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{{Adams
#REDIRECT [[IR 05000288/2018301]]
| number = ML18333A306
| issue date = 11/29/2018
| title = NRC Initial License Examination Report 05000288/2018301 and 05000306/2018301 (Rdb)
| author name = Baker R
| author affiliation = NRC/RGN-III/DRS/OB
| addressee name = Sharp S
| addressee affiliation = Northern States Power Company, Minnesota
| docket = 05000282, 05000306
| license number = DPR-042, DPR-060
| contact person =
| document report number = 50-282/18-301, 50-306/18-301
| package number = ML17165A317
| document type = Letter, License-Operator Examination Report
| page count = 10
}}
See also: [[see also::IR 05000306/2018301]]
 
=Text=
{{#Wiki_filter: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
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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.
}}

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