ML052090202

Notification of Brunswick Ssdpc IR 05000325-05-07 and 05000324-05-07

ML052090202
Person / Time
Site:	Brunswick
Issue date:	07/28/2005
From:	Ogle C Division of Reactor Safety II
To:	Gannon C Carolina Power & Light Co
References
IR-05-007
Download: ML052090202 (6)

See also: IR 05000324/2005007

Text

July 28, 2005

Carolina Power and Light Company

ATTN: Mr. C. J. Gannon

Vice President

Brunswick Steam Electric Plant

P. O. Box 10429

Southport, NC 28461

SUBJECT: NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT - SAFETY

SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION -

NRC INSPECTION REPORT 50-325/2005-07 AND 50-324/2005-07

Dear Mr. Keenan:

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 Brunswick Nuclear Plant during the weeks of October 31 - November 4, 2005 and

November 14 - 18, 2005. A team of five inspectors will perform this inspection. The inspection

team will be led by Mr. Larry Mellen, a Team Leader from the NRC Region II Office. This

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, respond to,

and mitigate a loss of residual heat removal (RHR) and RHR service water (RHRSW). The

inspection will also focus on events that may contribute to a loss of RHR and RHRSW. The

inspection will also evaluate personnel response to these events.

During a telephone conversation on July 27, 2005, Mr. Mellen of my staff and Mr. Charles

Elberfeld 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 October 3, 2005

• Onsite inspection: October 31, 2005 and November 14, 2005

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

outlined in the enclosure needed to support the inspection. Mr. Rudolph Bernhard, a Region II

Senior Reactor Analyst, may accompany Mr. Mellen 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. Mellen 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, Mr. Mellen will also discuss the following inspection

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

CP&L 2

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.

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

information requested or the inspection, please contact Mr. Mellen at (404) 562-4531 or me at

(404) 562-4605.

In accordance with 10 CFR 2.390 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 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 by L. R. Moore for\

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-325, 50-324

License Nos.: DPR-71, DPR-62

Enclosure: Information Request for the Safety System Design

and Performance Capability Inspection

cc w/encls:-(See page 3)

CP&L 3

cc w/encl:

T. P. Cleary, Director Peggy Force

Site Operations Assistant Attorney General

Brunswick Steam Electric Plant State of North Carolina

Progress Energy Carolinas, Inc. Electronic Mail Distribution

Electronic Mail Distribution

Chairman of the North Carolina

Benjamin C. Waldrep Utilities Commission

Plant Manager c/o Sam Watson, Staff Attorney

Brunswick Steam Electric Plant Electronic Mail Distribution

Carolina Power & Light Company

Electronic Mail Distribution Robert P. Gruber

Executive Director

James W. Holt, Manager Public Staff NCUC

Performance Evaluation and 4326 Mail Service Center

Regulatory Affairs PEB 7 Raleigh, NC 27699-4326

Carolina Power & Light Company

Electronic Mail Distribution Public Service Commission

State of South Carolina

Edward T. O'Neil, Manager P. O. Box 11649

Support Services Columbia, SC 29211

Carolina Power & Light Company

Brunswick Steam Electric Plant David R. Sandifer

Electronic Mail Distribution Brunswick County Board of

Commissioners

Lenny Beller, Supervisor P. O. Box 249

Licensing/Regulatory Programs Bolivia, NC 28422

Carolina Power and Light Company

Electronic Mail Distribution Warren Lee

Emergency Management Director

David T. Conley New Hanover County Department of

Associate General Counsel - Legal Dept. Emergency Management

Progress Energy Service Company, LLC P. O. Box 1525

Electronic Mail Distribution Wilmington, NC 28402-1525

John H. O'Neill, Jr.

Shaw, Pittman, Potts & Trowbridge

2300 N. Street, NW

Washington, DC 20037-1128

Beverly Hall, Acting Director

Division of Radiation Protection

N. C. Department of Environment

and Natural Resources

Electronic Mail Distribution

INFORMATION REQUEST FOR THE BRUNSWICK SAFETY SYSTEM DESIGN

AND PERFORMANCE CAPABILITY INSPECTION.

Residual Heat Removal (RHR) and RHR Service Water (RHRSW)

(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 someone who has a knowledge

of pressurized water reactor technology.)

1. Design basis documents for the RHR & RHRSW. Design basis documents for the

high, medium, and low voltage electrical systems that power RHR & RHRSW

components/systems.

2. All procedures used to implement the mitigation strategy for the loss of RHR & RHRSW

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 setpoint document as well as calculations used to support the setpoints in EOPs

for the LOCA event.

3. Piping and instrumentation drawings (P&IDs) for the systems used to mitigate the loss

of RHR & RHRSW event. Two (2) paper copies are preferred for these.

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

your Technical Specifications that is used during the mitigation of the RHR & RHRSW

event.

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

controls) applicable to the RHR & RHRSW components and other related systems used

for a loss of RHR & RHRSW event.

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

required for mitigation of a loss of RHR & RHRSW event for the past 3 years.

7. System descriptions and operator training modules for the loss of RHR & RHRSW event

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

RHR & RHRSW 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 the loss of RHR & RHRSW event.

9. A list of major modifications completed in the past five years to the components or

systems used to mitigate a RHR & RHRSW event.

10. Quality Assurance audits and/or self assessments performed on the RHR & RHRSW

and other systems used to mitigate a loss of RHR & RHRSW in the past 24 months.

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

2

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

13. Procedures that provide implementation guidance for the following programs:

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

Operating Experience Program.

14. Probabilistic risk assessment (PRA) event tree for the loss of RHR & RHRSW event. A

list of PRA identified system dependencies and success criteria for the ECCS and other

systems used to mitigate a loss of RHR & RHRSW. Provide the initiator summary

report, the importance measure report, and the top 500 cutsets report for both units for

the most current revision of your nominal maintenance PSA. If possible provide the risk

achievement worth measured with respect to your loss of nuclear service water, and

loss of normal service water initiators only (set all other initiators to false, solve, get new

importance measures for this solution). Provide the top 100 cutsets for the loss of

nuclear service water, and loss of normal service water initiators.

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

and other systems used to mitigate a loss of RHR & RHRSW event.

16. A list of condition reports and non-routine work requests initiated since 2000 affecting

the RHR & RHRSW and other systems used to detect and mitigate a loss of RHR &

RHRSW event.

17. 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.

18. Key one line diagrams for the alternating current and the 125-volt direct current systems

that provide power for the pumps, valves, and instrumentation and control circuits

associated with the RHR & RHRSW and other systems used to mitigate the loss of RHR

& RHRSW. Also, include the one line diagrams for the Class 1E medium and low

voltage switchgear and the 480 volt motor control centers. (Paper copies are preferred

for these).

19. Provide a list of valves used to mitigate a loss of RHR & RHRSW that are required to

change position or are manually manipulated during implementation of the loss of RHR

& RHRSW mitigation strategy. Provide equipment failure rates over the past 10 years

for these components.

_________________________

OFFICE RII:DRS RII:DRS

SIGNATURE P.Fredickson L.Mellen

NAME /RA/ /RA/

DATE 7/28/2005 7/28/2005 7/ /2005 7/ /2005 7/ /2005 7/ /2005 7/ /2005

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