IR 05000237/2004301

Er 05000237-04-301, 05000249-04-301; 08/16/04-08/20/04; Dresden Nuclear Power Station, Units 2 & 3; Initial License Examination Report

ML042660211
Person / Time
Site:	Dresden
Issue date:	09/20/2004
From:	Lanksbury R NRC/RGN-III/DRS/OLB
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
50-237/04-301, 50-249/04-301 50-237/04-301, 50-249/04-301
Download: ML042660211 (14)

Text

September 20, 2004

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 NRC INITIAL LICENSE EXAMINATION REPORT 05000237/2004301(DRS);

05000249/2004301(DRS)

Dear Mr. Crane:

On August 20, 2004, NRC examiners completed initial operator licensing examinations at your Dresden Nuclear Power Station. The enclosed report presents the results of the examination.

The NRC examiners administered initial license examination operating tests during the week of August 16, 2004, for four senior reactor operator applicants. Members of the Dresden Training Department administered an initial license written examination on August 16, 2004, to the applicants. The results of the operating tests and written examinations were finalized on September 15, 2004. Three applicants passed all sections of their respective examinations and were issued senior reactor operator licenses. One applicant failed the written examination and will not be issued a license.

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. 50-237; 50-249 License Nos. DPR-19; DPR-25

Enclosures:

1.

Operator Licensing Examination Report 05000237/2004301(DRS); 05000249/2004301(DRS)

2.

Simulation Facility Report

SRO Written Examination Post Examination Comments w/Resolution 4.

SRO Written Examinations and Keys

REGION III==

Docket Nos:

50-237; 50-249 License Nos:

DPR-19; DPR-25 Report No:

05000237/2004301(DRS); 05000249/2004301(DRS)

Licensee:

Exelon Generation Company, LLC Facility:

Dresden Nuclear Power Station, Units 2 and 3 Location:

6500 North Dresden Road Morris, IL 60450 Dates:

August 16 through August 20, 2004 Examiners M. Bielby, Chief Examiner M. Morris, Examiner Approved by:

R. Lanksbury, Chief Operations Branch Enclosure 1

Enclosure 1

SUMMARY OF FINDINGS

ER 05000237/2004301, 05000249/2004301; 08/16/04-08/20/04; Dresden Nuclear Power

Station, Units 2 & 3; Initial License Examination Report.

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

Examination Summary

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

• One SRO applicant failed the written examination and will not be issued a license. Three applicants passed all portions 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 on August 17 through August 20, 2004. The facilitys training staff administered an initial license written examination on August 16, 2004. The facility's training staff used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Draft, to prepare the operating test and written examination. Four senior reactor operator applicants were examined.

b. Findings

Written Examination The licensee developed the written examination. During their initial review, the 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 July 26, 2004, examination changes agreed upon between the NRC and the licensee were incorporated according to the guidance contained in NUREG-1021. Five post-examination comments were submitted for the written examination. No written examination pass/fail decisions were affected as a result of the comments. The post examination comments and their resolution is documented in 3, SRO Written Examination Post Examination Comments w/Resolution.

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 during the validation week in accordance with NUREG-1021 guidance. The licensee submitted no post examination comments on the operating test.

Examination Results Four senior reactor operator applicants were administered written examinations and operating tests for initial operator licensing. Three applicants passed all portions of their examinations and were issued senior reactor operator licenses. One applicant failed the written examination and will not be issued a license.

.2 Examination Security

a. Scope

The examiners reviewed and observed the licensee's implementation of examination security requirements during the examination preparation and administration.

b. Findings

The licensees implementation of examination security requirements during examination preparation and administration were acceptable and met the guidelines provided in NUREG-1021, Operator Licensing Examination Standards for Power Reactors. No violations of 10 CFR 55.49 occurred during the examination preparation and administration.

4OA6 Meetings

.1 Exit Meeting

The chief examiner presented the examination team's preliminary observations and findings on August 20, 2004, to Mr. D. Wozniak 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 meeting with the licensee. The licensee acknowledged the observations and findings presented.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

SUPPLEMENTAL INFORMATION

PARTIAL LIST OF PERSONS CONTACTED

Licensee

D. Wozniak, Plant Manager

F. Ferrero, Training

S. Frey, Training

R. Gadbois, Shift Operations Superintendent

J. Griffin, Regulatory Assurance - NRC Coordinator

J. Hansen, Regulatory Assurance Manager

J. Henry, Operations Director

A. Khanifar, Nuclear Oversight Manager

P. O'Connor, Training

D. O'Rourke, Nuclear Oversight

M. Otten, Training

S. Russel, Corporate Training

C. Symonds, Training Director

NRC

R. Lanksbury, Chief, Operations Branch

M. Bielby, Chief Examiner

ITEMS OPENED, CLOSED AND DISCUSSED

Opened

None

Closed

None

Discussed

None

LIST OF ACRONYMS USED

ADAMS

Agency-Wide Document Access and Management System

DRS

Division of Reactor Safety

NRC

Nuclear Regulatory Commission

PARS

Publicly Available Records

RO

Reactor Operator

SRO

Senior Reactor Operator

SIMULATION FACILITY REPORT

Facility Licensee:

Dresden Nuclear Power Station

Facility Docket No.:

50-237; 50-249

Operating Tests Administered:

August 16 - 20, 2004

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

None

SRO Written Examination Post Examination Comments w/Resolution

Question #

Licensee Comment

NRC Resolution

Enhance question by modifying

distractor B to specify the location

in the system/plant where Hydrogen

gas concentration is decreasing (Off

Gas Hydrogen Analyzer).

The NRC agreed. The enhancement

focuses the distractor on a specific

location. The question change was

made on the final examination

submitted to ADAMS and INPO. This

question modification did not result in

any change in applicant grades

because the information was

recognized by all applicants during the

examination.

Enhance question by changing

SRVs to ERVs to gain

consistency with Dresden

terminology, i.e., ERVs, Safety

Valves, or Target Rock/SRV

(singular), instead of BWROG

EPGs/SAGs terminology of SRVs.

The NRC agreed. The acronym

"SRVs" was replaced with ERVs in

distractor C. of the question submitted

to ADAMS and INPO. This question

modification did not result in any

change in applicant grades because

the information was recognized by all

applicants during the examination.

Enhance question by adding

verification of discharge inboard

and outboard valves to the three

choices that mention them.

Suggest the three choices read

...Suction and Discharge Inboard

and Outboard Isolation Valves... as

the 1001-1A&B, -2A,B&C, -4A,B&C,

and -5A&B all receive close signals

on Group III Isolation.

The NRC agreed. The term

discharge was inserted in the

appropriate location for choices A., B.,

and D. in the examination submitted to

ADAMS and to INPO. This question

modification did not result in any

change in applicant grades because

the information was recognized by all

applicants during the examination.

Remove the question from the exam

as it is operationally invalid, since the

bulleted information in the stem

creates a situation where fuel moves

are being conducted with the A

Train Smoke Purge surveillance in

progress - which is inconsistent with

Limitations and Actions of DOS

5750-6, i.e., Control Room

Ventilation is considered inoperable

while smoke purge is aligned - Refer

to Tech Spec 3.7.4.

The NRC agreed. Based on

discussions with the licensee, review of

DOS 5750-6 Limitations and Actions,

and Technical Specification 3.7.4, the

question was deleted from the written

examination submitted to ADAMS and

INPO. All exams were re-graded

based 24 vice 25 SRO questions, and a

total of 99 questions; however, the

overall examination pass/fail results

were unaffected.

SRO Written Examination Post Examination Comments w/Resolution (continued)

Question #

Licensee Comment

NRC Resolution

Enhance question by re-writing the

last Statement in stem to add

emphasis to both parts of question,

i.e., MAINTAIN COOL DOWN RATE,

as well as remove LEAST amount of

decay heat. In addition, choice C

appears to have wrong procedure

reference - it should be DOP 1200 -

2, NOT 1200-03.

The NRC agreed. The change more

accurately reflects the intent of the

question. The phrase was added to

the examination submitted to ADAMS

and INPO. This question modification

did not result in any change in

applicant grades because the

information was recognized by all

applicants during the examination.

WRITTEN EXAMINATIONS AND ANSWER KEY (SRO)

SRO Examination ADAMS Accession No. ML042540509

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