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| issue date = 11/29/2012
| issue date = 11/29/2012
| title = Er 05000352-12-301 and 05000353-12-301, on October 9 - 19, 2012, Limerick Generating Station Units 1 and 2, Initial Operator Licensing Examination Report
| title = Er 05000352-12-301 and 05000353-12-301, on October 9 - 19, 2012, Limerick Generating Station Units 1 and 2, Initial Operator Licensing Examination Report
| author name = Jackson D E
| author name = Jackson D
| author affiliation = NRC/RGN-I/DRS/OB
| author affiliation = NRC/RGN-I/DRS/OB
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000352, 05000353
| docket = 05000352, 05000353
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA, PENNSYLVANIA 19406.2713 November 29, ?ALz Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd.Warrenville, lL 60555
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA, PENNSYLVANIA 19406.2713
==SUBJECT:==
LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PO RT 05000352/20 1 230 1 and 05000 353120 1 2301


SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PO RT 05000352/20 1 230 1 and 05000 353120 1 2301
==Dear Mr. Pacilio:==
On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.


==Dear Mr. Pacilio:==
The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.
On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants.


The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.No findings were identified during this examination.
No findings were identified during this examination.


In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.oov/readinq- rm/adams.html (the Public Electronic Reading Room).Donald E. Jackson, Chief Operations Branch Division of Reactor Safety DocketNos.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.oov/readinq-rm/adams.html (the Public Electronic Reading Room).


50-352,50-353 License Nos. NPF-39, NPF-85 Mr. MichaelJ.
Donald E. Jackson, Chief Operations Branch Division of Reactor Safety DocketNos. 50-352,50-353 License Nos. NPF-39, NPF-85


Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd.Warrenville, lL 60555
Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd.


SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PORT 05000352/
Warrenville, lL 60555 SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PORT 05000352/ 20 1230 1 and 05000 353l 20 1 230 1
20 1230 1 and 05000 353 l 20 1 230 1


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==
On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants.
On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.


The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.No findings were identified during this examination.
The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.


ln accordance with 10 CFR 2390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.qov/readinq- rm/adams.html (the Public Electronic Reading Room).
No findings were identified during this examination.
 
ln accordance with 10 CFR 2390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).


Sincerely,
Sincerely,
/RN Donald E. Jackson, Chief Operations Branch Division of Reactor SafetY DocketNos.
/RN Donald E. Jackson, Chief Operations Branch Division of Reactor SafetY DocketNos. 50-352,50-353 License Nos. NPF-39, NPF-85 DOCUMENT NAME: G:\DRS\Operations Branch\CARUSO\Exam 13-LGS Oct12 NRC (U01858)\2012 LGS-EMM REPORT.doc ADAMS ACCESSION NUMBER: M112334A183 g Non-Sensitive  V Publicly Available V suNslReview tr Sensitive  D Non-PubliclyAvailable OFFICE RI/DRS RI/DRS NAME JCaruso DJackson DATE 11t20t12 11t29112 OFFICIAL RECORD PY


50-352,50-353 License Nos. NPF-39, NPF-85 DOCUMENT NAME: G:\DRS\Operations Branch\CARUSO\Exam 13-LGS Oct12 NRC (U01858)\2012 LGS-EMM REPORT.doc ADAMS ACCESSION NUMBER: M112334A183 V suNslReview g Non-Sensitive tr Sensitive V Publicly Available D Non-PubliclyAvailable OFFICE RI/DRS RI/DRS NAME JCaruso DJackson DATE 11t20t12 11t29112 PY OFFICIAL RECORD Enclosure:
===Enclosure:===
NRC Examination Report 0500035212012301 and 0500035312012301 w/Attachment:
NRC Examination Report 0500035212012301 and 0500035312012301 w/Attachment: Supplemental Information
Supplemental Information cc Mencl: Distribution via ListServ Distribution w/encl: W. Dean, RA (RIORAMAIL Resource)D. Lew, DRA (Rf ORAMAIL Resource)D. Roberts, DRP (RIDRPMAIL Resource)P. Wilson, DRP (RlDRPMail Resource)C. Miller, DRS (RiDRSMail Resource)J. Clifford, DRS (RlDRSMail Resource)D. Jackson, DRS J. Caruso, DRS P. Krohn, DRP A. Rosebrook, DRP S. lbarrola.


DRP E. DiPaolo, DRP, SRI J. Hawkins, DRP, Rl N. Esch, DRP, AA C. Santos, Rl, OEDO RidsNrrPMLimerick Resource RidsNrrDorlLpl 1 -2 Resource ROPrepo(s Resource DRS Master Exam File (C. Bixler) (w/concurrences)
REGION I Dockets: 50-352, 50-353 Licenses: NPF-39, NPF-85 Report: 05000352/201 2301 and 05000 3531 20 1 2301 Licensee: Exelon Generation Company, LLC Facility: Limerick Generating Station, Units 1 and 2 Location: Sanatoga, PA 19464 Dates: October 9-15, 2A12 (Operating Test Administration)
DRS File Dockets: Licenses: Report: Licensee: Facility: Location: Dates: Examiners:
Approved by: U,S. NUCLEAR REGULATORY COMMISSION REGION I 50-352, 50-353 NPF-39, NPF-85 05000352/201 2301 and 05000 3531 20 1 2301 Exelon Generation Company, LLC Limerick Generating Station, Units 1 and 2 Sanatoga, PA 19464 October 9-15, 2A12 (Operating Test Administration)
October 19, 2012 (Written Examination Administration)
October 19, 2012 (Written Examination Administration)
October 26,2Q12 (Licensee Submitted Post Exam Package)October 16 - November 14, 2012 (NRC Examination Grading)November 15, 2012 (Licenses lssued)J. Caruso, Chief Examiner, Operations Branch S. Hansell, Senior Resident Inspector/Examiner C. Lally, Operations Engineer M. Patel, Operations Engineer J. DeMarshall, Reactor Operations Engineer (Certification Exam)J. Tomlinson, Operations Engineer (Part Time)Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Enclosure A.B,
October 26,2Q12 (Licensee Submitted Post Exam Package)
October 16 - November 14, 2012 (NRC Examination Grading)
November 15, 2012 (Licenses lssued)
Examiners: J. Caruso, Chief Examiner, Operations Branch S. Hansell, Senior Resident Inspector/Examiner C. Lally, Operations Engineer M. Patel, Operations Engineer J. DeMarshall, Reactor Operations Engineer (Certification Exam)
J. Tomlinson, Operations Engineer (Part Time)
Approved by: Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Enclosure


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
ER 0500035212012301 and 05000353/2012301;
ER 0500035212012301 and 05000353/2012301; October 9 - 19, 2012; Limerick Generating
October 9 - 19, 2012; Limerick Generating Station Units 1 and2 lnitial Operator Licensing Examination Report.NRC examiners evaluated four reactor operator applicants, five instant senior reactor operator (SRO) applicants, and two upgrade senior reactor operator applicants at Limerick Generating Station, Units 1 and 2. The NRC developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the facitity on October 19,2012. NRC examiners administered the operating tests on October 9-15,2012.


The license examiners determined that eight of 1 1 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade SRO license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501. D.3.c.NRC-ldentified and Self-Revealinq Findinss No findings were identified.
Station Units 1 and2 lnitial Operator Licensing Examination Report.


Licensee-ldentified Violations No findings were identified.
NRC examiners evaluated four reactor operator applicants, five instant senior reactor operator (SRO) applicants, and two upgrade senior reactor operator applicants at Limerick Generating Station, Units 1 and 2. The NRC developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the facitity on October 19,2012. NRC examiners administered the operating tests on October 9-15,2012. The license examiners determined that eight of 1 1 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade SRO license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501. D.3.c.


1..1
A.       NRC-ldentified and Self-Revealinq Findinss No findings were identified.
 
B,      Licensee-ldentified Violations No findings were identified.


=REPORT DETAILS=
=REPORT DETAILS=
Line 71: Line 77:
==REACTOR SAFETY==
==REACTOR SAFETY==


===Cornerstone:===
===Cornerstone: Mitigating Systems    - Reactor Operator (RO) and Senior Reactor Operator===


Mitigating Systems - Reactor Operator (RO) and Senior Reactor Operator (SRO) Initial License Examination License Applications
      (SRO) Initial License Examination
 
===.1 License Applications===


====a. Scope====
====a. Scope====
The examiners reviewed all 11 license applications submitted by the licensee to ensure that each applicant satisfied relevant license eligibility requirements.
The examiners reviewed all 11 license applications submitted by the licensee to ensure that each applicant satisfied relevant license eligibility requirements. The applications were submitted on NRC Form 398, "Personal Qualification Statement," and NRC Form 396, "Certification of Medical Examination by Facility Licensee." The examiner also audited nine of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and onthe-job training, including control manipulations that provided significant reactivity changes.


The applications were submitted on NRC Form 398, "Personal Qualification Statement," and NRC Form 396, "Certification of Medical Examination by Facility Licensee." The examiner also audited nine of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications.
b. Findinqs No findings were identified.


This audit focused on the applicant's experience and onthe-job training, including control manipulations that provided significant reactivity changes.Findinqs No findings were identified.
,2    Operator Knowledqe and Performance


Operator Knowledqe and Performance Examination Scope On October 19,2012, the licensee proctored the administration of the written examinations to all 11 applicants.
====a. Examination Scope====
On October 19,2012, the licensee proctored the administration of the written examinations to all 11 applicants. The licensee staff graded the written examinations in parallel with the NRC, analyzed the results, and presented their analysis to the NRC on October 26.2012.


The licensee staff graded the written examinations in parallel with the NRC, analyzed the results, and presented their analysis to the NRC on October 26.2012.The NRC examination team administered the various portions of the operating examination to all 11 applicants during the period, October 9-15,2012.
The NRC examination team administered the various portions of the operating examination to all 11 applicants during the period, October 9-15,2012. The four applicants for reactor operator licenses participated in two to three dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of four administrative tasks. The five applicants seeking an instant senior operator license participated in three dynamic simulator scenarios, a control room and facilities walkthrough test consisting of 10 system tasks, and an administrative test consisting of five administrative tasks. The two applicants seeking an upgrade senior operator license participated in one dynamic simulator scenario, a control room and facilities walkthrough test consisting of five system tasks, and an administrative test consisting of five administrative tasks.


The four applicants for reactor operator licenses participated in two to three dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of four administrative tasks. The five applicants seeking an instant senior operator license participated in three dynamic simulator scenarios, a control room and facilities walkthrough test consisting of 10 system tasks, and an administrative test consisting of five administrative tasks. The two applicants seeking an upgrade senior operator license participated in one dynamic simulator scenario, a control room and facilities walkthrough test consisting of five system tasks, and an administrative test consisting of five administrative tasks.,2 b.a.Enclosure b.2 Findinqs Eight of 11 applicants passed all parts of the examination (i.e., two applicants failed the operating test and one failed the written exam). For the written examinations, the reactor operator applicants' average score was 85.33 percent and ranged from 84.00 to 88.00 percent, the senior operator applicants' average score was 86.42 percent and ranged from 77,00 to 91.00 percent. The overall written examination average was 86.02 percent. In accordance with current NRC policy, the release of this written examination will be delayed for 2 years. The text of the examination questions, and the licensee's examination analysis may be accessed in the Agencyruide Documents Access and Management System (ADAMS) under the accession numbers noted in attachment 1.Chapter ES-403 and Form ES-403-1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants.
b. Findinqs Eight of 11 applicants passed all parts of the examination (i.e., two applicants failed the operating test and one failed the written exam). For the written examinations, the reactor operator applicants' average score was 85.33 percent and ranged from 84.00 to 88.00 percent, the senior operator applicants' average score was 86.42 percent and ranged from 77,00 to 91.00 percent. The overall written examination average was 86.02 percent. In accordance with current NRC policy, the release of this written examination will be delayed for 2 years. The text of the examination questions, and the licensee's examination analysis may be accessed in the Agencyruide Documents Access and Management System (ADAMS) under the accession numbers noted in attachment 1.


The licensee conducted this performance analysis for six questions that met these criteria and submitted the analysis to the chief examiner.
Chapter ES-403 and Form ES-403-1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants. The licensee conducted this performance analysis for six questions that met these criteria and submitted the analysis to the chief examiner. This analysis concluded that all six of these questions were valid as written. There were no post written examination comments submitted by the licensee.


This analysis concluded that all six of these questions were valid as written. There were no post written examination comments submitted by the licensee.lnitial Licensinq Examination Development Examination Scooe The NRC developed the examinations in accordance with NUREG-1021 , Revision 9, Supplement
===.3 lnitial Licensinq Examination Development===


===1. All licensee facility training and operations ===
a. Examination Scooe The NRC developed the examinations in accordance with NUREG-1021 , Revision 9, Supplement 1. All licensee facility training and operations staff involved in examination review, validation, and administration were listed on a security agreement, The NRC conducted an onsite pre-validation of the operating examinations the week of August 6,2012 and a final validation of the operating examinations the week of September 10,2012. The licensee was afforded an opportunity to provide comments during these periods and the NRC Chief Examiner ensured resolution of all licensee comments prior to operating examination approval' b. Findinqs No findings were identified.


staff involved in examination review, validation, and administration were listed on a security agreement, The NRC conducted an onsite pre-validation of the operating examinations the week of August 6,2012 and a final validation of the operating examinations the week of September 10,2012. The licensee was afforded an opportunity to provide comments during these periods and the NRC Chief Examiner ensured resolution of all licensee comments prior to operating examination approval'Findinqs No findings were identified.
===.4 Simulation Facilitv Performance===


Simulation Facilitv Performance Examination Scope The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.
====a. Examination Scope====
The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.


Findinqs No findings were identified.
b. Findinqs No findings were identified.


===.3 a..4===
===.5 Examination Securitv===
b.a.b.Enclosure 3.5 Examination Securitv a. Examination Scope The examiners reviewed examination security for examination development and during both the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements.


Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
====a. Examination Scope====
The examiners reviewed examination security for examination development and during both the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.


b. Findinqs No findings were identified.
b. Findinqs No findings were identified.


4OAO Meetinos.
4OAO Meetinos. Includinq Exit The chief examiner presented examination results to Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director, on November 15, 2012.


Includinq Exit The chief examiner presented examination results to Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director, on November 15, 2012.The licensee did not identify any information or materials used during the examination as proprietary.
The licensee did not identify any information or materials used during the examination as proprietary.
:
:
Supplemental I nformation A-1 ATTACHMENT
Supplemental I nformation ATTACHMENT


=SUPPLEMENTAL
=SUPPLEMENTAL INFORMATION=
INFORMATION=


KEY POINTS OF CONTACT  
KEY POINTS OF CONTACT
===Licensee Personnel===
===Licensee Personnel===
: [[contact::A. Wasong]], Training Director  
: [[contact::A. Wasong]], Training Director
: [[contact::R. Kreider]], Operations
: [[contact::R. Kreider]], Operations Director
Director  
: [[contact::M. Gillin]], Shift Operations Superintendent
: [[contact::M. Gillin]], Shift Operations
: [[contact::J. Murphy]], Senior Manager Operations Support and Services
Superintendent
: [[contact::R. Ruffe]], Operations Training Director
: [[contact::J. Murphy]], Senior Manager Operations
: [[contact::J. Walton]], Licensed Operator lnitial Training Lead
Support and Services  
: [[contact::H. Weissinger]], Operations Shift Manager
: [[contact::R. Ruffe]], Operations
: [[contact::L. Stanford]], Exam Team Lead
Training Director  
: [[contact::J. Walton]], Licensed Operator lnitial Training Lead  
: [[contact::H. Weissinger]], Operations
Shift Manager  
: [[contact::L. Stanford]], Exam Team Lead  
===NRC Personnel===
===NRC Personnel===
: [[contact::J. Caruso]], Chief Examiner  
: [[contact::J. Caruso]], Chief Examiner
: [[contact::S. Hansell]], Senior Resident Inspector/Examiner
: [[contact::S. Hansell]], Senior Resident Inspector/Examiner
: [[contact::C. Lally]], Operations
: [[contact::C. Lally]], Operations Engineer
Engineer  
: [[contact::M. Patel]], Operations Engineer
: [[contact::M. Patel]], Operations
: [[contact::J. DeMarshall]], Senior Operations Engineer (Certification Exam)
Engineer  
: [[contact::J. Tomlinson]], Operations Engineer (Part Time)
: [[contact::J. DeMarshall]], Senior Operations
ITEMS OPENED, CLOSED, AND DISCUSSED
Engineer (Certification
Opened/C losed/Discussed
Exam)
NONE
: [[contact::J. Tomlinson]], Operations
ADAMS DOGUMENTS REFERENCED
Engineer (Part Time)ITEMS OPENED, CLOSED, AND DISCUSSED Opened/C losed/Discussed
Accession No. ML123254303     - FINAL-Written Exam
NONE ADAMS DOGUMENTS
Accession No. ML123254335     - FINAl-Written Exam Performance Analysis
REFERENCED
Accession No. ML12325A347     - FINAL-Operating Exam (Sections A, B, and C)
Accession
 
No. ML123254303 - FINAL-Written
ES-501                               Simulator Fidelity Report                   Attachment 2
Exam Accession
Facility:           Limerick Generating Station Units 1 and 2
No. ML123254335 - FINAl-Written
Facility Docket No.:                 50-352: 50-353
Exam Performance
Operating Test Administered on:           October 9 - 15,2012
Analysis Accession
This form is to be used only to report obseruations. These obseruations do not constitute
No. ML12325A347 - FINAL-Operating
audit or inspection findings and, without further verification and review in accordance with lP
Exam (Sections
71111.11 , are not indicative of noncompliance with 10 CFR 55.46.
A, B, and C)Attachment
While conducting the simulator portion of the operating tests, examiners observed the
ES-501 Simulator
following item:
Fidelity Report Attachment
Item                                       Description
Facility: Limerick Generating
During the JPM "E" administration, "Synchronize and load D12 Diesel
Station Units 1 and 2 Facility Docket No.: 50-352: 50-353 Operating
Generator to 1000 1(W", when closing the EDG breaker the EDG
Test Administered
breaker tripped on four different occasions. The licensee indicated that
on: October 9 - 15,2012 This form is to be used only to report obseruations.
a simulator electric plant mod was installed about 6 months ago that
These obseruations
might have unintentionally caused this issue. SWR 2012084114329
do not constitute
Simulator Vibration Monitoring System (VMS): Observed during Exam
audit or inspection
Validation that the screen vibration color did not change from yellow to
findings and, without further verification
red when the danger alarm was received for the "1A" Recirculation
and review in accordance
with lP 71111.11 , are not indicative
of noncompliance
with 10 CFR 55.46.While conducting
the simulator
portion of the operating
tests, examiners
observed the following
item: Item Description
During the JPM "E" administration, "Synchronize
and load D12 Diesel Generator
to 1000 1(W", when closing the EDG breaker the EDG breaker tripped on four different
occasions.
The licensee indicated
that a simulator
electric plant mod was installed
about 6 months ago that might have unintentionally
caused this issue. SWR 2012084114329
Simulator
Vibration
Monitoring
System (VMS): Observed during Exam Validation
that the screen vibration
color did not change from yellow to red when the danger alarm was received for the "1A" Recirculation
Pump. SWR 2001298/2680
Pump. SWR 2001298/2680
No malfunction
No malfunction currently exists for simulating a runaway Recirculation
currently
Pump with the new Adjustable Speed Drive (ASD) controller. ln order
exists for simulating
to simulate this malfunction, the Booth Operator had to repeatedly
a runaway Recirculation
insert a 10 RPM raise pushbutton override and then immediately
Pump with the new Adjustable
delete the override to prevent pushbutton lockout. lt was only possible
Speed Drive (ASD) controller.
to simulate an ASD controller incremental speed increase rather than
ln order to simulate this malfunction, the Booth Operator had to repeatedly
an actual runaway pump, as can be done with the Unit 2 Recirc MG
insert a 10 RPM raise pushbutton
Sets. lR 1441285
override and then immediately
 
delete the override to prevent pushbutton
Item                 Procedural lssues ldentified                 Attachment 3
lockout. lt was only possible to simulate an ASD controller
OT-112 provides no direct guidance for monitoring/managing Thermal
incremental
Hydraulic lnstability (THl), except in Attachment 3, which is only entered if
speed increase rather than an actual runaway pump, as can be done with the Unit 2 Recirc MG Sets. lR 1441285 Attachment
allfour OPRMs are inoperable due to common cause failure. lR 1441184
Item Procedural
Event procedure E-D134 does not address Refuel Floor isolation on Low
lssues ldentified
Zone differential pressure and the fact that both Standby Gas Treatment
1 OT-112 provides no direct guidance for monitoring/managing
Fans will start and draw down the Refuel Floor several minutes after a loss
Thermal Hydraulic
of D-134. lR 1441184
lnstability (THl), except in Attachment
The examiners observed that some of the applicants when performing
3, which is only entered if allfour OPRMs are inoperable
sync of the EDG in accordance with procedure S92.1.O.had the sync
due to common cause failure. lR 1441184 2 Event procedure
scope rotating faster than expected in the fast direction and closed the
E-D134 does not address Refuel Floor isolation
EDG output breaker in on the bus at the five past twelve position. The
on Low Zone differential
current procedure does not define what "slow in the fact direction" means.
pressure and the fact that both Standby Gas Treatment Fans will start and draw down the Refuel Floor several minutes after a loss of D-134. lR 1441184 3 The examiners
A suggestion was made to benchmark other utilities and consider
observed that some of the applicants
enhancing procedural guidance in S92.1.O.for sync scope rotation to
when performing
define what "slow in the fast direction" means. ]R 1441285
sync of the EDG in accordance
Event procedure E-D134 directs performance of 576.8.8 for Manually
with procedure
lnitiating a Reactor Enclosure Secondary Containment lsolation. Either
S92.1.O.had
Section 4.4 or 4.5 may be used to accomplish the Manual Initiation.
the sync scope rotating faster than expected in the fast direction
Section 4.5, "Reactor Enclosure Secondary Containment Manual Low DP
and closed the EDG output breaker in on the bus at the five past twelve position.
lsolation," is desirable from the standpoint that the associated actions do
The current procedure
not result in PCIG Containment Valve lsolations. However, Step 4.5.5 for
does not define what "slow in the fact direction" means.A suggestion
initiating an "A" Channel lsolation is unable to be performed due to the
was made to benchmark
Loss of D134 (i.e., no power to N2 Inerting Block Valve, HV-57-1604). lt
other utilities
was unclear as to whether or not Section 4.5 can be successfully
and consider enhancing
accomplished if unable to perform this step associated with initiating a
procedural
Channel "A" lsolation. lR 1441184
guidance in S92.1.O.for
GP5, Appendix 2, Rev. 67, step 3.1 .1.2.c incorrectly references
sync scope rotation to define what "slow in the fast direction" means. ]R 1441285 4 Event procedure
on Page 11. The step should reference Attachment 2.
E-D134 directs performance
tR 1441184
of 576.8.8 for Manually lnitiating
SE-10 has no bases document, and provides no basis for injecting SLC
a Reactor Enclosure
post-LOCA. !R1441184
Secondary
The simulator malfunction guide, MPR01 1B lists 108 E-3 as an expected
Containment
annunciator. The actual annunciator number is 108 F-3. lR 1441184
lsolation.
I S51.6.8 provides no direct guidance to close the RHR F009 valve, instead
Either Section 4.4 or 4.5 may be used to accomplish
it is relied on to be closed in S51.8.L lR 1441184
the Manual Initiation.
T-117 LQ-11 says 'reator' instead of 'reactor' lR 1441184
Section 4.5, "Reactor Enclosure
Attachment
Secondary
Containment
Manual Low DP lsolation," is desirable
from the standpoint
that the associated
actions do not result in PCIG Containment
Valve lsolations.
However, Step 4.5.5 for initiating
an "A" Channel lsolation
is unable to be performed
due to the Loss of D134 (i.e., no power to N2 Inerting Block Valve, HV-57-1604).
lt was unclear as to whether or not Section 4.5 can be successfully
accomplished
if unable to perform this step associated
with initiating
a Channel "A" lsolation.
lR 1441184 5 GP5, Appendix 2, Rev. 67, step 3.1 .1.2.c incorrectly
references
on Page 11. The step should reference
2.tR 1441184 6 SE-10 has no bases document, and provides no basis for injecting
SLC post-LOCA.  
!R1441184 7 The simulator
malfunction
guide, MPR01 1B lists 108 E-3 as an expected annunciator.
The actual annunciator
number is 108 F-3. lR 1441184 I S51.6.8 provides no direct guidance to close the RHR F009 valve, instead it is relied on to be closed in S51.8.L lR 1441184 9 T-117 LQ-11 says 'reator' instead of 'reactor'
lR 1441184 Attachment
}}
}}

Latest revision as of 20:39, 11 November 2019

Er 05000352-12-301 and 05000353-12-301, on October 9 - 19, 2012, Limerick Generating Station Units 1 and 2, Initial Operator Licensing Examination Report
ML12334A183
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/29/2012
From: Diane Jackson
Operations Branch I
To: Pacilio M
Exelon Generation Co, Exelon Nuclear
Shared Package
ML120230224 List:
References
50-352/12-301, 50-353/12-301
Download: ML12334A183 (12)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA, PENNSYLVANIA 19406.2713

SUBJECT:

LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PO RT 05000352/20 1 230 1 and 05000 353120 1 2301

Dear Mr. Pacilio:

On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.

The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.

No findings were identified during this examination.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.oov/readinq-rm/adams.html (the Public Electronic Reading Room).

Donald E. Jackson, Chief Operations Branch Division of Reactor Safety DocketNos. 50-352,50-353 License Nos. NPF-39, NPF-85

Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd.

Warrenville, lL 60555 SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - NRC EXAMINATION RE PORT 05000352/ 20 1230 1 and 05000 353l 20 1 230 1

Dear Mr. Pacilio:

On October 19,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator licensing examination at Limerick Generating Station, Units 1 and 2. The enclosed report documents the examination findings, which were discussed on November 15,2012, with Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director and other members of your staff.

The examination included the evaluation of four reactor operator applicants, five instant senior reactor operator applicants, and two upgrade senior reactor operator applicants. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The license examiners determined that eight of 11 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade senior reactor operator (SRO) license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501, D.3.c.

No findings were identified during this examination.

ln accordance with 10 CFR 2390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RN Donald E. Jackson, Chief Operations Branch Division of Reactor SafetY DocketNos. 50-352,50-353 License Nos. NPF-39, NPF-85 DOCUMENT NAME: G:\DRS\Operations Branch\CARUSO\Exam 13-LGS Oct12 NRC (U01858)\2012 LGS-EMM REPORT.doc ADAMS ACCESSION NUMBER: M112334A183 g Non-Sensitive V Publicly Available V suNslReview tr Sensitive D Non-PubliclyAvailable OFFICE RI/DRS RI/DRS NAME JCaruso DJackson DATE 11t20t12 11t29112 OFFICIAL RECORD PY

Enclosure:

NRC Examination Report 0500035212012301 and 0500035312012301 w/Attachment: Supplemental Information

REGION I Dockets: 50-352, 50-353 Licenses: NPF-39, NPF-85 Report: 05000352/201 2301 and 05000 3531 20 1 2301 Licensee: Exelon Generation Company, LLC Facility: Limerick Generating Station, Units 1 and 2 Location: Sanatoga, PA 19464 Dates: October 9-15, 2A12 (Operating Test Administration)

October 19, 2012 (Written Examination Administration)

October 26,2Q12 (Licensee Submitted Post Exam Package)

October 16 - November 14, 2012 (NRC Examination Grading)

November 15, 2012 (Licenses lssued)

Examiners: J. Caruso, Chief Examiner, Operations Branch S. Hansell, Senior Resident Inspector/Examiner C. Lally, Operations Engineer M. Patel, Operations Engineer J. DeMarshall, Reactor Operations Engineer (Certification Exam)

J. Tomlinson, Operations Engineer (Part Time)

Approved by: Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

ER 0500035212012301 and 05000353/2012301; October 9 - 19, 2012; Limerick Generating

Station Units 1 and2 lnitial Operator Licensing Examination Report.

NRC examiners evaluated four reactor operator applicants, five instant senior reactor operator (SRO) applicants, and two upgrade senior reactor operator applicants at Limerick Generating Station, Units 1 and 2. The NRC developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the facitity on October 19,2012. NRC examiners administered the operating tests on October 9-15,2012. The license examiners determined that eight of 1 1 applicants satisfied the requirements of 10 CFR Part 55, and seven licenses were issued on November 15, 2012. One of applicants for an upgrade SRO license passed the exam but his license is being held based on his SRO only written exam grade until the applicant who failed the written examination has had an opportunity to appeal his license denial in accordance with ES-501. D.3.c.

A. NRC-ldentified and Self-Revealinq Findinss No findings were identified.

B, Licensee-ldentified Violations No findings were identified.

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Mitigating Systems - Reactor Operator (RO) and Senior Reactor Operator

(SRO) Initial License Examination

.1 License Applications

a. Scope

The examiners reviewed all 11 license applications submitted by the licensee to ensure that each applicant satisfied relevant license eligibility requirements. The applications were submitted on NRC Form 398, "Personal Qualification Statement," and NRC Form 396, "Certification of Medical Examination by Facility Licensee." The examiner also audited nine of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and onthe-job training, including control manipulations that provided significant reactivity changes.

b. Findinqs No findings were identified.

,2 Operator Knowledqe and Performance

a. Examination Scope

On October 19,2012, the licensee proctored the administration of the written examinations to all 11 applicants. The licensee staff graded the written examinations in parallel with the NRC, analyzed the results, and presented their analysis to the NRC on October 26.2012.

The NRC examination team administered the various portions of the operating examination to all 11 applicants during the period, October 9-15,2012. The four applicants for reactor operator licenses participated in two to three dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of four administrative tasks. The five applicants seeking an instant senior operator license participated in three dynamic simulator scenarios, a control room and facilities walkthrough test consisting of 10 system tasks, and an administrative test consisting of five administrative tasks. The two applicants seeking an upgrade senior operator license participated in one dynamic simulator scenario, a control room and facilities walkthrough test consisting of five system tasks, and an administrative test consisting of five administrative tasks.

b. Findinqs Eight of 11 applicants passed all parts of the examination (i.e., two applicants failed the operating test and one failed the written exam). For the written examinations, the reactor operator applicants' average score was 85.33 percent and ranged from 84.00 to 88.00 percent, the senior operator applicants' average score was 86.42 percent and ranged from 77,00 to 91.00 percent. The overall written examination average was 86.02 percent. In accordance with current NRC policy, the release of this written examination will be delayed for 2 years. The text of the examination questions, and the licensee's examination analysis may be accessed in the Agencyruide Documents Access and Management System (ADAMS) under the accession numbers noted in attachment 1.

Chapter ES-403 and Form ES-403-1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants. The licensee conducted this performance analysis for six questions that met these criteria and submitted the analysis to the chief examiner. This analysis concluded that all six of these questions were valid as written. There were no post written examination comments submitted by the licensee.

.3 lnitial Licensinq Examination Development

a. Examination Scooe The NRC developed the examinations in accordance with NUREG-1021 , Revision 9, Supplement 1. All licensee facility training and operations staff involved in examination review, validation, and administration were listed on a security agreement, The NRC conducted an onsite pre-validation of the operating examinations the week of August 6,2012 and a final validation of the operating examinations the week of September 10,2012. The licensee was afforded an opportunity to provide comments during these periods and the NRC Chief Examiner ensured resolution of all licensee comments prior to operating examination approval' b. Findinqs No findings were identified.

.4 Simulation Facilitv Performance

a. Examination Scope

The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.

b. Findinqs No findings were identified.

.5 Examination Securitv

a. Examination Scope

The examiners reviewed examination security for examination development and during both the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.

b. Findinqs No findings were identified.

4OAO Meetinos. Includinq Exit The chief examiner presented examination results to Messrs. Anthony Wasong, Training Director and Robert Kreider, Operations Director, on November 15, 2012.

The licensee did not identify any information or materials used during the examination as proprietary.

Supplemental I nformation ATTACHMENT

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

A. Wasong, Training Director
R. Kreider, Operations Director
M. Gillin, Shift Operations Superintendent
J. Murphy, Senior Manager Operations Support and Services
R. Ruffe, Operations Training Director
J. Walton, Licensed Operator lnitial Training Lead
H. Weissinger, Operations Shift Manager
L. Stanford, Exam Team Lead

NRC Personnel

J. Caruso, Chief Examiner
S. Hansell, Senior Resident Inspector/Examiner
C. Lally, Operations Engineer
M. Patel, Operations Engineer
J. DeMarshall, Senior Operations Engineer (Certification Exam)
J. Tomlinson, Operations Engineer (Part Time)

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened/C losed/Discussed

NONE

ADAMS DOGUMENTS REFERENCED

Accession No. ML123254303 - FINAL-Written Exam

Accession No. ML123254335 - FINAl-Written Exam Performance Analysis

Accession No. ML12325A347 - FINAL-Operating Exam (Sections A, B, and C)

ES-501 Simulator Fidelity Report Attachment 2

Facility: Limerick Generating Station Units 1 and 2

Facility Docket No.: 50-352: 50-353

Operating Test Administered on: October 9 - 15,2012

This form is to be used only to report obseruations. These obseruations do not constitute

audit or inspection findings and, without further verification and review in accordance with lP

71111.11 , are not indicative of noncompliance with 10 CFR 55.46.

While conducting the simulator portion of the operating tests, examiners observed the

following item:

Item Description

During the JPM "E" administration, "Synchronize and load D12 Diesel

Generator to 1000 1(W", when closing the EDG breaker the EDG

breaker tripped on four different occasions. The licensee indicated that

a simulator electric plant mod was installed about 6 months ago that

might have unintentionally caused this issue. SWR 2012084114329

Simulator Vibration Monitoring System (VMS): Observed during Exam

Validation that the screen vibration color did not change from yellow to

red when the danger alarm was received for the "1A" Recirculation

Pump. SWR 2001298/2680

No malfunction currently exists for simulating a runaway Recirculation

Pump with the new Adjustable Speed Drive (ASD) controller. ln order

to simulate this malfunction, the Booth Operator had to repeatedly

insert a 10 RPM raise pushbutton override and then immediately

delete the override to prevent pushbutton lockout. lt was only possible

to simulate an ASD controller incremental speed increase rather than

an actual runaway pump, as can be done with the Unit 2 Recirc MG

Sets. lR 1441285

Item Procedural lssues ldentified Attachment 3

OT-112 provides no direct guidance for monitoring/managing Thermal

Hydraulic lnstability (THl), except in Attachment 3, which is only entered if

allfour OPRMs are inoperable due to common cause failure. lR 1441184

Event procedure E-D134 does not address Refuel Floor isolation on Low

Zone differential pressure and the fact that both Standby Gas Treatment

Fans will start and draw down the Refuel Floor several minutes after a loss

of D-134. lR 1441184

The examiners observed that some of the applicants when performing

sync of the EDG in accordance with procedure S92.1.O.had the sync

scope rotating faster than expected in the fast direction and closed the

EDG output breaker in on the bus at the five past twelve position. The

current procedure does not define what "slow in the fact direction" means.

A suggestion was made to benchmark other utilities and consider

enhancing procedural guidance in S92.1.O.for sync scope rotation to

define what "slow in the fast direction" means. ]R 1441285

Event procedure E-D134 directs performance of 576.8.8 for Manually

lnitiating a Reactor Enclosure Secondary Containment lsolation. Either

Section 4.4 or 4.5 may be used to accomplish the Manual Initiation.

Section 4.5, "Reactor Enclosure Secondary Containment Manual Low DP

lsolation," is desirable from the standpoint that the associated actions do

not result in PCIG Containment Valve lsolations. However, Step 4.5.5 for

initiating an "A" Channel lsolation is unable to be performed due to the

Loss of D134 (i.e., no power to N2 Inerting Block Valve, HV-57-1604). lt

was unclear as to whether or not Section 4.5 can be successfully

accomplished if unable to perform this step associated with initiating a

Channel "A" lsolation. lR 1441184

GP5, Appendix 2, Rev. 67, step 3.1 .1.2.c incorrectly references

on Page 11. The step should reference Attachment 2.

tR 1441184

SE-10 has no bases document, and provides no basis for injecting SLC

post-LOCA. !R1441184

The simulator malfunction guide, MPR01 1B lists 108 E-3 as an expected

annunciator. The actual annunciator number is 108 F-3. lR 1441184

I S51.6.8 provides no direct guidance to close the RHR F009 valve, instead

it is relied on to be closed in S51.8.L lR 1441184

T-117 LQ-11 says 'reator' instead of 'reactor' lR 1441184

Attachment

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