IR 05000282/2007301
| ML072640422 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/20/2007 |
| From: | Hironori Peterson Division of Reactor Safety III |
| To: | Wadley M Nuclear Management Co |
| References | |
| 50-282/07-301, 50-306/07-301 ER-07-301 | |
| Download: ML072640422 (13) | |
Text
September 20, 2007
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000282/2007301(DRS);
Dear Mr. Wadley:
On August 6, 2007, the NRC completed initial operator licensing examinations at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The enclosed report presents the results of the examination which were discussed on August 7 with Mr. J. Sternisha and other members of your staff. An exit meeting was conducted on August 17, 2007, with Mr. J. Sorenson and other members of the Prairie Island Nuclear Generating Plant Operations and Training Department staff to review the resolution of the plants post examination comments and the proposed final grading of the written examination for the license applicants.
The NRC examiners administered initial license examination operating tests during the week of July 30 and August 6, 2007. Members of the Prairie Island Nuclear Generating Plant Training Department administered an initial license written examination on August 7, 2007, to the applicants. Five senior reactor operator and five reactor operator applicants were administered license examinations. The results of the examinations were finalized on September 10, 2007.
All ten applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and five reactor operator licenses.
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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), 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/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60
Enclosures:
1.
Operator Licensing Examination Report 05000282/2007301(DRS); 05000306/2007301(DRS)
w/Attachment: Supplemental Information 2.
Simulation Facility Report 3.
Post Examination Comments and Resolutions 4.
Written Examinations and Answer Keys (RO/SRO)
REGION III==
Docket Nos:
50-282; 50-306 License Nos:
Licensee:
Nuclear Management Company, LLC Facility:
Prairie Island Nuclear Generating Plant, Units 1 and 2 Location:
Welch, MN 55089 Dates:
July 30 through August 6, 2007 Examiners:
M. Bielby, Chief Examiner R. Walton, Examiner D. Reeser, Examiner Approved by:
Hironori Peterson, Chief Operations Branch Division of Reactor Safety
Enclosure 1
SUMMARY OF FINDINGS
ER 05000282/2007301(DRS); 05000306/2007301(DRS); 07/30/07 - 08/06/07;
Prairie Island Nuclear Generating Plant, Units 1 and 2; Initial License Examination Report.
The announced operator licensing initial examination was conducted by regional examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9.
Examination Summary:
$
Ten examinations were administered (five senior reactor operators and five reactor operators).
$
Ten applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and five reactor operator licenses.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations
a. Examination Scope
The NRC examiners conducted an announced operator licensing initial examination during the weeks of July 30, and August 6, 2007. The facility licensees training staff used the guidance prescribed in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, to prepare the outline and develop the written examination and operating test. The examiners administered the operating test, consisting of job performance measures and dynamic simulator scenarios, during the period of July 30 through August 6, 2007. The facility licensee administered the written examination on August 7, 2007. Five senior reactor operator and five reactor operator applicants were examined. During the on-site validation week of July 9, 2007, the examiners audited one license application for accuracy.
b. Findings
Written Examination The NRC examiners determined that the written examination, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors. The licensee had no post examination comments on the written examination.
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. All changes made to the submitted examination were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The licensee had no post examination comments on the operating test; however, the NRC clarified a critical step on one administrative JPM that is documented in Enclosure 3, Post Examination Comments and Resolutions.
Examination Results Ten applicants passed all sections of their examinations resulting in the issuance of five senior reactor operator and five reactor operator licenses.
.2 Examination Security
a. Inspection Scope
The NRC examiners briefed the facility contact on the NRCs requirements and guidelines related to examination physical security (e.g., access restrictions and simulator considerations) and integrity in accordance with 10 CFR 55.49, Integrity of Examinations and Tests, and NUREG-1021, Operator Licensing Examination Standard for Power Reactors. The examiners reviewed and observed the licensees implementation and controls of examination security and integrity measures (e.g.,
security agreements) throughout the examination process.
b. Findings
No findings were noted in this area.
4OA6 Meetings
Debrief The chief examiner presented the examination team's preliminary observations and findings on August 7, 2007, to Mr. J. Sternisha and other members of the Prairie Island Operations and Training Department staff. The examiners 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.
Exit Meeting The chief examiner conducted an exit via teleconference on August 17, 2007, with Mr. J. Sorenson, Prairie Island Site Director and other members of the Prairie Island Operations and Training Department staff. The NRCs final disposition of the stations post-examination comments were discussed.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- J. Sorenson, Site Director
- S. Seilhymer, Assistant Operations Manager
- J. Sternisha, Training Manager
M.Walter, General Supervisor Operations Training
- T. Ouret, Operations Training Supervisor
- M. Davis, Licensing
- M. Peterson, Fleet General Supervisor-Simulator / NRC Examinations
NRC
- J. Adams, Senior Resident Inspector
- M. Bielby, Chief Examiner
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF ACRONYMS
Agency-Wide Document Access and Management System
CFR
Code of Federal Regulations
Division of Reactor Safety
NRC
Nuclear Regulatory Commission
Protective Action Recommendation
Publicly Available Records System
Reactor Operator
Senior Reactor Operator
SIMULATION FACILITY REPORT
Facility Licensee: Prairie Island Nuclear Generating Plant, Units 1 and 2
Facility Licensee Docket Nos. 50-282; 50-306
Operating Tests Administered: July 30 through August 6, 2007
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
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.
None.
Post Examination Comments and Resolutions
Administrative JPM (ADMIN-41, Emergency Classification of a Security Event)
Performance Step: Critical: Y (SEQ-1):
Fills out PINGP 577 as follows:
Circle 1. [A] Initial Report
Circle 2. [B] Drill/Exercise
[C] Prairie Island Nuclear Generating Plant is PRE-CIRCLED.
Circle 4. [D] General Emergency
5.[A] Fill in the proper date, time and EAL HG1.1
Circle 6. [A] None
Circle 7. [A] Not Applicable
Complete 8. From 258 degrees.
Complete 8. Downwind Sectors CIRCLE ALL LETTERS
Complete 9. miles/hr: 2
Complete 9. Stability Class F
10[B] - Complete EVACUATE ALL SECTORS OUT TO 2 MILES
10[B] - Complete EVACUATE ALL SECTORS OUT TO 5 MILES.
Circle Subareas 2, 5N, 5E, 5S, 5W.
Complete 11. EAL HG1.1 with sticker.
Complete approval signature.
NOTE: The Critical Steps are to classify as General Emergency, and to Evacuate all sectors
out to 5 miles.
Standard: Form is properly completed as indicated above.
NRC Comment and Resolution:
Upon post examination review of the JPM, the examiners identified that the NOTE: included in
the critical Performance Step SEQ-1 did not closely match the established Standard. As a
result the NOTE: was modified to more closely reflect the applicant performance required to
successfully complete the critical Performance Step.
During the examination validation, the NOTE: was intended to clarify that the critical portion of
the Performance Step was to make the correct classification and Protective Action
Recommendation (PAR), and correctly reflect the same information on the PINGP 577,
Revision 44, Emergency Notification Report Form. However, the second part of the NOTE:
incorrectly limited the PAR to evacuation of all sectors out to 5 miles.
As written, the PINGP 577 form should have been completed by the applicants and specifically
identified the following critical information: Step 5. [A], Classification, required an Emergency
Action Level (EAL) of HG1.1 (General Emergency); Step 8., Wind Direction From 258 degrees,
with all downwind sectors circled; Step 10. Protective Action Recommendations, [B], Evacuate
(or Shelter) all Sectors Out to 2 miles and all Sectors Out to 5 miles, and affected sub-areas 2,
5N, 5E, 5S, and 5W circled. The wording in the Performance Step SEQ-1, NOTE:, was
changed as follows: The Critical Steps are to classify as General Emergency, and to identify the
correct PAR.
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession #ML072570293.