ML042160143
| ML042160143 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/23/2004 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Rosalyn Jones Duke Energy Corp |
| References | |
| 50-269/04-301, 50-270/04-301, 50-287/04-301 | |
| Download: ML042160143 (10) | |
See also: IR 05000269/2004301
Text
July 23, 2004
Duke Energy Corporation
ATTN: Mr. Ronald A. Jones
Vice President
Oconee Site
7800 Rochester Highway
Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION - NRC EXAMINATION REPORT NOS.
05000269/2004301, 05000270/2004301, AND 05000287/2004301
Dear Mr. Jones:
During the period June 14 - 18, 2004, the Nuclear Regulatory Commission (NRC) administered
operating examinations to employees of your company who had applied for licenses to operate
the Oconee Nuclear Power Station. 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
June 25, 2004.
Four Reactor Operator applicants and seven Senior Reactor Operator applicants passed both
the written and operating examinations. One Senior Reactor Operator failed the written exam.
A Simulation Facility Report is included in this report as Enclosure 2. There was one post
examination comment identified in Enclosure 3.
In accordance with 10 CFR 2.390 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).
Should you have any questions concerning this letter, please contact me at (404) 562-4638.
Sincerely,
/RA/
Michael E. Ernstes, Chief
Operator Licensing and
Human Performance Branch
Division of Reactor Safety
Docket Nos. 50-269, 50-270, 50-287
License Nos. DPR-38, DPR-47, DPR-55
Enclosures: (See page 2)
2
Enclosures:
1. Report Details
2. Simulation Facility Report
3. NRC Resolution to Facility Comments
cc w/encls:
B. G. Davenport
Compliance Manager (ONS)
Duke Energy Corporation
Electronic Mail Distribution
Lisa Vaughn
Legal Department (PB05E)
Duke Energy Corporation
422 South Church Street
P. O. Box 1244
Charlotte, NC 28201-1244
Anne Cottingham
Winston & Strawn LLP
Electronic Mail Distribution
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environmental
Health & Natural Resources
Electronic Mail Distribution
Henry J. Porter, Assistant Director
Div. of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
R. Mike Gandy
Division of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
County Supervisor of
Oconee County
415 S. Pine Street
Walhalla, SC 29691-2145
Lyle Graber, LIS
NUS Corporation
Electronic Mail Distribution
R. L. Gill, Jr., Manager
Nuclear Regulatory Issues
and Industry Affairs
Duke Energy Corporation
526 S. Church Street
Charlotte, NC 28201-0006
Peggy Force
Assistant Attorney General
N. C. Department of Justice
Electronic Mail Distribution
Bentley K. Jones
Training Manager
Oconee Nuclear Station
7800 Rochester Highway
Seneca, SC 29672-0752
3
Distribution w/encls:
L. Olshan, NRR
C. Evans (Part 72 Only)
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:SRS
RII:DRS
RII:DRP
SIGNATURE
/RA/
/RA/
/RA By G. Hopper for/
/RA/
/RA By R. Carroll for/
NAME
GHopper:pmd
RAiello
GLaska
MErnstes
RHaag
DATE
7//22/04
7/22/04
7/22/04
7/22/04
7/23/04
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
PUBLIC DOCUMENT
YES
NO YES NO YES
NO YES
NO YES
NO YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML042160143.wpd
Enclosure 1
NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos.:
50-269, 50-270, 50-287
License Nos.:
Report No.:
05000269/2004301, 05000270/2004301, and
Licensee:
Duke Energy Corporation
Facility:
Oconee Nuclear Station
Location:
7800 Rochester Highway
Seneca, SC 29672
Dates:
Operating Tests - June 14 - 18, 2004
Written Examination - June 25, 2004
Examiners:
G. Hopper, Operator Licensing Team Leader
R. Aiello, Senior Operations Engineer
G. Laska, Senior Operations Examiner
Approved by:
M. Ernstes, Chief
Operator Licensing and Human Performance Branch
Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000269/2004301, 05000270/2004301, 05000287/2004301; 6/14 - 25/2004; Oconee
Nuclear Station; Licensed Operator Examinations.
The NRC examiners conducted operator licensing initial examinations in accordance with the
guidance of NUREG-1021, Draft Revision 9, Operator Licensing Examination Standards for
Power Reactors. This examination implemented the operator licensing requirements identified
in 10 CFR §55.41, §55.43, and §55.45.
The NRC administered the operating examination June 14 - 18, 2004. The Oconee Nuclear
Power Station training staff administered the written examination on June 25, 2004. All of the
outlines, the written examination, job performance measures (JPMs) and scenarios (3) were
developed by the Oconee training staff. Four Reactor Operators (RO) and seven Senior
Reactor Operator applicants (SRO), passed both the operating and written examinations. One
SRO applicant passed the operating examination but failed the written examination. All but one
applicant were issued operator licenses commensurate with the level of examination
administered.
No significant issues were identified.
Enclosure 1
Report Details
4.
OTHER ACTIVITIES (OA)
4OA5 Operator Licensing Initial Examinations
a.
Inspection Scope
The licensee developed operating tests and written examinations in accordance with
NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Draft
Revision 9. The NRC examination team reviewed the proposed examinations.
Examination changes agreed upon between the NRC and the licensee were made
according to NUREG-1021 and incorporated into the final version of the examination
materials.
The examiners also reviewed documentation associated with the licensees Once
Through Steam Generator (OTSG) replacement for Unit one to ensure conformance
with simulator requirements specified in 10 CFR 55.46. Specifically, the review was to
determine if the facility licensees simulation facility was acceptable for use in operating
licensing examinations. Replacement OTSGs had been installed in Unit One, and the
plant referenced simulator had not yet been upgraded with the new OTSG computer
model. The examiners reviewed the 10 CFR 50.59 evaluation, and the replacement
OTSG Accident Analysis Summary Report, and compared the current OTSG data
against the previous Unit One OTSG data to determine if there were thermal hydraulic
characteristics that may not be properly replicated on the current simulator model. The
examiners also reviewed and compared the main steam line break plant performance
curves from the old and new OTSGs. The examiners used the previous OTSG data and
simulator performance curves as acceptance criteria since these were the bases for the
current simulator model.
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 four Reactor Operator (RO) and eight Senior Reactor
Operator (SRO) applicants who were being assessed under the guidelines specified in
NUREG-1021. The examiners administered the operating tests during the period of
June 14-18, 2004. Members of the Oconee Nuclear Power Station training staff
administered the written examination on June 25, 2004. The evaluations of the
applicants and review of documentation were performed to determine if the applicants,
who applied for licensees to operate the Oconee Nuclear Power Station, met
requirements specified in 10 CFR Part 55.
b.
Findings
The examiners noted that the current simulator closely modeled the actual plant
performance and was sufficient in scope and fidelity to allow conduct of the operating
2
Enclosure 1
tests specified in 10 CFR 55.45 and for use in the licensees requalification program
while the licensee is completing the installation and testing of the new reference plant
model. The NRC noted that this model is expected to be installed by December 2004.
The licensees examination submittal was within the range of acceptability expected for
a proposed examination. Four RO and seven SRO applicants, passed both the
operating and written examinations. One SRO applicant passed the operating
examination but failed the written examination. The RO and SRO written examinations
and answer keys, licensees post examination comments, and combined RO/SRO
examination and examination references may be accessed in the ADAMS system
(ADAMS Accession Numbers, ML042020190 and ML042020184).
4OA6 Meetings
Exit Meeting Summary
On June 18, 2004, the examination team discussed generic issues with Mr. Regis
Repko and other members of your staff. The inspectors asked the licensee whether any
materials examined during the inspection should be considered proprietary. No
proprietary information was identified.
PARTIAL LIST OF PERSONS CONTACTED
Licensee personnel
B. Ayers, Training Instructor
G. Baumgarner, Training Instructor
B. Jones, Training Manager
N. Clarkson, Senior Engineer Regulatory Compliance
N. Constance, Operations Training Manager
R. Repko, Superintendent of Operations
J. Steely, Initial Training Supervisor
G. Washburn, Training Instructor
Enclosure 2
Enclosure 2
SIMULATION FACILITY REPORT
Facility Licensee: Oconee Nuclear Station
Facility Docket No.: 05000269/05000270/05000287
Operating Tests Administered on: June 14-18, 2004
This form is to be used only to report observations. These observations do not constitute audit
or inspection findings and are not, without further verification and review, 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, the following items were
observed:
ITEM
DESCRIPTION
GWR Flow Gauge Units on gauge were labeled psig vice cfm
Enclosure 3
NRC RESOLUTION OF OCONEES POST EXAM COMMENTS
Question # 13
Comment: The question asks for the reason why RCS temperature and pressure are stabilized
during a Station Blackout. The licensee recommends accepting choice B as an additional
correct answer. The licensee determined that the question was written based on the
information in the EAP-BO lesson plan. The current revision of the lesson plan does not
address the effects of cooling down on RCS inventory. The Oconee EOP Reference Document
contains additional information on this topic. The Blackout portion of the EOP Reference
Document describes the effects of cooling the RCS down below 550 F which would include
emptying the pressurizer and voiding the hot legs, thereby interrupting natural circulation.
NRC Resolution: Recommendation Accepted; the question has two correct answers (B and D).
Review of the EOP reference material for Station Blackout indicated that voiding in the hot legs
could occur and subsequently block reactor coolant flow if a cooldown were initiated. Due to
inadequate RCS makeup flow, a cooldown would empty the pressurizer and continued RCS
contraction would void the hot legs interrupting natural circulation.