IR 05000373/2005301

Er 05000373-05-301; Er 05000374-05-301; 03/07/2005 - 03/11/2005; LaSalle County Station; Units 1 and 2; Initial License Examination Report

ML050980206
Person / Time
Site:	LaSalle
Issue date:	04/08/2005
From:	Lanksbury R Division of Reactor Safety III
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
50-373/05-301, 50-374/05-301 50-373/05-301, 50-374/05-301
Download: ML050980206 (11)

Text

ril 8, 2005

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000373/2005301(DRS);

05000374/2005301(DRS)

Dear Mr. Crane:

On March 11, 2005, U.S. Nuclear Regulatory Commission (NRC) examiners completed initial operator licensing examinations at LaSalle County Station. The enclosed report documents the results of the examination which were discussed on March 10, 2005, with Ms. S. Landahl and other members of your staff.

The NRC examiners administered an initial license examination operating test during the week of March 7 through March 10, 2005. A written examination was administered by LaSalle County Station training personnel on March 11, 2005. Four senior reactor operator (SRO)

applicants were administered license examinations. The results of the examinations were finalized on March 24, 2005. Each of the applicants passed all sections of their respective examinations and were issued senior operator licenses.

In accordance with 10 CFR Part 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 (PARS) component of NRC's document system (ADAMS). ADAMS is 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/

Roger D. Lanksbury, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18

Enclosures:

1. Operator Licensing Examination Report 05000373/2005301(DRS);

0500374/2005301(DRS)

2. Simulation Facility Report 3. Written Examinations and Answer Key (SRO)

REGION III==

Docket No: 50-373; 50-374 License No: NPF-11; NPF-18 Report No: 05000373/2005301(DRS); 05000374/2005301(DRS)

Licensee: Exelon Generation Company, LLC Facility: LaSalle County Station, Units 1 and 2 Location: 2601 N. 21st Road Marseilles, IL 61341 Dates: March 7 through March 11, 2005 Examiners: B. Palagi, Chief Examiner N. Valos, Examiner Approved by: R. Lanksbury, Chief Operations Branch Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

ER 05000373/2005301(DRS); ER 05000374/2005301(DRS); 03/07/2005 - 03/11/2005; LaSalle

County Station; Units 1 and 2; Initial License Examination Report.

The announced operator licensing initial examination was conducted by NRC examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9.

A. Examination Summary

• Four senior reactor operator (SRO) applicants were each administered an initial license operating test and written examination.

• All four applicants passed all sections of their respective examinations and were issued senior reactor operator licenses. (Section 4OA5.1)

REPORT DETAILS

4OA5 Other

.1 Initial Licensing Examinations

a. Examination Scope

The NRC examiners conducted an announced operator licensing initial examination during March 7, 2005, through March 11, 2005. The plant's training staff used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, to prepare the examination outline and to develop the written examination and operating test. The NRC examiners administered the operating test from March 7, 2005, through March 10, 2005. LaSalle County Station training staff members administered the written examination on March 11, 2005. Four senior reactor operator (SRO) applicants were examined.

b. Findings

Written Examination The licensee developed the written examination. During their initial review, the NRC examiners determined that the examination, as submitted by the licensee, was within the range of acceptability expected for a proposed examination. During examination validation the week of February 21, 2005, examination changes agreed upon between the NRC and the licensee were incorporated according to the guidance contained in NUREG-1021.

Operating Test The NRC examiners determined that the operating test, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.

Examination changes, agreed upon between the NRC and the licensee, were made according to NUREG-1021.

Examination Results Four senior reactor operator applicants were administered written examinations and operating tests for initial operator licensing. Each of the applicants passed all sections of their respective examinations and were issued senior operator licenses.

.2 Examination Security

a. Examination Scope

The NRC examiners observed the licensees implementation of examination security and integrity measures (e.g., physical barriers, sequestering, security agreements, sampling criteria, and test item repetition) throughout the examination process.

b. Findings

The licensees implementation of examination security requirements during examination preparation and administration were acceptable and met the guidelines provided in NUREG-1021, Revision 9. However, during the facility licensees operating examination development one examination security incident occurred which had the potential to affect the integrity of the examination.

The incident occurred when an individual who had not signed the examination security agreement overheard two persons who were on the security agreement discussing the examination. The compromised material was deleted and replaced with new material prior to the examination validation.

The licensee documented this incident in the corrective action program (CAP) as AR 00303787. The NRC Chief Examiner was appropriately notified of the incident. The examiner reviewed the licensees assessment of this incident for a possible violation of 10 CFR 55.49, Integrity of Examinations and Tests. The examiner determined that no actual examination compromise had occurred. The apparent violation of the licensees examination security procedure was considered minor in nature and was not subject to enforcement action in accordance with NRC enforcement policy.

4OA6 Meetings

.1 Exit Meeting

The chief examiner presented the examination team's preliminary observations and findings on March 10, 2005, to Ms. Landahl and other members of the Operations and Training Department staff. No proprietary items were identified during the administration of the examination nor during the exit meetings with the licensee. The licensee acknowledged the observations and findings presented.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

Enclosure

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

S Landahl, Site Vice President

D. Enright, Plant Manager

C. Dieckmann, Training Director

S. Marik, Shift Operations Superintendent

E. Ross, Training Staff / Exam Developer

J. Bauer, Training Staff

S. Russell, Exelon Corporate Training

Nuclear Regulatory Commission

D. Kimble, Senior Resident Inspector

ITEMS OPENED, CLOSED AND DISCUSSED

Opened and Closed

None

Discussed

None

LIST OF ACRONYMS USED

ADAMS Agency-Wide Document Access and Management System

CAP Corrective Action Program

DRS Division of Reactor Safety

NRC Nuclear Regulatory Commission

PARS Publicly Available Records

SRO Senior Reactor Operator

Attachment

SIMULATION FACILITY REPORT

Facility Licensee: LaSalle County Station

Facility Docket No.: 50-373; 50-374

Operating Tests Administered: March 7, 2005, through March 10, 2005

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 10 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 the operating test a reverse power trip occurred when

1B Emergence attempting to synchronize the 1B Emergency Diesel Generator. This is

Diesel reverse a known problem that was introduced when the simulator software was

power trip modified to make the simulator match the plant on the shutdown of the

Emergency Generator.

During the operating test, on one occasion, an annunciator did not give

Annunciator Horn an audible alarm. This was an isolated case, the simulator silence

push-bottons were cleaned as minor maintenance (MMI # 3929).

WRITTEN EXAMINATIONS AND ANSWER KEY (SRO)

SRO Initial Examination ADAMS Accession # ML050900107