IR 05000045/2007301
| ML073620250 | |
| Person / Time | |
|---|---|
| Site: | Braidwood, 05000045  |
| Issue date: | 12/20/2007 |
| From: | Hironori Peterson Operations Branch III |
| To: | Pardee C Exelon Generation Co |
| References | |
| 50-456/07-301, 50-457/07-301 50-456/07-301, 50-457/07-301 | |
| Download: ML073620250 (14) | |
Text
December 20, 2007
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2,
NRC INITIAL LICENSE EXAMINATION REPORT 05000456/2007301(DRS);
Dear Mr. Pardee:
On December 10, 2007, the NRC completed initial operator licensing examinations at your Braidwood Station. The enclosed report presents the results of the examination which were discussed on December 7 and December 18, 2007, with Mr. Coutu and Mr. Dudek, respectively, and with other members of your staff.
The NRC examiners administered initial license examination operating tests during the week of December 3, 2007. Members of the Braidwood Station Training Department administered an initial license written examination on December 10, 2007, to the applicants. Five senior reactor operator and one reactor operator applicants were administered license examinations. The results of the examinations were finalized on December 19, 2007. Six applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and one reactor operator licenses.
In accordance with 10 CFR 2.390 of the NRC's "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 NRC's 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 05000456/2007301(DRS); 05000457/2007301(DRS)
2.
Simulation Facility Report
3.
Written Examinations and Answer Keys (RO/SRO)
REGION III==
Docket Nos.
50-456; 50-457
License Nos.
Report No:
Licensee:
Exelon Nuclear
Facility:
Braidwood Nuclear Plant, Units 1 and 2
Location:
Braceville, IL
Dates:
December 3 through December 10, 2007
Examiners:
N. Valos, Chief Examiner
B. Palagi, Examiner
C. Zoia, Examiner
Approved by:
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000456/2007301(DRS); 05000457/2007301(DRS); 12/03/07 - 12/10/07;
Braidwood Station, Units 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.
Examination Summary:
$
Six examinations were administered (five senior reactor operator and one reactor operator).
$
Six applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and one 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 week of December 3, 2007. The facility licensees training staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, 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 December 3 through December 6, 2007. The facility licensee administered the written examination on December 10, 2007. Five senior reactor operator and one reactor operator applicants were examined. During the on-site validation week of October 22, 2007, the examiners audited one license application 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. The licensee had no post examination comments on the written examination.
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.
Al changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors."
Examination Results
Six applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and one 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. 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
There was one issue associated with exam security identified by the facility during the week of the onsite validation of the examination. During the Initial License Test (ILT)training on the simulator on 10/22/07, which occurred immediately following an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period of NRC ILT validation, an ILT student identified place-keeping marks present in a procedure. This situation was considered potentially significant, since the place-keeping marks in a procedure can identify an event in a simulator exam scenario, and thus invalidate the simulator event. The issue was documented in the corrective action program as IR 00687959 and the station performed a Quick Human Performance Investigation (QHPI) associated with the issue.
The NRC was appropriately notified of this issue. As a result of the event, one simulator event was changed in a scenario. We reviewed and assessed the issue for a possible violation of 10 CFR 55.49, Integrity of Examinations and Tests. With the actions taken, it was determined that no actual examination compromise had occurred. The event was considered minor in nature and was not subject to enforcement action in accordance with NRC enforcement policy.
Other than the issue identified above, the licensees implementation of examination security requirements during examination preparation and administration were acceptable and met the guidelines provided in NUREG-1021, Operator Licensing Examination Standards for Power Reactors. No violations of 10 CFR 55.49 occurred during the examination preparation and administration.
.3 Failure to Control Regulatory Guide 1.97 Instrumentation Marking
Introduction:
The inspectors identified an Unresolved Item (URI) concerning the lack of procedural controls for labeling Regulatory Guide (RG) 1.97 post-accident indications on the main control room control panels.
Description:
The NRC examiners initially questioned the process for marking the post-accident monitoring indicators in the simulator and both the Unit 1 and Unit 2 control rooms during the week of the onsite validation for the examination (i.e., the week of October 22, 2007).
An NRC information request was documented as Issue Report (IR) 00688723, but was only partially completed by the time the examination was given during the week of December 3, 2007. Remaining IR actions included:
- Determine the extent of the stations commitment to RG 1.97, and then per Technical Specifications Table 3.3.3-1, Post Accident Monitoring Instrumentation, identify those instruments required to be properly marked;
- Evaluate the Operations Department and labeling procedures for changes required to maintain the RG 1.97 requirements; and
- Evaluate operator training for the need to familiarize licensed operators with RG 1.97 equipment marking.
Based on information received to date, the RG 1.97 instrumentation marked with a black dot is tracked within the Passport computer database but is not procedurally controlled. The inspectors identified several instruments on the Unit 1 control panels and in the simulator that were not properly marked, and informed the licensee.
The lack of procedural controls for labeling RG 1.97 post-accident indications on the control panels appeared to be a violation of NRC requirements, but is considered an Unresolved Item (URI) to allow the licensee to gather and submit the remaining information request items for NRC review. (URI 05000456/2007301-01)
4OA6 Meetings
Exit Meeting
The chief examiner presented the examination teams preliminary observations and findings with Mr. Dudek and other members of the licensee management on December 7, 2007. A subsequent exit via teleconference was held on December 18, 2007, with Mr. Dudek following the determination that there were no site post-examination comments. No proprietary items were identified during the exit meeting with the licensee. The licensee acknowledged the observations and findings presented.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- T. Coutu, Site Vice president
- G. Dudek, Training Director
- L. Brooks, Operations Services/Operations Director
- R. Gayheart, Operations
- S. Butler, Operations Training Manager
- D. Stiles, Training/Examination Author
- S. Deprest, Corporate Operations Training
- D. Gullott, Regulatory Assurance
NRC
- N. Valos, Chief Examiner
- B. Palagi, Examiner
- C. Zoia, Examiner
- G. Roach, Resident Inspector
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
Failure to Control Regulatory Guide 1.97 Instrumentation
Marking
Closed
None
Discussed
None
LIST OF ACRONYMS
Agency-Wide Document Access and Management System
CFR
Code of Federal Regulations
Division of Reactor Safety
Initial License Test
NRC
Nuclear Regulatory Commission
Publicly Available Records System
QHPI
Quick Human Performance Investigation
Regulatory Guide
Reactor Operator
Significance Determination Process
Senior Reactor Operator
Simulator Work Request
Unresolved Item
SIMULATION FACILITY REPORT
Facility Licensee: Braidwood Nuclear Plant, Units 1 and 2
Facility Licensee Docket Nos. 50-456; 50-457
Operating Tests Administered: December 3 through December 6, 2007
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
During a normal operations evolution in a simulator scenario, the candidates
noted that two incorrect Sequence of Events (SER) points actuated when the
expected annunciator occurred. When each Main Feedwater Pump (MFP) Lube
Oil Level Test control switch was placed in the Low Level position, SER points
printed indicating High Level. Similarly, when each MFP was placed in the High
Level position, SER points printed indicating Low Level. The SER points need to
be reversed. SWR #10529 was written associated with the issue.
During the start of a Non-Essential Service Water (WS) Pump, WS header
pressure dropped from 95 psig to 75 psig before returning to 120 psig. In
addition, the control room WS HDR Press Low alarm was received.
SWR #10530 was written associated with the issue.
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession No. ML073541076.