ML18333A306

NRC Initial License Examination Report 05000288/2018301 and 05000306/2018301 (Rdb)

ML18333A306
Person / Time
Site:	Prairie Island
Issue date:	11/29/2018
From:	Randy Baker Operations Branch III
To:	Sharp S Northern States Power Company, Minnesota
Shared Package
ML17165A317	List: IR 05000288/2018301 ML18333A306 ML22179A239 ML22179A243 ML22179A245 ML22179A247 ML22179A249 ML22179A250 ML22179A254 ML22179A256
References
50-282/18-301, 50-306/18-301
Download: ML18333A306 (10)

See also: IR 05000306/2018301

Text

November 29, 2018

Mr. Scott Sharp

Site Vice President

Prairie Island Nuclear Generating Plant

Northern States Power Company, Minnesota

1717 Wakonade Drive East

Welch, MN

55089-9642 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT

, UNIT S 1 AND 2-NRC INITIAL LICENSE EXAMINATION REPORT 05000 288/201 8 301 AND 05000 306/2018 3 01 Dear Mr. Sharp: On October 2, 201 8 , the U.S. Nuclear Regulatory Commission (NRC) completed the initial operator licensing examination

process for license applicants employed at your Prairie Island Nuclear Generating Plant

. The enclosed report documents the results of those examination

s. Preliminary observations noted during the examination process

were discussed on

September 18 , 201 8 , with you and other members of your facility's staff. An exit meeting was conducted by telephone on

October 16 , 201 8, between you and Mr. R. Baker , Operato r Licensing Chief Examiner, to review the proposed final grading of the written examination for the license applicants. During the telephone conversation, the NRC confirmed that

the station did not have any post-examination comments

requiring resolution

. The NRC examiners administered an initial license examination operating test during t he wee ks of September 10 and 17, 201 8. The written examination was administered by

the Prairie Island Nuclear Generating Plant Station training department personnel

on September 20

, 2018. Eleven Senior Reactor Operator and

four Reactor Operator applicants were administered license examinations. The

results of the examinations were finalized on

October 3 0 , 201 8. All fifteen applicants passed all sections of their respective examinations

and eleven applicants were issued

senior operator

license s and four applicants were issued operator license s for Prairie Island Nuclear Generating

Plant, Units 1 and 2

. The administered written examination

s and operating tests, as well as documents related to the development and review

of the examinations (outlines, proposed examinations, review comments , and resolutions, etc.), will be withheld from public disclosure for 24 months

until October 2, 2020.

S. Sharp -2- This letter, its enclosure, and your response (if any) will be available electronically for public inspection and copying at http://www.nrc.gov/reading

-rm/adams.html

and at the NRC's Public Document Room in accordance with Title 10 of the Code of Federal Regulations, Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely, /RA/ Robert J. Orlikowski , Chief Operations Branch Division of Reactor

Safety Docket Nos. 50

-282, 50-306 License Nos. DPR

-42, DPR-60 Enclosure s: 1. OL Examination

Report 05000

288/20 1 8 301; 05000 306/2018301 2. Simulation Facility Fidelity Report

cc: Distribution via LISTSERV

T. Wadley , Training Manager , Prairie Island Nuclear Generating

Plant

S. Sharp -3- Letter to Scott Sharp

from Robert Orlikowski dated November 29, 2018. SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2

-NRC INITIAL LICENSE EXAMINATION

REPORT 05000 288/201 8 301 AND 05000 306/2018 3 01 DISTRIBUTION

Christopher Cook

RidsNrrPMPrairieIsland Resource

RidsNrrDorlLpl3

RidsNrrDirsIrib Resource

Steven West

Darrell Roberts

Jamnes Cameron

Allan Barker

DRPIII DRSIII Caroline Randiki

Colleen Schmidt

ADAMS Accession Number: ML18333A306 OFFICE RIII RIII NAME RBaker:jw ROrlikowski

DATE 11/29/18 11/29/18 OFFICIAL RECORD COPY

Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Docket No s: 5 0-288; 50-306 License N o s: D PR-42; D P R-60 Report No:

05000 288/201 8 301; 05000 306/201 8 301 Licensee: Northern States Power Company, Minnesota

Facility: Prairie Island Nuclear Generating Plant, Units 1 and 2

Location: Welch , MN Dates: September 10, 2018, through October 2, 201 8 Inspectors:

R. Baker, Senior Operations Engineer , Chief Examiner

C. Zoia , Senior Operations Engineer, Examiner

B. Bergeon, Operations Engineer, Examiner

Approved by:

R. Orlikowski, Chief Operations Branch Division of Reactor

Safety

2 SUMMARY Examination

Report 0500 0 288 6/201 8 301; 05000 306/2018301; 0 9/10/201 8-1 0/02/201 8; Northern States Power Company, Minnesota

Prairie Island Nuclear Generating Plant , Units 1 and 2; Initial License Examination Report.

The announced initial operator licensing examination was conducted by regional Nuclear Regulatory Commission

examiners in accordance with the guidance of NUREG

-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 1 1. Examination Summary

Fifteen of fifteen applicants passed all sections of their respective examinations. Eleven applicants were issued senior operator licenses and four applicants were issued operator license

s for Unit s 1 and 2. (Section 4OA5.1).

3 REPORT DETAILS

4OA5 Other Activities

.1 Initial Licensing Examinations

a. Examination Scope

The U.S. Nuclear Regulatory Commission (NRC) examiners and members of the facility licensee's staff used the guidance prescribed in NUREG

-1021, "Operator

Licensing Examination Standards for Power Reactors," Revision

1 1, to develop, validate, administer, and grade the written examination and operating test. The NRC examiners prepared the written examination outline and members of the facility licensee's staff prepared the operating test outlines. Members of the facility licensee's staff developed the written examination and operating test.

The NRC examiners validated the proposed examination, with the assistance of members of the facility licensee's staff

, during the week of August 1 3 , 201 8. During the onsite validation week, the examiners audited two of the license applicatio

ns for accuracy. The NRC examiners, with the assistance

of members of the facility licensee's staff, administered the operating test, consisting of job performance measures

and dynamic simulator scenarios, during the period of

September 10 through 17 , 201 8. The facility licensee

administered the written examination on September 20, 201 8. b. Findings (1) Written Examination

The NRC examiners determined that the written examination, as proposed by the licensee, was within the range of acceptability expected for a proposed examination. Less than 20

percent of the proposed examination questions were determined to be unsatisfactory and required modification or replacement.

All changes made to the proposed written examination were made in accordance with NUREG

-1021, "Operator Licensing Examination Standards for Power Reactors," and were documented on Form ES-401-9, "Written Examination Review Worksheet."

The written examination outlines and worksheets, the proposed written examination and worksheets, as well as the final Form ES

-401-9, and the final as

-administered examination and answer key, will

be publicly available electronically in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Document Access and Management System (ADAMS)

on October 2, 2020. (ADAMS Accession Numbers ML1 7 16 5 A 3 21, ML17 16 5 A 3 22, ML17 1 6 5 A 31 7 , and ML17 1 6 5 A 3 1 8, respectively.

) O n October 2, 201 8 , the licensee submitted

documentation noting that there were no post-examination facility license

e comments, and

no post-examination applicant commen ts for consideration by

the NRC examiners when grading

the written examination.

The NRC examiners graded the written examination on

October 15, 201 8 , and conducted a review of each missed question to determine the accuracy and validity of the examination questions.

4 (2) Operating Test

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

All changes made to the operating test were made in accordance with NUREG

-1021, "Operator Licensing Examination Standards for Power Reactors," and were documented

on Form ES

-301-7, "Operating Test Review Worksheet."

The operating test outlines and worksheets, the proposed operating test

and worksheets, as well as the final Form ES-301-7, and the final

as-administered operating test, will be available electronically in the NRC Public Document Room or from the Publicly Available Records component of NRC's ADAMS, on

October 2, 2020. (ADAMS Accession Numbers ML17 16 5 A3 21, ML1716 5 A3 22, ML17 165A31 7, and ML17

16 5 A3 18, respectively.

) On October 2, 201 8, the licensee submitted documentation noting that there were

no post-examination facility licensee comments, and no

post-examination applicant comments for consideration by the NRC examiners when grading the operating test

. The NRC examiners completed operating test grading on

October 16, 201 8. (3) Examination Results

Eleven applicants at the Senior Reactor Operator

level and four applicants at the Reactor Operator

level were administered written examinations and operating tests.

All applicants passed all portions of their examinations and were issued their respective operating licenses

for Prairie Island Nuclear Generating Plant, Unit s 1 and 2 o n October 3 0 , 201 8. .2 Examination Security

a. Scope The NRC examiners reviewed and observed the licensee's implementation of examination security requirements during the examination validation and administration to assure compliance with Title 10 of the Code of Federal

Regulations , Part 55.49, "Integrity of Examinations and Tests.

" The examiners used the guidelines provided in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors

," to determine acceptability of the licensee

's examination security activities.

b. Findings No findings were identified.

4OA6 Management Meetings .1 Debrief The chief examiner presented the examination team's preliminary observations and findings on

September 18, 201 8 , to Mr. S. Sharp , Site Vice President

, and other members of the

Prairie Island

Nuclear Generating Plant Operations and Training Department staff.

5 .2 Exit Meeting

A telephone exit meeting was conducted

on October 16, 2018, by Mr. R. Baker , Operator Licensing Chief Examiner , with M r. S. Sharp , Site Vice President, and other members of the licensee staff. The NRC confirmed that there were no

post-examination comments during the telephone discussion. The examiner asked the licensee whether any of the material used to develop or administer the examination should be considered proprietary.

No proprietary or sensitive information was identified during the examination or debrief/exit meetings

. ATTACHMENT: SUPPLEMENTAL INFORMATION

Attachment

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC

T Licensee S. Sharp, Site Vice President

H. Hanson , Plant Manager

M. Peterson, Fleet General Supervisor Operations Training

T. Wadley , Training Manager J. Connors , Regulatory Affairs Manager U.S. Nuclear Regulatory Commission

L. Haeg , Senior Resident Inspector

K. Pusateri, Resident Inspector

R. Baker, Chief Examiner

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened, Closed, and Discussed

None LIST OF ACRONYMS USE

D ADAMS Agencywide Document Access and Management System

NRC U.S. Nuclear Regulatory Commission

Enclosure 2

SIMULATION FACILITY

FIDELITY REPORT Facility Licensee:

Prairie Island Nuclear Generating Plant, Units 1 and 2

Facility Docket No

s: 50-288; 50-306 Operating Tests Administered:

September 10

-17, 201 8 The following documents observations made by the U.S. Nuclear Regulatory Commission

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 Title 10 of the Code of Federal Regulations, Part 55.45(b). These observations do not affect U.S. Nuclear Regulatory Commission

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

SWO B8D-056 On the September

1 3, 2018, during the first run of Scenario #4, Event #3, the pressurizer pressure master controller, 1HC431K (4304101), Manual/Auto switch failed to shift to the manual position. The applicant took manual control of the pressurizer spray val

ves and heaters for the remainder of the scenario, which did not adversely impact the remaining scenario events. The switch was repaired following completion of the scenario and, and the controller failure did not recur during subsequent scenarios.