ML030730306
| ML030730306 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/13/2003 |
| From: | Ernstes M NRC/RGN-II |
| To: | Keenan J Carolina Power & Light Co |
| References | |
| 50-324/03-301, 50-325/03-301 50-324/03-301, 50-325/03-301 | |
| Download: ML030730306 (12) | |
See also: IR 05000325/2003301
Text
March 13, 2003
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 EXAMINATION REPORT
50-325/2003-301 AND 50-324/2003-301
Dear: Keenan:
During the period February 10-13, 2003, the Nuclear Regulatory Commission (NRC)
administered operating examinations to employees of your company who had applied for
licenses to operate the Brunswick Steam Electric Plant. At the conclusion of the examination,
the examiners discussed the examination questions and preliminary findings with those
members of your staff identified in the enclosed report. The written examination was
administered by your staff on February 19, 2003.
All seven applicants passed the operating examination. There were two post examination
written comments which are discussed in Enclosure 2. A Simulation Facility Report is included
as Enclosure 3.
In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its
enclosures 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/
Michael E. Ernstes, Chief
Operator Licensing and
Human Performance Branch
Division of Reactor Safety
Docket Nos. 50-325, 50-324
Enclosures: (See page 2)
CP&L 2
Enclosures: 1. Report Details
2. Post Examination Comment Resolution
3. Simulation Facility Report
cc w/encls:
C. J. Gannon, Director Peggy Force
Site Operations Assistant Attorney General
Brunswick Steam Electric Plant State of North Carolina
Carolina Power & Light Electronic Mail Distribution
Electronic Mail Distribution
Chairman of the North Carolina
W. C. Noll 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
Terry C. Morton, Manager Public Staff NCUC
Performance Evaluation and 4326 Mail Service Center
Regulatory Affairs CPB 7 Raleigh, NC 27699-4326
Carolina Power & Light Company
Electronic Mail Distribution Public Service Commission
State of South Carolina
Edward T. ONeil, Manager P. O. Box 11649
Support Services Columbia, SC 29211
Carolina Power & Light Company
Brunswick Steam Electric Plant Donald E. Warren
Electronic Mail Distribution Brunswick County Board of
Commissioners
Licensing Supervisor P. O. Box 249
Carolina Power and Light Company Bolivia, NC 28422
Electronic Mail Distribution
Dan E. Summers
William D. Johnson Emergency Management Coordinator
Vice President & Corporate Secretary New Hanover County Department of
Carolina Power and Light Company Emergency Management
Electronic Mail Distribution P. O. Box 1525
Wilmington, NC 28402
John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge Jackie Gawron
2300 N. Street, NW Training Manager
Washington, DC 20037-1128 Brunswick Steam Electric Plant
P. O. Box 10429
Beverly Hall, Acting Director Southport, NC 28461-0429
Division of Radiation Protection
N. C. Department of Environment
and Natural Resources
Electronic Mail Distribution
CP&L 3
Distribution w/encls:
L. Olshan, NRR
C. Evans (Part 72 Only)
RIDSRIDSNRRDIPMLIPB
PUBLIC
OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRP RI
SIGNATURE /RA/ /RA By RBaldwin for/ /RA By RBaldwin for/ /RA/ /RA/ /RA By RBaldwin for/
NAME RBaldwin:pmd KODonohue LMiller MErnstes PFredrickson GJohnson
DATE 3/12/2003 3/12/2003 3/12/2003 3/13/2003 3/12/2003 3/12/2003
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO
PUBLIC DOCUMENT YES NO
OFFICE RI
SIGNATURE /RA By RBaldwin for/
NAME HWilliams
DATE 3/12/2003
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO
PUBLIC DOCUMENT YES NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\ORPCheckout\FileNET\ML030730306.WPD
CP&L 4
NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos.: 50-325, 50-324
Report Nos.: 50-325/03-301, 50-324/03-301
Licensee: Carolina Power and Light
Facility: Brunswick Steam Electric Plant
Location: 8470 River Road SE
Southport, NC 28461
Dates: Operating Tests - February 10-13, 2003
Written Examination - February 19, 2003
Examiners: R. Baldwin, Chief Examiner
K. ODonohue, Senior Operations Engineer
L. Miller, Senior Operations Engineer
J. Williams, Senior Operations Engineer, Region I
G. Johnson, Operations Engineer, Trainee, Region I
Approved by: M. Ernstes, Chief
Operator Licensing and Human Performance Branch
Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000325/2003-301, ER 05000324/2003-301; Carolina Power and Light; on 2/10-13/2003;
Brunswick Steam Electric Plant, Units 1 and 2, Licensed Operator Examinations.
The NRC examiners conducted operator licensing initial examinations in accordance with the
guidance of Examiner Standards, NUREG-1021, Revision 8, Supplement 1. This examination
implemented the operator licensing requirements of 10 CFR §55.41, §55.43, and §55.45.
The NRC administered the operating tests during the period February 10-13, 2003. Members
of the Brunswick Steam Electric Plant training staff administered the written examination on
February 19, 2003. The written examinations were developed by the NRC. The operating tests
were developed by the Brunswick Steam Electric Plant staff from outlines developed by the
NRC. All applicants, three Reactor Operators (RO) and four Senior Reactor Operators (SRO)
passed both the operating and written examinations. All applicants were issued operator
licenses commensurate with the level of examination administered.
No significant issues were identified.
Report Details
4. OTHER ACTIVITIES (OA)
4OA5 Operator Licensing Initial Examinations
a. Inspection Scope
The examiners developed the written and operating examinations in accordance with
the guidelines specified in NUREG-1021, Revision 8, Supplement 1.
The examiners reviewed the licensees examination security measures while preparing
and administering the examinations to ensure examination security and integrity
complied with 10 CFR 55.49, Integrity of examinations and tests.
The examiners evaluated three Reactor Operator (RO) and four Senior Reactor
Operator (SRO) applicants who were being assessed under the guidelines specified in
NUREG-1021. They administered the operating tests during the period February 10-13,
2003. Members of the Brunswick Steam Electric Plant training staff administered the
written examination on February 19, 2003. The evaluations of the applicants and review
of documentation were performed to determine if the applicants, who applied for
licensees to operate the Brunswick Steam Electric Plant, met requirements specified in
b. Findings
No findings of significance were identified.
The licensee submitted two post examination comments concerning the written
examination (ADAMS Accession Number ML030650592). The RO and SRO written
examinations and answer keys, combined RO/SRO examination and examination
references may be accessed in the ADAMS system (ADAMS Accession Numbers
ML030650589, ML030650584, ML030650572 and ML030650560).
4OA6 Meetings
Exit Meeting Summary
On February 14, 2003, the Chief Examiner discussed generic applicant performance
and examination development issues with members of licensee management.
The inspectors asked the licensee whether any materials examined during the
inspection should be considered proprietary. No proprietary information was identified.
2
PARTIAL LIST OF PERSONS CONTACTED
Licensee
L. Beller, Supervisor, Licensing/Regulatory Programs
C. Elberfeld, Senior Engineering Technical Support Specialist
C. Gannon, Director Site Operations
J. Gawron, Manager, Training
J. Keenan, Vice President Brunswick Nuclear Plant
J. Leviner, Supervisor, Operator Training
W. Noll, Plant General Manager
E. ONeil, Manager, Support Services
A. Pope, Superintendent, Operator Training
M. Williams, Manager, Operations
NRC
T. Easlick, Senior Resident Inspector
NRC RESOLUTION OF FACILITY COMMENTS
RO QUESTION #36/ SRO QUESTION #25:
Facility Comment: The question asked for the expected ERFIS tail pipe temperature indication
for an SRV opened with RPV pressure at 1005 psig. The answer key indicated that "B" was the
correct answer (300 degrees). Answer "B" (300 degrees) corresponded to an isenthalpic
throttling process from 1000 psig to atmospheric pressure on the Mollier diagram. At the
Brunswick Plant, a temperature element is installed in each tail pipe just downstream of the SRV
which feeds a recorder, ERFIS, and a common control room annunciator. At the temperature
probe location, atmospheric conditions would not exist with an open SRV due to the
backpressures created from underwater discharge through a "T" quencher in the torus.
The facility recommended that the correct answer be changed to "C" (350 degrees). Per the
System Description Procedure (SD-20) which discusses temperature indications, the theoretical
temperature (indication) is 350 degrees F for steam being throttled through a leaking SRV. This
is supported by the annunciator procedure for SRV leaking (or open) which includes SRV
temperature alarm setpoints as high as 340 degrees F to indicate an open SRV.
NRC Resolution: Recommendation accepted. Review of additional reference material SD-20
page 14, indicated that 350 degrees F is the theoretical temperature for steam being throttled
through a leaking SRV. The answer key was changed to reflect C as being the correct answer.
RO QUESTION #82/ SRO QUESTION #77:
Facility Comment: The question asked for the plant impact from high radiation conditions in the
reactor building with a failure of ventilation isolation dampers to close and both Standby Gas
Treatment (SBGT) trains running. The answer key indicated that "D" (a ground level release of
radioactivity could occur) was the correct answer.
The facility recommended that "A" (an elevated release of radioactivity from the main stack could
occur) be accepted as an additional correct answer. This recommendation was based on both
SBGT trains running (discharging to the stack) with high radiation conditions in the reactor
building. Per the Brunswick Plant Updated FSAR, the SBGT (i.e., SGTS) system provides a
means for minimizing the release of radioactive material from containment to the environs by
filtering and exhausting the atmosphere from the reactor building during containment isolation
conditions. Per the UFSAR, an "elevated release is assured by exhausting to the plant stack."
With the SBGT system not 100% efficient in removal of radioactivity, with both systems in
operation under high radiation conditions in the reactor building, an elevated release from the
stack would result. Therefore, both answers "A" (an elevated release of radioactivity from the
main stack could occur) and answer "D" (a ground level release of radioactivity could occur) are
both correct.
NRC Resolution: Recommendation accepted. The expected answer, D, was based on the
assumption that a ground level release could occur if the Reactor Building Dp was zero along
with the other conditions given in the question. Implied in these conditions is that a higher level
Enclosure 3
2
of activity exists in the reactor building. If this were true then choice A is a true statement also,
since a higher level of activity passed through the SBGT system Could result in an elevated
release of radioactivity from the main stack. The answer key was changed to reflect A as an
additional correct answer.
Enclosure 3
SIMULATION FACILITY REPORT
Facility Licensee: Brunswick Steam Electric Plant
Facility Docket No.: 050-00325, 050-00324
Operating Tests Administered on: 02/10-13/2003
This form is to be used only to report observations. These observations do not constitute audit
or inspection findings and, without further verification and review, are not indicative of
noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or
approval of the simulation facility other than to provide information that may be used in future
evaluations. No licensee action is required in response to these observations.
While conducting the simulator portion of the operating tests, examiners observed the following
items:
ITEM DESCRIPTION
1. Augmented Off-gas (AOG) Guard Bed Fire did not produce an increase in
radioactive release from the plant stack as would have been expected. A
fire in the guard bed would have been expected to have a substantial
increase in plant stack radiation. During this event there was no increase
in stack release.
Enclosure 3