ML101330609: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(12 intermediate revisions by the same user not shown)
Line 1: Line 1:
#REDIRECT [[IR 05000270/2010301]]
{{Adams
| number = ML101330609
| issue date = 05/13/2010
| title = Er 05000296/10-301, 05000270/10-301, 05000287/10-301 on 03/29/10 - 04/02/10 for Oconee,
| author name = Widmann M
| author affiliation = NRC/RGN-II/DRP
| addressee name = Baxter D
| addressee affiliation = Duke Energy Carolinas, LLC
| docket = 05000269, 05000270, 05000287
| license number = DPR-038, DPR-047, DPR-055
| contact person =
| document report number = 50-270/10-301, 50-287/10-301, 50-296/10-301
| document type = Letter, License-Operator Examination Report
| page count = 13
}}
See also: [[see also::IR 05000296/2010301]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                              NUCLEAR REGULATORY COMMISSION
                                              REGION II
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                    ATLANTA, GEORGIA 30303-1257
                                      May 13, 2010
Mr. David A. Baxter
Site Vice President
Duke Energy Carolinas, LLC
Oconee Nuclear Station
7800 Rochester Highway
Seneca, SC 29672
SUBJECT:        OCONEE NUCLEAR STATION - NRC OPERATOR LICENSE EXAMINATION
                REPORT 05000269/2010301, 05000270/2010301, AND 05000287/2010301
Dear Mr. Baxter:
During the period March 29 - April 02, 2010 the Nuclear Regulatory Commission (NRC)
administered operating tests to employees of your company who had applied for licenses to
operate the Oconee Nuclear Station. At the conclusion of the tests, the examiners discussed
preliminary findings related to the operating tests with those members of your staff identified in
the enclosed report. The written examination was administered by your staff on April 07, 2010.
All applicants passed both the operating test and written examination. There were three post-
administration comments concerning the operating test. These comments, and the NRC
resolution of these comments, are summarized in Enclosure 2. A Simulator Fidelity Report is
included in this report as Enclosure 3.
In accordance with 10 CFR 2.390 of the NRCs 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 the NRCs document
system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
If you have any questions concerning this letter, please contact me at (404) 997-4550.
                                              Sincerely,
                                              /RA/
                                              Malcolm T. Widmann, Chief
                                              Operations Branch
                                              Division of Reactor Safety
Docket Nos.: 50-269, 50-270, and 50-287
License Nos.: DPR-38, DPR-47, and DPR-55
Enclosures:    1. Report Details
                2. Facility Comments and NRC Resolution
                3. Simulator Fidelity Report
 
 
_________________________                      G SUNSI REVIEW COMPLETE
OFFICE            RII:DRS          RII:DRS          RII:DRS          RII:DRS        RII:DRP
SIGNATURE          GWL /RA/        MTW /RA for/    RFA /RA/        MTW /RA/        MFK /RA/
NAME              GLaska          FEhrhardt        RAiello          MWidmann        MKing
DATE                  05/12/2010      05/13/2010      05/13/2010      05/13/2010      05/12/2010
E-MAIL COPY?          YES      NO  YES        NO  YES        NO  YES        NO  YES        NO  YES      NO YES NO
       
DPC                                        2
cc w/encl:                                  David A. Repka
Kent Alter                                  Winston Strawn LLP
Regulatory Compliance Manager                Electronic Mail Distribution
Oconee Nuclear Station
Duke Energy Carolinas, LLC                  Kathryn B. Nolan
Electronic Mail Distribution                Senior Counsel
                                            Duke Energy Corporation
Scott L. Batson                              526 South Church Street-EC07H
Engineering Manager                          Charlotte, NC 28202
Oconee Nuclear Station
Duke Energy Carolinas, LLC                  Charles Brinkman
Electronic Mail Distribution                Director
                                            Washington Operations
Clark E. Curry                              Westinghouse Electric Company, LLC
Engineering Manager                          Electronic Mail Distribution
Oconee Nuclear Station
Duke Energy Carolinas, LLC                  County Supervisor of Oconee County
Electronic Mail Distribution                415 S. Pine Street
                                            Walhalla, SC 29691-2145
Philip J. Culbertson
Oconee Nuclear Station                      R. Mike Gandy
Duke Energy Carolinas, LLC                  Division of Radioactive Waste Mgmt.
Electronic Mail Distribution                S.C. Department of Health and
                                            Environmental Control
Preston Gillespie                            Electronic Mail Distribution
Manager
Oconee Nuclear Station                      Susan E. Jenkins
Duke Energy Carolinas, LLC                  Director, Division of Waste Management
Electronic Mail Distribution                Bureau of Land and Waste Management
                                            S.C. Department of Health and
R. L. Gill, Jr.                              Environmental Control
Manager                                      Electronic Mail Distribution
Nuclear Regulatory Issues & Industry Affairs
Duke Energy Carolinas, LLC                  W. Lee Cox, III
Electronic Mail Distribution                Section Chief
                                            Radiation Protection Section
Dhiaa M. Jamil                              N.C. Department of Environmental
Group Executive and Chief Nuclear Officer    Commerce & Natural Resources
Duke Energy Carolinas, LLC                  Electronic Mail Distribution
Electronic Mail Distribution
                                            Dean M. Hubbard
Lisa F. Vaughn                              Training Manager
Associate General Counsel                    Oconee Nuclear Station
Duke Energy Corporation                      Electronic Mail Distribution
526 South Church Street-EC07H
Charlotte, NC 28202
 
DPC                                        3
Letter to David A. Baxter from Malcolm T. Widmann dated May 13, 2010
SUBJECT:      OCONEE NUCLEAR STATION - NRC OPERATOR LICENSE EXAMINATION
              REPORT 05000269/2010301, 05000270/2010301, AND 05000287/2010301
Distribution w/encl:
C. Evans, RII
L. Slack, RII
OE Mail
RIDSNRRDIRS
PUBLIC
RidsNrrPMOconee Resource
 
            NUCLEAR REGULATORY COMMISSION
                            REGION II
Docket No.:    50-269, 50-270, 50-287
License No.:  DPR-38, DPR-47, DPR-55
Report No.:    05000269/2010301, 05000270/2010301, 05000287/2010301
Licensee:      Duke Energy Corporation
Facility:      Oconee Nuclear Station
Location:      Seneca, SC 29672
Dates:        Operating Test - March 29 - April 02, 2010
              Written Examination - April 07, 2010
Examiners:    G. Laska, Chief Examiner, Senior Operations Examiner
              F. Ehrhardt, Senior Operations Engineer
              R. Aiello, Senior Operations Engineer
Approved by:  Malcolm T. Widmann, Chief
              Operations Branch
              Division of Reactor Safety
                                                                  Enclosure 1
 
                                  SUMMARY OF FINDINGS
ER 05000269/2010301, 05000270/2010301, 05000287/2010301, 03/29-04/02/2010 &
04/07/2010; Oconee Nuclear Station; Operator License Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in
accordance with the guidelines in Revision 9, Supplement 1, of NUREG-1021, "Operator
Licensing Examination Standards for Power Reactors." This examination implemented the
operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
Members of the Oconee Nuclear Station staff developed both the operating tests and the written
examination.
The NRC administered the operating tests during the period March 29 - April 02, 2010.
Members of the Oconee Nuclear Station training staff administered the written examination on
April 07, 2010. All Reactor Operator (RO) and Senior Reactor Operator (SRO) applicants
passed both the operating test and written examination. Nine applicants were issued licenses
commensurate with the level of examination administered.
There were three post-examination comments. The NRC resolutions to these comments are
summarized in Enclosure 2.
No findings of significance were identified.
                                                                                  Enclosure 1
 
                                      REPORT DETAILS
2.    OTHER ACTIVITIES
4OA5 Operator Licensing Initial Examinations
  a. Inspection Scope
      Members of the Oconee Nuclear Station staff developed both the operating tests and the
      written examination. All examination material was developed in accordance with the
      guidelines contained in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing
      Examination Standards for Power Reactors." The NRC examination team reviewed the
      proposed examination. Examination changes agreed upon between the NRC and the
      licensee were made per NUREG-1021 and incorporated into the final version of the
      examination materials.
      The NRC reviewed the licensees examination security measures while preparing and
      administering the examinations in order to ensure compliance with 10 CFR §55.49,
      Integrity of examinations and tests.
      The NRC examiners evaluated six Reactor Operator (RO) and three Senior Reactor
      Operator (SRO) applicants using the guidelines contained in NUREG-1021. The
      examiners administered the operating tests during the period March 29 - April 02, 2010.
      Members of the Oconee Nuclear Station training staff administered the written
      examination on April 07, 2010. Evaluations of applicants and reviews of associated
      documentation were performed to determine if the applicants, who applied for licenses to
      operate the Oconee Nuclear Station, met the requirements specified in 10 CFR Part 55,
      Operators Licenses.
  b. Findings
      No findings of significance were identified. The NRC determined, using NUREG-1021,
      that the licensees examination submittal was within the range of acceptability expected
      for a proposed examination.
      Nine applicants passed both the operating test and written examination and were issued
      licenses.
      Copies of all individual examination reports were sent to the facility Training Manager for
      evaluation of weaknesses and determination of appropriate remedial training.
      The licensee submitted three post-examination comments. A copy of the final written
      examination and answer key, with all changes incorporated, and post exam comments
      may be accessed in the ADAMS system (ADAMS Accession Number ML101310324 and
      ML101310308 and ML101310299).
                                                                                      Enclosure 1
 
                                              4
4OA6 Meetings
Exit Meeting Summary
On April 02, 2010 the NRC examination team discussed generic issues associated with the
operating test with you and members of the Oconee Nuclear Station staff. The examiners
asked the licensee if any of the examination material was proprietary. No proprietary
information was identified.
                                  KEY POINTS OF CONTACT
Licensee personnel
K. Alter, Regulatory Compliance
F. Baldwin, Operations Shift Manager
D. Baxter, Site VP
E. Burchfield, Operations Superintendent
P. Gillespie, Station Manager
D. Hubbard, Training Manager
S. Lark, ILT Supervisor
R. Meixell, Regulatory Compliance
R. Robinson, Operations Shift Manager
M. Stephens, Shift Operations Manager
P. Stovall, Training Manager Operations Fleet Training COE
G. Washburn, Initial Training Supervisor
C. Witherspoon, Training Instructor
NRC personnel
A. Sabisch, Senior Resident Inspector
                                                                                    Enclosure 1
 
              NRC Disposition of Oconee 2010-301 Post Examination Comments:
Three post exam comments were submitted on the operating test.
    1.) Control Room JPM a: CRO -108 (Perform Reactor Manual Trip Test)
STEP 11:        Step 12.2.2K
                Depress and Hold REACTOR TRIP pushbutton
STANDARD: Depress and Hold REACTOR TRIP pushbutton located on UB1.
This step is identified as a CRITIAL STEP.
COMMENT:
Depressing the REACTOR TRIP pushbutton is required to perform the test and meet the
acceptance criteria.
PT/1/A/0305/001 Reactor Manual Trip Test acceptance criteria states:
All CRD breakers open when Reactor Trip pushbutton is depressed
CRD breakers opening as required were accomplished in all observed cases of JPM
administration. The specific hold period as indicated in the procedure step is to ensure the
computer SPDS points update. The computer points updating are not part of the test
acceptance criteria and are not required for operability of the CRD breakers and trip subsystem.
This was verified with an on-shift Shift Technical Advisor and Operations Management.
If the reactor manual trip pushbutton were to be depressed but not held during actual plant
performance of the test, the test would be evaluated as acceptance criteria met and the hold
issue would be categorized as a procedure use issue and a PIP initiated to document.
After discussions with the Operations Superintendent, PIP O-10-2309 was written to evaluate
adding a note to the procedure prior to the step providing explanation on the specific desire to
hold the pushbutton to ensure the computer points update.
RECOMMENDATION:
The second part of the step (Hold REACTOR TRIP pushbutton and the step to release the
reactor trip pushbutton) should NOT be identified as critical.
NRC Resolution:
The NRC agrees the depressing and holding of the REACTOR TRIP pushbutton should not be
a critical step because it is not a part of the acceptance criteria, and the task can be completed
without holding the REACTOR TRIP pushbutton until directed by the procedure to be released.
The NRC will document the failure to hold the REACTOR TRIP pushbutton in until directed by
the procedure to release as a procedure adherence issue.
                                                                                        Enclosure 2
 
                                                2
    2.) Administrative JPM: Admin - 402 (Perform Actions for Medical Emergency)
STEP 14:          Step 1.8
                  IF Hospital evacuation is needed as determined by MERT Command or as
                  indicated by step 1.8.1 Then Arrange transport of patient to the hospital by one of
                  the following means:
                      *    EMS (ambulance)
                          Dial 9-911 from the Operations Shift Managers phone or Unit 1 Control
                          Room Sorts phone or dial 911 from the Bell South line - Unit 1, 2, and 3
                          Control Rooms. Refer to Step 1.8.2 prior to requesting EMS.
                      *    Company vehicle (less serious injury)
                      *    Personal Vehicle (less serious injury)
Cue: This will have to be simulated only, since simulator phones do not model outside
lines.
STANDARD: Determine that a Hospital evacuation is required due to the person being
                  unconscious. Ambulance is requested by calling 9-911. Ambulance is requested
                  to come to Oconee Nuclear Station.
This step is identified as a Critical Step.
COMMENT:
During administration of this JPM, one candidate completed this step by calling security and
requesting that they call for the ambulance. During performance of this task in the plant the RO
would often delegate other people to assist in completing steps of this procedure. This would
be done to expedite getting the injured person help. Ensuring that an ambulance is called is the
critical part of this step.
RECOMMENDATION:
Delegating calling the ambulance to another person is an acceptable method to complete this
step.
NRC Resolution:
The NRC agrees requesting an ambulance for the unconscious victim is critical. Delegating the
calling of the ambulance, while not listed as one of the means, does not appear to be in conflict
with the procedure. Delegating the arrangement of transportation to the hospital to security staff
is acceptable. Typically security would have to be notified to allow the ambulance on site, and
this would improve efficiency. The NRC accepts this recommendation, and directing the
requesting of an ambulance by security is acceptable.
                                                                                        Enclosure 2
 
                                              3
    3.) Administrative JPM: Admin - 402 (Perform Actions for Medical Emergency)
STEP 7:          Step 1.5.1
                Use the following directions to activate radios and pagers encoded to the MERT
                alert tones:
                1. Press the GREEN button labeled MERT on the paging console
                2. Press the RED button labeled transmit on the right bottom of the console
                    and wait approximately 3 seconds
                3. Pick up telephone handset on console and press the lever located inside
                    the handset
                4. Transmit message
STANDARD: Locate paging console in the OSM booth in the simulator.
Cue: Inform the candidate that the screen at the top of the phone is illuminated and
contains the word Operations
                Press the GREEN button labeled MERT on the paging console
Cue: Inform the candidate that upper light to the left of the green MERT key illuminates
green when the MERT button is depressed.
                Press the RED button labeled transmit on the right bottom of the console and
                wait approximately 3 seconds
Cue: Inform the candidate that light above the TRANSMIT key illuminates red and a
warble tone is heard when the TRANSMIT button is depressed.
                Pick up telephone handset on console and press the lever located inside the
                Handset
                Transmit message
This step is identified as a CRITICAL STEP.
COMMENT:
During administration of this JPM, the candidates indicated that they were not familiar with the
warble tone when the TRANSMIT button was depressed. This examiner cue was added
based on feedback during the validation of this JPM. It was intended to give the candidate
feedback on actions they were taking. It was not intended to be part of the critical step. The
Critical part of the step is depressing the transmit button. Verification of the audible feedback is
not required for completion of the step.
                                                                                          Enclosure 2
 
                                              4
RECOMMENDATION:
Knowledge of the warble tone should NOT be considered when determining completion of this
critical step.
NRC Resolution:
The NRC agrees that it is critical for the applicant to press the GREEN button labeled MERT
on the paging console, press the RED button labeled transmit on the right bottom of the
console and wait approximately 3 seconds, and then pick up telephone handset on console
and press the lever located inside the handset and transmit the message. Therefore as long as
the message was transmitted this step of the JPM will be graded as satisfactory.
                                                                                      Enclosure 2
 
                                SIMULATION FACILITY REPORT
Facility Licensee: Oconee Nuclear Station
Facility Docket Nos.: 05000269/05000270/05000287
Operating Tests Administered on: March 29 - April 2, 2010
This form is to be used only to report observations. These observations do not constitute audit
or inspection findings and, without further verification and review in accordance with Inspection
Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee
action is required in response to these observations.
While conducting the simulator portion of the operating test, examiners observed the following:
Items                              Description
All Heater Drain tank pump          During one scenario the crew attempted to secure the
Tripped                            1E1 HDP, and when its switch was taken to off all four
                                    HDPs tripped. WR 1765 was written to document the
                                    issue.
EH alarm during administration      An EH alarmed came in during the performance of JPM
of JPM CRO-601                      CRO-601 Synchronization with the grid after a load
                                    rejection, but did not come in on prep week. WR 1767
                                    was written to document the issue.
Simulator B had a simulator        During the preparation week while validating a scenario
STOP.                              simulator B displayed erroneous responses in both
                                    primary and secondary parameters which eventually
                                    resulted in a simulator STOP. The scenario was run on
                                    simulator A with the same results. WR1758 was written to
                                    document the issue.
Power Excursion when 4th            One of the scenarios initially contained a requirement to
reactor coolant pump started.      start the 4th RCP while at power. During preparations of
                                    the scenario the exam team identified a significant power
                                    excursion when the pump was started in accordance with
                                    existing procedures. PIP O-10-0716 was written to
                                    address and document the issue.
                                                                                      Enclosure 3
}}

Latest revision as of 17:31, 21 March 2020

Er 05000296/10-301, 05000270/10-301, 05000287/10-301 on 03/29/10 - 04/02/10 for Oconee,
ML101330609
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/13/2010
From: Widmann M
Division Reactor Projects II
To: Baxter D
Duke Energy Carolinas
References
50-270/10-301, 50-287/10-301, 50-296/10-301
Download: ML101330609 (13)


See also: IR 05000296/2010301

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

May 13, 2010

Mr. David A. Baxter

Site Vice President

Duke Energy Carolinas, LLC

Oconee Nuclear Station

7800 Rochester Highway

Seneca, SC 29672

SUBJECT: OCONEE NUCLEAR STATION - NRC OPERATOR LICENSE EXAMINATION

REPORT 05000269/2010301, 05000270/2010301, AND 05000287/2010301

Dear Mr. Baxter:

During the period March 29 - April 02, 2010 the Nuclear Regulatory Commission (NRC)

administered operating tests to employees of your company who had applied for licenses to

operate the Oconee Nuclear Station. At the conclusion of the tests, the examiners discussed

preliminary findings related to the operating tests with those members of your staff identified in

the enclosed report. The written examination was administered by your staff on April 07, 2010.

All applicants passed both the operating test and written examination. There were three post-

administration comments concerning the operating test. These comments, and the NRC

resolution of these comments, are summarized in Enclosure 2. A Simulator Fidelity Report is

included in this report as Enclosure 3.

In accordance with 10 CFR 2.390 of the NRCs 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 the NRCs document

system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

If you have any questions concerning this letter, please contact me at (404) 997-4550.

Sincerely,

/RA/

Malcolm T. Widmann, Chief

Operations Branch

Division of Reactor Safety

Docket Nos.: 50-269, 50-270, and 50-287

License Nos.: DPR-38, DPR-47, and DPR-55

Enclosures: 1. Report Details

2. Facility Comments and NRC Resolution

3. Simulator Fidelity Report

_________________________ G SUNSI REVIEW COMPLETE

OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRP

SIGNATURE GWL /RA/ MTW /RA for/ RFA /RA/ MTW /RA/ MFK /RA/

NAME GLaska FEhrhardt RAiello MWidmann MKing

DATE 05/12/2010 05/13/2010 05/13/2010 05/13/2010 05/12/2010

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

DPC 2

cc w/encl: David A. Repka

Kent Alter Winston Strawn LLP

Regulatory Compliance Manager Electronic Mail Distribution

Oconee Nuclear Station

Duke Energy Carolinas, LLC Kathryn B. Nolan

Electronic Mail Distribution Senior Counsel

Duke Energy Corporation

Scott L. Batson 526 South Church Street-EC07H

Engineering Manager Charlotte, NC 28202

Oconee Nuclear Station

Duke Energy Carolinas, LLC Charles Brinkman

Electronic Mail Distribution Director

Washington Operations

Clark E. Curry Westinghouse Electric Company, LLC

Engineering Manager Electronic Mail Distribution

Oconee Nuclear Station

Duke Energy Carolinas, LLC County Supervisor of Oconee County

Electronic Mail Distribution 415 S. Pine Street

Walhalla, SC 29691-2145

Philip J. Culbertson

Oconee Nuclear Station R. Mike Gandy

Duke Energy Carolinas, LLC Division of Radioactive Waste Mgmt.

Electronic Mail Distribution S.C. Department of Health and

Environmental Control

Preston Gillespie Electronic Mail Distribution

Manager

Oconee Nuclear Station Susan E. Jenkins

Duke Energy Carolinas, LLC Director, Division of Waste Management

Electronic Mail Distribution Bureau of Land and Waste Management

S.C. Department of Health and

R. L. Gill, Jr. Environmental Control

Manager Electronic Mail Distribution

Nuclear Regulatory Issues & Industry Affairs

Duke Energy Carolinas, LLC W. Lee Cox, III

Electronic Mail Distribution Section Chief

Radiation Protection Section

Dhiaa M. Jamil N.C. Department of Environmental

Group Executive and Chief Nuclear Officer Commerce & Natural Resources

Duke Energy Carolinas, LLC Electronic Mail Distribution

Electronic Mail Distribution

Dean M. Hubbard

Lisa F. Vaughn Training Manager

Associate General Counsel Oconee Nuclear Station

Duke Energy Corporation Electronic Mail Distribution

526 South Church Street-EC07H

Charlotte, NC 28202

DPC 3

Letter to David A. Baxter from Malcolm T. Widmann dated May 13, 2010

SUBJECT: OCONEE NUCLEAR STATION - NRC OPERATOR LICENSE EXAMINATION

REPORT 05000269/2010301, 05000270/2010301, AND 05000287/2010301

Distribution w/encl:

C. Evans, RII

L. Slack, RII

OE Mail

RIDSNRRDIRS

PUBLIC

RidsNrrPMOconee Resource

NUCLEAR REGULATORY COMMISSION

REGION II

Docket No.: 50-269, 50-270, 50-287

License No.: DPR-38, DPR-47, DPR-55

Report No.: 05000269/2010301, 05000270/2010301, 05000287/2010301

Licensee: Duke Energy Corporation

Facility: Oconee Nuclear Station

Location: Seneca, SC 29672

Dates: Operating Test - March 29 - April 02, 2010

Written Examination - April 07, 2010

Examiners: G. Laska, Chief Examiner, Senior Operations Examiner

F. Ehrhardt, Senior Operations Engineer

R. Aiello, Senior Operations Engineer

Approved by: Malcolm T. Widmann, Chief

Operations Branch

Division of Reactor Safety

Enclosure 1

SUMMARY OF FINDINGS

ER 05000269/2010301, 05000270/2010301, 05000287/2010301, 03/29-04/02/2010 &

04/07/2010; Oconee Nuclear Station; Operator License Examinations.

Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in

accordance with the guidelines in Revision 9, Supplement 1, of NUREG-1021, "Operator

Licensing Examination Standards for Power Reactors." This examination implemented the

operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.

Members of the Oconee Nuclear Station staff developed both the operating tests and the written

examination.

The NRC administered the operating tests during the period March 29 - April 02, 2010.

Members of the Oconee Nuclear Station training staff administered the written examination on

April 07, 2010. All Reactor Operator (RO) and Senior Reactor Operator (SRO) applicants

passed both the operating test and written examination. Nine applicants were issued licenses

commensurate with the level of examination administered.

There were three post-examination comments. The NRC resolutions to these comments are

summarized in Enclosure 2.

No findings of significance were identified.

Enclosure 1

REPORT DETAILS

2. OTHER ACTIVITIES

4OA5 Operator Licensing Initial Examinations

a. Inspection Scope

Members of the Oconee Nuclear Station staff developed both the operating tests and the

written examination. All examination material was developed in accordance with the

guidelines contained in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing

Examination Standards for Power Reactors." The NRC examination team reviewed the

proposed examination. Examination changes agreed upon between the NRC and the

licensee were made per NUREG-1021 and incorporated into the final version of the

examination materials.

The NRC reviewed the licensees examination security measures while preparing and

administering the examinations in order to ensure compliance with 10 CFR §55.49,

Integrity of examinations and tests.

The NRC examiners evaluated six Reactor Operator (RO) and three Senior Reactor

Operator (SRO) applicants using the guidelines contained in NUREG-1021. The

examiners administered the operating tests during the period March 29 - April 02, 2010.

Members of the Oconee Nuclear Station training staff administered the written

examination on April 07, 2010. Evaluations of applicants and reviews of associated

documentation were performed to determine if the applicants, who applied for licenses to

operate the Oconee Nuclear Station, met the requirements specified in 10 CFR Part 55,

Operators Licenses.

b. Findings

No findings of significance were identified. The NRC determined, using NUREG-1021,

that the licensees examination submittal was within the range of acceptability expected

for a proposed examination.

Nine applicants passed both the operating test and written examination and were issued

licenses.

Copies of all individual examination reports were sent to the facility Training Manager for

evaluation of weaknesses and determination of appropriate remedial training.

The licensee submitted three post-examination comments. A copy of the final written

examination and answer key, with all changes incorporated, and post exam comments

may be accessed in the ADAMS system (ADAMS Accession Number ML101310324 and

ML101310308 and ML101310299).

Enclosure 1

4

4OA6 Meetings

Exit Meeting Summary

On April 02, 2010 the NRC examination team discussed generic issues associated with the

operating test with you and members of the Oconee Nuclear Station staff. The examiners

asked the licensee if any of the examination material was proprietary. No proprietary

information was identified.

KEY POINTS OF CONTACT

Licensee personnel

K. Alter, Regulatory Compliance

F. Baldwin, Operations Shift Manager

D. Baxter, Site VP

E. Burchfield, Operations Superintendent

P. Gillespie, Station Manager

D. Hubbard, Training Manager

S. Lark, ILT Supervisor

R. Meixell, Regulatory Compliance

R. Robinson, Operations Shift Manager

M. Stephens, Shift Operations Manager

P. Stovall, Training Manager Operations Fleet Training COE

G. Washburn, Initial Training Supervisor

C. Witherspoon, Training Instructor

NRC personnel

A. Sabisch, Senior Resident Inspector

Enclosure 1

NRC Disposition of Oconee 2010-301 Post Examination Comments:

Three post exam comments were submitted on the operating test.

1.) Control Room JPM a: CRO -108 (Perform Reactor Manual Trip Test)

STEP 11: Step 12.2.2K

Depress and Hold REACTOR TRIP pushbutton

STANDARD: Depress and Hold REACTOR TRIP pushbutton located on UB1.

This step is identified as a CRITIAL STEP.

COMMENT:

Depressing the REACTOR TRIP pushbutton is required to perform the test and meet the

acceptance criteria.

PT/1/A/0305/001 Reactor Manual Trip Test acceptance criteria states:

All CRD breakers open when Reactor Trip pushbutton is depressed

CRD breakers opening as required were accomplished in all observed cases of JPM

administration. The specific hold period as indicated in the procedure step is to ensure the

computer SPDS points update. The computer points updating are not part of the test

acceptance criteria and are not required for operability of the CRD breakers and trip subsystem.

This was verified with an on-shift Shift Technical Advisor and Operations Management.

If the reactor manual trip pushbutton were to be depressed but not held during actual plant

performance of the test, the test would be evaluated as acceptance criteria met and the hold

issue would be categorized as a procedure use issue and a PIP initiated to document.

After discussions with the Operations Superintendent, PIP O-10-2309 was written to evaluate

adding a note to the procedure prior to the step providing explanation on the specific desire to

hold the pushbutton to ensure the computer points update.

RECOMMENDATION:

The second part of the step (Hold REACTOR TRIP pushbutton and the step to release the

reactor trip pushbutton) should NOT be identified as critical.

NRC Resolution:

The NRC agrees the depressing and holding of the REACTOR TRIP pushbutton should not be

a critical step because it is not a part of the acceptance criteria, and the task can be completed

without holding the REACTOR TRIP pushbutton until directed by the procedure to be released.

The NRC will document the failure to hold the REACTOR TRIP pushbutton in until directed by

the procedure to release as a procedure adherence issue.

Enclosure 2

2

2.) Administrative JPM: Admin - 402 (Perform Actions for Medical Emergency)

STEP 14: Step 1.8

IF Hospital evacuation is needed as determined by MERT Command or as

indicated by step 1.8.1 Then Arrange transport of patient to the hospital by one of

the following means:

  • EMS (ambulance)

Dial 9-911 from the Operations Shift Managers phone or Unit 1 Control

Room Sorts phone or dial 911 from the Bell South line - Unit 1, 2, and 3

Control Rooms. Refer to Step 1.8.2 prior to requesting EMS.

  • Company vehicle (less serious injury)
  • Personal Vehicle (less serious injury)

Cue: This will have to be simulated only, since simulator phones do not model outside

lines.

STANDARD: Determine that a Hospital evacuation is required due to the person being

unconscious. Ambulance is requested by calling 9-911. Ambulance is requested

to come to Oconee Nuclear Station.

This step is identified as a Critical Step.

COMMENT:

During administration of this JPM, one candidate completed this step by calling security and

requesting that they call for the ambulance. During performance of this task in the plant the RO

would often delegate other people to assist in completing steps of this procedure. This would

be done to expedite getting the injured person help. Ensuring that an ambulance is called is the

critical part of this step.

RECOMMENDATION:

Delegating calling the ambulance to another person is an acceptable method to complete this

step.

NRC Resolution:

The NRC agrees requesting an ambulance for the unconscious victim is critical. Delegating the

calling of the ambulance, while not listed as one of the means, does not appear to be in conflict

with the procedure. Delegating the arrangement of transportation to the hospital to security staff

is acceptable. Typically security would have to be notified to allow the ambulance on site, and

this would improve efficiency. The NRC accepts this recommendation, and directing the

requesting of an ambulance by security is acceptable.

Enclosure 2

3

3.) Administrative JPM: Admin - 402 (Perform Actions for Medical Emergency)

STEP 7: Step 1.5.1

Use the following directions to activate radios and pagers encoded to the MERT

alert tones:

1. Press the GREEN button labeled MERT on the paging console

2. Press the RED button labeled transmit on the right bottom of the console

and wait approximately 3 seconds

3. Pick up telephone handset on console and press the lever located inside

the handset

4. Transmit message

STANDARD: Locate paging console in the OSM booth in the simulator.

Cue: Inform the candidate that the screen at the top of the phone is illuminated and

contains the word Operations

Press the GREEN button labeled MERT on the paging console

Cue: Inform the candidate that upper light to the left of the green MERT key illuminates

green when the MERT button is depressed.

Press the RED button labeled transmit on the right bottom of the console and

wait approximately 3 seconds

Cue: Inform the candidate that light above the TRANSMIT key illuminates red and a

warble tone is heard when the TRANSMIT button is depressed.

Pick up telephone handset on console and press the lever located inside the

Handset

Transmit message

This step is identified as a CRITICAL STEP.

COMMENT:

During administration of this JPM, the candidates indicated that they were not familiar with the

warble tone when the TRANSMIT button was depressed. This examiner cue was added

based on feedback during the validation of this JPM. It was intended to give the candidate

feedback on actions they were taking. It was not intended to be part of the critical step. The

Critical part of the step is depressing the transmit button. Verification of the audible feedback is

not required for completion of the step.

Enclosure 2

4

RECOMMENDATION:

Knowledge of the warble tone should NOT be considered when determining completion of this

critical step.

NRC Resolution:

The NRC agrees that it is critical for the applicant to press the GREEN button labeled MERT

on the paging console, press the RED button labeled transmit on the right bottom of the

console and wait approximately 3 seconds, and then pick up telephone handset on console

and press the lever located inside the handset and transmit the message. Therefore as long as

the message was transmitted this step of the JPM will be graded as satisfactory.

Enclosure 2

SIMULATION FACILITY REPORT

Facility Licensee: Oconee Nuclear Station

Facility Docket Nos.: 05000269/05000270/05000287

Operating Tests Administered on: March 29 - April 2, 2010

This form is to be used only to report observations. These observations do not constitute audit

or inspection findings and, without further verification and review in accordance with Inspection

Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee

action is required in response to these observations.

While conducting the simulator portion of the operating test, examiners observed the following:

Items Description

All Heater Drain tank pump During one scenario the crew attempted to secure the

Tripped 1E1 HDP, and when its switch was taken to off all four

HDPs tripped. WR 1765 was written to document the

issue.

EH alarm during administration An EH alarmed came in during the performance of JPM

of JPM CRO-601 CRO-601 Synchronization with the grid after a load

rejection, but did not come in on prep week. WR 1767

was written to document the issue.

Simulator B had a simulator During the preparation week while validating a scenario

STOP. simulator B displayed erroneous responses in both

primary and secondary parameters which eventually

resulted in a simulator STOP. The scenario was run on

simulator A with the same results. WR1758 was written to

document the issue.

Power Excursion when 4th One of the scenarios initially contained a requirement to

reactor coolant pump started. start the 4th RCP while at power. During preparations of

the scenario the exam team identified a significant power

excursion when the pump was started in accordance with

existing procedures. PIP O-10-0716 was written to

address and document the issue.

Enclosure 3