspection.

SNOC 2

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact Mr. Smith at (404) 562-4630 or me at

(404) 562-4605.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publically 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/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-424 and 50-425

License Nos.: NPF-68 and NPF-81

Enclosure: Information Request for the Safety System Design and

Performance Capability Inspection

cc w/encl: (See page 3)

SNOC 3

cc w/encl:

J. T. Gasser

Executive Vice President Attorney General

Southern Nuclear Operating Company, Inc. Law Department

Electronic Mail Distribution 132 Judicial Building

Atlanta, GA 30334

W. F. Kitchens

General Manager, Plant Vogtle Laurence Bergen

Southern Nuclear Operating Company, Inc. Oglethorpe Power Corporation

Electronic Mail Distribution Electronic Mail Distribution

N. J. Stringfellow Resident Manager

Manager-Licensing Oglethorpe Power Corporation

Southern Nuclear Operating Company, Inc. Alvin W. Vogtle Nuclear Plant

Electronic Mail Distribution Electronic Mail Distribution

Director, Consumers' Utility Counsel Arthur H. Domby, Esq.

Division Troutman Sanders

Governor's Office of Consumer Affairs Electronic Mail Distributioin

2 M. L. King, Jr. Drive

Plaza Level East; Suite 356 Senior Engineer - Power Supply

Atlanta, GA 30334-4600 Municipal Electric Authority

of Georgia

Office of the County Commissioner Electronic Mail Distribution

Burke County Commission

Waynesboro, GA 30830 Reece McAlister

Executive Secretary

Director, Department of Natural Resources Georgia Public Service Commission

205 Butler Street, SE, Suite 1252 244 Washington Street, SW

Atlanta, GA 30334 Atlanta, GA 30334

Manager, Radioactive Materials Program

Department of Natural Resources

Electronic Mail Distribution

_________________________

OFFICE RII:DRS RII:DRP RII:DRS

SIGNATURE /RA/ /RA/ /RA/

NAME CSmith MWidmann COgle

DATE 5/31/05 6/2/05 6/3/05

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

INFORMATION REQUEST FOR VOGTLE SAFETY SYSTEM DESIGN

AND PERFORMANCE CAPABILITY INSPECTION

LOSS OF COOLANT ACCIDENT ( Small Break, Large Break, Inter-System)

(Please provide the information electronically in searchable .pdf files on CDROM. The

CDROM should be indexed and hyperlinked to facilitate ease of use. Information in

Lists should contain enough information to be easily understood by some one who has

a knowledge of pressurized water reactor technology.)

1. Design basis documents for the engineered safety features (ESF) and emergency core

cooling systems (ECCS) used to mitigate a loss of coolant event. Design basis

documents for the high, medium, and low voltage electrical systems that power the ESF

and ECCS components/systems.

2. All procedures used to implement the mitigation strategy for the loss of coolant

accidents (LOCA) event. Include alarm response procedures as well as normal,

abnormal, and emergency operating procedures (EOPs) as appropriate. Also include

the EOP users guide and EOP set-point document as well as calculations used to

support the set-points in EOPs for the LOCA event.

3. Piping and instrumentation drawings (PI&Ds) for the ECCS and other systems used to

mitigate the LOCA event. Two paper copies are preferred for these.

4. List of surveillance procedures used to ensure the operability of the equipment required

by your Technical Specifications that is used during the mitigating of the LOCA event.

5. List of engineering calculations (electrical, mechanical/nuclear, instrumentation and

controls) applicable to the ECCS components and other related systems used for a

LOCA event.

6. List of temporary modifications and operator work-arounds involving any components

required for mitigation of a LOCA event for the past three years.

7. System descriptions and operator training modules for the LOCA event, the ECCS, and

other systems used to mitigate the event. Include a brief overview of the LOCA event

mitigation strategy, including operator actions and equipment used.

8. List of operating experience program evaluations of industry, vendor, or NRC generic

issues related to a LOCA event within the last 2 years.

9. A list of major modifications completed in the past five years to the ECCS and other

systems used to mitigate a LOCA event.

Enclosure

2

10. Calibration and functional test procedures for instruments used to monitor reactor

coolant system (RCS) pressure, pressurizer level, RCS hot and cold leg temperatures,

RCS subcooling, high pressure coolant injection flow, low pressure coolant injection

flow, borated water storage tank level, auxiliary feedwater flow, condensate storage tank

level, and containment sump level.

11. Quality assurance audits and/or self-assessments performed on the ECCS and other

systems used to mitigate a LOCA in the past 24 months.

12. Plant Technical Specifications, Bases, and Technical Requirements Manual.

13. A current copy of the Updated Final Safety Analysis Report.

14. Procedures that provide implementation guidance for the following programs: Corrective

Action Program, Maintenance Rule Program, Design Control Program, and Operating

Experience Program.

15. Probabilistic risk assessment (PRA) event tree for the LOCA event. A list of PRA

identified system dependencies and success criteria for the ECSS and other systems

used to mitigate a LOCA. Provide LOCA cutsets and risk achievement worths for those

basic events ( assuming only a LOCA initiating event).

16. System health reports and/or other performance monitoring information for the ECCS

and other systems used to mitigate a LOCA event.

17. A list of condition reports and non-routine work requests initiated since 1999 affecting

the ECCS and other systems used to mitigate a LOCA event.

18. Maintenance rule performance criteria for systems used to detect and mitigate a LOCA

event. A list of maintenance rule failures of equipment used to detect or mitigate a

LOCA event.

19. Key one line diagrams for the alternating current and the 125 VDC systems that provide

power for the pumps , valves, and instrumentation and control circuits associated with

the ECCS and other systems used to mitigate the LOCA. Also, include the one line

diagrams for the Class 1E medium and low voltage switchgear and the 480 V motor

control centers. ( Paper copies are preferred for these).

20. Provide a list of valves used to mitigate a LOCA that are required to change position or

are manually manipulated during implementation of the LOCA mitigation strategy.

Provide equipment failure rates over the past 10 years for these components.

Enclosure