IR 05000456/2009301
| ML093310230 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/25/2009 |
| From: | Hironori Peterson Operations Branch III |
| To: | Pardee C Exelon Generation Co, Exelon Nuclear |
| References | |
| 50-456/09-301, 50-457/09-301 50-456/09-301, 50-457/09-301 | |
| Download: ML093310230 (10) | |
Text
November 25, 2009
SUBJECT:
BRAIDWOOD STATION
NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2009301(DRS);
Dear Mr. Pardee:
On October 29, 2009, the U. S. Nuclear Regulatory Commission (NRC) completed the initial operator licensing examination process at your Braidwood Station. The enclosed report presents the results of the examination which were discussed with Mr. L. Coyle and other members of your staff on October 16, 2009, and Mr. P. DiGiovanna on November 10, 2009.
The NRC examiners administered initial license examination operating tests from October 5 through October 16, 2009. Members of the Braidwood Training Department administered the initial license written examination on October 19, 2009. One reactor operator and 12 senior reactor operator license examinations were administered. One of the applicants was a previously licensed reactor operator at Braidwood Station. The results of the examinations were finalized on November 10, 2009. All 13 applicants passed all sections of their examinations resulting in the issuance of 1 reactor operator and 12 senior reactor operator licenses.
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 System (PARS) component of NRCs Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA/
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77
Enclosures:
1. Operator Licensing Examination
Report 05000456/2009301(DRS); 05000457/2009301(DRS)
2. Simulation Facility Report
3. Written Examinations and Answer Keys (RO and SRO)
REGION III==
Docket Nos:
50-456; 50-457 License Nos:
05000456/2009301(DRS); 05000457/2009301(DRS)
Licensee:
Exelon Generation Company, LLC Facility:
Braidwood Station, Units 1 and 2
Location:
Braceville, Illinois
Dates:
October 5 through October 29, 2009
Examiners:
B. Palagi, Chief Examiner
D. McNeil, Examiner
C. Zoia, Examiner
Approved by:
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000456/2009301(DRS); 05000457/2009301(DRS); 10/05/09 - 10/29/09; Exelon
Generation Company, LLC; Braidwood Station, Unit 1 and 2; Initial License Examination Report.
The announced operator licensing initial examination was conducted by regional examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1.
Examination Summary:
$
Thirteen examinations were administered (1 reactor operator and 12-senior reactor operator);
$
All 13 applicants passed all sections of their examinations resulting in the issuance of reactor operator and 12 senior reactor operator licenses.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations
a. Examination Scope
The NRC examiners conducted an announced operator licensing initial examination during the weeks of October 5 and October 12, 2009. The facility licensees training staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1, to prepare the outline and develop the written examination and operating test. The examiners administered the operating test, consisting of job performance measures and dynamic simulator scenarios, during the period of October 5 through October 16, 2009. The facility licensee administered the written examination on October 19, 2009. One reactor operator and 12 senior reactor operator applicants were examined. During the on-site validation week of September 14, 2009, the examiners audited four license applications for accuracy.
b. Findings
Written Examination
The NRC examiners determined that the written examination, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors, Revision 1, Supplement 1. The licensee graded the written examination on October 19, 2009, and conducted a review of each question to determine the accuracy and validity of the examination questions. On October 29, 2009, the NRC received the licensees letter concerning the post examination material. The licensee did not submit any post examination comments for consideration by the NRC examiners when grading the written examination or enhancements based on a post examination review with the applicants.
Operating Test
The NRC examiners determined that the operating test, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors,"
Revision 1, Supplement 1. The NRC examiners completed operating test grading on October 30, 2009.
Examination Results
All 13 applicants passed all sections of their examinations resulting in the issuance of 1 reactor operator and 12 senior reactor operator licenses.
.2 Examination Security
a. Inspection Scope
The NRC examiners briefed the facility contact on the NRCs requirements and guidelines related to examination physical security (e.g., access restrictions and simulator considerations) and integrity in accordance with 10 CFR 55.49, Integrity of Examinations and Tests, and NUREG-1021, Operator Licensing Examination Standard for Power Reactors, Revision 9, Supplement 1. The examiners reviewed and observed the licensees implementation and controls of examination security and integrity measures (e.g., security agreements) throughout the examination process.
b. Findings
No Findings
4OA6 Meetings
Debrief
The chief examiner presented the examination team's preliminary observations and findings on October 16, 2009, to Mr. L. Coyle, Plant Manager, and other members of the Braidwood Operations and Training Department staff.
Exit Meeting
The chief examiner conducted an exit meeting by telephone on November 10, 2009, with Mr. P. DiGiovanna, Operations Training Manager. The NRC=s preliminary examination results were provided to Mr. DiGiovanna during the telephone discussion. The examiners asked the licensee whether any of the material used to develop or administer the examination should be considered proprietary. No proprietary or sensitive information was identified during the examination or debrief/exit meetings.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
Larry Coyle, Plant Manager
Tom McCool, Operations Director
Tricia Matteson, Regulatory Engineer
Paul DiGiovanna, Operations Training Manager
Darren Stiles, Initial License Training Group Lead
Brian Kempen, Lead Regulatory Exam Author
Ken Norris, Senior Operations Training Instructor
Dan Burton, Simulator Supervisor
NRC
B Palagi, Chief Examiner
- D. McNeil, Examiner
- C. Zoia, Examiner
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF ACRONYMS
Agency-Wide Document Access and Management System
CFR
Code of Federal Regulations
Division of Reactor Safety
NRC
U. S. Nuclear Regulatory Commission
Publicly Available Records System
SIMULATION FACILITY REPORT
Facility Licensee: Braidwood Station, Unit 1 and 2
Facility Licensee Docket No. 50-456; 50-457
Operating Tests Administered: October 5 through October 16, 2009
The following documents observations made by the NRC examination team during the initial
operator license examination. These observations do not constitute audit or inspection findings
and are not, without further verification and review, indicative of non-compliance with
CFR 55.45(b). These observations do not affect NRC certification or approval of the
simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were
observed:
ITEM
DESCRIPTION
None
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession #ML093230542
C. Pardee
-2-
We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA/
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Docket Nos. 50-456; 50-457
Enclosures:
1. Operator Licensing Examination
Report 05000456/2009301(DRS); 05000457/2009301(DRS)
2. Simulation Facility Report
3. Written Examinations and Answer Keys (RO and SRO)
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