IR 05000352/2012301
| ML12334A183 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/29/2012 |
| From: | Jackson D E Operations Branch I |
| To: | Pacilio M J Exelon Generation Co, Exelon Nuclear |
| Shared Package | |
| ML120230224 | List: |
| References | |
| 50-352/12-301, 50-353/12-301 | |
| Download: ML12334A183 (12) | |
Text
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 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. MichaelJ.
Pacilio 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 353 l 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 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:
NRC Examination Report 0500035212012301 and 0500035312012301 w/Attachment:
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)
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 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,
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.NRC-ldentified and Self-Revealinq Findinss No findings were identified.
Licensee-ldentified Violations No findings were identified.
1..1
REPORT DETAILS
REACTOR SAFETY
Cornerstone:
Mitigating Systems - Reactor Operator (RO) and Senior Reactor Operator (SRO) Initial License Examination 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.Findinqs No findings were identified.
Operator Knowledqe and Performance 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.,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.
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.lnitial Licensinq Examination Development 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'Findinqs No findings were identified.
Simulation Facilitv Performance Examination Scope The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.
Findinqs No findings were identified.
.3 a..4
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.
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 A-1 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
- 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)Attachment
ES-501 Simulator
Fidelity Report Attachment
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 Attachment
Item Procedural
lssues ldentified
1 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 2 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 3 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 4 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 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