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Carolina Power and Light Company ATTN: Mr. J. S. Keenan Vice President
Carolina Power and Light Company
ATTN:
Mr. J. S. Keenan
Vice President
Brunswick Steam Electric Plant
P. O. Box 10429
Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - NRC INSPECTION REPORT
50-325/01-07, 50-324/01-07
Dear Mr. Keenan:
On October 19, 2001, the NRC completed a biennial safety system design and performance
capability inspection at your Brunswick Steam Electric Plant, Units 1 and 2. The enclosed
report documents the inspection findings which were discussed on October 19, 2001, with Mr.
C. Gannon, Plant General Manager, and other members of your staff.
This inspection was an examination of activities conducted under your license as they relate to
safety and compliance with the Commissions rules and regulations and with the conditions of
your license. The team reviewed selected procedures and records, observed activities, and
interviewed personnel.
No findings of significance were identified.
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 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/
Mark S. Lesser, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-325, 50-324
License Nos. DPR-71, DPR-62
Enclosure:
See page 2 2
CP&L
Enclosure: NRC Inspection Report
cc w/encl:
J. J. Lyash, Director
Site Operations
Brunswick Steam Electric Plant
Carolina Power & Light
Electronic Mail Distribution
C. J. Gannon
Plant Manager
Brunswick Steam Electric Plant
Carolina Power & Light Company
Electronic Mail Distribution
Terry C. Morton, Manager
Performance Evaluation and
Regulatory Affairs CPB 7
Carolina Power & Light Company
Electronic Mail Distribution
David C. DiCello, Manager
Regulatory Affairs
Carolina Power & Light Company
Brunswick Steam Electric Plant
Electronic Mail Distribution
Leonard Beller
Licensing Supervisor
Carolina Power and Light Company
Electronic Mail Distribution
William D. Johnson
Vice President & Corporate Secretary
Carolina Power and Light Company
Electronic Mail Distribution
John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washington, DC 20037-1128
(cc w/encl contd - See page 3) 3
CP&L
(cc w/encl contd)
Mel Fry, Director
Division of Radiation Protection
N. C. Department of Environment
and Natural Resources
Electronic Mail Distribution
Peggy Force
Assistant Attorney General
State of North Carolina
Electronic Mail Distribution
Robert P. Gruber
Executive Director
Public Staff NCUC
P. O. Box 29520
Raleigh, NC 27626-0520
Public Service Commission
State of South Carolina
P. O. Box 11649
Columbia, SC 29211
Donald E. Warren
Brunswick County Board of
Commissioners
P. O. Box 249
Bolivia, NC 28422
Dan E. Summers
Emergency Management Coordinator
New Hanover County Department of
Emergency Management
P. O. Box 1525
Wilmington, NC 28402
Distribution w/encl:
D. Ashley, NRR
A. Boland (Part 72 Only)
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRS
RII:DRS
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
NAME
JBLAKE
NMERRIWEATHER RSCHIN
KVANDOORN
KMAXEY
MMAYMI
BBONSER
DATE
11/31/2001
11/31/2001
11/30/2001
11/30/2001
11/30/2001
11/30/2001
11/30/2001
E-MAIL COPY?
YES
NO YES
NO YES NO YES
NO YES
NO YES
NO YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\Program Files\Adobe\Acrobat 4.0\PDF Output\brunswick ssdi 01-07
report.wpd U. S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket No:
50-325, 50-324
License No:
DPR-71, DPR-62
Report No:
50-325,324/01-07
Licensee:
Carolina Power & Light (CP&L)
Facility:
Brunswick Steam Electric Plant, Units 1 & 2
Location:
8470 River Road SE
Southport, NC 28461
Dates:
October 1 - 5, 2001 (Week 1)
October 15 - 19, 2001 (Week 2)
Inspectors:
J. Blake, Senior Project Manager (Team Leader)
N. Merriweather, Senior Reactor Inspector
R. Schin, Senior Reactor Inspector
P. VanDoorn, Senior Reactor Inspector
R. Maxey, Reactor Inspector
M. Maymi, Reactor Inspector
Approved:
Mark Lesser, Chief
Engineering Branch 2
Division of Reactor Safety SUMMARY OF FINDINGS
IR 05000325,324-01-07, on 10/1-19/01, Carolina Power and Light Company, Brunswick, Units 1
and 2, safety system design.
This safety system design and performance capability inspection was conducted by a team of
region-based inspectors. The NRCs program for overseeing the safe operation of commercial
nuclear power reactors is described at its Reactor Oversight Process website at
http://nrr10.nrc.gov/NRR/OVERSIGHT/index.html
.
No findings of significance were identified. REPORT DETAILS
1.
REACTOR SAFETY
CORNERSTONES: Initiating Events and Mitigating Systems
1R21
Safety System Design and Performance Capability (71111.21)
Introduction
Through review of the Brunswick Nuclear Plant Probabilistic Safety Assessment the
team selected a population of components and operator actions that could initiate a
Loss of Offsite Power (LOOP) with a Station Blackout (SBO) or mitigate the
consequences.
.1
System Needs
a.
Inspection Scope
Energy Source - Station Batteries
The team reviewed design basis documentation, calculations, and surveillance tests to
verify that for the first hour of an SBO event, the coping loads could be adequately
supplied by the 125/250 volt direct current (Vdc) batteries. The team reviewed
analyses to verify that the batteries conformed with IEEE 485-1983, Recommended
Practice for Sizing Large Lead Storage Batteries for Generating Stations and
Substations. The team also reviewed design basis documentation and calculations to
verify that, under minimum voltage conditions, the 125/250 Vdc batteries provided
adequate voltage for safety-related equipment to perform their design functions. The
ampacity of existing cables connecting the 125/250 Vdc batteries to essential
switchboards, motor control centers, and distribution panels were reviewed for
adequacy.
Controls - Vital Alternating Current
The team reviewed electrical drawings depicting the design of the degraded and loss
of voltage relay logic protecting the balance of plant (BOP) and Emergency 4160 volt
alternating current (Vac) switchgear buses to verify that, upon sensing a valid
degraded or loss of voltage condition on the buses, the emergency diesel generators
(EDG) would start and restore power to the boards and blackout loads would
automatically sequence onto the boards. The objective of the above review was to
verify that the EDG control logic was capable of performing the design functions
during a LOOP event consistent with the licensing and design basis for the plant.
Emergency Diesel Generators
The team reviewed design basis documentation, calculations, and surveillance tests to
verify that during an SBO event, the EDG possessed adequate capability to supply
loads for the non-blacked out unit and SBO coping loads for the blacked out unit. The
team reviewed analyses to verify the EDG system conformed with the alternate 2
alternating current (Aac) criteria as defined in NUMARC 87-00, Guidelines and
Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water
Reactors, and NRC Regulatory Guide 1.155, Station Blackout.
EDG Support System Power Supplies
The team reviewed design basis documentation associated with sizing of electrical
circuit breakers for the EDG ventilation supply fan motors, EDG fuel oil transfer pump
motors, and 125/250 Vdc battery chargers to verify that the breakers were adequately
sized for the associated loads.
EDG Fuel Oil
The team reviewed design documentation, technical specifications, drawings,
calculations, vendor manuals, test documentation, program and operating
procedures, and installed equipment to verify that the sizing of storage tanks and the
design of the fuel oil transfer pumps were adequate to provide the fuel requirements to
operate the EDG for the period of time assumed in accident analyses. This included
calculations that determined the EDG fuel consumption rate and calculations that
determined the fuel oil volume required for seven days of operation. Additionally, the
team reviewed test data sheets and the