ML101330609
| ML101330609 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| 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