IR 05000454/2010301
| ML103330393 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/24/2010 |
| From: | Hironori Peterson Operations Branch III |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| References | |
| 50-454/10-301, 50-455/10-301 | |
| Download: ML103330393 (14) | |
Text
November 24, 2010
SUBJECT:
BYRON STATION, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000454/2010301(DRS);
Dear Mr. Pacilio:
On October 15, 2010, U. S. Nuclear Regulatory Commission (NRC) examiners completed the initial operator licensing examination process for an examination administered at your Byron Station, Units 1 and 2. The enclosed report documents the results of the examination which were discussed during a debrief on October 6, 2010, with Mr. D. Enright, Mr. B. Adams, Ms. E. Bogue, and other members of your staff. An exit meeting was conducted by telephone on October 20, 2010, between Ms. E. Bogue, Training Manager, of your staff and Mr. M. Bielby, NRC Chief Examiner, to review the proposed final grading of the written examination for the license applicants. During the telephone conversation NRC resolutions to post examination comments initially received by the NRC on October 15, 2010, were discussed.
The NRC examiners administered an initial license examination operating test during the weeks of September 27 and October 4, 2010. The written examination was administered by the facility Training staff on October 8, 2010. Eight (8) Senior Reactor Operator (SRO) and six (6) Reactor Operator (RO) applicants were administered license examinations. One of the SRO applicants was a licensed RO at Byron Station. The results of the examination were finalized on November 10, 2010. All fourteen (14) applicants passed all sections of their respective examinations and thirteen (13) applicable operator licenses were issued. One SRO license was not issued pending completion of eligibility requirements.
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 by R. K. Walton for/
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Docket Nos. 50-454; 50-455 License No. NPF-37; NPF-66
Enclosures:
1. Operator Licensing Examination
Report 05000454/2010301(DRS); 05000455/2010301(DRS)
2. Simulation Facility Report
3. Post Examination Comments and Resolutions
4. Written Examinations and Answer Keys (RO and SRO)
REGION III==
Docket No.
50-454; 50-455
License No.
Report No:
05000454/2010301(DRS); 05000455/2010301(DRS);
Licensee:
Exelon Generation Company, LLC
Facility:
Byron Station, Units 1 and 2
Location:
Byron, IL
Dates:
September 27 - October 6, 2010
Examiners:
M. Bielby, Chief Examiner
B. Palagi, Examiner
R. Walton, Examiner
Approved by:
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000454/2010301(DRS); 05000455/2010301(DRS); 09/27/10 - 10/06/10; Exelon
Generation Company, LLC, Byron 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, Supplement 1.
Examination Summary:
$
Fourteen initial license examinations were administered (eight Senior Reactor Operator (SRO) and six Reactor Operator (RO).
$
Fourteen applicants passed all sections of their examinations resulting in the issuance of seven SRO and six RO licenses. One SRO license was not issued pending completion of eligibility requirements.
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 September 27 and October 4, 2010. 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 September 27 through October 6, 2010. The facility licensee administered the written examination on September 8, 2010. Eight Senior Reactor Operator (SRO) and six Reactor Operator (RO) applicants were examined.
During the on-site validation week of September 7, 2010, the examiners audited three license applications for accuracy.
b. Findings
Written Examination
The facility licensees training staff developed the written examination. Written examination changes agreed upon between the NRC and the licensee were made according to NUREG-1021, Revision 9, Supplement 1. Subsequent to administration, the NRC graded the written examination and conducted a review of each question to determine the accuracy and validity of the examination questions. The licensee submitted two post-examination question comments based on the applicants review by letter dated October 15, 2010, and received by NRC on October 15, 2010. The licensees recommendations included changing the correct answer to one question, and leaving one question unchanged. The contents of the letter were discussed with the licensee in advance during a pre-scheduled exit meeting by telephone on October 20, 2010. The NRC completed final grading of the written examination on November 10, 2010. The results of the NRCs review of the stations comments are documented in Enclosure 3, Post Examination Comments and Resolutions.
Operating Test
The facility licensees training staff developed the Operating Test. Operating Test changes agreed upon between the NRC and licensee were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors. The licensee submitted no post-examination comments on the Operating Test. The NRC examiners completed operating test grading on November 10, 2010.
Examination Results
Fourteen applicants passed all sections of their examinations resulting in the issuance of seven SRO and six RO licenses. One SRO license was not issued pending completion of eligibility requirements.
.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
No findings of significance were identified.
4OA6 Meetings
Exit Meeting
The chief examiner presented the examination teams preliminary observations and findings with Mr. D. Enright and other members of the licensee management and staff on October 6, 2010. An exit via teleconference was held on October 20, 2010, with Ms. E. Bogue and other members of the licensee staff following receipt of the site post-examination comments. The inspectors stated facility licensees training staff facility licensees training staff facility licensees training staff facility licensees training staff that they had reviewed proprietary information during the preparation and administration of the examination, but that the proprietary information would not be included in the examination report. The licensee acknowledged the observations provided.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- D. Enright, Site Vice President
- B. Adams, Plant Manager
- E. Bogue, Training Director
- T. Leaf, Shift Operations Superintendent
- R. Peterson, Training Instructor
- G. Pickar, Operations Training Manager
NRC
- M. Bielby, Chief Examiner
- B. Bartlett, Byron Senior Resident Inspector
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
CR
Condition Report
Division of Reactor Safety
Initial License Training
NRC
Nuclear Regulatory Commission
Publicly Available Records System
Reactor Operator
Significance Determination Process
Senior Reactor Operator
Simulator Work Order
SIMULATION FACILITY REPORT
Facility Licensee: Byron Station Units 1 and 2
Facility Licensee Docket No. 50-454; 50-455
Operating Tests Administered: September 27 - October 6, 2010
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 scenario the training building power supply breaker tripped for no
apparent reason. The failure resulted in the simulator power supply transferring
to batteries. The scenario was halted while an inspection of the power supply
was performed. No apparent cause was identified for the breaker trip and the
scenario was re-started from the failure point.
POST EXAMINATION COMMENTS AND RESOLUTIONS
Question: 053 (1.00)
Given the following plant conditions:
-Annunciator 1-1-C7, Remote S/D Panel Trouble is LIT
-SER Point 1846 is printed for Remote Shutdown Panel IA Press Low/Loss of Power
Alarm
Reference(s) Provided.
With this alarm LIT, Relay 1PSL-IA9X is __(1)__, and device 1EL-IA009 is __(2)__.
__(1)__
__(2)__
a.
de-energized
energized
b.
energized
energized
c.
energized
de-energized
d.
de-energized
de-energized
Answer: a.
Reference: Drawing 6E-1-4030IA06, Remote Shutdown Control Panel Instrument Air Header
Pressure Alarm
With low pressure, 1PSL-IA009 is open, de-energizing relay 1PSL-IA9X. Contact 1PSL-IA9X is
NC (closed), thus energizing 1EL-009. The annunciator has contact 1PSL-IA9X 3-4 which is
NC, and has to be closed to bring in the alarm.
Applicant Comment:
Choice d. is the correct answer. The question did not state that Radwaste Panel alarm
0PL01J-3-A6, Panel Inst Air Supply Press Low was lit, as would be expected if IA pressure
were low. Per NRC rules, since the alarm was not in, only a loss of power or blown fuse could
cause the listed alarm. If the annunciator circuit had lost power or fuse FU4-X or FU4-Y had
blown, then both Relay 1PSL-IA9X and device 1EL-IA009 would be de-energized.
Facility Proposed Resolution:
The licensee disagrees with the applicants recommended correct answer.
During the exam, the applicant asked for the following clarification on Question 53: Is the
failure a fuse or just a loss of air? The proctors response was delayed while the clarification
was being researched. However, in the interim, the applicant turned in his exam and left the
exam area.
POST EXAMINATION COMMENTS AND RESOLUTIONS
With 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> remaining before the end of the RO exam, the proctors response was Fuses are
intact and the annunciator circuit has power available which would have made choice a. the
only correct answer. No change to the original answer or grading is requested.
NRC Resolution:
Recommendation accepted. The recommendation is supported by a review of the electrical
drawing. The applicant was correct in his explanation of why answer d. could have been
correct based on the given question stem information and the assumptions made. However, the
applicant chose to turn in his exam and leave the exam area before further clarification supplied
by the proctor refuted the applicants assumption and made a. the only possible correct
answer. Based on the pre-and post-examination review by licensee training staff, licensed
operators and NRC examiners, the exam question and proctor clarification clearly did not
change the original answer. Therefore, the question answer will remain unchanged from the as
administered examination.
POST EXAMINATION COMMENTS AND RESOLUTIONS
Question: 091 (1.00)
Given the following plant conditions:
- Unit 1 is at 60 % power
- The controlling Pressurizer Level channel indicates 100%
- The other hot calibrated pressurizer Level channels indicate 40%
- CHG LINE FLOW HIGH LOW (1-9-D3) is LIT
- The AUTO and DECREASE lights on 1CV121 M/A Controller are LIT
There is __(1)__ GPM charging flow. The SRO will direct __(2)__ to address the failure.
a..
locally bypassing 1CV121 per BOP CV-26, CV Valves
Bypassing, Isolating and Restoration
b.
locally bypassing 1CV121 per BOP CV-26, CV Valves
Bypassing, Isolating and Restoration
c.
manual control of 1CV121 per 1BOA Inst-2, Operation
with a Failed Instrument Channel
d.
manual control of 1CV121 per 1BOA Inst-2, Operation
with a Failed Instrument Channel
Answer: a.
Reference: 1 BOA Inst-2, Operation with a Failed Instrument Channel, BCB-1, Fig 4.
Applicant Comment:
Choice d. is the correct answer. The controller for 1CV121 is controlled in automatic by the
Master Pressurizer Level controller. When the Master Pressurizer Level controller output goes
to minimum demand, it lowers the 1CV121 controller demand to about 26%. The 1CV121
Decrease light does not go on. 1CV121 has a control bias to maintain about 52 GPM charging
flow. For the given indication in the question that 1CV121 controller Decrease light is lit, there
must be 0% demand on 1CV121, indicating 1CV121 is closed. In this situation, charging flow
will be 0 GPM. Change correct answer to d.
Facility Proposed Resolution:
In the past, when the Master Pressurizer Level controller was at minimum, charging flow would
be maintained at 52 GPM and the 1CV121 Decrease light would be lit. However, Simulator
Work Request (SWR) 11733 M/A Station for 1CV121 should indicate approximately 26% in
Auto when at minimum flow of 52 GPM was created on 5/14/2009, based on IR 918608. The
simulator was subsequently changed so that when the Master Pressurizer Level controller has
minimum demand output, 1CV121 Decrease light is not lit, and there is 52 GPM charging flow.
POST EXAMINATION COMMENTS AND RESOLUTIONS
For the conditions stated in the question, if 1CV121 Decrease light is lit, 1CV121 will be fully
closed, and charging flow will be 0 GPM, as stated in choice d. The facility agrees with the
applicants comment, change the correct answer to choice d.
NRC Resolution:
Recommendation accepted. The examiners reviewed the referenced IR and SWR, and had the
licensee verify the correct operation of the Master Pressurizer Level controller output, the
1CV121 controller, and the 1CV121 Decrease light with the System Engineer and Instrument
Maintenance. The examiners also discussed the question review performed by various licensed
operators and training staff with the Training Manager who agreed this was a potential training
weakness that needs to be emphasized in requal training.
Choice a. was initially determined to be correct; however, based on additional reference
information provided, and verification of the current operation of the Master Pressurizer Level
controller, 1CV121 controller, and 1CV121 Decrease light by the System Engineer and
Instrument Maintenance, choice a. was determined to be incorrect, and the correct answer
was changed to d.
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession #ML103330449.
The release of the RO/SRO Initial Examination will be delayed until October 8, 2012.
M. Pacilio
-2-
We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA by R. K. Walton for/
Hironori Peterson, Chief
Operations Branch
Division of Reactor Safety
Docket Nos. 50-454; 50-455
Enclosures:
1. Operator Licensing Examination
Report 05000454/2010301(DRS); 05000455/2010301(DRS)
2. Simulation Facility Report
3. Post Examination Comments and Resolutions
4. Written Examinations and Answer Keys (RO and SRO)
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