IR 05000352/2012301
| ML12334A183 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| 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) | |
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
- 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